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| number = ML15316A134 | | number = ML15316A134 | ||
| issue date = 11/10/2015 | | issue date = 11/10/2015 | ||
| title = | | title = Initial Exam 2015-301 Final SRO Written Exam | ||
| author name = | | author name = | ||
| author affiliation = NRC/RGN-II/DRS | | author affiliation = NRC/RGN-II/DRS | ||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:ES-401 | {{#Wiki_filter: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: 20 OCT 2015 Facility / Unit FARLEY 1 & 2 Region: I II X III IV Reactor Type: W X CE BW GE Start Time: Finish Time: | |||
U. S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name: Date: Facility / Unit Region: | 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 8 hours to complete the combined examination, and 3 hours if you are only taking the SRO portion. | ||
Applicant Certification All work done on this examination is my own. I have neither given nor received aid. | |||
All work done on this examination is my own. I have neither given nor received aid. | Applicant's Signature Results RO/SRO-Only/Total Examination Values 75 / ______ | ||
______ 25 / ______ | |||
Applicant's Signature Results RO/SRO-Only/Total Examination Values ______ | 100 Points Applicant's Score ______ / ______ / ______ | ||
Points Applicant's Grade ______ / ______ / ______ | |||
Points Applicant's Score ______ | Percent ES-401, Page 38 of 50 | ||
: 1. Unit 1 is starting up IAW UOP-1.2, Startup of Unit from Hot Standby to Minimum Load, with the following condition: | |||
Points Applicant's Grade | * Reactor Power is 13%. | ||
The CONTROL ROD MOTION switch has been released following a rod withdrawal when the following occurs: | |||
Percent | |||
: 1. Unit 1 is starting up IAW UOP-1.2, | |||
The CONTROL ROD | |||
* Rods step out continuously. | * Rods step out continuously. | ||
Which one of the following completes the statements below? | |||
Which one of the following | The first action directed by AOP-19.0, Malfunction of Rod Control System, is to (1) . | ||
The first action directed by AOP-19.0, | With NO operator action the C-1, IR Hi Flux Rod Stop, (2) stop the outward rod motion. | ||
(1) manually Trip the Reactor (2) will NOT(1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) will NOT (1) manually Trip the Reactor (2) WILL(1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) WILL | A. (1) manually Trip the Reactor (2) will NOT B. (1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) will NOT C. (1) manually Trip the Reactor (2) WILL D. (1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) WILL | ||
: 2. Unit 1 is performing a Reactor | : 2. Unit 1 is performing a Reactor startup at MOL with the following conditions: | ||
-8 AMPS.Subsequently, control rods are withdrawn 3 steps. | * UOP-1.2, Startup of Unit From Hot Standby to Minimum Load, is in progress. | ||
Which one of the following | * The OATC has stabilized Reactor power. | ||
Reactor Power will rise then stablize (1) | * NI-35 and NI-36, INTERMEDIATE RANGE, indicate 1x10-8 AMPS. | ||
Subsequently, control rods are withdrawn 3 steps. | |||
: 3. Unit 1 is at 25% power | Which one of the following completes the statements below? | ||
At 1000:* 1A RX COOLANT PUMP AMPS indicates 700 AMPS. | Reactor Power will rise then stablize (1) the POAH. | ||
The first indication of reaching the POAH is rising (2) . | |||
(1) (2) | |||
A. below Pressurizer Level B. at Pressurizer Level C. below S/G Pressure D. at S/G Pressure | |||
: 3. Unit 1 is at 25% power when the following conditions occur: | |||
At 1000: | |||
* 1A RX COOLANT PUMP AMPS indicates 700 AMPS. | |||
At 1002: | At 1002: | ||
* The 1A RCP motor experiences a Sheared Shaft. | * The 1A RCP motor experiences a Sheared Shaft. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1002 the 1A RCP will draw (1) | At 1002 the 1A RCP will draw (1) electrical current than it did at 1000. | ||
The crew is required to immediately enter (2) . | |||
: 4. Unit 1 is operating at 100% | (1) (2) | ||
* PK-145, LP LTDN PRESS, is set to maintain | A. More EEP-0.0, Reactor Trip and Safety Injection B. Less EEP-0.0, Reactor Trip and Safety Injection C. More AOP-4.0, Loss of Reactor Coolant Flow D. Less AOP-4.0, Loss of Reactor Coolant Flow | ||
Subsequently, the RCS filter becomes completely clogged and does not allow any flow.Which one of the following | : 4. Unit 1 is operating at 100% power with the following conditions: | ||
* PK-145, LP LTDN PRESS, is set to maintain Letdown Pressure at 275 psig. | |||
Subsequently, the RCS filter becomes completely clogged and does not allow any flow. | |||
: 5. Which one of the following | Which one of the following completes the statements below? | ||
PK-145 controller demand will (1) . | |||
Level Transmitter Nomenclature LT-115, VCT LVL LT-112, VCT LVL | AOP-16.0, CVCS Malfunction, entry conditions (2) been met. | ||
(1) (2) | |||
A. Rise HAVE B. Rise have NOT C. Lower HAVE D. Lower have NOT | |||
: 5. Which one of the following completes the statement below? | |||
Charging Pump Suctions will automatically align to the RWST when (1) sense(s) (2) VCT Level. | |||
Level Transmitter Nomenclature LT-115, VCT LVL LT-112, VCT LVL (1) (2) | |||
A. either LT-115 or LT-112 5% | |||
B. both LT-115 and LT-112 5% | |||
C. either LT-115 or LT-112 15% | |||
D. both LT-115 and LT-112 15% | |||
: 6. Unit 1 is in MODE 4 with the following conditions: | : 6. Unit 1 is in MODE 4 with the following conditions: | ||
* Plant cooldown is in progress with the 'A' Train of RHR . | * Plant cooldown is in progress with the 'A' Train of RHR . | ||
* The OATC raises demand on FK-605A,1A RHR HX BYP FLOW, by 25%. | * The OATC raises demand on FK-605A,1A RHR HX BYP FLOW, by 25%. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Raising demand on FK-605A will (1) | Raising demand on FK-605A will (1) CCW temperature. | ||
CCW temperature. | Per SOP-23.0, Component Cooling Water System, the maximum allowable CCW outlet temperature for the CCW HX used for cooldown is (2) . | ||
Per SOP-23.0, Component Cooling Water System, the maximum | (1) (2) | ||
A. raise 120°F B. raise 135°F C. lower 120°F D. lower 135°F | |||
: 7. Unit 1 is shutdown when | : 7. Unit 1 is shutdown when the following conditions occur: | ||
* The 1A CCW pump tripped. | * The 1A CCW pump tripped. | ||
* The 'A' Train is the ON SERVICE Train. | * The 'A' Train is the ON SERVICE Train. | ||
Which one of the following | Which one of the following completes the statement below? | ||
Cooling is lost to the (1) RHR Heat Exchanger. | |||
The affected RHR train (2) available for transfer to Cold Leg Recirculation. | |||
(1) (2) | |||
A. 1A is NOT B. 1A IS C. 1B is NOT D. 1B IS | |||
: 8. Unit 1 has experienced a tube rupture on the 1A SG with the following conditions: | : 8. Unit 1 has experienced a tube rupture on the 1A SG with the following conditions: | ||
* A Loss of All Offsite Power has occurred. | * A Loss of All Offsite Power has occurred. | ||
* The operating crew is performing EEP-3, Steam | * The operating crew is performing EEP-3, Steam Generator Tube Rupture. | ||
* RCS cooldown is in progress. | * RCS cooldown is in progress. | ||
* INTEGRITY Critical Safety Function Status Tree has turned ORANGE due | * INTEGRITY Critical Safety Function Status Tree has turned ORANGE due to the 1A RCS LOOP cold leg temperature dropping rapidly. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The 1A RCS LOOP cold leg temperature drop was caused by increased (1) flow over the 1A RCS LOOP cold leg instrument. | |||
(2) is the highest listed cold leg temperature that could lead to this ORANGE INTEGRITY condition. | |||
(1) (2) | |||
A. Natural Circulation 270°F B. Natural Circulation 225°F C. High Head Safety Injection 270°F D. High Head Safety Injection 225°F | |||
: 9. A Safety Injection has just occurred on Unit 1. | : 9. A Safety Injection has just occurred on Unit 1. | ||
Which one of the following | Which one of the following completes the statement below? | ||
The minimum valve actuations that would lead to HHSI Pump cavitation | The minimum valve actuations that would lead to HHSI Pump cavitation are . | ||
LCV-115C, VCT OUTLET ISO LCV-115E, VCT OUTLET ISO | Valve Nomenclature: | ||
LCV-115C, VCT OUTLET ISO LCV-115E, VCT OUTLET ISO LCV-115D, RWST TO CHG PUMP LCV-115B, RWST TO CHG PUMP A. LCV-115C or LCV-115E opening B. LCV-115C and LCV-115E opening C. LCV-115B or LCV-115D closing D. LCV-115B and LCV-115D closing | |||
LCV-115D, RWST TO CHG PUMP | |||
LCV-115B, RWST TO CHG PUMP LCV-115C | |||
: 10. Nitrogen addition to the PRT on Unit 1 is in progress when the following occurs: | : 10. Nitrogen addition to the PRT on Unit 1 is in progress when the following occurs: | ||
* V-042, PRT N2 PRESS REG, fails causing PRT pressure to RISE. | * V-042, PRT N2 PRESS REG, fails causing PRT pressure to RISE. | ||
* PI-472, PRT PRESS, | * PI-472, PRT PRESS, stablizes at 15.0 psig. | ||
Which one of the following | Which one of the following completes the statements below? | ||
HE5, PRT PRESS HI, (1) in alarm. | |||
Per SOP-1.2, Reactor Coolant Pressure Relief System, normal nitrogen pressure prevents (2) . | |||
(1) (2) | |||
A. IS excessive corrosion due to oxygen B. is NOT excessive corrosion due to oxygen C. IS an explosive mixture of oxygen and hydrogen D. is NOT an explosive mixture of oxygen and hydrogen | |||
: 11. Unit 1 is operating at 100% power when the following conditions occur: | : 11. Unit 1 is operating at 100% power when the following conditions occur: | ||
* A large break has | * A large break has occurred at the inlet of a Pressurizer Safety Valve. | ||
Subsequently, the | Subsequently, the following condition exists: | ||
* Pressurizer Pressure is 1600 psig. | * Pressurizer Pressure is 1600 psig. | ||
* Charging Pump miniflow valves are open.Which one of the following | * Charging Pump miniflow valves are open. | ||
Which one of the following completes the statements below? | |||
Per EEP-0, Reactor Trip or Safety Injection, the crew (1) required to close the Charging Pump miniflow valves. | |||
Closing the Charging Pump miniflow valves when required will ensure (2) . | |||
(1) (2) | |||
A. IS HHSI pump injection flow is maximized B. is NOT HHSI pump injection flow is maximized C. IS HHSI pump heat is removed D. is NOT HHSI pump heat is removed | |||
: 12. Unit 1 is operating at 100% power with the following conditions: | : 12. Unit 1 is operating at 100% power with the following conditions: | ||
* A dual unit LOSP occurs. | * A dual unit LOSP occurs. | ||
Subsequently, | Subsequently, Unit 2 experiences a Safety Injection. | ||
Which one of the following | Which one of the following completes the statement below for Unit 1? | ||
The (1) CCW pump is being powered by the (2) DG. | |||
(1) (2) | |||
A. 1A 1-2A B. 1A 1C C. 1C 1-2A D. 1C 1C | |||
: 13. Unit 1 is in MODE 5 with the following conditions: | : 13. Unit 1 is in MODE 5 with the following conditions: | ||
* A cooldown is in progress. | * A cooldown is in progress. | ||
* RHR is on service. | * RHR is on service. | ||
Subsequently, the following conditions occur: | Subsequently, the following conditions occur: | ||
* V-8708A, RHR SUCTION RELIEF , has lifted and is stuck open. | * V-8708A, RHR SUCTION RELIEF, has lifted and is stuck open. | ||
Which of the following tank levels will immediately rise due to the malfunction? | Which of the following tank levels will immediately rise due to the malfunction? | ||
A. PRT B. RHT C. WHT D. RCDT | |||
: 14. A Design Basis Large Break | : 14. A Design Basis Large Break LOCA has occurred on Unit 1. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The Accumulators will inject directly to the (1) . | |||
The purpose of the Accumulator design capacity is to (2) refill the Reactor Vessel following a design basis accident. | |||
(1) (2) | |||
completely Cold Legs partially Cold Legs | A. Hot Legs partially B. Hot Legs completely C. Cold Legs partially D. Cold Legs completely | ||
: 15. Unit 1 is operating at 100% power and the following conditions exist: | : 15. Unit 1 is operating at 100% power and the following conditions exist: | ||
* Pressurizer Pressure is 2240 psig. | * Pressurizer Pressure is 2240 psig. | ||
Line 124: | Line 143: | ||
* Pressurizer Level is 60%. | * Pressurizer Level is 60%. | ||
* 600V LCC 1M has lost power. | * 600V LCC 1M has lost power. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Power has been lost to the (1) Pressurizer Heater Group. | |||
Pressurizer Heater Groups A and B are currently (2) . | |||
(1) (2) | |||
A. D Energized B. D De-Energized C. E Energized D. E De-Energized | |||
: 16. Unit 1 is operating at 100% Power when the following conditions occur: | : 16. Unit 1 is operating at 100% Power when the following conditions occur: | ||
* A short circuit occurs in PT-445, PRZR PRESS. | * A short circuit occurs in PT-445, PRZR PRESS. | ||
* Pressurizer Pressure remains stable. | * Pressurizer Pressure remains stable. | ||
Which one of the following | Which one of the following completes the statement below? | ||
The Pressurizer Pressure input to the Reactor Protection System will NOT be affected by this malfunction due to the use of . | |||
: 17. Unit 1 is operating at 100% power and | A. an independent control channel B. a median signal selector C. isolation devices D. de-energize to actuate bistables | ||
* A Safety Injection | : 17. Unit 1 is operating at 100% power and the following occurs: | ||
Several minutes following the safety | * A Safety Injection followed by an LOSP on Unit 1. | ||
Several minutes following the safety injection the following condition exists: | |||
* The 1B DG is running with the output breaker open. | * The 1B DG is running with the output breaker open. | ||
Which one of the following | Which one of the following completes the statements below? | ||
SOP-0.8, Transient Response Procedure User's Guide, (1) require a procedure be used prior to closing the 1B DG output breaker. | |||
The B1G sequencer (2) energize the 1C Air Compressor. | |||
(1) (2) | |||
A. DOES DOES B. DOES does NOT C. does NOT DOES D. does NOT does NOT | |||
: 18. The 1D Vital Panel becomes de-energized on Unit 1. | : 18. The 1D Vital Panel becomes de-energized on Unit 1. | ||
Which one of the following | Which one of the following completes the statements below. | ||
The 'B' Train SI actuated MOVs (1) automatically stroke upon an SI actuation. | |||
'B' Train ESF pumps (2) be started in LOCAL at the HSDP. | |||
: 19. Which one of the following completes the statements below? The C-11, Bank D Stop, is actuated by input from (1) | (1) (2) | ||
A. WILL CAN B. WILL CANNOT C. will NOT CAN D. will NOT CANNOT | |||
: 19. Which one of the following completes the statements below? | |||
The C-11, Bank D Stop, is actuated by input from (1) at a Bank D rod height of (2) steps. | |||
(1) (2) | |||
A. Digital Rod Position Indication 220 B. Digital Rod Position Indication 228 C. the Pulse-to-Analog Converter 220 D. the Pulse-to-Analog Converter 228 | |||
: 20. Unit 1 is in MODE 3 and the following RCP temperatures are observed: | : 20. Unit 1 is in MODE 3 and the following RCP temperatures are observed: | ||
Motor Bearing Temperature Motor Stator Temperature 1A RCP 190°F 235°F 1B RCP 200°F 220°F 1C RCP 190°F 230°F Which one of the following completes the statement below? | |||
1A RCP 1B RCP 1A and 1B RCPs 1A and 1C RCPs | Only the is (are) required to be secured. | ||
: 21. Which one of the following conditions would cause a Core Exit Thermocouple (CETC)monitor alarm? 1. ANY CETC input disconnected. 2. ONLY 10 valid CETCs. | A. 1A RCP B. 1B RCP C. 1A and 1B RCPs D. 1A and 1C RCPs | ||
: 21. Which one of the following conditions would cause a Core Exit Thermocouple (CETC) monitor alarm? | |||
: 1. ANY CETC input disconnected. | |||
: 2. ONLY 10 valid CETCs. | |||
: 3. ANY CETC temperature at 650°F. | : 3. ANY CETC temperature at 650°F. | ||
1 ONLY 1 AND 3 ONLY 2 ONLY 1, 2, AND 3 | A. 1 ONLY B. 1 AND 3 ONLY C. 2 ONLY D. 1, 2, AND 3 | ||
: 22. Unit 1 is operating at 100% power when the following conditions occurred: | : 22. Unit 1 is operating at 100% power when the following conditions occurred: | ||
* 1B Charging Pump is started. | * 1B Charging Pump is started. | ||
Line 155: | Line 187: | ||
* 1B CHG PUMP AMPS, begins to oscillate. | * 1B CHG PUMP AMPS, begins to oscillate. | ||
* FI-122A, CHG FLOW, begins to oscillate. | * FI-122A, CHG FLOW, begins to oscillate. | ||
Subsequently, the following | Subsequently, the following annunciators come into alarm: | ||
* EA2, CHG HDR FLOW HI-LO. | * EA2, CHG HDR FLOW HI-LO. | ||
* DD1, RCP SEAL INJ FLOW LO. | * DD1, RCP SEAL INJ FLOW LO. | ||
* DE1, REGEN HX LTDN FLOW DISCH TEMP HI. | * DE1, REGEN HX LTDN FLOW DISCH TEMP HI. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The alarms above are indicative of (1) . | |||
The maximum 1A RCP seal injection flowrate that would cause DD1 to alarm is (2) . | |||
(1) (2) | |||
A. FCV-122 closing 6 gpm B. 1B Charging Pump Cavitation 6 gpm C. FCV-122 closing 3 gpm D. 1B Charging Pump Cavitation 3 gpm | |||
: 23. Unit 1 is operating at 100% power with the following conditions: | : 23. Unit 1 is operating at 100% power with the following conditions: | ||
* A Large Break LOCA occurs. | * A Large Break LOCA occurs. | ||
Subsequently, a Loss of Offsite Power occurs. | Subsequently, a Loss of Offsite Power occurs. | ||
Which one of the following | Which one of the following completes the statement below 5 minutes after the Loss of Offsite Power? | ||
(1) Containment Cooler Fans are running in slow speed. | |||
The reduced speed prevents CTMT cooler (2) due to high moisture content in the Containment atmosphere. | |||
(1) (2) | |||
A. 2 fan motor overload B. 4 fan motor overload C. 2 cooling coil impingement damage D. 4 cooling coil impingement damage | |||
: 24. Unit 1 is in MODE 5 and the following condition exists: | : 24. Unit 1 is in MODE 5 and the following condition exists: | ||
* Both Trains of RHR are | * Both Trains of RHR are operating in the cooldown alignment. | ||
* Power is aligned to the RHR suction valves. | * Power is aligned to the RHR suction valves. | ||
* Tavg is 195°F. | * Tavg is 195°F. | ||
Subsequently, the following condition occurs: | Subsequently, the following condition occurs: | ||
* PT-402, 1C LOOP RCS NR PRESS, fails to 500 psig. | * PT-402, 1C LOOP RCS NR PRESS, fails to 500 psig. | ||
Which one of the following completes the statements below? | |||
Which one of the following | MOV-8701A, 1C RCS LOOP TO 1A RHR PUMP, (1) automatically close. | ||
IF MOV-8701A closes, then AOP-12.0, Residual Heat Removal System Malfunction, entry (2) required. | |||
(1) (2) | |||
A. DOES is NOT B. does NOT is NOT C. DOES IS D. does NOT IS | |||
: 25. Unit 1 is Shutdown following a LOCA with the following conditions: | : 25. Unit 1 is Shutdown following a LOCA with the following conditions: | ||
* PR-950, CTMT PRESS, peaked at 3.2 psig. | * PR-950, CTMT PRESS, peaked at 3.2 psig. | ||
* ECP-1.1, Loss of | * ECP-1.1, Loss of Emergency Coolant Recirculation, is in progress. | ||
Which one of the following | Which one of the following completes the statments below: | ||
Per ECP-1.1, the minimum CTMT Sump Level that can support Containment Spray pump operation is . | |||
A. 2.0 ft B. 3.8 ft C. 4.5 ft D. 5.3 ft | |||
: 26. Unit 1 is operating at 100% power when the following condition occurs: | : 26. Unit 1 is operating at 100% power when the following condition occurs: | ||
* PK-444A, PRZR PRESS | * PK-444A, PRZR PRESS REFERENCE, demand fails to 0%. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Initially, (1) PORV(s) will OPEN automatically. | |||
PCV-444C, 1A LOOP SPRAY VLV, will (2) . | |||
(1) (2) | |||
A. only ONE CLOSE B. only ONE OPEN C. BOTH CLOSE D. BOTH OPEN | |||
: 27. Unit 1 is operating at 100% power with the following conditions: | : 27. Unit 1 is operating at 100% power with the following conditions: | ||
* Containment Mini- | * Containment Mini-Purge is in operation Subsequently, the following conditions occur: | ||
* A Main Steam Line | * A Main Steam Line breaks inside Containment | ||
* PR-950Z, CTMT PRESS, stablizes at 14.5 psig. | * PR-950Z, CTMT PRESS, stablizes at 14.5 psig. | ||
Which one of the following | Which one of the following completes the statements below? | ||
CTMT Mini-Purge supply and exhaust fans (1) tripped automatically due to a Containment Ventilation Isolation signal. | |||
CTMT Mini-Purge supply and exhaust dampers (2) closed automatically due to a Containment Ventilation Isolation signal. | |||
(1) (2) | |||
A. HAVE HAVE B. HAVE have NOT C. have NOT HAVE D. have NOT have NOT | |||
: 28. Unit 1 is operating at 100% power with the following conditions: | : 28. Unit 1 is operating at 100% power with the following conditions: | ||
* STP-33.2A, Reactor Trip Breaker | * STP-33.2A, Reactor Trip Breaker Train A Operability Test, is in progress. | ||
* Reactor Trip | * Reactor Trip Breaker A is OPEN. | ||
* Reactor Trip Bypass Breaker A is CLOSED. | * Reactor Trip Bypass Breaker A is CLOSED. | ||
* Reactor Trip | * Reactor Trip Breaker B is CLOSED. | ||
Subsequently, the following conditions occur: | Subsequently, the following conditions occur: | ||
* An automatic reactor trip signal is generated. | * An automatic reactor trip signal is generated. | ||
* The Reactor does NOT trip. | * The Reactor does NOT trip. | ||
Which one of the following | Which one of the following completes the statements below? | ||
When the RX TRIP ACTUATION switch is taken to TRIP (1) will OPEN. | |||
Per EEP-0, Reactor Trip or Safety Injection, if the RX TRIP ACTUATION switches fail to trip the Reactor, the next action required is to (2) . | |||
A. (1) ONLY Reactor Trip Breaker B (2) trip the MG set supply breakers B. (1) BOTH Reactor Trip Bypass Breaker A and Reactor Trip Breaker B (2) trip the MG set supply breakers C. (1) ONLY Reactor Trip Breaker B (2) insert Control Rods manually D. (1) BOTH Reactor Trip Bypass Breaker A and Reactor Trip Breaker B (2) insert Control Rods manually | |||
: 29. Unit 2 is starting up per UOP-1.2, Startup of Unit From Hot Standby To Minimum Load, with the following conditions: | : 29. Unit 2 is starting up per UOP-1.2, Startup of Unit From Hot Standby To Minimum Load, with the following conditions: | ||
* Main Steam Header Warm Up is in Progress. | * Main Steam Header Warm Up is in Progress. | ||
Which one of the following actions would cause the 2B SG Pressure to lower due to increased steam demand from the 2B SG? | |||
Which one of the following actions | A. Lower PC-3371B, 2B MS ATMOS REL VLV, SETPT in AUTO. | ||
Lower PC-3371B, 2B MS ATMOS REL VLV, SETPT in AUTO. | B. Lower PC-3371B, 2B MS ATMOS REL VLV, OUTPUT in MAN. | ||
Lower PC-3371B, 2B MS ATMOS REL VLV, OUTPUT in MAN. | C. Lower PK-464, STM HDR PRESS, OUTPUT in MAN. | ||
Lower PK-464, STM HDR | D. Lower PK-464, STM HDR PRESS, SETPT in AUTO. | ||
Lower PK-464, STM HDR PRESS, SETPT in AUTO | : 30. Unit 1 is responding to a SGTR in the 1A SG with the following conditions: | ||
: 30. Unit 1 is responding to a SGTR in the 1A SG | |||
At 1000: | At 1000: | ||
* HIGHEST CORE EXIT TEMP CHAN A and B on the IPC, indicates 530°F. | * HIGHEST CORE EXIT TEMP CHAN A and B on the IPC, indicates 530°F. | ||
Line 217: | Line 262: | ||
* PI-403A, 1A LOOP RCS WR PRESS, indicates 1230 psig. | * PI-403A, 1A LOOP RCS WR PRESS, indicates 1230 psig. | ||
* RCS cooldown is in progress. | * RCS cooldown is in progress. | ||
At | At 1045: | ||
* HIGHEST CORE EXIT TEMP CHAN A and B, on | * HIGHEST CORE EXIT TEMP CHAN A and B, on the IPC indicates 450°F. | ||
. | |||
* 1A SG PRESS is 300 psig. | * 1A SG PRESS is 300 psig. | ||
* PI-403A, 1A LOOP RCS WR PRESS, indicates 565 psig. | * PI-403A, 1A LOOP RCS WR PRESS, indicates 565 psig. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Compared to the conditions at 1000, RCS subcooling at 1045 has (1) . | |||
Compared to the conditions at 1000, SG tube leakage rate at 1045 has (2) . | |||
Reference Provided (1) (2) | |||
A. risen risen B. risen lowered C. lowered lowered D. lowered risen | |||
: 31. Unit 1 is in Mode 3 at EOL with the following conditions: | : 31. Unit 1 is in Mode 3 at EOL with the following conditions: | ||
* A Reactor Startup is being planned for 24 hours after a reactor trip. | * A Reactor Startup is being planned for 24 hours after a reactor trip. | ||
* Tavg is being maintained by the Atmospheric Relief Valves (ARVs). | * Tavg is being maintained by the Atmospheric Relief Valves (ARVs). | ||
* The Estimated Critical Condition (ECC) calculation predicts criticality at 100 | * The Estimated Critical Condition (ECC) calculation predicts criticality at 100 steps on Control Bank D. | ||
Which one of the following conditions will | Which one of the following conditions will result in critical rod height being HIGHER than the value predicted by the ECC? | ||
For your answer, consider that no operator actions are taken to mitigate or compensate for the below events. | For your answer, consider that no operator actions are taken to mitigate or compensate for the below events. | ||
A dilution of 500 gallons is performed. | A. A dilution of 500 gallons is performed. | ||
Auxiliary Feedwater flow is RAISED to all SGs. | B. Auxiliary Feedwater flow is RAISED to all SGs. | ||
A post maintenance test results in the closure of all ARVs. | C. A post maintenance test results in the closure of all ARVs. | ||
Reactor startup occurs 30 | D. Reactor startup occurs 30 hours after the reactor trip. | ||
: 32. Unit 2 is at 68% power ramping down due to a problem with #4 Governor Valve with the following conditions: | |||
: 32. Unit 2 is at 68% power ramping down due to a problem with #4 Governor Valve with the following conditions:* EH is isolated to #4 Governor valve. | * EH is isolated to #4 Governor valve. | ||
* A subsequent failure causes #2 Governor Valve to fail closed.* Turbine load drops to 450 MW. | * A subsequent failure causes #2 Governor Valve to fail closed. | ||
Which one of the following | * Turbine load drops to 450 MW. | ||
Which one of the following completes the statements below? | |||
The #2 governor valve closure results in (1) . | |||
Per SOP-72.0, General Instructions for DEH Operators Console, the operating crew is required to (2) . | |||
A. (1) automatic removal of the IMP Press Loop (2) trip the Main Turbine B. (1) automatic removal of the IMP Press Loop (2) match reactor power with turbine load C. (1) opposed governor valve closure (2) trip the Main Turbine D. (1) opposed governor valve closure (2) match reactor power with turbine load | |||
: 33. Unit 1 is operating at 100% power with the following conditions: | : 33. Unit 1 is operating at 100% power with the following conditions: | ||
AT 1000: | AT 1000: | ||
* 1A Circulating Water Pump Trips. | * 1A Circulating Water Pump Trips. | ||
AT 1005: | AT 1005: | ||
* KK1, TURB COND VAC LO, comes into alarm Which one of the following | * KK1, TURB COND VAC LO, comes into alarm Which one of the following completes the statements below? | ||
(1) is the earliest time AOP-8.0, Partial Loss of Condenser Vacuum, entry is required. | |||
At 100% Reactor power, | At 100% Reactor power, (2) is the lowest condenser pressure a manual Reactor Trip is required. | ||
(1) (2) | |||
A. 1000 3.800 psia B. 1005 3.800 psia C. 1000 2.901 psia D. 1005 2.901 psia | |||
: 34. Unit 1 entered FRP-H.1, Response to Loss of Secondary Heat Sink, with the following conditions: | : 34. Unit 1 entered FRP-H.1, Response to Loss of Secondary Heat Sink, with the following conditions: | ||
Time 1000 1015 1030 1100 1A S/G WR LVL (%) 37.00 28.00 18.00 11.00 1B S/G WR LVL (%) 32.00 20.00 10.00 6.00 1C S/G WR LVL (%) 29.00 19.00 9.00 3.00 CNMT PRESS (PSIG) 1.50 2.00 3.00 4.50 AFW TOTAL FLOW (GPM) 0 0 0 0 Which one of the following is the EARLIEST time that a manual Safety Injection is required due to meeting Bleed and Feed criteria per FRP-H.1? | |||
A. 1000 B. 1015 C. 1030 D. 1100 | |||
: 35. Which one of the following is the purpose of depressurizing all intact SGs during the performance of ECP-0.0, Loss of All AC Power? | : 35. Which one of the following is the purpose of depressurizing all intact SGs during the performance of ECP-0.0, Loss of All AC Power? | ||
Rapidly reduces DP across SG U-tubes to minimize RCS inventory loss from a potential tube rupture. | A. Rapidly reduces DP across SG U-tubes to minimize RCS inventory loss from a potential tube rupture. | ||
Cools RCP seals in a | B. Cools RCP seals in a controlled manner and minimizes loss of RCS inventory. | ||
Maximizes Natural | C. Maximizes Natural Circulation flow before reflux cooling begins as the RCS becomes saturated. | ||
D. Maximizes Natural Circulation flow to allow reactor vessel head to cool since CRDM cooling fans are unavailable. | |||
: 36. Unit 1 is operating at 100% power and the following condition exists: | : 36. Unit 1 is operating at 100% power and the following condition exists: | ||
* Main Condenser Pressure is rising due to a failure of the 1A SJAE. | * Main Condenser Pressure is rising due to a failure of the 1A SJAE. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Main Condenser Hotwell Temperature will initially (1) . | |||
AOP-8.0, Partial Loss of Condenser Vacuum, will direct placing (2) on service. | |||
(1) (2) | |||
A. RISE a Hogger B. LOWER a Hogger C. RISE the 1B SJAE D. LOWER the 1B SJAE | |||
: 37. The following conditions exist: | : 37. The following conditions exist: | ||
* Unit 1 is in MODE 5. | * Unit 1 is in MODE 5. | ||
Line 267: | Line 321: | ||
* 4160V busses 2F, 2K, 2G, and 2L de-energize. | * 4160V busses 2F, 2K, 2G, and 2L de-energize. | ||
* The 1-2A DG Trips and cannot be restored. | * The 1-2A DG Trips and cannot be restored. | ||
Which one of the following | Which one of the following completes the statement below? | ||
: 38. Which one of the following completes the statement below? The Main Turbine exhaust hood sprays use (1) | The first procedure the Unit 1 Operating Crew is required to enter is (1) . | ||
The Operating Crew will restore power to Unit 1 with the (2) . | |||
A. (1) AOP-5.0, Loss of A or B Train Electrical Power (2) 1C DG B. (1) ECP-0.0, Loss of All AC Power (2) 1C DG C. (1) AOP-5.0, Loss of A or B Train Electrical Power (2) 2C DG D. (1) ECP-0.0, Loss of All AC Power (2) 2C DG | |||
: 38. Which one of the following completes the statement below? | |||
The Main Turbine exhaust hood sprays use (1) to automatically prevent excessive temperatures at the exhaust of the LP Turbine (2) 15% Turbine Load. | |||
(1) (2) | |||
A. demin water above B. demin water below C. condensate above D. condensate below | |||
: 39. Unit 1 is operating at 100% power when the following occurs: | : 39. Unit 1 is operating at 100% power when the following occurs: | ||
* The 1C 120 VAC Vital | * The 1C 120 VAC Vital Instrumentation Panel is de-energized. | ||
Which one of the following | Which one of the following completes the statements below? | ||
LCV-459, LTDN LINE ISO, | LCV-459, LTDN LINE ISO, (1) automatically close if a Pressurizer Low Level condition occurs. | ||
LCV-115A (2) immediately divert to the RHT. | |||
: 40. Unit 1 is operating at 8% power and the following conditions occur:* The Battery Input Breaker on the 1B inverter trips. | (1) (2) | ||
A. WILL WILL B. WILL will NOT C. will NOT WILL D. will NOT will NOT | |||
: 40. Unit 1 is operating at 8% power and the following conditions occur: | |||
* The Battery Input Breaker on the 1B inverter trips. | |||
* WD2, 1B INV FAULT, annunciator alarms. | * WD2, 1B INV FAULT, annunciator alarms. | ||
* No Other Annunciators are in Alarm due to the fault. | * No Other Annunciators are in Alarm due to the fault. | ||
Subsequently, the Rover reports the | Subsequently, the Rover reports the following indications from the 1B Inverter. | ||
* INVERTER POWERING LOAD lamp NOT lit. | * INVERTER POWERING LOAD lamp NOT lit. | ||
* BYPASS SOURCE | * BYPASS SOURCE AVAILABLE lamp is LIT. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The 1B 120V Vital AC panel is (1) . | |||
The 1B INVERTER AMPERES meter on the EPB indicates (2) . | |||
A. (1) Energized (2) 0 Amps B. (1) Energized (2) Full Load Amps C. (1) De-energized (2) 0 Amps. When the MANUAL BYPASS SWITCH is taken to BYPASS SOURCE TO LOAD position it will indicate Full Load Amps. | |||
D. (1) De-energized (2) 0 Amps. When the MANUAL BYPASS SWITCH is taken to BYPASS SOURCE TO LOAD position it will continue to indicate 0 Amps. | |||
: 41. Unit 1 is operating at 100% power when the following conditions occur: | : 41. Unit 1 is operating at 100% power when the following conditions occur: | ||
* Annunciator KB4, SGFP SUCT PRESS LO, alarms | * Annunciator KB4, SGFP SUCT PRESS LO, alarms | ||
* PR-4039, SGFP SUCT PRESS, indicates 300 psig and lowering. | * PR-4039, SGFP SUCT PRESS, indicates 300 psig and lowering. | ||
Which one of the following | Which one of the following completes the statement below? | ||
The earliest time the standby condensate pump will start is when . | |||
: 42. A | A. KB4 has been in alarm for 10 seconds B. KB4 has been in alarm for 30 seconds C. SGFP suction pressure has remained below 275 PSIG for 10 seconds D. SGFP suction pressure has remained below 275 PSIG for 30 seconds | ||
: 42. A gas transfer is in progress to the #8 Waste Gas Decay Tank on Unit 1 when the following conditions occur: | |||
* The #8 Waste Gas Decay Tank relief valve lifts. | * The #8 Waste Gas Decay Tank relief valve lifts. | ||
* The relief valve fails to reseat. | * The relief valve fails to reseat. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The relief valve lifting will initially be detected by (1) | The relief valve lifting will initially be detected by (1) . | ||
The release (2) be automatically isolated from the environment if an alarm condition exists. | |||
: 43. Unit 1 is Operating at 100% Reactor Power when the following conditions occur: | (1) (2) | ||
A. R-13, WASTE GAS MONITOR WILL B. R-13, WASTE GAS MONITOR will NOT C. R-14, PLANT VENT MONITOR WILL D. R-14, PLANT VENT MONITOR will NOT | |||
: 43. Unit 1 is Operating at 100% Reactor Power when the following conditions occur: | |||
Time 1000 1005 1010 1015 1A S/G NR LVL (%) 26.00 23.00 21.00 7.00 1B S/G NR LVL (%) 34.00 27.00 25.00 8.00 1C S/G NR LVL (%) 35.00 33.00 31.00 12.00 1A SGFP STATUS Running Running Tripped Tripped 1B SGFP STATUS Running Running Tripped Tripped Which one of the following is the earliest time when all AFW Pumps have recieved an AUTO START signal? | |||
A. 1000 B. 1005 C. 1010 D. 1015 | |||
: 44. Unit 1 is operating at 100% power with the following condition: | : 44. Unit 1 is operating at 100% power with the following condition: | ||
* An LOSP occurs. | * An LOSP occurs. | ||
Which one of the following completes the statements below? | |||
Which one of the following | 10 seconds after power is restored to the 1F 4160V bus: | ||
10 seconds after power is restored to the 1F 4160V bus: | 1A CHG PUMP AMPS will indicate (1) AMPS. | ||
1A MDAFWP AMPS will indicate (2) | 1A MDAFWP AMPS will indicate (2) AMPS. | ||
(1) (2) | |||
A. greater than zero greater than zero B. greater than zero zero C. zero greater than zero D. zero zero | |||
: 45. Unit 1 is operating at 100% power when the following condition occurs: | : 45. Unit 1 is operating at 100% power when the following condition occurs: | ||
* The Reactor Trips | * The Reactor Trips Subsequently, the following indications are displayed continously on the MCB. | ||
* V-515, SW TO TURB BLDG ISO A TRN, RED and GREEN Lights are LIT. | |||
Subsequently, the following indications are displayed continously on the MCB.* V-515, SW TO TURB BLDG ISO A TRN, RED and GREEN Lights are LIT.* V-517, SW TO TURB BLDG ISO B TRN, RED and GREEN Lights are LIT. | * V-517, SW TO TURB BLDG ISO B TRN, RED and GREEN Lights are LIT. | ||
* V-516, SW TO TURB BLDG ISO A TRN, RED and GREEN Lights are LIT.* V-514, SW TO TURB BLDG ISO B TRN, RED and GREEN Lights are LIT. | * V-516, SW TO TURB BLDG ISO A TRN, RED and GREEN Lights are LIT. | ||
Which one of the following | * V-514, SW TO TURB BLDG ISO B TRN, RED and GREEN Lights are LIT. | ||
Which one of the following completes the statement below? | |||
: 46. Which one of the following completes the statements below? The | The valve actuation was initiated by a (1) . | ||
The valve position prevents (2) . | |||
A. (1) Safety Injection (2) damage to turbine building auxiliaries. | |||
: 47. Unit 1 is at 100% power when the following condition occurs in the | B. (1) Loss of Offsite Power (2) complete isolation of SW flow to the Air Compressors C. (1) Safety Injection (2) complete isolation of SW flow to the Air Compressors D. (1) Loss of Offsite Power (2) damage to turbine building auxiliaries. | ||
: 46. Which one of the following completes the statements below? | |||
The (1) RCP(s) can be powered from the 1A Startup Transformer. | |||
The (2) RCP(s) can be powered from the 2B Startup Transformer. | |||
(1) (2) | |||
A. 1A RCP 2A RCP B. 1A RCP 2B and 2C RCPs C. 1B and 1C RCPs 2A RCP D. 1B and 1C RCPs 2B and 2C RCPs | |||
: 47. Unit 1 is at 100% power when the following condition occurs in the Aux Bldg DC distribution system: | |||
* The 125V DC Bus 1B has been de-energized. | * The 125V DC Bus 1B has been de-energized. | ||
Subsequently, an LOSP occurs on Unit 1. | Subsequently, an LOSP occurs on Unit 1. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The 1B DG (1) be started from the EPB. | |||
The B1G Sequencer (2) automatically sequence loads. | |||
: 48. Which one of the following completes | (1) (2) | ||
A. CAN WILL B. CANNOT will NOT C. CANNOT WILL D. CAN will NOT | |||
: 48. Which one of the following completes the statement below for the 1B DG Air Recievers? | |||
The maximum Air Receiver pressure that will cause an alarm on the 1B DG Local Control Panel is (1) . | |||
At the alarm setpoint there is enough air pressure to ensure a maximum of (2) start attempts are available. | |||
(1) (2) | |||
A. 200 psig 3 B. 200 psig 5 C. 350 psig 3 D. 350 psig 5 | |||
: 49. Unit 1 is operating at 100% power when the following conditions occur: | : 49. Unit 1 is operating at 100% power when the following conditions occur: | ||
* MH1, FIRE, annunciator on the Unit 1 Main Control Board (MCB) alarms. * | * MH1, FIRE, annunciator on the Unit 1 Main Control Board (MCB) alarms. | ||
* The Rover reports that the window | * Aux Bldg El 139 W Side Det 1A-39, 43, 46, 53 1A-55, 59, 106", light is lit on the Control Room Fire Panel. | ||
The Control Room Fire Panel alarm must be acknowledged. | * The Rover reports that the window for 1A-59 at the PYR-A-LARM panel is lit. | ||
and | What is (are) the minimum required action(s) to ensure MH1, FIRE, will alarm again if 1A-39 comes into alarm? | ||
The Control Room Fire Panel alarm must be acknowledged. | A. The Control Room Fire Panel alarm must be acknowledged. | ||
and | and 1A-59 must be placed in OVERRIDE on the PYR-A-LARM panel. | ||
ONLY 1A-59 must be placed in OVERRIDE on the PYR-A-LARM panel.ONLY the Reflash Panel alarm for detection system 1A-59 must be acknowledged | B. The Control Room Fire Panel alarm must be acknowledged. | ||
and The Reflash Panel alarm for detection system 1A-59 must be acknowledged. | |||
: 50. AOP-28.0, Control Room | C. ONLY 1A-59 must be placed in OVERRIDE on the PYR-A-LARM panel. | ||
Which one of the following | D. ONLY the Reflash Panel alarm for detection system 1A-59 must be acknowledged. | ||
The 1A MDAFWP will be | : 50. AOP-28.0, Control Room Inaccessibility, is in progress on Unit 1. | ||
Which one of the following completes the statements below? | |||
FCVs in LOCAL at | The 1A MDAFWP will be operated in LOCAL at the (1) HSDP. | ||
Operator action is required to control the MDAFWP FCVs in LOCAL at the HSDP in order to prevent (2) . | |||
: 51. Unit 2 is at 100% power with the following conditions:* A #1 Waste Monitor Tank (WMT) release is in progress with the #1 WMT pump running. | (1) (2) | ||
A. F low SG water level due to valve position B. F isolating letdown due to cooldown C. A low SG water level due to valve position D. A isolating letdown due to cooldown | |||
: 51. Unit 2 is at 100% power with the following conditions: | |||
* A #1 Waste Monitor Tank (WMT) release is in progress with the #1 WMT pump running. | |||
* RCV-18, WMT DISCH TO ENVIRONMENT, is open. | * RCV-18, WMT DISCH TO ENVIRONMENT, is open. | ||
Subsequently R-18, LIQ | Subsequently R-18, LIQ WASTE DISCH, alarms HIGH. | ||
Which one of the following | Which one of the following completes the statements below? | ||
RCV-18 will (1) . | |||
The #1 WMT pump will (2) . | |||
(1) (2) | |||
A. remain open trip B. remain open continue to run C. close trip D. close continue to run | |||
: 52. Unit 1 is operating at 100% power with the following condition: | : 52. Unit 1 is operating at 100% power with the following condition: | ||
* A SG Tube Leak is in progress. | * A SG Tube Leak is in progress. | ||
* FCV-1152, SGBD HX Outlet Flow Control Valve, is stuck in the | * FCV-1152, SGBD HX Outlet Flow Control Valve, is stuck in the OPEN position. | ||
Which one of the following radiation monitors is able to automatically stop a release to the environment due to the SG Tube Rupture? | Which one of the following radiation monitors is able to automatically stop a release to the environment due to the SG Tube Rupture? | ||
R-23A, SGBD SRG TK INLET | A. R-23A, SGBD SRG TK INLET B. R-23B, SGBD SRG TK DISCH C. R-19, SGBD SAMPLE D. R-70A, SG TUBE LEAK DET | ||
R-23B, SGBD SRG TK DISCH R-19, SGBD SAMPLE R-70A, SG TUBE LEAK DET | |||
: 53. Unit 1 is operating at 100% power when the following occurs: | : 53. Unit 1 is operating at 100% power when the following occurs: | ||
* A Large Break LOCA | * A Large Break LOCA occurs inside containment. | ||
* Containment Pressure reaches 35 psig. | * Containment Pressure reaches 35 psig. | ||
Which one of the following | Which one of the following completes the statements below? | ||
MOV-3024A, EMERG SW FROM 1A CTMT CLR, opened due to a(n) | |||
(1) signal. | |||
Each CTMT Cooler will be supplied with approximately (2) GPM of Service Water flow. | |||
(1) (2) | |||
A. Safety Injection 2000 B. Safety Injection 800 C. Containment Spray 2000 D. Containment Spray 800 | |||
: 54. Unit 1 experienced a Safety Injection with LOSP. | : 54. Unit 1 experienced a Safety Injection with LOSP. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The 1A Charging Pump Room Cooler will automatically start due to a signal generated by the 1A Charging Pump (1) . | |||
Controls for starting the Charging Pump Room Coolers (2) located on the BOP Panel. | |||
(1) (2) | |||
A. Breaker ARE B. Breaker are NOT C. Room Thermostat ARE D. Room Thermostat are NOT | |||
: 55. Unit 1 is operating at 100% power with the following conditions: | : 55. Unit 1 is operating at 100% power with the following conditions: | ||
* The Gross Failed Fuel Detector (GFFD) has steadily indicated 2500 cpm | * The Gross Failed Fuel Detector (GFFD) has steadily indicated 2500 cpm during the entire fuel cycle. | ||
Subsequently, the following readings are recorded: | Subsequently, the following readings are recorded: | ||
Time 1000 1100 1200 1300 GFFD Indication (cpm) 1.1 X 104 1.5 X 104 4.4 X 104 1.3 X 105 Which one of the following is the earliest time the GFFD will be in High Alarm? | |||
A. 1000 B. 1100 C. 1200 D. 1300 | |||
: 56. Unit 1 is operating at 100% power with the following conditions: | : 56. Unit 1 is operating at 100% power with the following conditions: | ||
* AOP-5.2, Degraded Grid, has just been entered. | * AOP-5.2, Degraded Grid, has just been entered. | ||
* Voltage on all emergency busses for both units is reading 3875 volts. | * Voltage on all emergency busses for both units is reading 3875 volts. | ||
* MEGAVARS are reading (+) 100 on the MCB. | * MEGAVARS are reading (+) 100 on the MCB. | ||
* The Shift Supervisor has directed the UO to maintain (+) 400 MVARs in | * The Shift Supervisor has directed the UO to maintain (+) 400 MVARs in accordance with the voltage schedule. | ||
* The Unit 2 UO maintains MVARS | * The Unit 2 UO maintains MVARS stable on Unit 2 during the adjustment. | ||
Which one of the following will occur when the Unit 1 UO performs the adjustment as directed by the Shift Supervisor? | Which one of the following will occur when the Unit 1 UO performs the adjustment as directed by the Shift Supervisor? | ||
The operator will (1) | The operator will (1) Voltage, to reach (+) 400 MVARs. | ||
Voltage, to | After adjusting voltage, the temperature of large pump motors, such as the RCP or CW pump motors, will (2) . | ||
(1) (2) | |||
A. raise lower B. raise rise C. lower lower D. lower rise | |||
: 57. Unit 1 was manually tripped from 100% power and the following conditions exist: | : 57. Unit 1 was manually tripped from 100% power and the following conditions exist: | ||
* AOP-6.0, Loss of Instrument Air, is in progress. | * AOP-6.0, Loss of Instrument Air, is in progress. | ||
* The TDAFW pump automatically started. | * The TDAFW pump automatically started. | ||
* BOTH MDAFW pumps failed to start. | * BOTH MDAFW pumps failed to start. | ||
* The MSVR is not accessible | * The MSVR is not accessible. | ||
Subsequently, the following report is received from Mechanical Maintenance: | |||
* Restoration of | * Restoration of Instrument Air will take 3 hours. | ||
Which one of the following describes the required AOP-6.0 operator action(s), if any, and the reason? | Which one of the following describes the required AOP-6.0 operator action(s), if any, and the reason? | ||
No action is required | A. No action is required because the TDAFWP steam admission valves fail to the "as is" position. | ||
Manually close the TDAFWP steam | B. Manually close the TDAFWP steam admission valves to avoid causing an uncontrolled cooldown. | ||
Manually open the TDAFWP steam admission valves to provide an adequate heat sink. | C. Manually open the TDAFWP steam admission valves to provide an adequate heat sink. | ||
Manually align emergency air to the TDAFW | D. Manually align emergency air to the TDAFW pump steam admission valves to provide an adequate heat sink. | ||
: 58. Unit 1 is operating at 100% power when the following occurs: | : 58. Unit 1 is operating at 100% power when the following occurs: | ||
At 1000 | At 1000 | ||
* An Instrument Air malfunction occurs. | * An Instrument Air malfunction occurs. | ||
At 1015 | At 1015 | ||
* PI-4004B, INST AIR PRESS, indicates 50 psig and stable Which one of the following | * PI-4004B, INST AIR PRESS, indicates 50 psig and stable Which one of the following completes the statements below? | ||
At 1015 V904, Instrument Air to the Service Building, is (1) | At 1015 V904, Instrument Air to the Service Building, is (1) . | ||
A(n) (2) maintains MSIV air pressure following loss of instrument air pressure. | |||
(1) (2) | |||
A. OPEN accumulator B. OPEN compressed nitrogen cylinder C. CLOSED accumulator D. CLOSED compressed nitrogen cylinder | |||
: 59. Unit 1 is shutdown following a LOCA with the following conditions: | : 59. Unit 1 is shutdown following a LOCA with the following conditions: | ||
* PI-402A and PI-403A, RCS WR | * PI-402A and PI-403A, RCS WR PRESS, indicate 600 psig and stable. | ||
* PR-950Z, CTMT PRESS, | * PR-950Z, CTMT PRESS, indicates 32 psig and slowly lowering. | ||
Subsequently, ONLY the | Subsequently, ONLY the following actions are taken: | ||
* SI BLOCK RESET A | * SI BLOCK RESET A TRN pushbutton is depressed. | ||
* SI BLOCK RESET B | * SI BLOCK RESET B TRN pushbutton is depressed. | ||
* PHASE B CTMT | * PHASE B CTMT ISO RESET A TRN pushbutton is depressed. | ||
* PHASE B CTMT | * PHASE B CTMT ISO RESET B TRN pushbutton is depressed. | ||
Which one of the following | Which one of the following completes the statements below: | ||
PHASE A CNMT ISO (1) reset. | |||
PHASE B CNMT ISO (2) reset. | |||
(1) (2) | |||
A. IS is NOT B. IS IS C. is NOT is NOT D. is NOT IS | |||
: 60. Unit 1 is operating at 100% power when the following conditions occur: | : 60. Unit 1 is operating at 100% power when the following conditions occur: | ||
* Phase A is actuated using the MCB handswitches. | * Phase A is actuated using the MCB handswitches. | ||
How has the Phase A signal affected the following valve positions? | How has the Phase A signal affected the following valve positions? | ||
Valve Nomenclature | Valve Nomenclature: | ||
HV-8152, LTDN LINE CTMT ISO MOV-8112, RCP SEAL WTR RTN ISO HV-8149A, LTDN ORIF ISO 45 GPM MOV-3052, CCW TO RCP CLRS A. Only HV-8152, HV-8149A, and MOV-8112 have closed. | |||
B. Only HV-8152, MOV-8112, and MOV-3052 have closed. | |||
MOV-8112, RCP SEAL WTR RTN ISO | C. Only HV-8152, and HV-8149A have closed. | ||
D. Only HV-8152 has closed. | |||
HV-8149A, LTDN ORIF ISO 45 GPM | |||
MOV-3052, CCW TO RCP CLRS Only HV-8152, HV-8149A, and MOV-8112 have closed. | |||
Only HV-8152, MOV-8112, and MOV-3052 have closed. | |||
Only HV-8152, and HV-8149A have closed. | |||
Only HV-8152 has closed | |||
: 61. A Main Control Board Deficiency related to a MCB handswitch has been identified. | : 61. A Main Control Board Deficiency related to a MCB handswitch has been identified. | ||
Which one of the following completes | Which one of the following completes the statements below IAW SOP-0.10, FNP Operations Site Specific Policies? | ||
A (1) is required to be created to identify the deficiency. | |||
The identifier (Deficiency Tag/Control Room DOT) will be (2) . | |||
(1) (2) | |||
A. Deficiency Tag affixed to the MCB handswitch B. Deficiency Tag placed in the deficiency notebook C. Control Room DOT affixed to the MCB handswitch D. Control Room DOT placed in the deficiency notebook | |||
: 62. Unit 1 experiences a Reactor Trip with Safety injection. | : 62. Unit 1 experiences a Reactor Trip with Safety injection. | ||
Subsequently, the following occurs: | Subsequently, the following occurs: | ||
* The UO directs the Turbine | * The UO directs the Turbine Building Systems Operator (TB SO) to perform the TB SO Actions Following a Reactor Trip or Safety Injection. | ||
Which one of the following completes the statements below per SOP-0.0, Appendix A, TB SO Actions Following a | Which one of the following completes the statements below per SOP-0.0, Appendix A, TB SO Actions Following a Reactor Trip and/or Safety Injection? | ||
The TB SO is required to close V-503A, 1A MSR 2ND STG STM SUPP ISO (1) . | |||
: 63. Which one of the following completes the statements below per NMP-AP-001-003, Review and | The TB SO is required to close V-905A, 1A MS LINE DRN POT TO COND ISO (2) . | ||
(1) (2) | |||
A. following any Reactor trip following any Reactor trip B. following any Reactor trip only when specifically directed C. only when specifically directed following any Reactor trip D. only when specifically directed only when specifically directed | |||
: 63. Which one of the following completes the statements below per NMP-AP-001-003, Review and Approval of Site Procedures? | |||
The "Pen and Ink" Change Process may be used for (1) changes. | |||
A Condition Report (2) required following use of a procedure with "Pen and Ink" changes. | |||
(1) (2) | |||
A. editorial IS B. editorial is NOT C. temporary IS D. temporary is NOT | |||
: 64. Unit 1 is in a Refueling Outage with fuel being loaded into the core. | : 64. Unit 1 is in a Refueling Outage with fuel being loaded into the core. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Per TRM 13.1.6, Borated | Per TRM 13.1.6, Borated Water Source - Shutdown, the minimum operable BAT Tank Temperature is (1) . | ||
Per TRM 13.1.6, the minimum operable BAT Tank Volume is (2) . | |||
: 65. Unit 1 is exiting a refueling outage with the following conditions: | (1) (2) | ||
A. 35°F 2000 gallons B. 35°F 11336 gallons C. 65°F 2000 gallons D. 65°F 11336 gallons | |||
: 65. Unit 1 is exiting a refueling outage with the following conditions: | |||
Time 1000 1200 1400 1600 Average Coolant Temp (°F) 300 450 547 547 Rated Thermal Power (%) 0 0 2 6 Keff <.99 <.99 1.00 1.00 Which one of the following completes the statements below? | |||
The earliest time Unit 1 is in MODE 4 is at (1) . | |||
The earliest time Unit 1 is in MODE 1 is at (2) . | |||
(1) (2) | |||
A. 1000 1400 B. 1000 1600 C. 1200 1400 D. 1200 1600 | |||
: 66. A Plant Operator has been assigned a portable RAM 100 frisker for personnel monitoring when exiting the dry cask storage area with the following condition: | : 66. A Plant Operator has been assigned a portable RAM 100 frisker for personnel monitoring when exiting the dry cask storage area with the following condition: | ||
* The Frisker Response Checks were last performed 7 days ago. | * The Frisker Response Checks were last performed 7 days ago. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The frisker detects (1) . | |||
The Frisker Response Checks for the assigned frisker are required to be performed (2) . | |||
A. (1) Beta and Gamma radiation (2) prior to use B. (1) Beta and Gamma radiation (2) 6 months from the date of the last response check C. (1) ONLY Gamma radiation (2) prior to use D. (1) ONLY Gamma radiation (2) 6 months from the date of the last response check | |||
: 67. You are assigned a task: | : 67. You are assigned a task: | ||
* Your current TEDE is 1500 mrem. | * Your current TEDE is 1500 mrem. | ||
* Dose rate in the area you | * Dose rate in the area you are required to work is 1500 mr/hr. | ||
Which one of the following is the maximum amount of time you can stay in the area without exceeding Farley Administrative TEDE limits with no additional approval? | Which one of the following is the maximum amount of time you can stay in the area without exceeding Farley Administrative TEDE limits with no additional approval? | ||
20 minutes 100 minutes 120 minutes 140 minutes | A. 20 minutes B. 100 minutes C. 120 minutes D. 140 minutes | ||
: 68. EEP-0.0, Reactor Trip or Safety Injection, provides specific Reactor Coolant Pump (RCP) trip criteria on the foldout page. | : 68. EEP-0.0, Reactor Trip or Safety Injection, provides specific Reactor Coolant Pump (RCP) trip criteria on the foldout page. | ||
Which one of the following is the reason | Which one of the following is the reason for tripping the RCPs when these conditions occur? | ||
Prevents RCP seal damage | A. Conserves RCS inventory during a Small Break LOCA with subsequent LOSP. | ||
Prevents pump runout | B. Prevents RCP seal damage following a Small Break LOCA. | ||
Ensures core reflood | C. Prevents pump runout following a Large Break LOCA. | ||
D. Ensures core reflood following a Large Break LOCA. | |||
: 69. Unit 1 and Unit 2 are operating at 100% power when the following condition occurs:* | : 69. Unit 1 and Unit 2 are operating at 100% power when the following condition occurs: | ||
Which one of the following | * The Outside System Operator reports a fire in the Liquid hydrogen storage tank vent stack. | ||
Which one of the following completes the statement below? | |||
discharging a portable fire | Per AOP-29.0, Plant Fire, and SOP-34.0, Hydrogen-Oxygen System the fire will be extinguished by . | ||
establishing a helium purge and isolating the leak. | A. spraying water directly on the vent stack and isolating the leak. | ||
isolating the leak ONLY | B. discharging a portable fire extinguisher into the vent stack and isolating the leak. | ||
C. establishing a helium purge and isolating the leak. | |||
D. isolating the leak ONLY. | |||
: 70. The following condition exist on Unit 1: | : 70. The following condition exist on Unit 1: | ||
* The TSC is fully manned and is | * The TSC is fully manned and is directing the plant response to a NOUE. | ||
Subsequently, the following occurs: | Subsequently, the following occurs: | ||
* The Emergency Director declares a SITE AREA EMERGENCY. | * The Emergency Director declares a SITE AREA EMERGENCY. | ||
Which one of the following completes the statements below? | |||
Which one of the following | Per NMP-EP-111, Emergency Notifications, a (1) tone will be sounded prior to the onsite notification announcement. | ||
Per NMP-EP-111, Emergency Notifications, the (2) | Per NMP-EP-111, Emergency Notifications, the (2) is responsible for approving notifcations to State and Local Authorities of the emergency condition. | ||
(1) (2) | |||
A. YELP Emergency Director B. WARBLE Emergency Director C. YELP Shift Manager D. WARBLE Shift Manager | |||
: 71. An RCS soak is in progress per FRP-P.1, Response to Imminent Pressurized Thermal Shock Condition, on Unit 1. | : 71. An RCS soak is in progress per FRP-P.1, Response to Imminent Pressurized Thermal Shock Condition, on Unit 1. | ||
Which one of the following actions is permitted? | Which one of the following actions is permitted? | ||
Start a Charging Pump. | A. Start a Charging Pump. | ||
B. Energize PZR heaters. | |||
Energize PZR heaters. | C. Start an RCP. | ||
Start an RCP. | D. Isolate Accumulators. | ||
Isolate Accumulators | |||
: 72. Unit 1 is shutdown following a Large Break LOCA followed by an LOSP. The following conditions occur: | : 72. Unit 1 is shutdown following a Large Break LOCA followed by an LOSP. The following conditions occur: | ||
At 1000: | At 1000: | ||
* WA2, 1-2A DG GEN FAULT TRIP, alarms. | * WA2, 1-2A DG GEN FAULT TRIP, alarms. | ||
At 1015:* CF3, 1A OR 1B RHR PUMP OVERLOAD TRIP, alarms. | At 1015: | ||
* RWST level is 3 ft.* Containment Spray pump | * CF3, 1A OR 1B RHR PUMP OVERLOAD TRIP, alarms. | ||
Which one of the following | * RWST level is 3 ft. | ||
At 1015 (1) | * Containment Spray pump suctions are aligned to the RWST. | ||
Which one of the following completes the statements below? | |||
: 73. Unit 1 is shutdown with ECP-2.1, Uncontrolled Depressurization of All Steam Generators in progress. | At 1015 (1) train(s) of emergency coolant recirculation capability has(have) been lost. | ||
* All MSIV - TRIP | The operating crew (2) required to secure all CTMT Spray at 1015. | ||
(1) (2) | |||
A. ONLY one IS B. ONLY one is NOT C. BOTH IS D. BOTH is NOT | |||
: 73. Unit 1 is shutdown with ECP-2.1, Uncontrolled Depressurization of All Steam Generators in progress. The following conditions exist: | |||
* All MSIV - TRIP handswitches have been taken to CLOSE. | |||
* JH1, 1A SG MSIV CLOSED is NOT lit. | * JH1, 1A SG MSIV CLOSED is NOT lit. | ||
* JH2, 1B SG MSIV CLOSED is NOT lit. | * JH2, 1B SG MSIV CLOSED is NOT lit. | ||
* JH3, 1C SG MSIV CLOSED is NOT lit. | * JH3, 1C SG MSIV CLOSED is NOT lit. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The next action the crew is required to take per ECP-2.1 is (1) . | |||
If an MSIV is closed, ECP-2.1 directs use of (2) to determine if a Steam Generator has been isolated. | |||
A. (1) Place the MSIV -TEST handswitch to TEST (2) Cold Leg Temperature B. (1) Place the MSIV - TEST handswitch to TEST (2) SG Pressure C. (1) Manually remove air pressure from the MSIVs (2) Cold Leg Temperature D. (1) Manually remove air pressure from the MSIVs (2) SG Pressure | |||
: 74. Unit 1 is shutdown with the following conditions: | : 74. Unit 1 is shutdown with the following conditions: | ||
* 1A SG Pressure is 1145 psig and rising. | * 1A SG Pressure is 1145 psig and rising. | ||
* The 1A Atmospheric Relief Valve is mechanically bound and | * The 1A Atmospheric Relief Valve is mechanically bound and cannot be opened. | ||
* All MSIV and MSIV Bypasses are closed. | * All MSIV and MSIV Bypasses are closed. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Entry conditions for FRP-H.2, Response to Steam Generator Overpressure (1) been met When FRP-H.2 is entered, the crew would be directed to lower 1A SG Pressure by (2) . | |||
(1) (2) | |||
A. have NOT dumping steam to the TDAFWP B. HAVE dumping steam to the TDAFWP C. have NOT opening MSIV bypasses D. HAVE opening MSIV bypasses | |||
: 75. Unit 1 has experienced a Large Break LOCA with the following conditions: | : 75. Unit 1 has experienced a Large Break LOCA with the following conditions: | ||
* PR-0950Z, CTMT PRESS NR, indicates 30 psig. | * PR-0950Z, CTMT PRESS NR, indicates 30 psig. | ||
* LI-3594A, CTMT SUMP LVL, indicates 8 FT. | * LI-3594A, CTMT SUMP LVL, indicates 8 FT. | ||
* FI-958 A and B, CS FLOW , indicate 1200 GPM each. | * FI-958 A and B, CS FLOW, indicate 1200 GPM each. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Per CSF-0.5, Containment, the crew is required to enter a(n) (1) path FRP due to (2) . | |||
(1) (2) | |||
A. RED CTMT Pressure B. RED CTMT Sump Level C. ORANGE CTMT Pressure D. ORANGE CTMT Sump Level | |||
: 76. Unit 1 was operating at 100% power when the following occurred: | : 76. Unit 1 was operating at 100% power when the following occurred: | ||
At 1000: | At 1000: | ||
* All Control Banks are at 231 steps. | * All Control Banks are at 231 steps. | ||
At 1010:* Rod K4 fell to 130 steps.* Rod M6 fell to 150 steps. | At 1010: | ||
* Rod K4 fell to 130 steps. | |||
* Rod M6 fell to 150 steps. | |||
* RCS Tavg lowered. | * RCS Tavg lowered. | ||
* Pressurizer pressure lowered. | * Pressurizer pressure lowered. | ||
Which one of the following | Which one of the following completes the statement below? | ||
Per AOP-19, Malfunction of Rod Control System, the operating crew is required to | Per AOP-19, Malfunction of Rod Control System, the operating crew is required to . | ||
A. shutdown the unit using UOP-3.1, Power Operation B. trip the Reactor and go to EEP-0.0, Reactor Trip and Safety Injection C. reduce power to less than 75% within 1 hour using UOP-3.1, Power Operation D. address restoration of rods using SOP-41.0, Control Rod Drive and Position Indication System | |||
: 77. Unit 1 is operating at 100% power when the following occurs: | : 77. Unit 1 is operating at 100% power when the following occurs: | ||
At 1000: | At 1000: | ||
* HH4, RCP VIB TRBL (WHITE | * HH4, RCP VIB TRBL (WHITE annunciator window), comes into alarm. | ||
* 1A RCP shaft vibration is reported as 21 mils and stable. | * 1A RCP shaft vibration is reported as 21 mils and stable. | ||
* DC2, RCP #1 SEAL LKOF FLOW HI (YELLOW annunciator window), | * DC2, RCP #1 SEAL LKOF FLOW HI (YELLOW annunciator window), | ||
* FR145A, | comes into alarm. | ||
* FR145A, RCP SEAL LKOF HIGH RANGE, for the 1A RCP indicates 6.5 gpm and stable. | |||
At 1600: | At 1600: | ||
* The Unit is in MODE 3. | * The Unit is in MODE 3. | ||
Line 523: | Line 637: | ||
* 1B and 1C RCPs are running. | * 1B and 1C RCPs are running. | ||
* 1A RCP is tagged out. | * 1A RCP is tagged out. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1000 , the operating crew is required to (1) | At 1000, the operating crew is required to (1) , then secure the 1A RCP. | ||
At 1600 , RCS pressure control is via (2) | At 1600, RCS pressure control is via (2) . | ||
A. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Normal Spray B. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Normal Spray C. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Auxiliary Spray D. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Auxiliary Spray | |||
: 78. Unit 1 is operating at 100% power when the following occurs: | : 78. Unit 1 is operating at 100% power when the following occurs: | ||
* Due to a Pressurizer pressure | * Due to a Pressurizer pressure control malfunction, PCV-445A, PRZR PORV opens and reseats several times. | ||
* PRT parameters are: | * PRT parameters are: | ||
- Level: 84% and is stable. | |||
- Temperature: 180°F and stable. | |||
- Pressure: 30 psig and stable. | |||
Which one of the following | Which one of the following completes the statements below? | ||
Draining the PRT using the RCDT pump per | HE4, PRT LVL HI-LO, (1) in alarm. | ||
Procedure name | Draining the PRT using the RCDT pump per Section 4.3, Filling and Draining the PRT, of SOP-1.2 (2) restore all PRT parameters to within normal log specifications. | ||
: SOP-1.2, Reactor Coolant Pressure Relief System (1) | Procedure name: SOP-1.2, Reactor Coolant Pressure Relief System (1) (2) | ||
A. is NOT will NOT B. IS will NOT C. is NOT WILL D. IS WILL | |||
: 79. Unit 1 is in MODE 3 with the following conditions: | : 79. Unit 1 is in MODE 3 with the following conditions: | ||
At 1000: | At 1000: | ||
Line 542: | Line 657: | ||
At 1005: | At 1005: | ||
* A complete loss of offsite power occurs. | * A complete loss of offsite power occurs. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1005, manual action (1) | At 1005, manual action (1) required to generate a P-4 signal. | ||
Per the BASES of Tech Spec 3.3.2, ESFAS | Per the BASES of Tech Spec 3.3.2, ESFAS Instrumentation, P-4 is required to be OPERABLE to prevent (2) . | ||
: 80. Unit 1 is operating at 100% power with the following conditions:* A malfunction occurred | A. (1) IS (2) excessive Containment pressure due to a steamline break B. (1) is NOT (2) excessive Containment pressure due to a steamline break C. (1) IS (2) damage to the Main Steam lines and SG safeties due to SG overfill D. (1) is NOT (2) damage to the Main Steam lines and SG safeties due to SG overfill | ||
* PRT pressure, level and temperature are stable.* HA4, PRZR SAFETY VLV TEMP HI, is in alarm.* HA5, PRZR PORV TEMP HI, is in alarm. | : 80. Unit 1 is operating at 100% power with the following conditions: | ||
* A malfunction occurred resulting in PCV-444B, PRZR PORV, opening. | |||
Subsequently, the immediate operator actions of AOP-100, Instrumentation Malfunction, were performed and the following conditions exist: | |||
* PCV-444B GREEN light is LIT. | |||
* MOV-8000B, PRZR PORV ISO, RED light is LIT. | |||
* RCS pressure is 2180 psig and stable. | |||
* PRT pressure, level and temperature are stable. | |||
* HA4, PRZR SAFETY VLV TEMP HI, is in alarm. | |||
* HA5, PRZR PORV TEMP HI, is in alarm. | |||
* HD1, PRZR PRESS REL VLV 445A OR B/U HTRS ON, is in alarm. | * HD1, PRZR PRESS REL VLV 445A OR B/U HTRS ON, is in alarm. | ||
Which one of the following | Which one of the following completes the statements below? | ||
PCV-444B | PCV-444B (1) leaking by. | ||
Per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), PCV-444B (2) | Per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), PCV-444B (2) OPERABLE. | ||
(1) (2) | |||
A. IS IS B. IS is NOT C. is NOT IS D. is NOT is NOT | |||
: 81. Unit 1 is at 100% power with the following conditions: | : 81. Unit 1 is at 100% power with the following conditions: | ||
* PT-950, CTMT PRESS (Channel 1), was | * PT-950, CTMT PRESS (Channel 1), was declared INOPERABLE. | ||
* PT-950 bistables were positioned as required by Tech Spec 3.3.2, | * PT-950 bistables were positioned as required by Tech Spec 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, for continuous operation with an inoperable channel. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Per Tech Spec 3.3.2, the | The Safety Injection function (1) affected by the PT-950 malfunction. | ||
Per Tech Spec 3.3.2, the REQUIRED ACTION is to place the PT-950 bistables in (2) . | |||
(1) (2) | |||
A. IS TRIP B. IS BYPASS C. is NOT TRIP D. is NOT BYPASS | |||
: 82. Unit 1 is in MODE 3 with the following conditions: | : 82. Unit 1 is in MODE 3 with the following conditions: | ||
* All RCPs are running. | * All RCPs are running. | ||
* A CCW leak occurs on the 1A RCP Oil Cooler inlet connection. | * A CCW leak occurs on the 1A RCP Oil Cooler inlet connection. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The method used in the Main Control Room (MCR) to isolate the CCW leak is to (1) | The method used in the Main Control Room (MCR) to isolate the CCW leak is to (1) . | ||
Per the BASES of Tech Spec 3.7.7 - CCW System, once the CCW leak is isolated from the MCR, the CCW System is (2) . | |||
A. (1) isolate CCW to ALL RCPs (2) INOPERABLE B. (1) isolate CCW to the 1A RCP ONLY (2) INOPERABLE C. (1) isolate CCW to ALL RCPs (2) OPERABLE D. (1) isolate CCW to the 1A RCP ONLY (2) OPERABLE | |||
: 83. Unit 1 has experienced a LOCA. The following conditions exist: | : 83. Unit 1 has experienced a LOCA. The following conditions exist: | ||
* EEP-1.0, Loss of Reactor or Secondary Coolant, is in progress. | * EEP-1.0, Loss of Reactor or Secondary Coolant, is in progress. | ||
* Containment Hydrogen is 6% | * Containment Hydrogen is 6% by volume of dry air. | ||
by volume of dry air. | Which one of the following completes the statements below? | ||
Which one of the following | The hydrogen concentration (1) exceed the lower FLAMMABILITY limit. | ||
The hydrogen concentration (1) | Hydrogen concentration will be lowered using (2) . | ||
: 84. Unit 1 is operating at 100% | A. (1) DOES (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System B. (1) DOES (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation C. (1) does NOT (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System D. (1) does NOT (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation | ||
: 84. Unit 1 is operating at 100% when a Pressurizer level control malfunction occurs and the following conditions exist: | |||
* Pressurizer level is 70% and rising. | * Pressurizer level is 70% and rising. | ||
* Charging flow is 120 gpm. | * Charging flow is 120 gpm. | ||
Line 576: | Line 704: | ||
* RCP seal injection is 8 gpm to each RCP. | * RCP seal injection is 8 gpm to each RCP. | ||
* RCP seal leakoff is 3 gpm per pump. | * RCP seal leakoff is 3 gpm per pump. | ||
* Actions in the field are being taken to regain | * Actions in the field are being taken to regain control of Charging. | ||
* It will take 8 minutes to regain control of Charging. | * It will take 8 minutes to regain control of Charging. | ||
Which one of the following | Which one of the following completes the statements below? | ||
An | An automatic reactor trip (1) occur before control of Charging is regained. | ||
Per the BASES of Tech Spec 3.3. | Per the BASES of Tech Spec 3.3.1, Reactor Trip System (RTS) | ||
1, Reactor Trip System (RTS) | Instrumentation, the purpose of the automatic Reactor Trip on Pressurizer Water Level - High is to (2) . | ||
Instrumentation, the purpose of the | Reference Provided A. (1) WILL (2) provide protection against water relief through the PORV's B. (1) WILL (2) prevent thermal shock of the Spray Nozzle C. (1) will NOT (2) provide protection against water relief through the PORV's D. (1) will NOT (2) prevent thermal shock of the Spray Nozzle | ||
: 85. Unit 1 is conducting a fuel reload and the following occurs: | : 85. Unit 1 is conducting a fuel reload and the following occurs: | ||
At 1015: An Intermediate Leg leak is in progress on the 1A RCS loop with the following conditions. | At 1015: An Intermediate Leg leak is in progress on the 1A RCS loop with the following conditions. | ||
Line 588: | Line 716: | ||
* EH2, SFP LVL HI-LO is in alarm. | * EH2, SFP LVL HI-LO is in alarm. | ||
* Both RHR pumps have been secured due to cavitation. | * Both RHR pumps have been secured due to cavitation. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1030 , an emergency classification , per NMP-EP-110, Emergency Classification | At 1030, an emergency classification, per NMP-EP-110, Emergency Classification Determination and Initial Action, (1) required. | ||
Per AOP-12, Residual Heat | Per AOP-12, Residual Heat Removal System Malfunction, the maximum time to complete Containment closure is (2) hour(s). | ||
(1) (2) | |||
A. IS 1 B. IS 2 C. is NOT 1 D. is NOT 2 | |||
: 86. A fuel shuffle is in progress in the Unit 1 SFP with the following conditions: | : 86. A fuel shuffle is in progress in the Unit 1 SFP with the following conditions: | ||
At 1000: | At 1000: | ||
* An 1800 lb. load is | * An 1800 lb. load is being moved over spent fuel. | ||
At 1015: | At 1015: | ||
* The load is dropped causing damage to the spent fuel. | * The load is dropped causing damage to the spent fuel. | ||
At 1015 , which one of the | At 1015, which one of the following describes the minimum Radiation Monitor(s) required to be in alarm to meet AOP-30, Refueling Accident, entry conditions? | ||
AND Which one of the following describes the the expected worst case consequences of dropping an 1800 lb. | AND Which one of the following describes the the expected worst case consequences of dropping an 1800 lb. load onto the spent fuel Per the Bases of TR 13.9.4, Crane Travel-Spent Fuel Storage Building? | ||
A. | |||
* R-5 OR R-25A | |||
* The activity release will be limited to that contained in a single fuel assembly. | |||
B. | |||
* R-5 OR R-25A | |||
* The offsite dose may be as high as but not more than the 10 CFR 100 limit. | |||
C. | |||
* R-5 AND R-25A | |||
* The activity release will be limited to that contained in a single fuel assembly. | |||
D. | |||
* R-5 AND R-25A | |||
* The offsite dose may be as high as but not more than the 10 CFR 100 limit. | |||
: 87. Unit 1 was operating at 100% power with the following conditions: | : 87. Unit 1 was operating at 100% power with the following conditions: | ||
At 1000: | At 1000: A Loss of Offsite Power occurs. | ||
At 1015: | At 1015: The following conditions exist - | ||
* DG-02, | * DG-02, 1G 4160 V bus tie to 1L 4160 V bus, has AMBER and GREEN Lights LIT. | ||
* 4160V BUS 1L AC PWR AVAIL lights are NOT lit. | * 4160V BUS 1L AC PWR AVAIL lights are NOT lit. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1015: The 1B DG (1) | At 1015: The 1B DG (1) have cooling water supplied. | ||
At 1015: The REQUIRED ACTION(S) of | At 1015: The REQUIRED ACTION(S) of Tech Spec(s) (2) is(are) required to be performed. | ||
Tech Spec nomenclature: 3.8.9, Distribution Systems - Operating 3.7.8, Service Water System (SWS) | |||
Tech Spec(s) | (1) (2) | ||
A. WILL 3.8.9 AND 3.7.8 B. will NOT 3.8.9 AND 3.7.8 C. WILL 3.8.9 ONLY D. will NOT 3.8.9 ONLY | |||
: 88. Unit 1 is in Mode 3 with the following conditions: | : 88. Unit 1 is in Mode 3 with the following conditions: | ||
* Pressurizer level is 22% and stable. | * Pressurizer level is 22% and stable. | ||
Subsequently, a rupture occurs on the Instrument Air header piping in the MSVR and AOP-6.0, Loss of Instrument Air, is in progress. | |||
Subsequently, a rupture occurs on the | Which one of the following completes the statements below? | ||
Which one of the following | Pressurizer level will (1) . | ||
Procedure Names | Per AOP-6.0, to maintain Pressurizer level, the operating crew is required to perform actions of (2) in conjunction with AOP-6.0. | ||
: AOP-16.0, CVCS Malfunction | Procedure Names: AOP-16.0, CVCS Malfunction SOP-2.1, CVCS Plant Startup and Operation (1) (2) | ||
A. lower AOP-16.0 B. rise AOP-16.0 C. lower SOP-2.1 D. rise SOP-2.1 | |||
: 89. Unit 1 is operating at 100% power when the following occurs: | : 89. Unit 1 is operating at 100% power when the following occurs: | ||
* R-27B, CTMT HIGH RANGE, is tagged out. | * R-27B, CTMT HIGH RANGE, is tagged out. | ||
* The instrument power supply fuse to R-27A, CTMT HIGH RANGE, blows. | * The instrument power supply fuse to R-27A, CTMT HIGH RANGE, blows. | ||
Which one of the following | Which one of the following completes the statements below? | ||
R-27A indication will fail (1) | R-27A indication will fail (1) . | ||
Per Tech Spec 3.3.3, Post Accident Monitoring Instrumentation, the REQUIRED ACTION is to (2) . | |||
Reference Provided A. (1) HIGH (2) immediately initiate action in accordance with Specification 5.6.8 B. (1) HIGH (2) restore R-27A OR R-27B to OPERABLE status in 7 days C. (1) LOW (2) immediately initiate action in accordance with Specification 5.6.8 D. (1) LOW (2) restore R-27A OR R-27B to OPERABLE status in 7 days | |||
: 90. Unit 1 is operating at 100% power and the following occurs: | : 90. Unit 1 is operating at 100% power and the following occurs: | ||
* R-15A, SJAE EXH, power supply | * R-15A, SJAE EXH, power supply becomes erratic causing its indication to become unreliable but it does not alarm. | ||
No actions are required. | Per the ODCM, which one of the following actions are required to continue the release via this pathway, if any? | ||
Continuously collect samples using auxiliary equipment. | A. No actions are required. | ||
Place SJAE filtration in service until R-15A is restored to operable. | B. Continuously collect samples using auxiliary equipment. | ||
Perform grab samples at least once per 8 hours and analyze them within 24 hours | C. Place SJAE filtration in service until R-15A is restored to operable. | ||
D. Perform grab samples at least once per 8 hours and analyze them within 24 hours. | |||
: 91. Unit 1 is in MODE 6 with the following conditions: | : 91. Unit 1 is in MODE 6 with the following conditions: | ||
* Core reload is complete. | * Core reload is complete. | ||
* Control Rod Drive Shaft Latching and RCCA Drag Testing is about to begin per | * Control Rod Drive Shaft Latching and RCCA Drag Testing is about to begin per FHP-5.1, Control Rod Drive Shaft Latching/Unlatching Tool Operating Instruction. | ||
Which one of the following | Which one of the following completes the statements below? | ||
(1) is required to be in Containment(2) are NOT (1) is required to be in Containment (2) ARE (1) may be in the Control Room in direct | Per FHP-0.0, Refueling Organization, the Fuel Handling Supervisor (1) . | ||
: 92. A tagout is required to be cleared during night shift and the Work Document Holder is not | Per UOP-4.1, Controlling Procedure for Refueling, two Source Range Nuclear Instruments (2) required to be OPERABLE. | ||
Per NMP-AD-003, Equipment Clearance and Tagging, which one of the following can sign off | A. (1) is required to be in Containment (2) are NOT B. (1) is required to be in Containment (2) ARE C. (1) may be in the Control Room in direct Communication with Containment (2) are NOT D. (1) may be in the Control Room in direct Communication with Containment (2) ARE | ||
Shift Manager Operations Director Maintenance Director Maintenance Manager | : 92. A tagout is required to be cleared during night shift and the Work Document Holder is not on site and cannot be contacted to gain their approval. | ||
Per NMP-AD-003, Equipment Clearance and Tagging, which one of the following can sign off the Work Document Holder? | |||
A. Shift Manager B. Operations Director C. Maintenance Director D. Maintenance Manager | |||
: 93. Unit 1 is at 6% power with the following conditions: | : 93. Unit 1 is at 6% power with the following conditions: | ||
* The 1A SGFP has been started. | * The 1A SGFP has been started. | ||
Line 646: | Line 788: | ||
* The Main Feed Regulating Valves are closed. | * The Main Feed Regulating Valves are closed. | ||
At 1000 on January 1, 2015: | At 1000 on January 1, 2015: | ||
* MOV-3232B, MAIN FW TO 1B SG | * MOV-3232B, MAIN FW TO 1B SG STOP VLV , is declared INOPERABLE. | ||
At 1200 on January 1, 2015 | At 1200 on January 1, 2015: | ||
: | |||
* FCV-489, 1B SG FW BYP FLOW, is declared INOPERABLE. | * FCV-489, 1B SG FW BYP FLOW, is declared INOPERABLE. | ||
Subsequently it is determined that | Subsequently it is determined that repairs will take 96 hours for each valve. | ||
Which one of the following | Which one of the following completes the statement below? | ||
Per Tech Spec 3.7.3, Main Feedwater | Per Tech Spec 3.7.3, Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves, the earliest time that feed flow to the 1B SG must be isolated is . | ||
Reference Provided A. 1800 on January 1, 2015 B. 2000 on January 1, 2015 C. 1000 on January 4, 2015 D. 1200 on January 4, 2015 | |||
: 94. A General Emergency on Unit 1 has been declared with following conditions: | : 94. A General Emergency on Unit 1 has been declared with following conditions: | ||
* An Emergency Response Team is required to be dispatched to isolate an | * An Emergency Response Team is required to be dispatched to isolate an offsite release source. | ||
* The TSC has not yet been manned. | * The TSC has not yet been manned. | ||
* The expected exposure for the job is 35 REM TEDE per person. | * The expected exposure for the job is 35 REM TEDE per person. | ||
Which one of the following | Which one of the following completes the statements below? | ||
To receive the dose listed above, operators (1) | To receive the dose listed above, operators (1) required to be volunteers. | ||
The (2) will authorize the exposure. | |||
(1) (2) | |||
A. are NOT RP Supervisor B. are NOT Shift Manager C. ARE RP Supervisor D. ARE Shift Manager | |||
: 95. Unit 1 is in MODE 6 with core offload in progress with the following condition: | : 95. Unit 1 is in MODE 6 with core offload in progress with the following condition: | ||
* A spent fuel assembly is being moved from its assigned location in the core to | * A spent fuel assembly is being moved from its assigned location in the core to the upender. | ||
Subsequently, AOP-30.0, | Subsequently, AOP-30.0, Refueling Accident, is entered Which one of the following completes the statements below? | ||
Per AOP-30.0, the Refueling SRO will direct the fuel assembly to be (1) | Per AOP-30.0, the Refueling SRO will direct the fuel assembly to be (1) . | ||
Per the BASES of Tech Spec 3.9.6, Refueling Cavity Water Level, 23 ft of water is required to be maintained above the fuel to (2) . | |||
A. (1) placed in any empty fuel location in the core (2) provide back up decay heat removal B. (1) placed in any empty fuel location in the core (2) retain iodine fission product activity in the water during a fuel handling accident C. (1) returned to its assigned location in the core (2) provide back up decay heat removal D. (1) returned to its assigned location in the core (2) retain iodine fission product activity in the water during a fuel handling accident | |||
: 96. Unit 2 reactor startup is in progress and the following conditions exist: | : 96. Unit 2 reactor startup is in progress and the following conditions exist: | ||
* NI31, SR1 COUNT RATE is | * NI31, SR1 COUNT RATE is 106 cps and stable. | ||
* NI32, SR2 COUNT RATE is | * NI32, SR2 COUNT RATE is 104 cps and stable. | ||
* TSLB-3 1-1, SR HI Q NC-31D is lit. | * TSLB-3 1-1, SR HI Q NC-31D is lit. | ||
* TSLB-3 1-2, SR HI Q NC-32D is NOT lit. | * TSLB-3 1-2, SR HI Q NC-32D is NOT lit. | ||
* GA1, SR HI FLUX TRIP, is in alarm. | * GA1, SR HI FLUX TRIP, is in alarm. | ||
* The Reactor Trip breakers are closed.Subsequently, The Shift Supervisor directs a manual Reactor trip. | * The Reactor Trip breakers are closed. | ||
* The | Subsequently, The Shift Supervisor directs a manual Reactor trip. | ||
* The Reactor Trip breakers open. | |||
Which one of the following completes the statements below? | |||
: 97. Unit 1 is performing the actions of EEP-0.0, Reactor Trip or Safety Injection, and AOP-9, Loss of Component Cooling | An emergency classification threshold value (1) been exceeded per NMP-EP-110-GL01, FNP EALS - ICs, Threshold Values And Basis. | ||
The latest time the NRC can be notified is (2) hour(s) after the event / emergency declaration. | |||
(1) (2) | |||
A. has NOT 4 B. HAS 4 C. has NOT 1 D. HAS 1 | |||
: 97. Unit 1 is performing the actions of EEP-0.0, Reactor Trip or Safety Injection, and AOP-9, Loss of Component Cooling Water. Conditions are as follows: | |||
* 1F 4160V bus is de-energized. | * 1F 4160V bus is de-energized. | ||
* B Train CCW is the | * B Train CCW is the on service Train. | ||
* 1B CCW pump is Tagged Out. | * 1B CCW pump is Tagged Out. | ||
* 1A CCW pump tripped. | * 1A CCW pump tripped. | ||
* 1C CHG PUMP is running. | * 1C CHG PUMP is running. | ||
Subsequently, the Shift | Subsequently, the Shift Supervisor determines that Firewater is required to be aligned to the 1B Charging pump. | ||
Which one of the following completes the statements below? | |||
The 1C Charging pump will be (1) while aligning Firewater to the 1B Charging pump. | |||
(2) Charging pump CCW oil cooler piping will become chemically contaminated. | |||
(1) (2) | |||
A. secured ONLY the 1B B. secured BOTH 1B and 1C C. maintained running ONLY the 1B D. maintained running BOTH 1B and 1C | |||
: 98. Unit 1 operating crew has exited EEP-0.0, Reactor Trip or Safety Injection, and is now performing ECP-1.2, LOCA Outside Containment with the following conditions: | : 98. Unit 1 operating crew has exited EEP-0.0, Reactor Trip or Safety Injection, and is now performing ECP-1.2, LOCA Outside Containment with the following conditions: | ||
* The leak isolation steps are completed. | * The leak isolation steps are completed. | ||
* RWST level is 12.5 ft. | * RWST level is 12.5 ft. | ||
* RCS pressure continues to lower. | * RCS pressure continues to lower. | ||
Which one of the following | Which one of the following completes the statement below? | ||
The next procedure the operating crew is required to transition to is . | |||
A. EEP-0.0, Reactor Trip or Safety Injection B. ESP-1.3, Transfer to Cold Leg Recirculation C. EEP-1.0, Loss of Reactor or Secondary Coolant D. ECP-1.1, Loss of Emergency Coolant Recirculation | |||
: 99. Unit 2 is performing the actions of FRP-H.1, Response to Loss of Secondary Heat Sink, and the following conditions exist: | : 99. Unit 2 is performing the actions of FRP-H.1, Response to Loss of Secondary Heat Sink, and the following conditions exist: | ||
* The TDAFW pump has been returned to service. | * The TDAFW pump has been returned to service. | ||
* Containment pressure is 0 psig. | * Containment pressure is 0 psig. | ||
* RCS Bleed and Feed was | * RCS Bleed and Feed was initiated, but has now been secured. | ||
* RCS pressure is 1600 psig and rising. | * RCS pressure is 1600 psig and rising. | ||
* Pressurizer level is 23% and rising. | * Pressurizer level is 23% and rising. | ||
Which one of the following | Which one of the following completes the statements below? | ||
(2) ESP-1.1, SI Termination(1) Wide Range level at 14% | The minimum SG level that permitted securing Bleed and Feed was at least one SG (1) . | ||
(2) EEP-1, Loss of Reactor or Secondary Coolant (1) Narrow Range level at 33% | The operating crew will transition to (2) from FRP-H.1. | ||
(2) ESP-1.1, SI Termination (1) | A. (1) Wide Range level at 14% | ||
(2) EEP-1, Loss of Reactor or Secondary Coolant | (2) ESP-1.1, SI Termination B. (1) Wide Range level at 14% | ||
(2) EEP-1, Loss of Reactor or Secondary Coolant C. (1) Narrow Range level at 33% | |||
(2) ESP-1.1, SI Termination D. (1) Narrow Range level at 33% | |||
(2) EEP-1, Loss of Reactor or Secondary Coolant | |||
100. Unit 1 is cooling down per ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding, and the following conditions exist: | 100. Unit 1 is cooling down per ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding, and the following conditions exist: | ||
* RVLIS is not available. | * RVLIS is not available. | ||
* RCS Hot leg is 450°F and slowly lowering. | * RCS Hot leg is 450°F and slowly lowering. | ||
* RCS Cold leg is 425°F and slowly lowering. | * RCS Cold leg is 425°F and slowly lowering. | ||
* The crew is cooling down at | * The crew is cooling down at the maximum rate allowed by procedure. | ||
* Pressurizer level has just | * Pressurizer level has just rapidly risen to 78% and is stable | ||
* RCS pressure reduction is not required. | * RCS pressure reduction is not required. | ||
* CST level is 9ft. | * CST level is 9ft. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The operating crew will transition to ESP-0.4, | The operating crew will transition to ESP-0.4, Natural Circulation Cooldown with Allowance for Reactor Vessel Head Steam Voiding (Without RVLIS), based on (1) . | ||
The maximum allowable cooldown rate in ESP-0.4 is (2) . | |||
Reference Provided A. (1) CST Level (2) <100°F in any 60 minute period B. (1) CST Level (2) <50°F/hr C. (1) Reactor Vessel void formation being indicated (2) <100°F in any 60 minute period D. (1) Reactor Vessel void formation being indicated (2) <50°F/hr | |||
PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE. | |||
APPLICABILITY: MODES 1, 2, and 3. | |||
ACTIONS | |||
-----------------------------------------------------------NOTE-------------------------------------------------------- | -----------------------------------------------------------NOTE-------------------------------------------------------- | ||
Separate Condition entry is allowed for each Function. | Separate Condition entry is allowed for each Function. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required channel 30 days with one required to OPERABLE status. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with one required | |||
channel inoperable. | channel inoperable. | ||
B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A Specification 5.6.8. | |||
not met. | |||
C. One or more Functions C.1 Restore one channel to 7 days with two required OPERABLE status. | |||
Specification 5.6.8. | |||
channels inoperable. | channels inoperable. | ||
Farley Units 1 and 2 3.3.3-1 Amendment No. 170 (Unit 1) | |||
Amendment No. 163 (Unit 2) | |||
Amendment No. | |||
Specification 5.6.8. | PAM Instrumentation 3.3.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.3-1 for the not met. channel. | ||
E. As required by Required E.1 Be in MODE 3. 6 hours Action D.1 and referenced in AND Table 3.3.3-1. | |||
E.2 Be in MODE 4. 12 hours F. As required by Required F.1 Initiate action in Immediately Action D.1 and accordance with referenced in Specification 5.6.8. | |||
Table 3.3.3-1. | |||
SURVEILLANCE REQUIREMENTS | |||
-------------------------------------------------------NOTE-------------------------------------------------------------- | |||
SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1. | |||
SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required In accordance with instrumentation channel that is normally energized. the Surveillance Frequency Control Program SR 3.3.3.2 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.3.3-2 Amendment No. 185 (Unit 1) | |||
Amendment No. 180 (Unit 2) | |||
PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 1) | |||
Post Accident Monitoring Instrumentation CONDITION REFERENCED FROM REQUIRED REQUIRED FUNCTION CHANNELS ACTION D.1 | |||
: 1. RCS Hot Leg Temperature (Wide Range) 2 E | |||
: 2. RCS Cold Leg Temperature (Wide Range) 2 E | |||
: 3. RCS Pressure (Wide Range) 2 E | |||
: 4. Steam Generator (SG) Water Level (Wide or 2/SG E Narrow Range) | |||
: 5. Refueling Water Storage Tank Level 2 E | |||
: 6. Containment Pressure (Narrow Range) 2 E | |||
: 7. Pressurizer Water Level 2 E | |||
: 8. Steam Line Pressure 2/SG E | |||
: 9. Auxiliary Feedwater Flow Rate 2 E | |||
: 10. RCS Subcooling Margin Monitor 2 E | |||
: 11. Containment Water Level (Wide Range) 2 E | |||
: 12. Core Exit Temperature - Quadrant 1 2 (a) E | |||
: 13. Core Exit Temperature - Quadrant 2 2(a) E | |||
: 14. Core Exit Temperature - Quadrant 3 2(a) E | |||
: 15. Core Exit Temperature - Quadrant 4 2(a) E | |||
: 16. Reactor Vessel Level Indicating System 2 F | |||
: 17. Condensate Storage Tank Level 2 E | |||
: 18. Deleted | |||
: 19. Containment Area Radiation (High Range) 2 F (a) A channel consists of two core exit thermocouples. | |||
Farley Units 1 and 2 3.3.3-3 Amendment No. 167 (Unit 1) | |||
Amendment No. 159 (Unit 2) | |||
-------------------------------------------------------NOTE-------------------------------------------------------------- | Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves LCO 3.7.3 Three Main FW Stop Valves, three MFRVs, and associated bypass valves shall be OPERABLE. | ||
APPLICABILITY: MODES 1 and 2, except when all main feedwater lines are isolated by either a Main FW Stop Valve, a MFRV and its associated bypass valve or by a closed manual valve. | |||
ACTIONS | |||
--------------------------------------------------------NOTE------------------------------------------------------------- | |||
Separate Condition entry is allowed for each valve. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Main FW A.1 Close or isolate Main FW 72 hours Stop Valves inoperable. Stop Valve. | |||
AND A.2 Verify Main FW Stop Valve Once per 7 days is closed or isolated. | |||
B. One or more MFRVs B.1 Close or isolate MFRV. 72 hours inoperable. | |||
AND B.2 Verify MFRV is closed or Once per 7 days isolated. | |||
Farley Units 1 and 2 3.7.3-1 Amendment No. 146 (Unit 1) | |||
Amendment No. 137 (Unit 2) | |||
Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One or more MFRV C.1 Close or isolate bypass 72 hours bypass valves valve. | |||
inoperable. | |||
AND C.2 Verify bypass valve is closed Once per 7 days or isolated. | |||
D. Two valves in the same D.1 Isolate affected flow path. 8 hours flow path inoperable. | |||
E. Required Action and E.1 Be in MODE 3. 6 hours associated Completion Time not met. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each Main FW Stop Valve, In accordance with MFRV, and associated bypass valve is in accordance the Inservice with the time requirement in the Inservice Testing Testing Program. | |||
Plan. | |||
Farley Units 1 and 2 3.7.3-2 Amendment No. 146 (Unit 1) | |||
Amendment No. 137 (Unit 2) | |||
-------- | 1/22/2013 14:30 | ||
'/1&41 | |||
UNIT 1 | |||
/"563"-$*3$6-"5*0/$00-%08/5013&7&/53&"$503 3FWJTJPO | |||
7&44&-)&"%45&".70*%*/( | |||
"55"$).&/5 | |||
$"-$6-"5*0/'03"%&26"5&"7"*-"#-&$45*/7&/503: | |||
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: 20 OCT 2015 Facility / Unit FARLEY 1 & 2 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 8 hours to complete the combined examination, and 3 hours if you are only taking the SRO portion. | |||
Applicant Certification All work done on this examination is my own. I have neither given nor received aid. | |||
Applicant's Signature Results RO/SRO-Only/Total Examination Values 75 / ______ | |||
______ 25 / ______ | |||
100 Points Applicant's Score ______ / ______ / ______ | |||
Points Applicant's Grade ______ / ______ / ______ | |||
Percent ES-401, Page 38 of 50 | |||
: 1. Unit 1 is starting up IAW UOP-1.2, Startup of Unit from Hot Standby to Minimum Load, with the following condition: | |||
* Reactor Power is 13%. | |||
The CONTROL ROD MOTION switch has been released following a rod withdrawal when the following occurs: | |||
U. S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name: Date: Facility / Unit Region: | |||
All work done on this examination is my own. I have neither given nor received aid. | |||
Applicant's Signature Results RO/SRO-Only/Total Examination Values ______ | |||
Points Applicant's Score ______ | |||
Points Applicant's Grade | |||
Percent | |||
: 1. Unit 1 is starting up IAW UOP-1.2, | |||
The CONTROL ROD | |||
* Rods step out continuously. | * Rods step out continuously. | ||
Which one of the following completes the statements below? | |||
Which one of the following | The first action directed by AOP-19.0, Malfunction of Rod Control System, is to (1) . | ||
The first action directed by AOP-19.0, | With NO operator action the C-1, IR Hi Flux Rod Stop, (2) stop the outward rod motion. | ||
(1) manually Trip the Reactor (2) will NOT(1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) will NOT (1) manually Trip the Reactor (2) WILL(1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) WILL | A. (1) manually Trip the Reactor (2) will NOT B. (1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) will NOT C. (1) manually Trip the Reactor (2) WILL D. (1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) WILL | ||
: 2. Unit 1 is performing a Reactor | : 2. Unit 1 is performing a Reactor startup at MOL with the following conditions: | ||
-8 AMPS.Subsequently, control rods are withdrawn 3 steps. | * UOP-1.2, Startup of Unit From Hot Standby to Minimum Load, is in progress. | ||
Which one of the following | * The OATC has stabilized Reactor power. | ||
Reactor Power will rise then stablize (1) | * NI-35 and NI-36, INTERMEDIATE RANGE, indicate 1x10-8 AMPS. | ||
Subsequently, control rods are withdrawn 3 steps. | |||
: 3. Unit 1 is at 25% power | Which one of the following completes the statements below? | ||
At 1000:* 1A RX COOLANT PUMP AMPS indicates 700 AMPS. | Reactor Power will rise then stablize (1) the POAH. | ||
The first indication of reaching the POAH is rising (2) . | |||
(1) (2) | |||
A. below Pressurizer Level B. at Pressurizer Level C. below S/G Pressure D. at S/G Pressure | |||
: 3. Unit 1 is at 25% power when the following conditions occur: | |||
At 1000: | |||
* 1A RX COOLANT PUMP AMPS indicates 700 AMPS. | |||
At 1002: | At 1002: | ||
* The 1A RCP motor experiences a Sheared Shaft. | * The 1A RCP motor experiences a Sheared Shaft. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1002 the 1A RCP will draw (1) | At 1002 the 1A RCP will draw (1) electrical current than it did at 1000. | ||
The crew is required to immediately enter (2) . | |||
: 4. Unit 1 is operating at 100% | (1) (2) | ||
* PK-145, LP LTDN PRESS, is set to maintain | A. More EEP-0.0, Reactor Trip and Safety Injection B. Less EEP-0.0, Reactor Trip and Safety Injection C. More AOP-4.0, Loss of Reactor Coolant Flow D. Less AOP-4.0, Loss of Reactor Coolant Flow | ||
Subsequently, the RCS filter becomes completely clogged and does not allow any flow.Which one of the following | : 4. Unit 1 is operating at 100% power with the following conditions: | ||
* PK-145, LP LTDN PRESS, is set to maintain Letdown Pressure at 275 psig. | |||
Subsequently, the RCS filter becomes completely clogged and does not allow any flow. | |||
: 5. Which one of the following | Which one of the following completes the statements below? | ||
PK-145 controller demand will (1) . | |||
Level Transmitter Nomenclature LT-115, VCT LVL LT-112, VCT LVL | AOP-16.0, CVCS Malfunction, entry conditions (2) been met. | ||
(1) (2) | |||
A. Rise HAVE B. Rise have NOT C. Lower HAVE D. Lower have NOT | |||
: 5. Which one of the following completes the statement below? | |||
Charging Pump Suctions will automatically align to the RWST when (1) sense(s) (2) VCT Level. | |||
Level Transmitter Nomenclature LT-115, VCT LVL LT-112, VCT LVL (1) (2) | |||
A. either LT-115 or LT-112 5% | |||
B. both LT-115 and LT-112 5% | |||
C. either LT-115 or LT-112 15% | |||
D. both LT-115 and LT-112 15% | |||
: 6. Unit 1 is in MODE 4 with the following conditions: | : 6. Unit 1 is in MODE 4 with the following conditions: | ||
* Plant cooldown is in progress with the 'A' Train of RHR . | * Plant cooldown is in progress with the 'A' Train of RHR . | ||
* The OATC raises demand on FK-605A,1A RHR HX BYP FLOW, by 25%. | * The OATC raises demand on FK-605A,1A RHR HX BYP FLOW, by 25%. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Raising demand on FK-605A will (1) | Raising demand on FK-605A will (1) CCW temperature. | ||
CCW temperature. | Per SOP-23.0, Component Cooling Water System, the maximum allowable CCW outlet temperature for the CCW HX used for cooldown is (2) . | ||
Per SOP-23.0, Component Cooling Water System, the maximum | (1) (2) | ||
A. raise 120°F B. raise 135°F C. lower 120°F D. lower 135°F | |||
: 7. Unit 1 is shutdown when | : 7. Unit 1 is shutdown when the following conditions occur: | ||
* The 1A CCW pump tripped. | * The 1A CCW pump tripped. | ||
* The 'A' Train is the ON SERVICE Train. | * The 'A' Train is the ON SERVICE Train. | ||
Which one of the following | Which one of the following completes the statement below? | ||
Cooling is lost to the (1) RHR Heat Exchanger. | |||
The affected RHR train (2) available for transfer to Cold Leg Recirculation. | |||
(1) (2) | |||
A. 1A is NOT B. 1A IS C. 1B is NOT D. 1B IS | |||
: 8. Unit 1 has experienced a tube rupture on the 1A SG with the following conditions: | : 8. Unit 1 has experienced a tube rupture on the 1A SG with the following conditions: | ||
* A Loss of All Offsite Power has occurred. | * A Loss of All Offsite Power has occurred. | ||
* The operating crew is performing EEP-3, Steam | * The operating crew is performing EEP-3, Steam Generator Tube Rupture. | ||
* RCS cooldown is in progress. | * RCS cooldown is in progress. | ||
* INTEGRITY Critical Safety Function Status Tree has turned ORANGE due | * INTEGRITY Critical Safety Function Status Tree has turned ORANGE due to the 1A RCS LOOP cold leg temperature dropping rapidly. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The 1A RCS LOOP cold leg temperature drop was caused by increased (1) flow over the 1A RCS LOOP cold leg instrument. | |||
(2) is the highest listed cold leg temperature that could lead to this ORANGE INTEGRITY condition. | |||
(1) (2) | |||
A. Natural Circulation 270°F B. Natural Circulation 225°F C. High Head Safety Injection 270°F D. High Head Safety Injection 225°F | |||
: 9. A Safety Injection has just occurred on Unit 1. | : 9. A Safety Injection has just occurred on Unit 1. | ||
Which one of the following | Which one of the following completes the statement below? | ||
The minimum valve actuations that would lead to HHSI Pump cavitation | The minimum valve actuations that would lead to HHSI Pump cavitation are . | ||
LCV-115C, VCT OUTLET ISO LCV-115E, VCT OUTLET ISO | Valve Nomenclature: | ||
LCV-115C, VCT OUTLET ISO LCV-115E, VCT OUTLET ISO LCV-115D, RWST TO CHG PUMP LCV-115B, RWST TO CHG PUMP A. LCV-115C or LCV-115E opening B. LCV-115C and LCV-115E opening C. LCV-115B or LCV-115D closing D. LCV-115B and LCV-115D closing | |||
LCV-115D, RWST TO CHG PUMP | |||
LCV-115B, RWST TO CHG PUMP LCV-115C | |||
: 10. Nitrogen addition to the PRT on Unit 1 is in progress when the following occurs: | : 10. Nitrogen addition to the PRT on Unit 1 is in progress when the following occurs: | ||
* V-042, PRT N2 PRESS REG, fails causing PRT pressure to RISE. | * V-042, PRT N2 PRESS REG, fails causing PRT pressure to RISE. | ||
* PI-472, PRT PRESS, | * PI-472, PRT PRESS, stablizes at 15.0 psig. | ||
Which one of the following | Which one of the following completes the statements below? | ||
HE5, PRT PRESS HI, (1) in alarm. | |||
Per SOP-1.2, Reactor Coolant Pressure Relief System, normal nitrogen pressure prevents (2) . | |||
(1) (2) | |||
A. IS excessive corrosion due to oxygen B. is NOT excessive corrosion due to oxygen C. IS an explosive mixture of oxygen and hydrogen D. is NOT an explosive mixture of oxygen and hydrogen | |||
: 11. Unit 1 is operating at 100% power when the following conditions occur: | : 11. Unit 1 is operating at 100% power when the following conditions occur: | ||
* A large break has | * A large break has occurred at the inlet of a Pressurizer Safety Valve. | ||
Subsequently, the | Subsequently, the following condition exists: | ||
* Pressurizer Pressure is 1600 psig. | * Pressurizer Pressure is 1600 psig. | ||
* Charging Pump miniflow valves are open.Which one of the following | * Charging Pump miniflow valves are open. | ||
Which one of the following completes the statements below? | |||
Per EEP-0, Reactor Trip or Safety Injection, the crew (1) required to close the Charging Pump miniflow valves. | |||
Closing the Charging Pump miniflow valves when required will ensure (2) . | |||
(1) (2) | |||
A. IS HHSI pump injection flow is maximized B. is NOT HHSI pump injection flow is maximized C. IS HHSI pump heat is removed D. is NOT HHSI pump heat is removed | |||
: 12. Unit 1 is operating at 100% power with the following conditions: | : 12. Unit 1 is operating at 100% power with the following conditions: | ||
* A dual unit LOSP occurs. | * A dual unit LOSP occurs. | ||
Subsequently, | Subsequently, Unit 2 experiences a Safety Injection. | ||
Which one of the following | Which one of the following completes the statement below for Unit 1? | ||
The (1) CCW pump is being powered by the (2) DG. | |||
(1) (2) | |||
A. 1A 1-2A B. 1A 1C C. 1C 1-2A D. 1C 1C | |||
: 13. Unit 1 is in MODE 5 with the following conditions: | : 13. Unit 1 is in MODE 5 with the following conditions: | ||
* A cooldown is in progress. | * A cooldown is in progress. | ||
* RHR is on service. | * RHR is on service. | ||
Subsequently, the following conditions occur: | Subsequently, the following conditions occur: | ||
* V-8708A, RHR SUCTION RELIEF , has lifted and is stuck open. | * V-8708A, RHR SUCTION RELIEF, has lifted and is stuck open. | ||
Which of the following tank levels will immediately rise due to the malfunction? | Which of the following tank levels will immediately rise due to the malfunction? | ||
A. PRT B. RHT C. WHT D. RCDT | |||
: 14. A Design Basis Large Break | : 14. A Design Basis Large Break LOCA has occurred on Unit 1. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The Accumulators will inject directly to the (1) . | |||
The purpose of the Accumulator design capacity is to (2) refill the Reactor Vessel following a design basis accident. | |||
(1) (2) | |||
completely Cold Legs partially Cold Legs | A. Hot Legs partially B. Hot Legs completely C. Cold Legs partially D. Cold Legs completely | ||
: 15. Unit 1 is operating at 100% power and the following conditions exist: | : 15. Unit 1 is operating at 100% power and the following conditions exist: | ||
* Pressurizer Pressure is 2240 psig. | * Pressurizer Pressure is 2240 psig. | ||
Line 914: | Line 1,079: | ||
* Pressurizer Level is 60%. | * Pressurizer Level is 60%. | ||
* 600V LCC 1M has lost power. | * 600V LCC 1M has lost power. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Power has been lost to the (1) Pressurizer Heater Group. | |||
Pressurizer Heater Groups A and B are currently (2) . | |||
(1) (2) | |||
A. D Energized B. D De-Energized C. E Energized D. E De-Energized | |||
: 16. Unit 1 is operating at 100% Power when the following conditions occur: | : 16. Unit 1 is operating at 100% Power when the following conditions occur: | ||
* A short circuit occurs in PT-445, PRZR PRESS. | * A short circuit occurs in PT-445, PRZR PRESS. | ||
* Pressurizer Pressure remains stable. | * Pressurizer Pressure remains stable. | ||
Which one of the following | Which one of the following completes the statement below? | ||
The Pressurizer Pressure input to the Reactor Protection System will NOT be affected by this malfunction due to the use of . | |||
: 17. Unit 1 is operating at 100% power and | A. an independent control channel B. a median signal selector C. isolation devices D. de-energize to actuate bistables | ||
* A Safety Injection | : 17. Unit 1 is operating at 100% power and the following occurs: | ||
Several minutes following the safety | * A Safety Injection followed by an LOSP on Unit 1. | ||
Several minutes following the safety injection the following condition exists: | |||
* The 1B DG is running with the output breaker open. | * The 1B DG is running with the output breaker open. | ||
Which one of the following | Which one of the following completes the statements below? | ||
SOP-0.8, Transient Response Procedure User's Guide, (1) require a procedure be used prior to closing the 1B DG output breaker. | |||
The B1G sequencer (2) energize the 1C Air Compressor. | |||
(1) (2) | |||
A. DOES DOES B. DOES does NOT C. does NOT DOES D. does NOT does NOT | |||
: 18. The 1D Vital Panel becomes de-energized on Unit 1. | : 18. The 1D Vital Panel becomes de-energized on Unit 1. | ||
Which one of the following | Which one of the following completes the statements below. | ||
The 'B' Train SI actuated MOVs (1) automatically stroke upon an SI actuation. | |||
'B' Train ESF pumps (2) be started in LOCAL at the HSDP. | |||
: 19. Which one of the following completes the statements below? The C-11, Bank D Stop, is actuated by input from (1) | (1) (2) | ||
A. WILL CAN B. WILL CANNOT C. will NOT CAN D. will NOT CANNOT | |||
: 19. Which one of the following completes the statements below? | |||
The C-11, Bank D Stop, is actuated by input from (1) at a Bank D rod height of (2) steps. | |||
(1) (2) | |||
A. Digital Rod Position Indication 220 B. Digital Rod Position Indication 228 C. the Pulse-to-Analog Converter 220 D. the Pulse-to-Analog Converter 228 | |||
: 20. Unit 1 is in MODE 3 and the following RCP temperatures are observed: | : 20. Unit 1 is in MODE 3 and the following RCP temperatures are observed: | ||
Motor Bearing Temperature Motor Stator Temperature 1A RCP 190°F 235°F 1B RCP 200°F 220°F 1C RCP 190°F 230°F Which one of the following completes the statement below? | |||
1A RCP 1B RCP 1A and 1B RCPs 1A and 1C RCPs | Only the is (are) required to be secured. | ||
: 21. Which one of the following conditions would cause a Core Exit Thermocouple (CETC)monitor alarm? 1. ANY CETC input disconnected. 2. ONLY 10 valid CETCs. | A. 1A RCP B. 1B RCP C. 1A and 1B RCPs D. 1A and 1C RCPs | ||
: 21. Which one of the following conditions would cause a Core Exit Thermocouple (CETC) monitor alarm? | |||
: 1. ANY CETC input disconnected. | |||
: 2. ONLY 10 valid CETCs. | |||
: 3. ANY CETC temperature at 650°F. | : 3. ANY CETC temperature at 650°F. | ||
1 ONLY 1 AND 3 ONLY 2 ONLY 1, 2, AND 3 | A. 1 ONLY B. 1 AND 3 ONLY C. 2 ONLY D. 1, 2, AND 3 | ||
: 22. Unit 1 is operating at 100% power when the following conditions occurred: | : 22. Unit 1 is operating at 100% power when the following conditions occurred: | ||
* 1B Charging Pump is started. | * 1B Charging Pump is started. | ||
Line 945: | Line 1,123: | ||
* 1B CHG PUMP AMPS, begins to oscillate. | * 1B CHG PUMP AMPS, begins to oscillate. | ||
* FI-122A, CHG FLOW, begins to oscillate. | * FI-122A, CHG FLOW, begins to oscillate. | ||
Subsequently, the following | Subsequently, the following annunciators come into alarm: | ||
* EA2, CHG HDR FLOW HI-LO. | * EA2, CHG HDR FLOW HI-LO. | ||
* DD1, RCP SEAL INJ FLOW LO. | * DD1, RCP SEAL INJ FLOW LO. | ||
* DE1, REGEN HX LTDN FLOW DISCH TEMP HI. | * DE1, REGEN HX LTDN FLOW DISCH TEMP HI. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The alarms above are indicative of (1) . | |||
The maximum 1A RCP seal injection flowrate that would cause DD1 to alarm is (2) . | |||
(1) (2) | |||
A. FCV-122 closing 6 gpm B. 1B Charging Pump Cavitation 6 gpm C. FCV-122 closing 3 gpm D. 1B Charging Pump Cavitation 3 gpm | |||
: 23. Unit 1 is operating at 100% power with the following conditions: | : 23. Unit 1 is operating at 100% power with the following conditions: | ||
* A Large Break LOCA occurs. | * A Large Break LOCA occurs. | ||
Subsequently, a Loss of Offsite Power occurs. | Subsequently, a Loss of Offsite Power occurs. | ||
Which one of the following | Which one of the following completes the statement below 5 minutes after the Loss of Offsite Power? | ||
(1) Containment Cooler Fans are running in slow speed. | |||
The reduced speed prevents CTMT cooler (2) due to high moisture content in the Containment atmosphere. | |||
(1) (2) | |||
A. 2 fan motor overload B. 4 fan motor overload C. 2 cooling coil impingement damage D. 4 cooling coil impingement damage | |||
: 24. Unit 1 is in MODE 5 and the following condition exists: | : 24. Unit 1 is in MODE 5 and the following condition exists: | ||
* Both Trains of RHR are | * Both Trains of RHR are operating in the cooldown alignment. | ||
* Power is aligned to the RHR suction valves. | * Power is aligned to the RHR suction valves. | ||
* Tavg is 195°F. | * Tavg is 195°F. | ||
Subsequently, the following condition occurs: | Subsequently, the following condition occurs: | ||
* PT-402, 1C LOOP RCS NR PRESS, fails to 500 psig. | * PT-402, 1C LOOP RCS NR PRESS, fails to 500 psig. | ||
Which one of the following completes the statements below? | |||
Which one of the following | MOV-8701A, 1C RCS LOOP TO 1A RHR PUMP, (1) automatically close. | ||
IF MOV-8701A closes, then AOP-12.0, Residual Heat Removal System Malfunction, entry (2) required. | |||
(1) (2) | |||
A. DOES is NOT B. does NOT is NOT C. DOES IS D. does NOT IS | |||
: 25. Unit 1 is Shutdown following a LOCA with the following conditions: | : 25. Unit 1 is Shutdown following a LOCA with the following conditions: | ||
* PR-950, CTMT PRESS, peaked at 3.2 psig. | * PR-950, CTMT PRESS, peaked at 3.2 psig. | ||
* ECP-1.1, Loss of | * ECP-1.1, Loss of Emergency Coolant Recirculation, is in progress. | ||
Which one of the following | Which one of the following completes the statments below: | ||
Per ECP-1.1, the minimum CTMT Sump Level that can support Containment Spray pump operation is . | |||
A. 2.0 ft B. 3.8 ft C. 4.5 ft D. 5.3 ft | |||
: 26. Unit 1 is operating at 100% power when the following condition occurs: | : 26. Unit 1 is operating at 100% power when the following condition occurs: | ||
* PK-444A, PRZR PRESS | * PK-444A, PRZR PRESS REFERENCE, demand fails to 0%. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Initially, (1) PORV(s) will OPEN automatically. | |||
PCV-444C, 1A LOOP SPRAY VLV, will (2) . | |||
(1) (2) | |||
A. only ONE CLOSE B. only ONE OPEN C. BOTH CLOSE D. BOTH OPEN | |||
: 27. Unit 1 is operating at 100% power with the following conditions: | : 27. Unit 1 is operating at 100% power with the following conditions: | ||
* Containment Mini- | * Containment Mini-Purge is in operation Subsequently, the following conditions occur: | ||
* A Main Steam Line | * A Main Steam Line breaks inside Containment | ||
* PR-950Z, CTMT PRESS, stablizes at 14.5 psig. | * PR-950Z, CTMT PRESS, stablizes at 14.5 psig. | ||
Which one of the following | Which one of the following completes the statements below? | ||
CTMT Mini-Purge supply and exhaust fans (1) tripped automatically due to a Containment Ventilation Isolation signal. | |||
CTMT Mini-Purge supply and exhaust dampers (2) closed automatically due to a Containment Ventilation Isolation signal. | |||
(1) (2) | |||
A. HAVE HAVE B. HAVE have NOT C. have NOT HAVE D. have NOT have NOT | |||
: 28. Unit 1 is operating at 100% power with the following conditions: | : 28. Unit 1 is operating at 100% power with the following conditions: | ||
* STP-33.2A, Reactor Trip Breaker | * STP-33.2A, Reactor Trip Breaker Train A Operability Test, is in progress. | ||
* Reactor Trip | * Reactor Trip Breaker A is OPEN. | ||
* Reactor Trip Bypass Breaker A is CLOSED. | * Reactor Trip Bypass Breaker A is CLOSED. | ||
* Reactor Trip | * Reactor Trip Breaker B is CLOSED. | ||
Subsequently, the following conditions occur: | Subsequently, the following conditions occur: | ||
* An automatic reactor trip signal is generated. | * An automatic reactor trip signal is generated. | ||
* The Reactor does NOT trip. | * The Reactor does NOT trip. | ||
Which one of the following | Which one of the following completes the statements below? | ||
When the RX TRIP ACTUATION switch is taken to TRIP (1) will OPEN. | |||
Per EEP-0, Reactor Trip or Safety Injection, if the RX TRIP ACTUATION switches fail to trip the Reactor, the next action required is to (2) . | |||
A. (1) ONLY Reactor Trip Breaker B (2) trip the MG set supply breakers B. (1) BOTH Reactor Trip Bypass Breaker A and Reactor Trip Breaker B (2) trip the MG set supply breakers C. (1) ONLY Reactor Trip Breaker B (2) insert Control Rods manually D. (1) BOTH Reactor Trip Bypass Breaker A and Reactor Trip Breaker B (2) insert Control Rods manually | |||
: 29. Unit 2 is starting up per UOP-1.2, Startup of Unit From Hot Standby To Minimum Load, with the following conditions: | : 29. Unit 2 is starting up per UOP-1.2, Startup of Unit From Hot Standby To Minimum Load, with the following conditions: | ||
* Main Steam Header Warm Up is in Progress. | * Main Steam Header Warm Up is in Progress. | ||
Which one of the following actions would cause the 2B SG Pressure to lower due to increased steam demand from the 2B SG? | |||
Which one of the following actions | A. Lower PC-3371B, 2B MS ATMOS REL VLV, SETPT in AUTO. | ||
Lower PC-3371B, 2B MS ATMOS REL VLV, SETPT in AUTO. | B. Lower PC-3371B, 2B MS ATMOS REL VLV, OUTPUT in MAN. | ||
Lower PC-3371B, 2B MS ATMOS REL VLV, OUTPUT in MAN. | C. Lower PK-464, STM HDR PRESS, OUTPUT in MAN. | ||
Lower PK-464, STM HDR | D. Lower PK-464, STM HDR PRESS, SETPT in AUTO. | ||
Lower PK-464, STM HDR PRESS, SETPT in AUTO | : 30. Unit 1 is responding to a SGTR in the 1A SG with the following conditions: | ||
: 30. Unit 1 is responding to a SGTR in the 1A SG | |||
At 1000: | At 1000: | ||
* HIGHEST CORE EXIT TEMP CHAN A and B on the IPC, indicates 530°F. | * HIGHEST CORE EXIT TEMP CHAN A and B on the IPC, indicates 530°F. | ||
Line 1,007: | Line 1,198: | ||
* PI-403A, 1A LOOP RCS WR PRESS, indicates 1230 psig. | * PI-403A, 1A LOOP RCS WR PRESS, indicates 1230 psig. | ||
* RCS cooldown is in progress. | * RCS cooldown is in progress. | ||
At | At 1045: | ||
* HIGHEST CORE EXIT TEMP CHAN A and B, on | * HIGHEST CORE EXIT TEMP CHAN A and B, on the IPC indicates 450°F. | ||
. | |||
* 1A SG PRESS is 300 psig. | * 1A SG PRESS is 300 psig. | ||
* PI-403A, 1A LOOP RCS WR PRESS, indicates 565 psig. | * PI-403A, 1A LOOP RCS WR PRESS, indicates 565 psig. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Compared to the conditions at 1000, RCS subcooling at 1045 has (1) . | |||
Compared to the conditions at 1000, SG tube leakage rate at 1045 has (2) . | |||
Reference Provided (1) (2) | |||
A. risen risen B. risen lowered C. lowered lowered D. lowered risen | |||
: 31. Unit 1 is in Mode 3 at EOL with the following conditions: | : 31. Unit 1 is in Mode 3 at EOL with the following conditions: | ||
* A Reactor Startup is being planned for 24 hours after a reactor trip. | * A Reactor Startup is being planned for 24 hours after a reactor trip. | ||
* Tavg is being maintained by the Atmospheric Relief Valves (ARVs). | * Tavg is being maintained by the Atmospheric Relief Valves (ARVs). | ||
* The Estimated Critical Condition (ECC) calculation predicts criticality at 100 | * The Estimated Critical Condition (ECC) calculation predicts criticality at 100 steps on Control Bank D. | ||
Which one of the following conditions will | Which one of the following conditions will result in critical rod height being HIGHER than the value predicted by the ECC? | ||
For your answer, consider that no operator actions are taken to mitigate or compensate for the below events. | For your answer, consider that no operator actions are taken to mitigate or compensate for the below events. | ||
A dilution of 500 gallons is performed. | A. A dilution of 500 gallons is performed. | ||
Auxiliary Feedwater flow is RAISED to all SGs. | B. Auxiliary Feedwater flow is RAISED to all SGs. | ||
A post maintenance test results in the closure of all ARVs. | C. A post maintenance test results in the closure of all ARVs. | ||
Reactor startup occurs 30 | D. Reactor startup occurs 30 hours after the reactor trip. | ||
: 32. Unit 2 is at 68% power ramping down due to a problem with #4 Governor Valve with the following conditions: | |||
: 32. Unit 2 is at 68% power ramping down due to a problem with #4 Governor Valve with the following conditions:* EH is isolated to #4 Governor valve. | * EH is isolated to #4 Governor valve. | ||
* A subsequent failure causes #2 Governor Valve to fail closed.* Turbine load drops to 450 MW. | * A subsequent failure causes #2 Governor Valve to fail closed. | ||
Which one of the following | * Turbine load drops to 450 MW. | ||
Which one of the following completes the statements below? | |||
The #2 governor valve closure results in (1) . | |||
Per SOP-72.0, General Instructions for DEH Operators Console, the operating crew is required to (2) . | |||
A. (1) automatic removal of the IMP Press Loop (2) trip the Main Turbine B. (1) automatic removal of the IMP Press Loop (2) match reactor power with turbine load C. (1) opposed governor valve closure (2) trip the Main Turbine D. (1) opposed governor valve closure (2) match reactor power with turbine load | |||
: 33. Unit 1 is operating at 100% power with the following conditions: | : 33. Unit 1 is operating at 100% power with the following conditions: | ||
AT 1000: | AT 1000: | ||
* 1A Circulating Water Pump Trips. | * 1A Circulating Water Pump Trips. | ||
AT 1005: | AT 1005: | ||
* KK1, TURB COND VAC LO, comes into alarm Which one of the following | * KK1, TURB COND VAC LO, comes into alarm Which one of the following completes the statements below? | ||
(1) is the earliest time AOP-8.0, Partial Loss of Condenser Vacuum, entry is required. | |||
At 100% Reactor power, | At 100% Reactor power, (2) is the lowest condenser pressure a manual Reactor Trip is required. | ||
(1) (2) | |||
A. 1000 3.800 psia B. 1005 3.800 psia C. 1000 2.901 psia D. 1005 2.901 psia | |||
: 34. Unit 1 entered FRP-H.1, Response to Loss of Secondary Heat Sink, with the following conditions: | : 34. Unit 1 entered FRP-H.1, Response to Loss of Secondary Heat Sink, with the following conditions: | ||
Time 1000 1015 1030 1100 1A S/G WR LVL (%) 37.00 28.00 18.00 11.00 1B S/G WR LVL (%) 32.00 20.00 10.00 6.00 1C S/G WR LVL (%) 29.00 19.00 9.00 3.00 CNMT PRESS (PSIG) 1.50 2.00 3.00 4.50 AFW TOTAL FLOW (GPM) 0 0 0 0 Which one of the following is the EARLIEST time that a manual Safety Injection is required due to meeting Bleed and Feed criteria per FRP-H.1? | |||
A. 1000 B. 1015 C. 1030 D. 1100 | |||
: 35. Which one of the following is the purpose of depressurizing all intact SGs during the performance of ECP-0.0, Loss of All AC Power? | : 35. Which one of the following is the purpose of depressurizing all intact SGs during the performance of ECP-0.0, Loss of All AC Power? | ||
Rapidly reduces DP across SG U-tubes to minimize RCS inventory loss from a potential tube rupture. | A. Rapidly reduces DP across SG U-tubes to minimize RCS inventory loss from a potential tube rupture. | ||
Cools RCP seals in a | B. Cools RCP seals in a controlled manner and minimizes loss of RCS inventory. | ||
Maximizes Natural | C. Maximizes Natural Circulation flow before reflux cooling begins as the RCS becomes saturated. | ||
D. Maximizes Natural Circulation flow to allow reactor vessel head to cool since CRDM cooling fans are unavailable. | |||
: 36. Unit 1 is operating at 100% power and the following condition exists: | : 36. Unit 1 is operating at 100% power and the following condition exists: | ||
* Main Condenser Pressure is rising due to a failure of the 1A SJAE. | * Main Condenser Pressure is rising due to a failure of the 1A SJAE. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Main Condenser Hotwell Temperature will initially (1) . | |||
AOP-8.0, Partial Loss of Condenser Vacuum, will direct placing (2) on service. | |||
(1) (2) | |||
A. RISE a Hogger B. LOWER a Hogger C. RISE the 1B SJAE D. LOWER the 1B SJAE | |||
: 37. The following conditions exist: | : 37. The following conditions exist: | ||
* Unit 1 is in MODE 5. | * Unit 1 is in MODE 5. | ||
Line 1,057: | Line 1,257: | ||
* 4160V busses 2F, 2K, 2G, and 2L de-energize. | * 4160V busses 2F, 2K, 2G, and 2L de-energize. | ||
* The 1-2A DG Trips and cannot be restored. | * The 1-2A DG Trips and cannot be restored. | ||
Which one of the following | Which one of the following completes the statement below? | ||
: 38. Which one of the following completes the statement below? The Main Turbine exhaust hood sprays use (1) | The first procedure the Unit 1 Operating Crew is required to enter is (1) . | ||
The Operating Crew will restore power to Unit 1 with the (2) . | |||
A. (1) AOP-5.0, Loss of A or B Train Electrical Power (2) 1C DG B. (1) ECP-0.0, Loss of All AC Power (2) 1C DG C. (1) AOP-5.0, Loss of A or B Train Electrical Power (2) 2C DG D. (1) ECP-0.0, Loss of All AC Power (2) 2C DG | |||
: 38. Which one of the following completes the statement below? | |||
The Main Turbine exhaust hood sprays use (1) to automatically prevent excessive temperatures at the exhaust of the LP Turbine (2) 15% Turbine Load. | |||
(1) (2) | |||
A. demin water above B. demin water below C. condensate above D. condensate below | |||
: 39. Unit 1 is operating at 100% power when the following occurs: | : 39. Unit 1 is operating at 100% power when the following occurs: | ||
* The 1C 120 VAC Vital | * The 1C 120 VAC Vital Instrumentation Panel is de-energized. | ||
Which one of the following | Which one of the following completes the statements below? | ||
LCV-459, LTDN LINE ISO, | LCV-459, LTDN LINE ISO, (1) automatically close if a Pressurizer Low Level condition occurs. | ||
LCV-115A (2) immediately divert to the RHT. | |||
: 40. Unit 1 is operating at 8% power and the following conditions occur:* The Battery Input Breaker on the 1B inverter trips. | (1) (2) | ||
A. WILL WILL B. WILL will NOT C. will NOT WILL D. will NOT will NOT | |||
: 40. Unit 1 is operating at 8% power and the following conditions occur: | |||
* The Battery Input Breaker on the 1B inverter trips. | |||
* WD2, 1B INV FAULT, annunciator alarms. | * WD2, 1B INV FAULT, annunciator alarms. | ||
* No Other Annunciators are in Alarm due to the fault. | * No Other Annunciators are in Alarm due to the fault. | ||
Subsequently, the Rover reports the | Subsequently, the Rover reports the following indications from the 1B Inverter. | ||
* INVERTER POWERING LOAD lamp NOT lit. | * INVERTER POWERING LOAD lamp NOT lit. | ||
* BYPASS SOURCE | * BYPASS SOURCE AVAILABLE lamp is LIT. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The 1B 120V Vital AC panel is (1) . | |||
The 1B INVERTER AMPERES meter on the EPB indicates (2) . | |||
A. (1) Energized (2) 0 Amps B. (1) Energized (2) Full Load Amps C. (1) De-energized (2) 0 Amps. When the MANUAL BYPASS SWITCH is taken to BYPASS SOURCE TO LOAD position it will indicate Full Load Amps. | |||
D. (1) De-energized (2) 0 Amps. When the MANUAL BYPASS SWITCH is taken to BYPASS SOURCE TO LOAD position it will continue to indicate 0 Amps. | |||
: 41. Unit 1 is operating at 100% power when the following conditions occur: | : 41. Unit 1 is operating at 100% power when the following conditions occur: | ||
* Annunciator KB4, SGFP SUCT PRESS LO, alarms | * Annunciator KB4, SGFP SUCT PRESS LO, alarms | ||
* PR-4039, SGFP SUCT PRESS, indicates 300 psig and lowering. | * PR-4039, SGFP SUCT PRESS, indicates 300 psig and lowering. | ||
Which one of the following | Which one of the following completes the statement below? | ||
The earliest time the standby condensate pump will start is when . | |||
: 42. A | A. KB4 has been in alarm for 10 seconds B. KB4 has been in alarm for 30 seconds C. SGFP suction pressure has remained below 275 PSIG for 10 seconds D. SGFP suction pressure has remained below 275 PSIG for 30 seconds | ||
: 42. A gas transfer is in progress to the #8 Waste Gas Decay Tank on Unit 1 when the following conditions occur: | |||
* The #8 Waste Gas Decay Tank relief valve lifts. | * The #8 Waste Gas Decay Tank relief valve lifts. | ||
* The relief valve fails to reseat. | * The relief valve fails to reseat. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The relief valve lifting will initially be detected by (1) | The relief valve lifting will initially be detected by (1) . | ||
The release (2) be automatically isolated from the environment if an alarm condition exists. | |||
: 43. Unit 1 is Operating at 100% Reactor Power when the following conditions occur: | (1) (2) | ||
A. R-13, WASTE GAS MONITOR WILL B. R-13, WASTE GAS MONITOR will NOT C. R-14, PLANT VENT MONITOR WILL D. R-14, PLANT VENT MONITOR will NOT | |||
: 43. Unit 1 is Operating at 100% Reactor Power when the following conditions occur: | |||
Time 1000 1005 1010 1015 1A S/G NR LVL (%) 26.00 23.00 21.00 7.00 1B S/G NR LVL (%) 34.00 27.00 25.00 8.00 1C S/G NR LVL (%) 35.00 33.00 31.00 12.00 1A SGFP STATUS Running Running Tripped Tripped 1B SGFP STATUS Running Running Tripped Tripped Which one of the following is the earliest time when all AFW Pumps have recieved an AUTO START signal? | |||
A. 1000 B. 1005 C. 1010 D. 1015 | |||
: 44. Unit 1 is operating at 100% power with the following condition: | : 44. Unit 1 is operating at 100% power with the following condition: | ||
* An LOSP occurs. | * An LOSP occurs. | ||
Which one of the following completes the statements below? | |||
Which one of the following | 10 seconds after power is restored to the 1F 4160V bus: | ||
10 seconds after power is restored to the 1F 4160V bus: | 1A CHG PUMP AMPS will indicate (1) AMPS. | ||
1A MDAFWP AMPS will indicate (2) | 1A MDAFWP AMPS will indicate (2) AMPS. | ||
(1) (2) | |||
A. greater than zero greater than zero B. greater than zero zero C. zero greater than zero D. zero zero | |||
: 45. Unit 1 is operating at 100% power when the following condition occurs: | : 45. Unit 1 is operating at 100% power when the following condition occurs: | ||
* The Reactor Trips | * The Reactor Trips Subsequently, the following indications are displayed continously on the MCB. | ||
* V-515, SW TO TURB BLDG ISO A TRN, RED and GREEN Lights are LIT. | |||
Subsequently, the following indications are displayed continously on the MCB.* V-515, SW TO TURB BLDG ISO A TRN, RED and GREEN Lights are LIT.* V-517, SW TO TURB BLDG ISO B TRN, RED and GREEN Lights are LIT. | * V-517, SW TO TURB BLDG ISO B TRN, RED and GREEN Lights are LIT. | ||
* V-516, SW TO TURB BLDG ISO A TRN, RED and GREEN Lights are LIT.* V-514, SW TO TURB BLDG ISO B TRN, RED and GREEN Lights are LIT. | * V-516, SW TO TURB BLDG ISO A TRN, RED and GREEN Lights are LIT. | ||
Which one of the following | * V-514, SW TO TURB BLDG ISO B TRN, RED and GREEN Lights are LIT. | ||
Which one of the following completes the statement below? | |||
: 46. Which one of the following completes the statements below? The | The valve actuation was initiated by a (1) . | ||
The valve position prevents (2) . | |||
A. (1) Safety Injection (2) damage to turbine building auxiliaries. | |||
: 47. Unit 1 is at 100% power when the following condition occurs in the | B. (1) Loss of Offsite Power (2) complete isolation of SW flow to the Air Compressors C. (1) Safety Injection (2) complete isolation of SW flow to the Air Compressors D. (1) Loss of Offsite Power (2) damage to turbine building auxiliaries. | ||
: 46. Which one of the following completes the statements below? | |||
The (1) RCP(s) can be powered from the 1A Startup Transformer. | |||
The (2) RCP(s) can be powered from the 2B Startup Transformer. | |||
(1) (2) | |||
A. 1A RCP 2A RCP B. 1A RCP 2B and 2C RCPs C. 1B and 1C RCPs 2A RCP D. 1B and 1C RCPs 2B and 2C RCPs | |||
: 47. Unit 1 is at 100% power when the following condition occurs in the Aux Bldg DC distribution system: | |||
* The 125V DC Bus 1B has been de-energized. | * The 125V DC Bus 1B has been de-energized. | ||
Subsequently, an LOSP occurs on Unit 1. | Subsequently, an LOSP occurs on Unit 1. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The 1B DG (1) be started from the EPB. | |||
The B1G Sequencer (2) automatically sequence loads. | |||
: 48. Which one of the following completes | (1) (2) | ||
A. CAN WILL B. CANNOT will NOT C. CANNOT WILL D. CAN will NOT | |||
: 48. Which one of the following completes the statement below for the 1B DG Air Recievers? | |||
The maximum Air Receiver pressure that will cause an alarm on the 1B DG Local Control Panel is (1) . | |||
At the alarm setpoint there is enough air pressure to ensure a maximum of (2) start attempts are available. | |||
(1) (2) | |||
A. 200 psig 3 B. 200 psig 5 C. 350 psig 3 D. 350 psig 5 | |||
: 49. Unit 1 is operating at 100% power when the following conditions occur: | : 49. Unit 1 is operating at 100% power when the following conditions occur: | ||
* MH1, FIRE, annunciator on the Unit 1 Main Control Board (MCB) alarms. * | * MH1, FIRE, annunciator on the Unit 1 Main Control Board (MCB) alarms. | ||
* The Rover reports that the window | * Aux Bldg El 139 W Side Det 1A-39, 43, 46, 53 1A-55, 59, 106", light is lit on the Control Room Fire Panel. | ||
The Control Room Fire Panel alarm must be acknowledged. | * The Rover reports that the window for 1A-59 at the PYR-A-LARM panel is lit. | ||
and | What is (are) the minimum required action(s) to ensure MH1, FIRE, will alarm again if 1A-39 comes into alarm? | ||
The Control Room Fire Panel alarm must be acknowledged. | A. The Control Room Fire Panel alarm must be acknowledged. | ||
and | and 1A-59 must be placed in OVERRIDE on the PYR-A-LARM panel. | ||
ONLY 1A-59 must be placed in OVERRIDE on the PYR-A-LARM panel.ONLY the Reflash Panel alarm for detection system 1A-59 must be acknowledged | B. The Control Room Fire Panel alarm must be acknowledged. | ||
and The Reflash Panel alarm for detection system 1A-59 must be acknowledged. | |||
: 50. AOP-28.0, Control Room | C. ONLY 1A-59 must be placed in OVERRIDE on the PYR-A-LARM panel. | ||
Which one of the following | D. ONLY the Reflash Panel alarm for detection system 1A-59 must be acknowledged. | ||
The 1A MDAFWP will be | : 50. AOP-28.0, Control Room Inaccessibility, is in progress on Unit 1. | ||
Which one of the following completes the statements below? | |||
FCVs in LOCAL at | The 1A MDAFWP will be operated in LOCAL at the (1) HSDP. | ||
Operator action is required to control the MDAFWP FCVs in LOCAL at the HSDP in order to prevent (2) . | |||
: 51. Unit 2 is at 100% power with the following conditions:* A #1 Waste Monitor Tank (WMT) release is in progress with the #1 WMT pump running. | (1) (2) | ||
A. F low SG water level due to valve position B. F isolating letdown due to cooldown C. A low SG water level due to valve position D. A isolating letdown due to cooldown | |||
: 51. Unit 2 is at 100% power with the following conditions: | |||
* A #1 Waste Monitor Tank (WMT) release is in progress with the #1 WMT pump running. | |||
* RCV-18, WMT DISCH TO ENVIRONMENT, is open. | * RCV-18, WMT DISCH TO ENVIRONMENT, is open. | ||
Subsequently R-18, LIQ | Subsequently R-18, LIQ WASTE DISCH, alarms HIGH. | ||
Which one of the following | Which one of the following completes the statements below? | ||
RCV-18 will (1) . | |||
The #1 WMT pump will (2) . | |||
(1) (2) | |||
A. remain open trip B. remain open continue to run C. close trip D. close continue to run | |||
: 52. Unit 1 is operating at 100% power with the following condition: | : 52. Unit 1 is operating at 100% power with the following condition: | ||
* A SG Tube Leak is in progress. | * A SG Tube Leak is in progress. | ||
* FCV-1152, SGBD HX Outlet Flow Control Valve, is stuck in the | * FCV-1152, SGBD HX Outlet Flow Control Valve, is stuck in the OPEN position. | ||
Which one of the following radiation monitors is able to automatically stop a release to the environment due to the SG Tube Rupture? | Which one of the following radiation monitors is able to automatically stop a release to the environment due to the SG Tube Rupture? | ||
R-23A, SGBD SRG TK INLET | A. R-23A, SGBD SRG TK INLET B. R-23B, SGBD SRG TK DISCH C. R-19, SGBD SAMPLE D. R-70A, SG TUBE LEAK DET | ||
R-23B, SGBD SRG TK DISCH R-19, SGBD SAMPLE R-70A, SG TUBE LEAK DET | |||
: 53. Unit 1 is operating at 100% power when the following occurs: | : 53. Unit 1 is operating at 100% power when the following occurs: | ||
* A Large Break LOCA | * A Large Break LOCA occurs inside containment. | ||
* Containment Pressure reaches 35 psig. | * Containment Pressure reaches 35 psig. | ||
Which one of the following | Which one of the following completes the statements below? | ||
MOV-3024A, EMERG SW FROM 1A CTMT CLR, opened due to a(n) | |||
(1) signal. | |||
Each CTMT Cooler will be supplied with approximately (2) GPM of Service Water flow. | |||
(1) (2) | |||
A. Safety Injection 2000 B. Safety Injection 800 C. Containment Spray 2000 D. Containment Spray 800 | |||
: 54. Unit 1 experienced a Safety Injection with LOSP. | : 54. Unit 1 experienced a Safety Injection with LOSP. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The 1A Charging Pump Room Cooler will automatically start due to a signal generated by the 1A Charging Pump (1) . | |||
Controls for starting the Charging Pump Room Coolers (2) located on the BOP Panel. | |||
(1) (2) | |||
A. Breaker ARE B. Breaker are NOT C. Room Thermostat ARE D. Room Thermostat are NOT | |||
: 55. Unit 1 is operating at 100% power with the following conditions: | : 55. Unit 1 is operating at 100% power with the following conditions: | ||
* The Gross Failed Fuel Detector (GFFD) has steadily indicated 2500 cpm | * The Gross Failed Fuel Detector (GFFD) has steadily indicated 2500 cpm during the entire fuel cycle. | ||
Subsequently, the following readings are recorded: | Subsequently, the following readings are recorded: | ||
Time 1000 1100 1200 1300 GFFD Indication (cpm) 1.1 X 104 1.5 X 104 4.4 X 104 1.3 X 105 Which one of the following is the earliest time the GFFD will be in High Alarm? | |||
A. 1000 B. 1100 C. 1200 D. 1300 | |||
: 56. Unit 1 is operating at 100% power with the following conditions: | : 56. Unit 1 is operating at 100% power with the following conditions: | ||
* AOP-5.2, Degraded Grid, has just been entered. | * AOP-5.2, Degraded Grid, has just been entered. | ||
* Voltage on all emergency busses for both units is reading 3875 volts. | * Voltage on all emergency busses for both units is reading 3875 volts. | ||
* MEGAVARS are reading (+) 100 on the MCB. | * MEGAVARS are reading (+) 100 on the MCB. | ||
* The Shift Supervisor has directed the UO to maintain (+) 400 MVARs in | * The Shift Supervisor has directed the UO to maintain (+) 400 MVARs in accordance with the voltage schedule. | ||
* The Unit 2 UO maintains MVARS | * The Unit 2 UO maintains MVARS stable on Unit 2 during the adjustment. | ||
Which one of the following will occur when the Unit 1 UO performs the adjustment as directed by the Shift Supervisor? | Which one of the following will occur when the Unit 1 UO performs the adjustment as directed by the Shift Supervisor? | ||
The operator will (1) | The operator will (1) Voltage, to reach (+) 400 MVARs. | ||
Voltage, to | After adjusting voltage, the temperature of large pump motors, such as the RCP or CW pump motors, will (2) . | ||
(1) (2) | |||
A. raise lower B. raise rise C. lower lower D. lower rise | |||
: 57. Unit 1 was manually tripped from 100% power and the following conditions exist: | : 57. Unit 1 was manually tripped from 100% power and the following conditions exist: | ||
* AOP-6.0, Loss of Instrument Air, is in progress. | * AOP-6.0, Loss of Instrument Air, is in progress. | ||
* The TDAFW pump automatically started. | * The TDAFW pump automatically started. | ||
* BOTH MDAFW pumps failed to start. | * BOTH MDAFW pumps failed to start. | ||
* The MSVR is not accessible | * The MSVR is not accessible. | ||
Subsequently, the following report is received from Mechanical Maintenance: | |||
* Restoration of | * Restoration of Instrument Air will take 3 hours. | ||
Which one of the following describes the required AOP-6.0 operator action(s), if any, and the reason? | Which one of the following describes the required AOP-6.0 operator action(s), if any, and the reason? | ||
No action is required | A. No action is required because the TDAFWP steam admission valves fail to the "as is" position. | ||
Manually close the TDAFWP steam | B. Manually close the TDAFWP steam admission valves to avoid causing an uncontrolled cooldown. | ||
Manually open the TDAFWP steam admission valves to provide an adequate heat sink. | C. Manually open the TDAFWP steam admission valves to provide an adequate heat sink. | ||
Manually align emergency air to the TDAFW | D. Manually align emergency air to the TDAFW pump steam admission valves to provide an adequate heat sink. | ||
: 58. Unit 1 is operating at 100% power when the following occurs: | : 58. Unit 1 is operating at 100% power when the following occurs: | ||
At 1000 | At 1000 | ||
* An Instrument Air malfunction occurs. | * An Instrument Air malfunction occurs. | ||
At 1015 | At 1015 | ||
* PI-4004B, INST AIR PRESS, indicates 50 psig and stable Which one of the following | * PI-4004B, INST AIR PRESS, indicates 50 psig and stable Which one of the following completes the statements below? | ||
At 1015 V904, Instrument Air to the Service Building, is (1) | At 1015 V904, Instrument Air to the Service Building, is (1) . | ||
A(n) (2) maintains MSIV air pressure following loss of instrument air pressure. | |||
(1) (2) | |||
A. OPEN accumulator B. OPEN compressed nitrogen cylinder C. CLOSED accumulator D. CLOSED compressed nitrogen cylinder | |||
: 59. Unit 1 is shutdown following a LOCA with the following conditions: | : 59. Unit 1 is shutdown following a LOCA with the following conditions: | ||
* PI-402A and PI-403A, RCS WR | * PI-402A and PI-403A, RCS WR PRESS, indicate 600 psig and stable. | ||
* PR-950Z, CTMT PRESS, | * PR-950Z, CTMT PRESS, indicates 32 psig and slowly lowering. | ||
Subsequently, ONLY the | Subsequently, ONLY the following actions are taken: | ||
* SI BLOCK RESET A | * SI BLOCK RESET A TRN pushbutton is depressed. | ||
* SI BLOCK RESET B | * SI BLOCK RESET B TRN pushbutton is depressed. | ||
* PHASE B CTMT | * PHASE B CTMT ISO RESET A TRN pushbutton is depressed. | ||
* PHASE B CTMT | * PHASE B CTMT ISO RESET B TRN pushbutton is depressed. | ||
Which one of the following | Which one of the following completes the statements below: | ||
PHASE A CNMT ISO (1) reset. | |||
PHASE B CNMT ISO (2) reset. | |||
(1) (2) | |||
A. IS is NOT B. IS IS C. is NOT is NOT D. is NOT IS | |||
: 60. Unit 1 is operating at 100% power when the following conditions occur: | : 60. Unit 1 is operating at 100% power when the following conditions occur: | ||
* Phase A is actuated using the MCB handswitches. | * Phase A is actuated using the MCB handswitches. | ||
How has the Phase A signal affected the following valve positions? | How has the Phase A signal affected the following valve positions? | ||
Valve Nomenclature | Valve Nomenclature: | ||
HV-8152, LTDN LINE CTMT ISO MOV-8112, RCP SEAL WTR RTN ISO HV-8149A, LTDN ORIF ISO 45 GPM MOV-3052, CCW TO RCP CLRS A. Only HV-8152, HV-8149A, and MOV-8112 have closed. | |||
B. Only HV-8152, MOV-8112, and MOV-3052 have closed. | |||
MOV-8112, RCP SEAL WTR RTN ISO | C. Only HV-8152, and HV-8149A have closed. | ||
D. Only HV-8152 has closed. | |||
HV-8149A, LTDN ORIF ISO 45 GPM | |||
MOV-3052, CCW TO RCP CLRS Only HV-8152, HV-8149A, and MOV-8112 have closed. | |||
Only HV-8152, MOV-8112, and MOV-3052 have closed. | |||
Only HV-8152, and HV-8149A have closed. | |||
Only HV-8152 has closed | |||
: 61. A Main Control Board Deficiency related to a MCB handswitch has been identified. | : 61. A Main Control Board Deficiency related to a MCB handswitch has been identified. | ||
Which one of the following completes | Which one of the following completes the statements below IAW SOP-0.10, FNP Operations Site Specific Policies? | ||
A (1) is required to be created to identify the deficiency. | |||
The identifier (Deficiency Tag/Control Room DOT) will be (2) . | |||
(1) (2) | |||
A. Deficiency Tag affixed to the MCB handswitch B. Deficiency Tag placed in the deficiency notebook C. Control Room DOT affixed to the MCB handswitch D. Control Room DOT placed in the deficiency notebook | |||
: 62. Unit 1 experiences a Reactor Trip with Safety injection. | : 62. Unit 1 experiences a Reactor Trip with Safety injection. | ||
Subsequently, the following occurs: | Subsequently, the following occurs: | ||
* The UO directs the Turbine | * The UO directs the Turbine Building Systems Operator (TB SO) to perform the TB SO Actions Following a Reactor Trip or Safety Injection. | ||
Which one of the following completes the statements below per SOP-0.0, Appendix A, TB SO Actions Following a | Which one of the following completes the statements below per SOP-0.0, Appendix A, TB SO Actions Following a Reactor Trip and/or Safety Injection? | ||
The TB SO is required to close V-503A, 1A MSR 2ND STG STM SUPP ISO (1) . | |||
: 63. Which one of the following completes the statements below per NMP-AP-001-003, Review and | The TB SO is required to close V-905A, 1A MS LINE DRN POT TO COND ISO (2) . | ||
(1) (2) | |||
A. following any Reactor trip following any Reactor trip B. following any Reactor trip only when specifically directed C. only when specifically directed following any Reactor trip D. only when specifically directed only when specifically directed | |||
: 63. Which one of the following completes the statements below per NMP-AP-001-003, Review and Approval of Site Procedures? | |||
The "Pen and Ink" Change Process may be used for (1) changes. | |||
A Condition Report (2) required following use of a procedure with "Pen and Ink" changes. | |||
(1) (2) | |||
A. editorial IS B. editorial is NOT C. temporary IS D. temporary is NOT | |||
: 64. Unit 1 is in a Refueling Outage with fuel being loaded into the core. | : 64. Unit 1 is in a Refueling Outage with fuel being loaded into the core. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Per TRM 13.1.6, Borated | Per TRM 13.1.6, Borated Water Source - Shutdown, the minimum operable BAT Tank Temperature is (1) . | ||
Per TRM 13.1.6, the minimum operable BAT Tank Volume is (2) . | |||
: 65. Unit 1 is exiting a refueling outage with the following conditions: | (1) (2) | ||
A. 35°F 2000 gallons B. 35°F 11336 gallons C. 65°F 2000 gallons D. 65°F 11336 gallons | |||
: 65. Unit 1 is exiting a refueling outage with the following conditions: | |||
Time 1000 1200 1400 1600 Average Coolant Temp (°F) 300 450 547 547 Rated Thermal Power (%) 0 0 2 6 Keff <.99 <.99 1.00 1.00 Which one of the following completes the statements below? | |||
The earliest time Unit 1 is in MODE 4 is at (1) . | |||
The earliest time Unit 1 is in MODE 1 is at (2) . | |||
(1) (2) | |||
A. 1000 1400 B. 1000 1600 C. 1200 1400 D. 1200 1600 | |||
: 66. A Plant Operator has been assigned a portable RAM 100 frisker for personnel monitoring when exiting the dry cask storage area with the following condition: | : 66. A Plant Operator has been assigned a portable RAM 100 frisker for personnel monitoring when exiting the dry cask storage area with the following condition: | ||
* The Frisker Response Checks were last performed 7 days ago. | * The Frisker Response Checks were last performed 7 days ago. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The frisker detects (1) . | |||
The Frisker Response Checks for the assigned frisker are required to be performed (2) . | |||
A. (1) Beta and Gamma radiation (2) prior to use B. (1) Beta and Gamma radiation (2) 6 months from the date of the last response check C. (1) ONLY Gamma radiation (2) prior to use D. (1) ONLY Gamma radiation (2) 6 months from the date of the last response check | |||
: 67. You are assigned a task: | : 67. You are assigned a task: | ||
* Your current TEDE is 1500 mrem. | * Your current TEDE is 1500 mrem. | ||
* Dose rate in the area you | * Dose rate in the area you are required to work is 1500 mr/hr. | ||
Which one of the following is the maximum amount of time you can stay in the area without exceeding Farley Administrative TEDE limits with no additional approval? | Which one of the following is the maximum amount of time you can stay in the area without exceeding Farley Administrative TEDE limits with no additional approval? | ||
20 minutes 100 minutes 120 minutes 140 minutes | A. 20 minutes B. 100 minutes C. 120 minutes D. 140 minutes | ||
: 68. EEP-0.0, Reactor Trip or Safety Injection, provides specific Reactor Coolant Pump (RCP) trip criteria on the foldout page. | : 68. EEP-0.0, Reactor Trip or Safety Injection, provides specific Reactor Coolant Pump (RCP) trip criteria on the foldout page. | ||
Which one of the following is the reason | Which one of the following is the reason for tripping the RCPs when these conditions occur? | ||
Prevents RCP seal damage | A. Conserves RCS inventory during a Small Break LOCA with subsequent LOSP. | ||
Prevents pump runout | B. Prevents RCP seal damage following a Small Break LOCA. | ||
Ensures core reflood | C. Prevents pump runout following a Large Break LOCA. | ||
D. Ensures core reflood following a Large Break LOCA. | |||
: 69. Unit 1 and Unit 2 are operating at 100% power when the following condition occurs:* | : 69. Unit 1 and Unit 2 are operating at 100% power when the following condition occurs: | ||
Which one of the following | * The Outside System Operator reports a fire in the Liquid hydrogen storage tank vent stack. | ||
Which one of the following completes the statement below? | |||
discharging a portable fire | Per AOP-29.0, Plant Fire, and SOP-34.0, Hydrogen-Oxygen System the fire will be extinguished by . | ||
establishing a helium purge and isolating the leak. | A. spraying water directly on the vent stack and isolating the leak. | ||
isolating the leak ONLY | B. discharging a portable fire extinguisher into the vent stack and isolating the leak. | ||
C. establishing a helium purge and isolating the leak. | |||
D. isolating the leak ONLY. | |||
: 70. The following condition exist on Unit 1: | : 70. The following condition exist on Unit 1: | ||
* The TSC is fully manned and is | * The TSC is fully manned and is directing the plant response to a NOUE. | ||
Subsequently, the following occurs: | Subsequently, the following occurs: | ||
* The Emergency Director declares a SITE AREA EMERGENCY. | * The Emergency Director declares a SITE AREA EMERGENCY. | ||
Which one of the following completes the statements below? | |||
Which one of the following | Per NMP-EP-111, Emergency Notifications, a (1) tone will be sounded prior to the onsite notification announcement. | ||
Per NMP-EP-111, Emergency Notifications, the (2) | Per NMP-EP-111, Emergency Notifications, the (2) is responsible for approving notifcations to State and Local Authorities of the emergency condition. | ||
(1) (2) | |||
A. YELP Emergency Director B. WARBLE Emergency Director C. YELP Shift Manager D. WARBLE Shift Manager | |||
: 71. An RCS soak is in progress per FRP-P.1, Response to Imminent Pressurized Thermal Shock Condition, on Unit 1. | : 71. An RCS soak is in progress per FRP-P.1, Response to Imminent Pressurized Thermal Shock Condition, on Unit 1. | ||
Which one of the following actions is permitted? | Which one of the following actions is permitted? | ||
Start a Charging Pump. | A. Start a Charging Pump. | ||
B. Energize PZR heaters. | |||
Energize PZR heaters. | C. Start an RCP. | ||
Start an RCP. | D. Isolate Accumulators. | ||
Isolate Accumulators | |||
: 72. Unit 1 is shutdown following a Large Break LOCA followed by an LOSP. The following conditions occur: | : 72. Unit 1 is shutdown following a Large Break LOCA followed by an LOSP. The following conditions occur: | ||
At 1000: | At 1000: | ||
* WA2, 1-2A DG GEN FAULT TRIP, alarms. | * WA2, 1-2A DG GEN FAULT TRIP, alarms. | ||
At 1015:* CF3, 1A OR 1B RHR PUMP OVERLOAD TRIP, alarms. | At 1015: | ||
* RWST level is 3 ft.* Containment Spray pump | * CF3, 1A OR 1B RHR PUMP OVERLOAD TRIP, alarms. | ||
Which one of the following | * RWST level is 3 ft. | ||
At 1015 (1) | * Containment Spray pump suctions are aligned to the RWST. | ||
Which one of the following completes the statements below? | |||
: 73. Unit 1 is shutdown with ECP-2.1, Uncontrolled Depressurization of All Steam Generators in progress. | At 1015 (1) train(s) of emergency coolant recirculation capability has(have) been lost. | ||
* All MSIV - TRIP | The operating crew (2) required to secure all CTMT Spray at 1015. | ||
(1) (2) | |||
A. ONLY one IS B. ONLY one is NOT C. BOTH IS D. BOTH is NOT | |||
: 73. Unit 1 is shutdown with ECP-2.1, Uncontrolled Depressurization of All Steam Generators in progress. The following conditions exist: | |||
* All MSIV - TRIP handswitches have been taken to CLOSE. | |||
* JH1, 1A SG MSIV CLOSED is NOT lit. | * JH1, 1A SG MSIV CLOSED is NOT lit. | ||
* JH2, 1B SG MSIV CLOSED is NOT lit. | * JH2, 1B SG MSIV CLOSED is NOT lit. | ||
* JH3, 1C SG MSIV CLOSED is NOT lit. | * JH3, 1C SG MSIV CLOSED is NOT lit. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The next action the crew is required to take per ECP-2.1 is (1) . | |||
If an MSIV is closed, ECP-2.1 directs use of (2) to determine if a Steam Generator has been isolated. | |||
A. (1) Place the MSIV -TEST handswitch to TEST (2) Cold Leg Temperature B. (1) Place the MSIV - TEST handswitch to TEST (2) SG Pressure C. (1) Manually remove air pressure from the MSIVs (2) Cold Leg Temperature D. (1) Manually remove air pressure from the MSIVs (2) SG Pressure | |||
: 74. Unit 1 is shutdown with the following conditions: | : 74. Unit 1 is shutdown with the following conditions: | ||
* 1A SG Pressure is 1145 psig and rising. | * 1A SG Pressure is 1145 psig and rising. | ||
* The 1A Atmospheric Relief Valve is mechanically bound and | * The 1A Atmospheric Relief Valve is mechanically bound and cannot be opened. | ||
* All MSIV and MSIV Bypasses are closed. | * All MSIV and MSIV Bypasses are closed. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Entry conditions for FRP-H.2, Response to Steam Generator Overpressure (1) been met When FRP-H.2 is entered, the crew would be directed to lower 1A SG Pressure by (2) . | |||
(1) (2) | |||
A. have NOT dumping steam to the TDAFWP B. HAVE dumping steam to the TDAFWP C. have NOT opening MSIV bypasses D. HAVE opening MSIV bypasses | |||
: 75. Unit 1 has experienced a Large Break LOCA with the following conditions: | : 75. Unit 1 has experienced a Large Break LOCA with the following conditions: | ||
* PR-0950Z, CTMT PRESS NR, indicates 30 psig. | * PR-0950Z, CTMT PRESS NR, indicates 30 psig. | ||
* LI-3594A, CTMT SUMP LVL, indicates 8 FT. | * LI-3594A, CTMT SUMP LVL, indicates 8 FT. | ||
* FI-958 A and B, CS FLOW , indicate 1200 GPM each. | * FI-958 A and B, CS FLOW, indicate 1200 GPM each. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Per CSF-0.5, Containment, the crew is required to enter a(n) (1) path FRP due to (2) . | |||
(1) (2) | |||
A. RED CTMT Pressure B. RED CTMT Sump Level C. ORANGE CTMT Pressure D. ORANGE CTMT Sump Level | |||
: 76. Unit 1 was operating at 100% power when the following occurred: | : 76. Unit 1 was operating at 100% power when the following occurred: | ||
At 1000: | At 1000: | ||
* All Control Banks are at 231 steps. | * All Control Banks are at 231 steps. | ||
At 1010:* Rod K4 fell to 130 steps.* Rod M6 fell to 150 steps. | At 1010: | ||
* Rod K4 fell to 130 steps. | |||
* Rod M6 fell to 150 steps. | |||
* RCS Tavg lowered. | * RCS Tavg lowered. | ||
* Pressurizer pressure lowered. | * Pressurizer pressure lowered. | ||
Which one of the following | Which one of the following completes the statement below? | ||
Per AOP-19, Malfunction of Rod Control System, the operating crew is required to | Per AOP-19, Malfunction of Rod Control System, the operating crew is required to . | ||
A. shutdown the unit using UOP-3.1, Power Operation B. trip the Reactor and go to EEP-0.0, Reactor Trip and Safety Injection C. reduce power to less than 75% within 1 hour using UOP-3.1, Power Operation D. address restoration of rods using SOP-41.0, Control Rod Drive and Position Indication System | |||
: 77. Unit 1 is operating at 100% power when the following occurs: | : 77. Unit 1 is operating at 100% power when the following occurs: | ||
At 1000: | At 1000: | ||
* HH4, RCP VIB TRBL (WHITE | * HH4, RCP VIB TRBL (WHITE annunciator window), comes into alarm. | ||
* 1A RCP shaft vibration is reported as 21 mils and stable. | * 1A RCP shaft vibration is reported as 21 mils and stable. | ||
* DC2, RCP #1 SEAL LKOF FLOW HI (YELLOW annunciator window), | * DC2, RCP #1 SEAL LKOF FLOW HI (YELLOW annunciator window), | ||
* FR145A, | comes into alarm. | ||
* FR145A, RCP SEAL LKOF HIGH RANGE, for the 1A RCP indicates 6.5 gpm and stable. | |||
At 1600: | At 1600: | ||
* The Unit is in MODE 3. | * The Unit is in MODE 3. | ||
Line 1,313: | Line 1,573: | ||
* 1B and 1C RCPs are running. | * 1B and 1C RCPs are running. | ||
* 1A RCP is tagged out. | * 1A RCP is tagged out. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1000 , the operating crew is required to (1) | At 1000, the operating crew is required to (1) , then secure the 1A RCP. | ||
At 1600 , RCS pressure control is via (2) | At 1600, RCS pressure control is via (2) . | ||
A. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Normal Spray B. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Normal Spray C. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Auxiliary Spray D. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Auxiliary Spray | |||
: 78. Unit 1 is operating at 100% power when the following occurs: | : 78. Unit 1 is operating at 100% power when the following occurs: | ||
* Due to a Pressurizer pressure | * Due to a Pressurizer pressure control malfunction, PCV-445A, PRZR PORV opens and reseats several times. | ||
* PRT parameters are: | * PRT parameters are: | ||
- Level: 84% and is stable. | |||
- Temperature: 180°F and stable. | |||
- Pressure: 30 psig and stable. | |||
Which one of the following | Which one of the following completes the statements below? | ||
Draining the PRT using the RCDT pump per | HE4, PRT LVL HI-LO, (1) in alarm. | ||
Procedure name | Draining the PRT using the RCDT pump per Section 4.3, Filling and Draining the PRT, of SOP-1.2 (2) restore all PRT parameters to within normal log specifications. | ||
: SOP-1.2, Reactor Coolant Pressure Relief System (1) | Procedure name: SOP-1.2, Reactor Coolant Pressure Relief System (1) (2) | ||
A. is NOT will NOT B. IS will NOT C. is NOT WILL D. IS WILL | |||
: 79. Unit 1 is in MODE 3 with the following conditions: | : 79. Unit 1 is in MODE 3 with the following conditions: | ||
At 1000: | At 1000: | ||
Line 1,332: | Line 1,593: | ||
At 1005: | At 1005: | ||
* A complete loss of offsite power occurs. | * A complete loss of offsite power occurs. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1005, manual action (1) | At 1005, manual action (1) required to generate a P-4 signal. | ||
Per the BASES of Tech Spec 3.3.2, ESFAS | Per the BASES of Tech Spec 3.3.2, ESFAS Instrumentation, P-4 is required to be OPERABLE to prevent (2) . | ||
: 80. Unit 1 is operating at 100% power with the following conditions:* A malfunction occurred | A. (1) IS (2) excessive Containment pressure due to a steamline break B. (1) is NOT (2) excessive Containment pressure due to a steamline break C. (1) IS (2) damage to the Main Steam lines and SG safeties due to SG overfill D. (1) is NOT (2) damage to the Main Steam lines and SG safeties due to SG overfill | ||
* PRT pressure, level and temperature are stable.* HA4, PRZR SAFETY VLV TEMP HI, is in alarm.* HA5, PRZR PORV TEMP HI, is in alarm. | : 80. Unit 1 is operating at 100% power with the following conditions: | ||
* A malfunction occurred resulting in PCV-444B, PRZR PORV, opening. | |||
Subsequently, the immediate operator actions of AOP-100, Instrumentation Malfunction, were performed and the following conditions exist: | |||
* PCV-444B GREEN light is LIT. | |||
* MOV-8000B, PRZR PORV ISO, RED light is LIT. | |||
* RCS pressure is 2180 psig and stable. | |||
* PRT pressure, level and temperature are stable. | |||
* HA4, PRZR SAFETY VLV TEMP HI, is in alarm. | |||
* HA5, PRZR PORV TEMP HI, is in alarm. | |||
* HD1, PRZR PRESS REL VLV 445A OR B/U HTRS ON, is in alarm. | * HD1, PRZR PRESS REL VLV 445A OR B/U HTRS ON, is in alarm. | ||
Which one of the following | Which one of the following completes the statements below? | ||
PCV-444B | PCV-444B (1) leaking by. | ||
Per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), PCV-444B (2) | Per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), PCV-444B (2) OPERABLE. | ||
(1) (2) | |||
A. IS IS B. IS is NOT C. is NOT IS D. is NOT is NOT | |||
: 81. Unit 1 is at 100% power with the following conditions: | : 81. Unit 1 is at 100% power with the following conditions: | ||
* PT-950, CTMT PRESS (Channel 1), was | * PT-950, CTMT PRESS (Channel 1), was declared INOPERABLE. | ||
* PT-950 bistables were positioned as required by Tech Spec 3.3.2, | * PT-950 bistables were positioned as required by Tech Spec 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, for continuous operation with an inoperable channel. | ||
Which one of the following | Which one of the following completes the statements below? | ||
Per Tech Spec 3.3.2, the | The Safety Injection function (1) affected by the PT-950 malfunction. | ||
Per Tech Spec 3.3.2, the REQUIRED ACTION is to place the PT-950 bistables in (2) . | |||
(1) (2) | |||
A. IS TRIP B. IS BYPASS C. is NOT TRIP D. is NOT BYPASS | |||
: 82. Unit 1 is in MODE 3 with the following conditions: | : 82. Unit 1 is in MODE 3 with the following conditions: | ||
* All RCPs are running. | * All RCPs are running. | ||
* A CCW leak occurs on the 1A RCP Oil Cooler inlet connection. | * A CCW leak occurs on the 1A RCP Oil Cooler inlet connection. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The method used in the Main Control Room (MCR) to isolate the CCW leak is to (1) | The method used in the Main Control Room (MCR) to isolate the CCW leak is to (1) . | ||
Per the BASES of Tech Spec 3.7.7 - CCW System, once the CCW leak is isolated from the MCR, the CCW System is (2) . | |||
A. (1) isolate CCW to ALL RCPs (2) INOPERABLE B. (1) isolate CCW to the 1A RCP ONLY (2) INOPERABLE C. (1) isolate CCW to ALL RCPs (2) OPERABLE D. (1) isolate CCW to the 1A RCP ONLY (2) OPERABLE | |||
: 83. Unit 1 has experienced a LOCA. The following conditions exist: | : 83. Unit 1 has experienced a LOCA. The following conditions exist: | ||
* EEP-1.0, Loss of Reactor or Secondary Coolant, is in progress. | * EEP-1.0, Loss of Reactor or Secondary Coolant, is in progress. | ||
* Containment Hydrogen is 6% | * Containment Hydrogen is 6% by volume of dry air. | ||
by volume of dry air. | Which one of the following completes the statements below? | ||
Which one of the following | The hydrogen concentration (1) exceed the lower FLAMMABILITY limit. | ||
The hydrogen concentration (1) | Hydrogen concentration will be lowered using (2) . | ||
: 84. Unit 1 is operating at 100% | A. (1) DOES (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System B. (1) DOES (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation C. (1) does NOT (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System D. (1) does NOT (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation | ||
: 84. Unit 1 is operating at 100% when a Pressurizer level control malfunction occurs and the following conditions exist: | |||
* Pressurizer level is 70% and rising. | * Pressurizer level is 70% and rising. | ||
* Charging flow is 120 gpm. | * Charging flow is 120 gpm. | ||
Line 1,366: | Line 1,640: | ||
* RCP seal injection is 8 gpm to each RCP. | * RCP seal injection is 8 gpm to each RCP. | ||
* RCP seal leakoff is 3 gpm per pump. | * RCP seal leakoff is 3 gpm per pump. | ||
* Actions in the field are being taken to regain | * Actions in the field are being taken to regain control of Charging. | ||
* It will take 8 minutes to regain control of Charging. | * It will take 8 minutes to regain control of Charging. | ||
Which one of the following | Which one of the following completes the statements below? | ||
An | An automatic reactor trip (1) occur before control of Charging is regained. | ||
Per the BASES of Tech Spec 3.3. | Per the BASES of Tech Spec 3.3.1, Reactor Trip System (RTS) | ||
1, Reactor Trip System (RTS) | Instrumentation, the purpose of the automatic Reactor Trip on Pressurizer Water Level - High is to (2) . | ||
Instrumentation, the purpose of the | Reference Provided A. (1) WILL (2) provide protection against water relief through the PORV's B. (1) WILL (2) prevent thermal shock of the Spray Nozzle C. (1) will NOT (2) provide protection against water relief through the PORV's D. (1) will NOT (2) prevent thermal shock of the Spray Nozzle | ||
: 85. Unit 1 is conducting a fuel reload and the following occurs: | : 85. Unit 1 is conducting a fuel reload and the following occurs: | ||
At 1015: An Intermediate Leg leak is in progress on the 1A RCS loop with the following conditions. | At 1015: An Intermediate Leg leak is in progress on the 1A RCS loop with the following conditions. | ||
Line 1,378: | Line 1,652: | ||
* EH2, SFP LVL HI-LO is in alarm. | * EH2, SFP LVL HI-LO is in alarm. | ||
* Both RHR pumps have been secured due to cavitation. | * Both RHR pumps have been secured due to cavitation. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1030 , an emergency classification , per NMP-EP-110, Emergency Classification | At 1030, an emergency classification, per NMP-EP-110, Emergency Classification Determination and Initial Action, (1) required. | ||
Per AOP-12, Residual Heat | Per AOP-12, Residual Heat Removal System Malfunction, the maximum time to complete Containment closure is (2) hour(s). | ||
(1) (2) | |||
A. IS 1 B. IS 2 C. is NOT 1 D. is NOT 2 | |||
: 86. A fuel shuffle is in progress in the Unit 1 SFP with the following conditions: | : 86. A fuel shuffle is in progress in the Unit 1 SFP with the following conditions: | ||
At 1000: | At 1000: | ||
* An 1800 lb. load is | * An 1800 lb. load is being moved over spent fuel. | ||
At 1015: | At 1015: | ||
* The load is dropped causing damage to the spent fuel. | * The load is dropped causing damage to the spent fuel. | ||
At 1015 , which one of the | At 1015, which one of the following describes the minimum Radiation Monitor(s) required to be in alarm to meet AOP-30, Refueling Accident, entry conditions? | ||
AND Which one of the following describes the the expected worst case consequences of dropping an 1800 lb. | AND Which one of the following describes the the expected worst case consequences of dropping an 1800 lb. load onto the spent fuel Per the Bases of TR 13.9.4, Crane Travel-Spent Fuel Storage Building? | ||
A. | |||
* R-5 OR R-25A | |||
* The activity release will be limited to that contained in a single fuel assembly. | |||
B. | |||
* R-5 OR R-25A | |||
* The offsite dose may be as high as but not more than the 10 CFR 100 limit. | |||
C. | |||
* R-5 AND R-25A | |||
* The activity release will be limited to that contained in a single fuel assembly. | |||
D. | |||
* R-5 AND R-25A | |||
* The offsite dose may be as high as but not more than the 10 CFR 100 limit. | |||
: 87. Unit 1 was operating at 100% power with the following conditions: | : 87. Unit 1 was operating at 100% power with the following conditions: | ||
At 1000: | At 1000: A Loss of Offsite Power occurs. | ||
At 1015: | At 1015: The following conditions exist - | ||
* DG-02, | * DG-02, 1G 4160 V bus tie to 1L 4160 V bus, has AMBER and GREEN Lights LIT. | ||
* 4160V BUS 1L AC PWR AVAIL lights are NOT lit. | * 4160V BUS 1L AC PWR AVAIL lights are NOT lit. | ||
Which one of the following | Which one of the following completes the statements below? | ||
At 1015: The 1B DG (1) | At 1015: The 1B DG (1) have cooling water supplied. | ||
At 1015: The REQUIRED ACTION(S) of | At 1015: The REQUIRED ACTION(S) of Tech Spec(s) (2) is(are) required to be performed. | ||
Tech Spec nomenclature: 3.8.9, Distribution Systems - Operating 3.7.8, Service Water System (SWS) | |||
Tech Spec(s) | (1) (2) | ||
A. WILL 3.8.9 AND 3.7.8 B. will NOT 3.8.9 AND 3.7.8 C. WILL 3.8.9 ONLY D. will NOT 3.8.9 ONLY | |||
: 88. Unit 1 is in Mode 3 with the following conditions: | : 88. Unit 1 is in Mode 3 with the following conditions: | ||
* Pressurizer level is 22% and stable. | * Pressurizer level is 22% and stable. | ||
Subsequently, a rupture occurs on the Instrument Air header piping in the MSVR and AOP-6.0, Loss of Instrument Air, is in progress. | |||
Subsequently, a rupture occurs on the | Which one of the following completes the statements below? | ||
Which one of the following | Pressurizer level will (1) . | ||
Procedure Names | Per AOP-6.0, to maintain Pressurizer level, the operating crew is required to perform actions of (2) in conjunction with AOP-6.0. | ||
: AOP-16.0, CVCS Malfunction | Procedure Names: AOP-16.0, CVCS Malfunction SOP-2.1, CVCS Plant Startup and Operation (1) (2) | ||
A. lower AOP-16.0 B. rise AOP-16.0 C. lower SOP-2.1 D. rise SOP-2.1 | |||
: 89. Unit 1 is operating at 100% power when the following occurs: | : 89. Unit 1 is operating at 100% power when the following occurs: | ||
* R-27B, CTMT HIGH RANGE, is tagged out. | * R-27B, CTMT HIGH RANGE, is tagged out. | ||
* The instrument power supply fuse to R-27A, CTMT HIGH RANGE, blows. | * The instrument power supply fuse to R-27A, CTMT HIGH RANGE, blows. | ||
Which one of the following | Which one of the following completes the statements below? | ||
R-27A indication will fail (1) | R-27A indication will fail (1) . | ||
Per Tech Spec 3.3.3, Post Accident Monitoring Instrumentation, the REQUIRED ACTION is to (2) . | |||
Reference Provided A. (1) HIGH (2) immediately initiate action in accordance with Specification 5.6.8 B. (1) HIGH (2) restore R-27A OR R-27B to OPERABLE status in 7 days C. (1) LOW (2) immediately initiate action in accordance with Specification 5.6.8 D. (1) LOW (2) restore R-27A OR R-27B to OPERABLE status in 7 days | |||
: 90. Unit 1 is operating at 100% power and the following occurs: | : 90. Unit 1 is operating at 100% power and the following occurs: | ||
* R-15A, SJAE EXH, power supply | * R-15A, SJAE EXH, power supply becomes erratic causing its indication to become unreliable but it does not alarm. | ||
No actions are required. | Per the ODCM, which one of the following actions are required to continue the release via this pathway, if any? | ||
Continuously collect samples using auxiliary equipment. | A. No actions are required. | ||
Place SJAE filtration in service until R-15A is restored to operable. | B. Continuously collect samples using auxiliary equipment. | ||
Perform grab samples at least once per 8 hours and analyze them within 24 hours | C. Place SJAE filtration in service until R-15A is restored to operable. | ||
D. Perform grab samples at least once per 8 hours and analyze them within 24 hours. | |||
: 91. Unit 1 is in MODE 6 with the following conditions: | : 91. Unit 1 is in MODE 6 with the following conditions: | ||
* Core reload is complete. | * Core reload is complete. | ||
* Control Rod Drive Shaft Latching and RCCA Drag Testing is about to begin per | * Control Rod Drive Shaft Latching and RCCA Drag Testing is about to begin per FHP-5.1, Control Rod Drive Shaft Latching/Unlatching Tool Operating Instruction. | ||
Which one of the following | Which one of the following completes the statements below? | ||
(1) is required to be in Containment(2) are NOT (1) is required to be in Containment (2) ARE (1) may be in the Control Room in direct | Per FHP-0.0, Refueling Organization, the Fuel Handling Supervisor (1) . | ||
: 92. A tagout is required to be cleared during night shift and the Work Document Holder is not | Per UOP-4.1, Controlling Procedure for Refueling, two Source Range Nuclear Instruments (2) required to be OPERABLE. | ||
Per NMP-AD-003, Equipment Clearance and Tagging, which one of the following can sign off | A. (1) is required to be in Containment (2) are NOT B. (1) is required to be in Containment (2) ARE C. (1) may be in the Control Room in direct Communication with Containment (2) are NOT D. (1) may be in the Control Room in direct Communication with Containment (2) ARE | ||
Shift Manager Operations Director Maintenance Director Maintenance Manager | : 92. A tagout is required to be cleared during night shift and the Work Document Holder is not on site and cannot be contacted to gain their approval. | ||
Per NMP-AD-003, Equipment Clearance and Tagging, which one of the following can sign off the Work Document Holder? | |||
A. Shift Manager B. Operations Director C. Maintenance Director D. Maintenance Manager | |||
: 93. Unit 1 is at 6% power with the following conditions: | : 93. Unit 1 is at 6% power with the following conditions: | ||
* The 1A SGFP has been started. | * The 1A SGFP has been started. | ||
Line 1,436: | Line 1,724: | ||
* The Main Feed Regulating Valves are closed. | * The Main Feed Regulating Valves are closed. | ||
At 1000 on January 1, 2015: | At 1000 on January 1, 2015: | ||
* MOV-3232B, MAIN FW TO 1B SG | * MOV-3232B, MAIN FW TO 1B SG STOP VLV , is declared INOPERABLE. | ||
At 1200 on January 1, 2015 | At 1200 on January 1, 2015: | ||
: | |||
* FCV-489, 1B SG FW BYP FLOW, is declared INOPERABLE. | * FCV-489, 1B SG FW BYP FLOW, is declared INOPERABLE. | ||
Subsequently it is determined that | Subsequently it is determined that repairs will take 96 hours for each valve. | ||
Which one of the following | Which one of the following completes the statement below? | ||
Per Tech Spec 3.7.3, Main Feedwater | Per Tech Spec 3.7.3, Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves, the earliest time that feed flow to the 1B SG must be isolated is . | ||
Reference Provided A. 1800 on January 1, 2015 B. 2000 on January 1, 2015 C. 1000 on January 4, 2015 D. 1200 on January 4, 2015 | |||
: 94. A General Emergency on Unit 1 has been declared with following conditions: | : 94. A General Emergency on Unit 1 has been declared with following conditions: | ||
* An Emergency Response Team is required to be dispatched to isolate an | * An Emergency Response Team is required to be dispatched to isolate an offsite release source. | ||
* The TSC has not yet been manned. | * The TSC has not yet been manned. | ||
* The expected exposure for the job is 35 REM TEDE per person. | * The expected exposure for the job is 35 REM TEDE per person. | ||
Which one of the following | Which one of the following completes the statements below? | ||
To receive the dose listed above, operators (1) | To receive the dose listed above, operators (1) required to be volunteers. | ||
The (2) will authorize the exposure. | |||
(1) (2) | |||
A. are NOT RP Supervisor B. are NOT Shift Manager C. ARE RP Supervisor D. ARE Shift Manager | |||
: 95. Unit 1 is in MODE 6 with core offload in progress with the following condition: | : 95. Unit 1 is in MODE 6 with core offload in progress with the following condition: | ||
* A spent fuel assembly is being moved from its assigned location in the core to | * A spent fuel assembly is being moved from its assigned location in the core to the upender. | ||
Subsequently, AOP-30.0, | Subsequently, AOP-30.0, Refueling Accident, is entered Which one of the following completes the statements below? | ||
Per AOP-30.0, the Refueling SRO will direct the fuel assembly to be (1) | Per AOP-30.0, the Refueling SRO will direct the fuel assembly to be (1) . | ||
Per the BASES of Tech Spec 3.9.6, Refueling Cavity Water Level, 23 ft of water is required to be maintained above the fuel to (2) . | |||
A. (1) placed in any empty fuel location in the core (2) provide back up decay heat removal B. (1) placed in any empty fuel location in the core (2) retain iodine fission product activity in the water during a fuel handling accident C. (1) returned to its assigned location in the core (2) provide back up decay heat removal D. (1) returned to its assigned location in the core (2) retain iodine fission product activity in the water during a fuel handling accident | |||
: 96. Unit 2 reactor startup is in progress and the following conditions exist: | : 96. Unit 2 reactor startup is in progress and the following conditions exist: | ||
* NI31, SR1 COUNT RATE is | * NI31, SR1 COUNT RATE is 106 cps and stable. | ||
* NI32, SR2 COUNT RATE is | * NI32, SR2 COUNT RATE is 104 cps and stable. | ||
* TSLB-3 1-1, SR HI Q NC-31D is lit. | * TSLB-3 1-1, SR HI Q NC-31D is lit. | ||
* TSLB-3 1-2, SR HI Q NC-32D is NOT lit. | * TSLB-3 1-2, SR HI Q NC-32D is NOT lit. | ||
* GA1, SR HI FLUX TRIP, is in alarm. | * GA1, SR HI FLUX TRIP, is in alarm. | ||
* The Reactor Trip breakers are closed.Subsequently, The Shift Supervisor directs a manual Reactor trip. | * The Reactor Trip breakers are closed. | ||
* The | Subsequently, The Shift Supervisor directs a manual Reactor trip. | ||
* The Reactor Trip breakers open. | |||
Which one of the following completes the statements below? | |||
: 97. Unit 1 is performing the actions of EEP-0.0, Reactor Trip or Safety Injection, and AOP-9, Loss of Component Cooling | An emergency classification threshold value (1) been exceeded per NMP-EP-110-GL01, FNP EALS - ICs, Threshold Values And Basis. | ||
The latest time the NRC can be notified is (2) hour(s) after the event / emergency declaration. | |||
(1) (2) | |||
A. has NOT 4 B. HAS 4 C. has NOT 1 D. HAS 1 | |||
: 97. Unit 1 is performing the actions of EEP-0.0, Reactor Trip or Safety Injection, and AOP-9, Loss of Component Cooling Water. Conditions are as follows: | |||
* 1F 4160V bus is de-energized. | * 1F 4160V bus is de-energized. | ||
* B Train CCW is the | * B Train CCW is the on service Train. | ||
* 1B CCW pump is Tagged Out. | * 1B CCW pump is Tagged Out. | ||
* 1A CCW pump tripped. | * 1A CCW pump tripped. | ||
* 1C CHG PUMP is running. | * 1C CHG PUMP is running. | ||
Subsequently, the Shift | Subsequently, the Shift Supervisor determines that Firewater is required to be aligned to the 1B Charging pump. | ||
Which one of the following completes the statements below? | |||
The 1C Charging pump will be (1) while aligning Firewater to the 1B Charging pump. | |||
(2) Charging pump CCW oil cooler piping will become chemically contaminated. | |||
(1) (2) | |||
A. secured ONLY the 1B B. secured BOTH 1B and 1C C. maintained running ONLY the 1B D. maintained running BOTH 1B and 1C | |||
: 98. Unit 1 operating crew has exited EEP-0.0, Reactor Trip or Safety Injection, and is now performing ECP-1.2, LOCA Outside Containment with the following conditions: | : 98. Unit 1 operating crew has exited EEP-0.0, Reactor Trip or Safety Injection, and is now performing ECP-1.2, LOCA Outside Containment with the following conditions: | ||
* The leak isolation steps are completed. | * The leak isolation steps are completed. | ||
* RWST level is 12.5 ft. | * RWST level is 12.5 ft. | ||
* RCS pressure continues to lower. | * RCS pressure continues to lower. | ||
Which one of the following | Which one of the following completes the statement below? | ||
The next procedure the operating crew is required to transition to is . | |||
A. EEP-0.0, Reactor Trip or Safety Injection B. ESP-1.3, Transfer to Cold Leg Recirculation C. EEP-1.0, Loss of Reactor or Secondary Coolant D. ECP-1.1, Loss of Emergency Coolant Recirculation | |||
: 99. Unit 2 is performing the actions of FRP-H.1, Response to Loss of Secondary Heat Sink, and the following conditions exist: | : 99. Unit 2 is performing the actions of FRP-H.1, Response to Loss of Secondary Heat Sink, and the following conditions exist: | ||
* The TDAFW pump has been returned to service. | * The TDAFW pump has been returned to service. | ||
* Containment pressure is 0 psig. | * Containment pressure is 0 psig. | ||
* RCS Bleed and Feed was | * RCS Bleed and Feed was initiated, but has now been secured. | ||
* RCS pressure is 1600 psig and rising. | * RCS pressure is 1600 psig and rising. | ||
* Pressurizer level is 23% and rising. | * Pressurizer level is 23% and rising. | ||
Which one of the following | Which one of the following completes the statements below? | ||
(2) ESP-1.1, SI Termination(1) Wide Range level at 14% | The minimum SG level that permitted securing Bleed and Feed was at least one SG (1) . | ||
(2) EEP-1, Loss of Reactor or Secondary Coolant (1) Narrow Range level at 33% | The operating crew will transition to (2) from FRP-H.1. | ||
(2) ESP-1.1, SI Termination (1) | A. (1) Wide Range level at 14% | ||
(2) EEP-1, Loss of Reactor or Secondary Coolant | (2) ESP-1.1, SI Termination B. (1) Wide Range level at 14% | ||
(2) EEP-1, Loss of Reactor or Secondary Coolant C. (1) Narrow Range level at 33% | |||
(2) ESP-1.1, SI Termination D. (1) Narrow Range level at 33% | |||
(2) EEP-1, Loss of Reactor or Secondary Coolant | |||
100. Unit 1 is cooling down per ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding, and the following conditions exist: | 100. Unit 1 is cooling down per ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding, and the following conditions exist: | ||
* RVLIS is not available. | * RVLIS is not available. | ||
* RCS Hot leg is 450°F and slowly lowering. | * RCS Hot leg is 450°F and slowly lowering. | ||
* RCS Cold leg is 425°F and slowly lowering. | * RCS Cold leg is 425°F and slowly lowering. | ||
* The crew is cooling down at | * The crew is cooling down at the maximum rate allowed by procedure. | ||
* Pressurizer level has just | * Pressurizer level has just rapidly risen to 78% and is stable | ||
* RCS pressure reduction is not required. | * RCS pressure reduction is not required. | ||
* CST level is 9ft. | * CST level is 9ft. | ||
Which one of the following | Which one of the following completes the statements below? | ||
The operating crew will transition to ESP-0.4, | The operating crew will transition to ESP-0.4, Natural Circulation Cooldown with Allowance for Reactor Vessel Head Steam Voiding (Without RVLIS), based on (1) . | ||
The maximum allowable cooldown rate in ESP-0.4 is (2) . | |||
Reference Provided A. (1) CST Level (2) <100°F in any 60 minute period B. (1) CST Level (2) <50°F/hr C. (1) Reactor Vessel void formation being indicated (2) <100°F in any 60 minute period D. (1) Reactor Vessel void formation being indicated (2) <50°F/hr | |||
PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE. | |||
APPLICABILITY: MODES 1, 2, and 3. | |||
ACTIONS | |||
-----------------------------------------------------------NOTE-------------------------------------------------------- | -----------------------------------------------------------NOTE-------------------------------------------------------- | ||
Separate Condition entry is allowed for each Function. | Separate Condition entry is allowed for each Function. | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required channel 30 days with one required to OPERABLE status. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with one required | |||
channel inoperable. | channel inoperable. | ||
B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A Specification 5.6.8. | |||
not met. | |||
C. One or more Functions C.1 Restore one channel to 7 days with two required OPERABLE status. | |||
Specification 5.6.8. | |||
channels inoperable. | channels inoperable. | ||
Farley Units 1 and 2 3.3.3-1 Amendment No. 170 (Unit 1) | |||
Amendment No. 163 (Unit 2) | |||
Amendment No. | |||
-------------------------------------------------------------------------------------------------------------------------- | PAM Instrumentation 3.3.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.3-1 for the not met. channel. | ||
E. As required by Required E.1 Be in MODE 3. 6 hours Action D.1 and referenced in AND Table 3.3.3-1. | |||
E.2 Be in MODE 4. 12 hours F. As required by Required F.1 Initiate action in Immediately Action D.1 and accordance with referenced in Specification 5.6.8. | |||
Table 3.3.3-1. | |||
SURVEILLANCE REQUIREMENTS | |||
-------------------------------------------------------NOTE-------------------------------------------------------------- | |||
SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1. | |||
SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required In accordance with instrumentation channel that is normally energized. the Surveillance Frequency Control Program SR 3.3.3.2 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.3.3-2 Amendment No. 185 (Unit 1) | |||
Amendment No. 180 (Unit 2) | |||
PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 1) | |||
Post Accident Monitoring Instrumentation CONDITION REFERENCED FROM REQUIRED REQUIRED FUNCTION CHANNELS ACTION D.1 | |||
Amendment No. 159 | : 1. RCS Hot Leg Temperature (Wide Range) 2 E | ||
: 2. RCS Cold Leg Temperature (Wide Range) 2 E | |||
: 3. RCS Pressure (Wide Range) 2 E | |||
: 4. Steam Generator (SG) Water Level (Wide or 2/SG E Narrow Range) | |||
: 5. Refueling Water Storage Tank Level 2 E | |||
: 6. Containment Pressure (Narrow Range) 2 E | |||
: 7. Pressurizer Water Level 2 E | |||
: 8. Steam Line Pressure 2/SG E | |||
: 9. Auxiliary Feedwater Flow Rate 2 E | |||
: 10. RCS Subcooling Margin Monitor 2 E | |||
: 11. Containment Water Level (Wide Range) 2 E | |||
: 12. Core Exit Temperature - Quadrant 1 2 (a) E | |||
: 13. Core Exit Temperature - Quadrant 2 2(a) E | |||
: 14. Core Exit Temperature - Quadrant 3 2(a) E | |||
: 15. Core Exit Temperature - Quadrant 4 2(a) E | |||
: 16. Reactor Vessel Level Indicating System 2 F | |||
: 17. Condensate Storage Tank Level 2 E | |||
: 18. Deleted | |||
: 19. Containment Area Radiation (High Range) 2 F (a) A channel consists of two core exit thermocouples. | |||
Farley Units 1 and 2 3.3.3-3 Amendment No. 167 (Unit 1) | |||
Amendment No. 159 (Unit 2) | |||
Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves LCO 3.7.3 Three Main FW Stop Valves, three MFRVs, and associated bypass valves shall be OPERABLE. | |||
: 1 | APPLICABILITY: MODES 1 and 2, except when all main feedwater lines are isolated by either a Main FW Stop Valve, a MFRV and its associated bypass valve or by a closed manual valve. | ||
ACTIONS | |||
--------------------------------------------------------NOTE------------------------------------------------------------- | |||
Separate Condition entry is allowed for each valve. | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Main FW A.1 Close or isolate Main FW 72 hours Stop Valves inoperable. Stop Valve. | |||
AND A.2 Verify Main FW Stop Valve Once per 7 days is closed or isolated. | |||
B. One or more MFRVs B.1 Close or isolate MFRV. 72 hours inoperable. | |||
AND B.2 Verify MFRV is closed or Once per 7 days isolated. | |||
Farley Units 1 and 2 3.7.3-1 Amendment No. 146 (Unit 1) | |||
Amendment No. 137 (Unit 2) | |||
Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 | Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One or more MFRV C.1 Close or isolate bypass 72 hours bypass valves valve. | ||
inoperable. | |||
AND C.2 Verify bypass valve is closed Once per 7 days or isolated. | |||
D. Two valves in the same D.1 Isolate affected flow path. 8 hours flow path inoperable. | |||
E. Required Action and E.1 Be in MODE 3. 6 hours associated Completion Time not met. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each Main FW Stop Valve, In accordance with MFRV, and associated bypass valve is in accordance the Inservice with the time requirement in the Inservice Testing Testing Program. | |||
Plan. | |||
Farley Units 1 and 2 3.7.3-2 Amendment No. 146 (Unit 1) | |||
Amendment No. 137 (Unit 2) | |||
1/22/2013 14:30 | |||
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UNIT 1 | |||
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$"-$6-"5*0/'03"%&26"5&"7"*-"#-&$45*/7&/503: | |||
}} |
Latest revision as of 08:38, 5 February 2020
ML15316A134 | |
Person / Time | |
---|---|
Site: | Farley ![]() |
Issue date: | 11/10/2015 |
From: | Division of Reactor Safety II |
To: | Southern Nuclear Operating Co |
References | |
50-348/15-301, 50-364/15-301 | |
Download: ML15316A134 (108) | |
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: 20 OCT 2015 Facility / Unit FARLEY 1 & 2 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 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results RO/SRO-Only/Total Examination Values 75 / ______
______ 25 / ______
100 Points Applicant's Score ______ / ______ / ______
Points Applicant's Grade ______ / ______ / ______
Percent ES-401, Page 38 of 50
- 1. Unit 1 is starting up IAW UOP-1.2, Startup of Unit from Hot Standby to Minimum Load, with the following condition:
- Reactor Power is 13%.
The CONTROL ROD MOTION switch has been released following a rod withdrawal when the following occurs:
- Rods step out continuously.
Which one of the following completes the statements below?
The first action directed by AOP-19.0, Malfunction of Rod Control System, is to (1) .
With NO operator action the C-1, IR Hi Flux Rod Stop, (2) stop the outward rod motion.
A. (1) manually Trip the Reactor (2) will NOT B. (1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) will NOT C. (1) manually Trip the Reactor (2) WILL D. (1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) WILL
- 2. Unit 1 is performing a Reactor startup at MOL with the following conditions:
- UOP-1.2, Startup of Unit From Hot Standby to Minimum Load, is in progress.
- The OATC has stabilized Reactor power.
- NI-35 and NI-36, INTERMEDIATE RANGE, indicate 1x10-8 AMPS.
Subsequently, control rods are withdrawn 3 steps.
Which one of the following completes the statements below?
Reactor Power will rise then stablize (1) the POAH.
The first indication of reaching the POAH is rising (2) .
(1) (2)
A. below Pressurizer Level B. at Pressurizer Level C. below S/G Pressure D. at S/G Pressure
- 3. Unit 1 is at 25% power when the following conditions occur:
At 1000:
- 1A RX COOLANT PUMP AMPS indicates 700 AMPS.
At 1002:
- The 1A RCP motor experiences a Sheared Shaft.
Which one of the following completes the statements below?
At 1002 the 1A RCP will draw (1) electrical current than it did at 1000.
The crew is required to immediately enter (2) .
(1) (2)
A. More EEP-0.0, Reactor Trip and Safety Injection B. Less EEP-0.0, Reactor Trip and Safety Injection C. More AOP-4.0, Loss of Reactor Coolant Flow D. Less AOP-4.0, Loss of Reactor Coolant Flow
- 4. Unit 1 is operating at 100% power with the following conditions:
- PK-145, LP LTDN PRESS, is set to maintain Letdown Pressure at 275 psig.
Subsequently, the RCS filter becomes completely clogged and does not allow any flow.
Which one of the following completes the statements below?
PK-145 controller demand will (1) .
AOP-16.0, CVCS Malfunction, entry conditions (2) been met.
(1) (2)
A. Rise HAVE B. Rise have NOT C. Lower HAVE D. Lower have NOT
- 5. Which one of the following completes the statement below?
Charging Pump Suctions will automatically align to the RWST when (1) sense(s) (2) VCT Level.
Level Transmitter Nomenclature LT-115, VCT LVL LT-112, VCT LVL (1) (2)
A. either LT-115 or LT-112 5%
B. both LT-115 and LT-112 5%
C. either LT-115 or LT-112 15%
D. both LT-115 and LT-112 15%
- 6. Unit 1 is in MODE 4 with the following conditions:
- Plant cooldown is in progress with the 'A' Train of RHR .
Which one of the following completes the statements below?
Raising demand on FK-605A will (1) CCW temperature.
Per SOP-23.0, Component Cooling Water System, the maximum allowable CCW outlet temperature for the CCW HX used for cooldown is (2) .
(1) (2)
A. raise 120°F B. raise 135°F C. lower 120°F D. lower 135°F
- 7. Unit 1 is shutdown when the following conditions occur:
- The 1A CCW pump tripped.
- The 'A' Train is the ON SERVICE Train.
Which one of the following completes the statement below?
Cooling is lost to the (1) RHR Heat Exchanger.
The affected RHR train (2) available for transfer to Cold Leg Recirculation.
(1) (2)
A. 1A is NOT B. 1A IS C. 1B is NOT D. 1B IS
- 8. Unit 1 has experienced a tube rupture on the 1A SG with the following conditions:
- A Loss of All Offsite Power has occurred.
- The operating crew is performing EEP-3, Steam Generator Tube Rupture.
- RCS cooldown is in progress.
- INTEGRITY Critical Safety Function Status Tree has turned ORANGE due to the 1A RCS LOOP cold leg temperature dropping rapidly.
Which one of the following completes the statements below?
The 1A RCS LOOP cold leg temperature drop was caused by increased (1) flow over the 1A RCS LOOP cold leg instrument.
(2) is the highest listed cold leg temperature that could lead to this ORANGE INTEGRITY condition.
(1) (2)
A. Natural Circulation 270°F B. Natural Circulation 225°F C. High Head Safety Injection 270°F D. High Head Safety Injection 225°F
- 9. A Safety Injection has just occurred on Unit 1.
Which one of the following completes the statement below?
The minimum valve actuations that would lead to HHSI Pump cavitation are .
Valve Nomenclature:
LCV-115C, VCT OUTLET ISO LCV-115E, VCT OUTLET ISO LCV-115D, RWST TO CHG PUMP LCV-115B, RWST TO CHG PUMP A. LCV-115C or LCV-115E opening B. LCV-115C and LCV-115E opening C. LCV-115B or LCV-115D closing D. LCV-115B and LCV-115D closing
- PI-472, PRT PRESS, stablizes at 15.0 psig.
Which one of the following completes the statements below?
HE5, PRT PRESS HI, (1) in alarm.
Per SOP-1.2, Reactor Coolant Pressure Relief System, normal nitrogen pressure prevents (2) .
(1) (2)
A. IS excessive corrosion due to oxygen B. is NOT excessive corrosion due to oxygen C. IS an explosive mixture of oxygen and hydrogen D. is NOT an explosive mixture of oxygen and hydrogen
- 11. Unit 1 is operating at 100% power when the following conditions occur:
- A large break has occurred at the inlet of a Pressurizer Safety Valve.
Subsequently, the following condition exists:
- Pressurizer Pressure is 1600 psig.
- Charging Pump miniflow valves are open.
Which one of the following completes the statements below?
Per EEP-0, Reactor Trip or Safety Injection, the crew (1) required to close the Charging Pump miniflow valves.
Closing the Charging Pump miniflow valves when required will ensure (2) .
(1) (2)
A. IS HHSI pump injection flow is maximized B. is NOT HHSI pump injection flow is maximized C. IS HHSI pump heat is removed D. is NOT HHSI pump heat is removed
- 12. Unit 1 is operating at 100% power with the following conditions:
- A dual unit LOSP occurs.
Subsequently, Unit 2 experiences a Safety Injection.
Which one of the following completes the statement below for Unit 1?
The (1) CCW pump is being powered by the (2) DG.
(1) (2)
A. 1A 1-2A B. 1A 1C C. 1C 1-2A D. 1C 1C
- 13. Unit 1 is in MODE 5 with the following conditions:
- A cooldown is in progress.
- RHR is on service.
Subsequently, the following conditions occur:
- V-8708A, RHR SUCTION RELIEF, has lifted and is stuck open.
Which of the following tank levels will immediately rise due to the malfunction?
- 14. A Design Basis Large Break LOCA has occurred on Unit 1.
Which one of the following completes the statements below?
The Accumulators will inject directly to the (1) .
The purpose of the Accumulator design capacity is to (2) refill the Reactor Vessel following a design basis accident.
(1) (2)
A. Hot Legs partially B. Hot Legs completely C. Cold Legs partially D. Cold Legs completely
- 15. Unit 1 is operating at 100% power and the following conditions exist:
- Pressurizer Pressure is 2240 psig.
- Tavg is 572°F.
- Pressurizer Level Control is in manual.
- Pressurizer Level is 60%.
- 600V LCC 1M has lost power.
Which one of the following completes the statements below?
Power has been lost to the (1) Pressurizer Heater Group.
Pressurizer Heater Groups A and B are currently (2) .
(1) (2)
A. D Energized B. D De-Energized C. E Energized D. E De-Energized
- 16. Unit 1 is operating at 100% Power when the following conditions occur:
- A short circuit occurs in PT-445, PRZR PRESS.
- Pressurizer Pressure remains stable.
Which one of the following completes the statement below?
The Pressurizer Pressure input to the Reactor Protection System will NOT be affected by this malfunction due to the use of .
A. an independent control channel B. a median signal selector C. isolation devices D. de-energize to actuate bistables
- 17. Unit 1 is operating at 100% power and the following occurs:
- A Safety Injection followed by an LOSP on Unit 1.
Several minutes following the safety injection the following condition exists:
- The 1B DG is running with the output breaker open.
Which one of the following completes the statements below?
SOP-0.8, Transient Response Procedure User's Guide, (1) require a procedure be used prior to closing the 1B DG output breaker.
The B1G sequencer (2) energize the 1C Air Compressor.
(1) (2)
A. DOES DOES B. DOES does NOT C. does NOT DOES D. does NOT does NOT
- 18. The 1D Vital Panel becomes de-energized on Unit 1.
Which one of the following completes the statements below.
The 'B' Train SI actuated MOVs (1) automatically stroke upon an SI actuation.
'B' Train ESF pumps (2) be started in LOCAL at the HSDP.
(1) (2)
A. WILL CAN B. WILL CANNOT C. will NOT CAN D. will NOT CANNOT
- 19. Which one of the following completes the statements below?
The C-11, Bank D Stop, is actuated by input from (1) at a Bank D rod height of (2) steps.
(1) (2)
A. Digital Rod Position Indication 220 B. Digital Rod Position Indication 228 C. the Pulse-to-Analog Converter 220 D. the Pulse-to-Analog Converter 228
- 20. Unit 1 is in MODE 3 and the following RCP temperatures are observed:
Motor Bearing Temperature Motor Stator Temperature 1A RCP 190°F 235°F 1B RCP 200°F 220°F 1C RCP 190°F 230°F Which one of the following completes the statement below?
Only the is (are) required to be secured.
A. 1A RCP B. 1B RCP C. 1A and 1B RCPs D. 1A and 1C RCPs
- 21. Which one of the following conditions would cause a Core Exit Thermocouple (CETC) monitor alarm?
- 1. ANY CETC input disconnected.
- 2. ONLY 10 valid CETCs.
- 3. ANY CETC temperature at 650°F.
A. 1 ONLY B. 1 AND 3 ONLY C. 2 ONLY D. 1, 2, AND 3
- 22. Unit 1 is operating at 100% power when the following conditions occurred:
- 1B Charging Pump is started.
- 1A Charging Pump is secured.
- 1B CHG PUMP AMPS, begins to oscillate.
- FI-122A, CHG FLOW, begins to oscillate.
Subsequently, the following annunciators come into alarm:
- EA2, CHG HDR FLOW HI-LO.
- DE1, REGEN HX LTDN FLOW DISCH TEMP HI.
Which one of the following completes the statements below?
The alarms above are indicative of (1) .
The maximum 1A RCP seal injection flowrate that would cause DD1 to alarm is (2) .
(1) (2)
A. FCV-122 closing 6 gpm B. 1B Charging Pump Cavitation 6 gpm C. FCV-122 closing 3 gpm D. 1B Charging Pump Cavitation 3 gpm
- 23. Unit 1 is operating at 100% power with the following conditions:
- A Large Break LOCA occurs.
Subsequently, a Loss of Offsite Power occurs.
Which one of the following completes the statement below 5 minutes after the Loss of Offsite Power?
(1) Containment Cooler Fans are running in slow speed.
The reduced speed prevents CTMT cooler (2) due to high moisture content in the Containment atmosphere.
(1) (2)
A. 2 fan motor overload B. 4 fan motor overload C. 2 cooling coil impingement damage D. 4 cooling coil impingement damage
- 24. Unit 1 is in MODE 5 and the following condition exists:
- Both Trains of RHR are operating in the cooldown alignment.
- Power is aligned to the RHR suction valves.
- Tavg is 195°F.
Subsequently, the following condition occurs:
Which one of the following completes the statements below?
MOV-8701A, 1C RCS LOOP TO 1A RHR PUMP, (1) automatically close.
IF MOV-8701A closes, then AOP-12.0, Residual Heat Removal System Malfunction, entry (2) required.
(1) (2)
A. DOES is NOT B. does NOT is NOT C. DOES IS D. does NOT IS
- 25. Unit 1 is Shutdown following a LOCA with the following conditions:
- PR-950, CTMT PRESS, peaked at 3.2 psig.
- ECP-1.1, Loss of Emergency Coolant Recirculation, is in progress.
Which one of the following completes the statments below:
Per ECP-1.1, the minimum CTMT Sump Level that can support Containment Spray pump operation is .
A. 2.0 ft B. 3.8 ft C. 4.5 ft D. 5.3 ft
- 26. Unit 1 is operating at 100% power when the following condition occurs:
- PK-444A, PRZR PRESS REFERENCE, demand fails to 0%.
Which one of the following completes the statements below?
Initially, (1) PORV(s) will OPEN automatically.
PCV-444C, 1A LOOP SPRAY VLV, will (2) .
(1) (2)
A. only ONE CLOSE B. only ONE OPEN C. BOTH CLOSE D. BOTH OPEN
- 27. Unit 1 is operating at 100% power with the following conditions:
- Containment Mini-Purge is in operation Subsequently, the following conditions occur:
- A Main Steam Line breaks inside Containment
- PR-950Z, CTMT PRESS, stablizes at 14.5 psig.
Which one of the following completes the statements below?
CTMT Mini-Purge supply and exhaust fans (1) tripped automatically due to a Containment Ventilation Isolation signal.
CTMT Mini-Purge supply and exhaust dampers (2) closed automatically due to a Containment Ventilation Isolation signal.
(1) (2)
A. HAVE HAVE B. HAVE have NOT C. have NOT HAVE D. have NOT have NOT
- 28. Unit 1 is operating at 100% power with the following conditions:
- STP-33.2A, Reactor Trip Breaker Train A Operability Test, is in progress.
- Reactor Trip Breaker A is OPEN.
- Reactor Trip Bypass Breaker A is CLOSED.
- Reactor Trip Breaker B is CLOSED.
Subsequently, the following conditions occur:
- An automatic reactor trip signal is generated.
- The Reactor does NOT trip.
Which one of the following completes the statements below?
When the RX TRIP ACTUATION switch is taken to TRIP (1) will OPEN.
Per EEP-0, Reactor Trip or Safety Injection, if the RX TRIP ACTUATION switches fail to trip the Reactor, the next action required is to (2) .
A. (1) ONLY Reactor Trip Breaker B (2) trip the MG set supply breakers B. (1) BOTH Reactor Trip Bypass Breaker A and Reactor Trip Breaker B (2) trip the MG set supply breakers C. (1) ONLY Reactor Trip Breaker B (2) insert Control Rods manually D. (1) BOTH Reactor Trip Bypass Breaker A and Reactor Trip Breaker B (2) insert Control Rods manually
- 29. Unit 2 is starting up per UOP-1.2, Startup of Unit From Hot Standby To Minimum Load, with the following conditions:
- Main Steam Header Warm Up is in Progress.
Which one of the following actions would cause the 2B SG Pressure to lower due to increased steam demand from the 2B SG?
A. Lower PC-3371B, 2B MS ATMOS REL VLV, SETPT in AUTO.
B. Lower PC-3371B, 2B MS ATMOS REL VLV, OUTPUT in MAN.
C. Lower PK-464, STM HDR PRESS, OUTPUT in MAN.
D. Lower PK-464, STM HDR PRESS, SETPT in AUTO.
At 1000:
- HIGHEST CORE EXIT TEMP CHAN A and B on the IPC, indicates 530°F.
- 1A SG PRESS is 810 psig.
- RCS cooldown is in progress.
At 1045:
- HIGHEST CORE EXIT TEMP CHAN A and B, on the IPC indicates 450°F.
- 1A SG PRESS is 300 psig.
Which one of the following completes the statements below?
Compared to the conditions at 1000, RCS subcooling at 1045 has (1) .
Compared to the conditions at 1000, SG tube leakage rate at 1045 has (2) .
Reference Provided (1) (2)
A. risen risen B. risen lowered C. lowered lowered D. lowered risen
- 31. Unit 1 is in Mode 3 at EOL with the following conditions:
- A Reactor Startup is being planned for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a reactor trip.
- Tavg is being maintained by the Atmospheric Relief Valves (ARVs).
- The Estimated Critical Condition (ECC) calculation predicts criticality at 100 steps on Control Bank D.
Which one of the following conditions will result in critical rod height being HIGHER than the value predicted by the ECC?
For your answer, consider that no operator actions are taken to mitigate or compensate for the below events.
A. A dilution of 500 gallons is performed.
B. Auxiliary Feedwater flow is RAISED to all SGs.
C. A post maintenance test results in the closure of all ARVs.
D. Reactor startup occurs 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> after the reactor trip.
- 32. Unit 2 is at 68% power ramping down due to a problem with #4 Governor Valve with the following conditions:
- EH is isolated to #4 Governor valve.
- A subsequent failure causes #2 Governor Valve to fail closed.
- Turbine load drops to 450 MW.
Which one of the following completes the statements below?
The #2 governor valve closure results in (1) .
Per SOP-72.0, General Instructions for DEH Operators Console, the operating crew is required to (2) .
A. (1) automatic removal of the IMP Press Loop (2) trip the Main Turbine B. (1) automatic removal of the IMP Press Loop (2) match reactor power with turbine load C. (1) opposed governor valve closure (2) trip the Main Turbine D. (1) opposed governor valve closure (2) match reactor power with turbine load
- 33. Unit 1 is operating at 100% power with the following conditions:
AT 1000:
AT 1005:
- KK1, TURB COND VAC LO, comes into alarm Which one of the following completes the statements below?
(1) is the earliest time AOP-8.0, Partial Loss of Condenser Vacuum, entry is required.
At 100% Reactor power, (2) is the lowest condenser pressure a manual Reactor Trip is required.
(1) (2)
A. 1000 3.800 psia B. 1005 3.800 psia C. 1000 2.901 psia D. 1005 2.901 psia
- 34. Unit 1 entered FRP-H.1, Response to Loss of Secondary Heat Sink, with the following conditions:
Time 1000 1015 1030 1100 1A S/G WR LVL (%) 37.00 28.00 18.00 11.00 1B S/G WR LVL (%) 32.00 20.00 10.00 6.00 1C S/G WR LVL (%) 29.00 19.00 9.00 3.00 CNMT PRESS (PSIG) 1.50 2.00 3.00 4.50 AFW TOTAL FLOW (GPM) 0 0 0 0 Which one of the following is the EARLIEST time that a manual Safety Injection is required due to meeting Bleed and Feed criteria per FRP-H.1?
A. 1000 B. 1015 C. 1030 D. 1100
- 35. Which one of the following is the purpose of depressurizing all intact SGs during the performance of ECP-0.0, Loss of All AC Power?
A. Rapidly reduces DP across SG U-tubes to minimize RCS inventory loss from a potential tube rupture.
B. Cools RCP seals in a controlled manner and minimizes loss of RCS inventory.
C. Maximizes Natural Circulation flow before reflux cooling begins as the RCS becomes saturated.
D. Maximizes Natural Circulation flow to allow reactor vessel head to cool since CRDM cooling fans are unavailable.
- 36. Unit 1 is operating at 100% power and the following condition exists:
- Main Condenser Pressure is rising due to a failure of the 1A SJAE.
Which one of the following completes the statements below?
Main Condenser Hotwell Temperature will initially (1) .
AOP-8.0, Partial Loss of Condenser Vacuum, will direct placing (2) on service.
(1) (2)
A. RISE a Hogger B. LOWER a Hogger C. RISE the 1B SJAE D. LOWER the 1B SJAE
- 37. The following conditions exist:
- Unit 1 is in MODE 5.
- Unit 2 is operating at 100% power.
- The 1B DG is INOPERABLE.
Subsequently, the following occurs simultaneously:
- 4160V busses 1F, 1K, 1G, and 1L de-energize.
- 4160V busses 2F, 2K, 2G, and 2L de-energize.
- The 1-2A DG Trips and cannot be restored.
Which one of the following completes the statement below?
The first procedure the Unit 1 Operating Crew is required to enter is (1) .
The Operating Crew will restore power to Unit 1 with the (2) .
A. (1) AOP-5.0, Loss of A or B Train Electrical Power (2) 1C DG B. (1) ECP-0.0, Loss of All AC Power (2) 1C DG C. (1) AOP-5.0, Loss of A or B Train Electrical Power (2) 2C DG D. (1) ECP-0.0, Loss of All AC Power (2) 2C DG
- 38. Which one of the following completes the statement below?
The Main Turbine exhaust hood sprays use (1) to automatically prevent excessive temperatures at the exhaust of the LP Turbine (2) 15% Turbine Load.
(1) (2)
A. demin water above B. demin water below C. condensate above D. condensate below
- 39. Unit 1 is operating at 100% power when the following occurs:
- The 1C 120 VAC Vital Instrumentation Panel is de-energized.
Which one of the following completes the statements below?
LCV-459, LTDN LINE ISO, (1) automatically close if a Pressurizer Low Level condition occurs.
LCV-115A (2) immediately divert to the RHT.
(1) (2)
A. WILL WILL B. WILL will NOT C. will NOT WILL D. will NOT will NOT
- 40. Unit 1 is operating at 8% power and the following conditions occur:
- The Battery Input Breaker on the 1B inverter trips.
- WD2, 1B INV FAULT, annunciator alarms.
- No Other Annunciators are in Alarm due to the fault.
Subsequently, the Rover reports the following indications from the 1B Inverter.
- INVERTER POWERING LOAD lamp NOT lit.
- BYPASS SOURCE AVAILABLE lamp is LIT.
Which one of the following completes the statements below?
The 1B 120V Vital AC panel is (1) .
The 1B INVERTER AMPERES meter on the EPB indicates (2) .
A. (1) Energized (2) 0 Amps B. (1) Energized (2) Full Load Amps C. (1) De-energized (2) 0 Amps. When the MANUAL BYPASS SWITCH is taken to BYPASS SOURCE TO LOAD position it will indicate Full Load Amps.
D. (1) De-energized (2) 0 Amps. When the MANUAL BYPASS SWITCH is taken to BYPASS SOURCE TO LOAD position it will continue to indicate 0 Amps.
- 41. Unit 1 is operating at 100% power when the following conditions occur:
- Annunciator KB4, SGFP SUCT PRESS LO, alarms
- PR-4039, SGFP SUCT PRESS, indicates 300 psig and lowering.
Which one of the following completes the statement below?
The earliest time the standby condensate pump will start is when .
A. KB4 has been in alarm for 10 seconds B. KB4 has been in alarm for 30 seconds C. SGFP suction pressure has remained below 275 PSIG for 10 seconds D. SGFP suction pressure has remained below 275 PSIG for 30 seconds
- 42. A gas transfer is in progress to the #8 Waste Gas Decay Tank on Unit 1 when the following conditions occur:
- The #8 Waste Gas Decay Tank relief valve lifts.
- The relief valve fails to reseat.
Which one of the following completes the statements below?
The relief valve lifting will initially be detected by (1) .
The release (2) be automatically isolated from the environment if an alarm condition exists.
(1) (2)
A. R-13, WASTE GAS MONITOR WILL B. R-13, WASTE GAS MONITOR will NOT C. R-14, PLANT VENT MONITOR WILL D. R-14, PLANT VENT MONITOR will NOT
- 43. Unit 1 is Operating at 100% Reactor Power when the following conditions occur:
Time 1000 1005 1010 1015 1A S/G NR LVL (%) 26.00 23.00 21.00 7.00 1B S/G NR LVL (%) 34.00 27.00 25.00 8.00 1C S/G NR LVL (%) 35.00 33.00 31.00 12.00 1A SGFP STATUS Running Running Tripped Tripped 1B SGFP STATUS Running Running Tripped Tripped Which one of the following is the earliest time when all AFW Pumps have recieved an AUTO START signal?
A. 1000 B. 1005 C. 1010 D. 1015
- 44. Unit 1 is operating at 100% power with the following condition:
- An LOSP occurs.
Which one of the following completes the statements below?
10 seconds after power is restored to the 1F 4160V bus:
1A CHG PUMP AMPS will indicate (1) AMPS.
1A MDAFWP AMPS will indicate (2) AMPS.
(1) (2)
A. greater than zero greater than zero B. greater than zero zero C. zero greater than zero D. zero zero
- 45. Unit 1 is operating at 100% power when the following condition occurs:
- The Reactor Trips Subsequently, the following indications are displayed continously on the MCB.
Which one of the following completes the statement below?
The valve actuation was initiated by a (1) .
The valve position prevents (2) .
A. (1) Safety Injection (2) damage to turbine building auxiliaries.
B. (1) Loss of Offsite Power (2) complete isolation of SW flow to the Air Compressors C. (1) Safety Injection (2) complete isolation of SW flow to the Air Compressors D. (1) Loss of Offsite Power (2) damage to turbine building auxiliaries.
- 46. Which one of the following completes the statements below?
The (1) RCP(s) can be powered from the 1A Startup Transformer.
The (2) RCP(s) can be powered from the 2B Startup Transformer.
(1) (2)
A. 1A RCP 2A RCP B. 1A RCP 2B and 2C RCPs C. 1B and 1C RCPs 2A RCP D. 1B and 1C RCPs 2B and 2C RCPs
- 47. Unit 1 is at 100% power when the following condition occurs in the Aux Bldg DC distribution system:
- The 125V DC Bus 1B has been de-energized.
Subsequently, an LOSP occurs on Unit 1.
Which one of the following completes the statements below?
The 1B DG (1) be started from the EPB.
The B1G Sequencer (2) automatically sequence loads.
(1) (2)
A. CAN WILL B. CANNOT will NOT C. CANNOT WILL D. CAN will NOT
- 48. Which one of the following completes the statement below for the 1B DG Air Recievers?
The maximum Air Receiver pressure that will cause an alarm on the 1B DG Local Control Panel is (1) .
At the alarm setpoint there is enough air pressure to ensure a maximum of (2) start attempts are available.
(1) (2)
A. 200 psig 3 B. 200 psig 5 C. 350 psig 3 D. 350 psig 5
- 49. Unit 1 is operating at 100% power when the following conditions occur:
- MH1, FIRE, annunciator on the Unit 1 Main Control Board (MCB) alarms.
- Aux Bldg El 139 W Side Det 1A-39, 43, 46, 53 1A-55, 59, 106", light is lit on the Control Room Fire Panel.
- The Rover reports that the window for 1A-59 at the PYR-A-LARM panel is lit.
What is (are) the minimum required action(s) to ensure MH1, FIRE, will alarm again if 1A-39 comes into alarm?
A. The Control Room Fire Panel alarm must be acknowledged.
and 1A-59 must be placed in OVERRIDE on the PYR-A-LARM panel.
B. The Control Room Fire Panel alarm must be acknowledged.
and The Reflash Panel alarm for detection system 1A-59 must be acknowledged.
C. ONLY 1A-59 must be placed in OVERRIDE on the PYR-A-LARM panel.
D. ONLY the Reflash Panel alarm for detection system 1A-59 must be acknowledged.
- 50. AOP-28.0, Control Room Inaccessibility, is in progress on Unit 1.
Which one of the following completes the statements below?
The 1A MDAFWP will be operated in LOCAL at the (1) HSDP.
Operator action is required to control the MDAFWP FCVs in LOCAL at the HSDP in order to prevent (2) .
(1) (2)
A. F low SG water level due to valve position B. F isolating letdown due to cooldown C. A low SG water level due to valve position D. A isolating letdown due to cooldown
- 51. Unit 2 is at 100% power with the following conditions:
- A #1 Waste Monitor Tank (WMT) release is in progress with the #1 WMT pump running.
- RCV-18, WMT DISCH TO ENVIRONMENT, is open.
Subsequently R-18, LIQ WASTE DISCH, alarms HIGH.
Which one of the following completes the statements below?
RCV-18 will (1) .
The #1 WMT pump will (2) .
(1) (2)
A. remain open trip B. remain open continue to run C. close trip D. close continue to run
- 52. Unit 1 is operating at 100% power with the following condition:
- A SG Tube Leak is in progress.
Which one of the following radiation monitors is able to automatically stop a release to the environment due to the SG Tube Rupture?
A. R-23A, SGBD SRG TK INLET B. R-23B, SGBD SRG TK DISCH C. R-19, SGBD SAMPLE D. R-70A, SG TUBE LEAK DET
- 53. Unit 1 is operating at 100% power when the following occurs:
- A Large Break LOCA occurs inside containment.
- Containment Pressure reaches 35 psig.
Which one of the following completes the statements below?
MOV-3024A, EMERG SW FROM 1A CTMT CLR, opened due to a(n)
(1) signal.
Each CTMT Cooler will be supplied with approximately (2) GPM of Service Water flow.
(1) (2)
A. Safety Injection 2000 B. Safety Injection 800 C. Containment Spray 2000 D. Containment Spray 800
- 54. Unit 1 experienced a Safety Injection with LOSP.
Which one of the following completes the statements below?
The 1A Charging Pump Room Cooler will automatically start due to a signal generated by the 1A Charging Pump (1) .
Controls for starting the Charging Pump Room Coolers (2) located on the BOP Panel.
(1) (2)
A. Breaker ARE B. Breaker are NOT C. Room Thermostat ARE D. Room Thermostat are NOT
- 55. Unit 1 is operating at 100% power with the following conditions:
- The Gross Failed Fuel Detector (GFFD) has steadily indicated 2500 cpm during the entire fuel cycle.
Subsequently, the following readings are recorded:
Time 1000 1100 1200 1300 GFFD Indication (cpm) 1.1 X 104 1.5 X 104 4.4 X 104 1.3 X 105 Which one of the following is the earliest time the GFFD will be in High Alarm?
A. 1000 B. 1100 C. 1200 D. 1300
- 56. Unit 1 is operating at 100% power with the following conditions:
- AOP-5.2, Degraded Grid, has just been entered.
- Voltage on all emergency busses for both units is reading 3875 volts.
- MEGAVARS are reading (+) 100 on the MCB.
- The Shift Supervisor has directed the UO to maintain (+) 400 MVARs in accordance with the voltage schedule.
- The Unit 2 UO maintains MVARS stable on Unit 2 during the adjustment.
Which one of the following will occur when the Unit 1 UO performs the adjustment as directed by the Shift Supervisor?
The operator will (1) Voltage, to reach (+) 400 MVARs.
After adjusting voltage, the temperature of large pump motors, such as the RCP or CW pump motors, will (2) .
(1) (2)
A. raise lower B. raise rise C. lower lower D. lower rise
- 57. Unit 1 was manually tripped from 100% power and the following conditions exist:
- AOP-6.0, Loss of Instrument Air, is in progress.
- The TDAFW pump automatically started.
- BOTH MDAFW pumps failed to start.
- The MSVR is not accessible.
Subsequently, the following report is received from Mechanical Maintenance:
- Restoration of Instrument Air will take 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
Which one of the following describes the required AOP-6.0 operator action(s), if any, and the reason?
A. No action is required because the TDAFWP steam admission valves fail to the "as is" position.
B. Manually close the TDAFWP steam admission valves to avoid causing an uncontrolled cooldown.
C. Manually open the TDAFWP steam admission valves to provide an adequate heat sink.
D. Manually align emergency air to the TDAFW pump steam admission valves to provide an adequate heat sink.
- 58. Unit 1 is operating at 100% power when the following occurs:
At 1000
- An Instrument Air malfunction occurs.
At 1015
- PI-4004B, INST AIR PRESS, indicates 50 psig and stable Which one of the following completes the statements below?
At 1015 V904, Instrument Air to the Service Building, is (1) .
A(n) (2) maintains MSIV air pressure following loss of instrument air pressure.
(1) (2)
A. OPEN accumulator B. OPEN compressed nitrogen cylinder C. CLOSED accumulator D. CLOSED compressed nitrogen cylinder
- 59. Unit 1 is shutdown following a LOCA with the following conditions:
- PR-950Z, CTMT PRESS, indicates 32 psig and slowly lowering.
Subsequently, ONLY the following actions are taken:
- SI BLOCK RESET A TRN pushbutton is depressed.
- SI BLOCK RESET B TRN pushbutton is depressed.
Which one of the following completes the statements below:
(1) (2)
A. IS is NOT B. IS IS C. is NOT is NOT D. is NOT IS
- 60. Unit 1 is operating at 100% power when the following conditions occur:
- Phase A is actuated using the MCB handswitches.
How has the Phase A signal affected the following valve positions?
Valve Nomenclature:
HV-8152, LTDN LINE CTMT ISO MOV-8112, RCP SEAL WTR RTN ISO HV-8149A, LTDN ORIF ISO 45 GPM MOV-3052, CCW TO RCP CLRS A. Only HV-8152, HV-8149A, and MOV-8112 have closed.
B. Only HV-8152, MOV-8112, and MOV-3052 have closed.
C. Only HV-8152, and HV-8149A have closed.
D. Only HV-8152 has closed.
- 61. A Main Control Board Deficiency related to a MCB handswitch has been identified.
Which one of the following completes the statements below IAW SOP-0.10, FNP Operations Site Specific Policies?
A (1) is required to be created to identify the deficiency.
The identifier (Deficiency Tag/Control Room DOT) will be (2) .
(1) (2)
A. Deficiency Tag affixed to the MCB handswitch B. Deficiency Tag placed in the deficiency notebook C. Control Room DOT affixed to the MCB handswitch D. Control Room DOT placed in the deficiency notebook
- 62. Unit 1 experiences a Reactor Trip with Safety injection.
Subsequently, the following occurs:
- The UO directs the Turbine Building Systems Operator (TB SO) to perform the TB SO Actions Following a Reactor Trip or Safety Injection.
Which one of the following completes the statements below per SOP-0.0, Appendix A, TB SO Actions Following a Reactor Trip and/or Safety Injection?
The TB SO is required to close V-503A, 1A MSR 2ND STG STM SUPP ISO (1) .
The TB SO is required to close V-905A, 1A MS LINE DRN POT TO COND ISO (2) .
(1) (2)
A. following any Reactor trip following any Reactor trip B. following any Reactor trip only when specifically directed C. only when specifically directed following any Reactor trip D. only when specifically directed only when specifically directed
- 63. Which one of the following completes the statements below per NMP-AP-001-003, Review and Approval of Site Procedures?
The "Pen and Ink" Change Process may be used for (1) changes.
A Condition Report (2) required following use of a procedure with "Pen and Ink" changes.
(1) (2)
A. editorial IS B. editorial is NOT C. temporary IS D. temporary is NOT
- 64. Unit 1 is in a Refueling Outage with fuel being loaded into the core.
Which one of the following completes the statements below?
Per TRM 13.1.6, Borated Water Source - Shutdown, the minimum operable BAT Tank Temperature is (1) .
Per TRM 13.1.6, the minimum operable BAT Tank Volume is (2) .
(1) (2)
A. 35°F 2000 gallons B. 35°F 11336 gallons C. 65°F 2000 gallons D. 65°F 11336 gallons
- 65. Unit 1 is exiting a refueling outage with the following conditions:
Time 1000 1200 1400 1600 Average Coolant Temp (°F) 300 450 547 547 Rated Thermal Power (%) 0 0 2 6 Keff <.99 <.99 1.00 1.00 Which one of the following completes the statements below?
The earliest time Unit 1 is in MODE 4 is at (1) .
The earliest time Unit 1 is in MODE 1 is at (2) .
(1) (2)
A. 1000 1400 B. 1000 1600 C. 1200 1400 D. 1200 1600
- 66. A Plant Operator has been assigned a portable RAM 100 frisker for personnel monitoring when exiting the dry cask storage area with the following condition:
- The Frisker Response Checks were last performed 7 days ago.
Which one of the following completes the statements below?
The frisker detects (1) .
The Frisker Response Checks for the assigned frisker are required to be performed (2) .
A. (1) Beta and Gamma radiation (2) prior to use B. (1) Beta and Gamma radiation (2) 6 months from the date of the last response check C. (1) ONLY Gamma radiation (2) prior to use D. (1) ONLY Gamma radiation (2) 6 months from the date of the last response check
- 67. You are assigned a task:
- Your current TEDE is 1500 mrem.
- Dose rate in the area you are required to work is 1500 mr/hr.
Which one of the following is the maximum amount of time you can stay in the area without exceeding Farley Administrative TEDE limits with no additional approval?
A. 20 minutes B. 100 minutes C. 120 minutes D. 140 minutes
- 68. EEP-0.0, Reactor Trip or Safety Injection, provides specific Reactor Coolant Pump (RCP) trip criteria on the foldout page.
Which one of the following is the reason for tripping the RCPs when these conditions occur?
A. Conserves RCS inventory during a Small Break LOCA with subsequent LOSP.
B. Prevents RCP seal damage following a Small Break LOCA.
C. Prevents pump runout following a Large Break LOCA.
D. Ensures core reflood following a Large Break LOCA.
- 69. Unit 1 and Unit 2 are operating at 100% power when the following condition occurs:
- The Outside System Operator reports a fire in the Liquid hydrogen storage tank vent stack.
Which one of the following completes the statement below?
Per AOP-29.0, Plant Fire, and SOP-34.0, Hydrogen-Oxygen System the fire will be extinguished by .
A. spraying water directly on the vent stack and isolating the leak.
B. discharging a portable fire extinguisher into the vent stack and isolating the leak.
C. establishing a helium purge and isolating the leak.
D. isolating the leak ONLY.
- 70. The following condition exist on Unit 1:
Subsequently, the following occurs:
- The Emergency Director declares a SITE AREA EMERGENCY.
Which one of the following completes the statements below?
Per NMP-EP-111, Emergency Notifications, a (1) tone will be sounded prior to the onsite notification announcement.
Per NMP-EP-111, Emergency Notifications, the (2) is responsible for approving notifcations to State and Local Authorities of the emergency condition.
(1) (2)
A. YELP Emergency Director B. WARBLE Emergency Director C. YELP Shift Manager D. WARBLE Shift Manager
- 71. An RCS soak is in progress per FRP-P.1, Response to Imminent Pressurized Thermal Shock Condition, on Unit 1.
Which one of the following actions is permitted?
A. Start a Charging Pump.
B. Energize PZR heaters.
C. Start an RCP.
D. Isolate Accumulators.
- 72. Unit 1 is shutdown following a Large Break LOCA followed by an LOSP. The following conditions occur:
At 1000:
- WA2, 1-2A DG GEN FAULT TRIP, alarms.
At 1015:
- RWST level is 3 ft.
- Containment Spray pump suctions are aligned to the RWST.
Which one of the following completes the statements below?
At 1015 (1) train(s) of emergency coolant recirculation capability has(have) been lost.
The operating crew (2) required to secure all CTMT Spray at 1015.
(1) (2)
A. ONLY one IS B. ONLY one is NOT C. BOTH IS D. BOTH is NOT
- 73. Unit 1 is shutdown with ECP-2.1, Uncontrolled Depressurization of All Steam Generators in progress. The following conditions exist:
- All MSIV - TRIP handswitches have been taken to CLOSE.
Which one of the following completes the statements below?
The next action the crew is required to take per ECP-2.1 is (1) .
If an MSIV is closed, ECP-2.1 directs use of (2) to determine if a Steam Generator has been isolated.
A. (1) Place the MSIV -TEST handswitch to TEST (2) Cold Leg Temperature B. (1) Place the MSIV - TEST handswitch to TEST (2) SG Pressure C. (1) Manually remove air pressure from the MSIVs (2) Cold Leg Temperature D. (1) Manually remove air pressure from the MSIVs (2) SG Pressure
- 74. Unit 1 is shutdown with the following conditions:
- 1A SG Pressure is 1145 psig and rising.
- The 1A Atmospheric Relief Valve is mechanically bound and cannot be opened.
Which one of the following completes the statements below?
Entry conditions for FRP-H.2, Response to Steam Generator Overpressure (1) been met When FRP-H.2 is entered, the crew would be directed to lower 1A SG Pressure by (2) .
(1) (2)
A. have NOT dumping steam to the TDAFWP B. HAVE dumping steam to the TDAFWP C. have NOT opening MSIV bypasses D. HAVE opening MSIV bypasses
- 75. Unit 1 has experienced a Large Break LOCA with the following conditions:
- PR-0950Z, CTMT PRESS NR, indicates 30 psig.
- FI-958 A and B, CS FLOW, indicate 1200 GPM each.
Which one of the following completes the statements below?
Per CSF-0.5, Containment, the crew is required to enter a(n) (1) path FRP due to (2) .
(1) (2)
A. RED CTMT Pressure B. RED CTMT Sump Level C. ORANGE CTMT Pressure D. ORANGE CTMT Sump Level
- 76. Unit 1 was operating at 100% power when the following occurred:
At 1000:
- All Control Banks are at 231 steps.
At 1010:
- Rod K4 fell to 130 steps.
- Rod M6 fell to 150 steps.
- RCS Tavg lowered.
- Pressurizer pressure lowered.
Which one of the following completes the statement below?
Per AOP-19, Malfunction of Rod Control System, the operating crew is required to .
A. shutdown the unit using UOP-3.1, Power Operation B. trip the Reactor and go to EEP-0.0, Reactor Trip and Safety Injection C. reduce power to less than 75% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using UOP-3.1, Power Operation D. address restoration of rods using SOP-41.0, Control Rod Drive and Position Indication System
- 77. Unit 1 is operating at 100% power when the following occurs:
At 1000:
- HH4, RCP VIB TRBL (WHITE annunciator window), comes into alarm.
- 1A RCP shaft vibration is reported as 21 mils and stable.
- DC2, RCP #1 SEAL LKOF FLOW HI (YELLOW annunciator window),
comes into alarm.
At 1600:
- The Unit is in MODE 3.
- The Reactor Trip Breakers are open.
- 1B and 1C RCPs are running.
- 1A RCP is tagged out.
Which one of the following completes the statements below?
At 1000, the operating crew is required to (1) , then secure the 1A RCP.
At 1600, RCS pressure control is via (2) .
A. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Normal Spray B. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Normal Spray C. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Auxiliary Spray D. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Auxiliary Spray
- 78. Unit 1 is operating at 100% power when the following occurs:
- Due to a Pressurizer pressure control malfunction, PCV-445A, PRZR PORV opens and reseats several times.
- PRT parameters are:
- Level: 84% and is stable.
- Temperature: 180°F and stable.
- Pressure: 30 psig and stable.
Which one of the following completes the statements below?
HE4, PRT LVL HI-LO, (1) in alarm.
Draining the PRT using the RCDT pump per Section 4.3, Filling and Draining the PRT, of SOP-1.2 (2) restore all PRT parameters to within normal log specifications.
Procedure name: SOP-1.2, Reactor Coolant Pressure Relief System (1) (2)
A. is NOT will NOT B. IS will NOT C. is NOT WILL D. IS WILL
- 79. Unit 1 is in MODE 3 with the following conditions:
At 1000:
- The Shutdown Banks are withdrawn.
At 1005:
- A complete loss of offsite power occurs.
Which one of the following completes the statements below?
At 1005, manual action (1) required to generate a P-4 signal.
Per the BASES of Tech Spec 3.3.2, ESFAS Instrumentation, P-4 is required to be OPERABLE to prevent (2) .
A. (1) IS (2) excessive Containment pressure due to a steamline break B. (1) is NOT (2) excessive Containment pressure due to a steamline break C. (1) IS (2) damage to the Main Steam lines and SG safeties due to SG overfill D. (1) is NOT (2) damage to the Main Steam lines and SG safeties due to SG overfill
- 80. Unit 1 is operating at 100% power with the following conditions:
- A malfunction occurred resulting in PCV-444B, PRZR PORV, opening.
Subsequently, the immediate operator actions of AOP-100, Instrumentation Malfunction, were performed and the following conditions exist:
- PCV-444B GREEN light is LIT.
- RCS pressure is 2180 psig and stable.
- PRT pressure, level and temperature are stable.
- HA4, PRZR SAFETY VLV TEMP HI, is in alarm.
- HA5, PRZR PORV TEMP HI, is in alarm.
Which one of the following completes the statements below?
PCV-444B (1) leaking by.
Per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), PCV-444B (2) OPERABLE.
(1) (2)
A. IS IS B. IS is NOT C. is NOT IS D. is NOT is NOT
- 81. Unit 1 is at 100% power with the following conditions:
- PT-950, CTMT PRESS (Channel 1), was declared INOPERABLE.
- PT-950 bistables were positioned as required by Tech Spec 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, for continuous operation with an inoperable channel.
Which one of the following completes the statements below?
The Safety Injection function (1) affected by the PT-950 malfunction.
Per Tech Spec 3.3.2, the REQUIRED ACTION is to place the PT-950 bistables in (2) .
(1) (2)
A. IS TRIP B. IS BYPASS C. is NOT TRIP D. is NOT BYPASS
- 82. Unit 1 is in MODE 3 with the following conditions:
- All RCPs are running.
Which one of the following completes the statements below?
The method used in the Main Control Room (MCR) to isolate the CCW leak is to (1) .
Per the BASES of Tech Spec 3.7.7 - CCW System, once the CCW leak is isolated from the MCR, the CCW System is (2) .
A. (1) isolate CCW to ALL RCPs (2) INOPERABLE B. (1) isolate CCW to the 1A RCP ONLY (2) INOPERABLE C. (1) isolate CCW to ALL RCPs (2) OPERABLE D. (1) isolate CCW to the 1A RCP ONLY (2) OPERABLE
- 83. Unit 1 has experienced a LOCA. The following conditions exist:
- EEP-1.0, Loss of Reactor or Secondary Coolant, is in progress.
- Containment Hydrogen is 6% by volume of dry air.
Which one of the following completes the statements below?
The hydrogen concentration (1) exceed the lower FLAMMABILITY limit.
Hydrogen concentration will be lowered using (2) .
A. (1) DOES (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System B. (1) DOES (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation C. (1) does NOT (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System D. (1) does NOT (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation
- 84. Unit 1 is operating at 100% when a Pressurizer level control malfunction occurs and the following conditions exist:
- Pressurizer level is 70% and rising.
- Charging flow is 120 gpm.
- Letdown is 60 gpm.
- RCP seal leakoff is 3 gpm per pump.
- Actions in the field are being taken to regain control of Charging.
- It will take 8 minutes to regain control of Charging.
Which one of the following completes the statements below?
An automatic reactor trip (1) occur before control of Charging is regained.
Per the BASES of Tech Spec 3.3.1, Reactor Trip System (RTS)
Instrumentation, the purpose of the automatic Reactor Trip on Pressurizer Water Level - High is to (2) .
Reference Provided A. (1) WILL (2) provide protection against water relief through the PORV's B. (1) WILL (2) prevent thermal shock of the Spray Nozzle C. (1) will NOT (2) provide protection against water relief through the PORV's D. (1) will NOT (2) prevent thermal shock of the Spray Nozzle
- 85. Unit 1 is conducting a fuel reload and the following occurs:
At 1015: An Intermediate Leg leak is in progress on the 1A RCS loop with the following conditions.
- R-2, CTMT 155 FT, is in alarm.
- EH2, SFP LVL HI-LO is in alarm.
- Both RHR pumps have been secured due to cavitation.
Which one of the following completes the statements below?
At 1030, an emergency classification, per NMP-EP-110, Emergency Classification Determination and Initial Action, (1) required.
Per AOP-12, Residual Heat Removal System Malfunction, the maximum time to complete Containment closure is (2) hour(s).
(1) (2)
A. IS 1 B. IS 2 C. is NOT 1 D. is NOT 2
- 86. A fuel shuffle is in progress in the Unit 1 SFP with the following conditions:
At 1000:
- An 1800 lb. load is being moved over spent fuel.
At 1015:
- The load is dropped causing damage to the spent fuel.
At 1015, which one of the following describes the minimum Radiation Monitor(s) required to be in alarm to meet AOP-30, Refueling Accident, entry conditions?
AND Which one of the following describes the the expected worst case consequences of dropping an 1800 lb. load onto the spent fuel Per the Bases of TR 13.9.4, Crane Travel-Spent Fuel Storage Building?
A.
- R-5 OR R-25A
- The activity release will be limited to that contained in a single fuel assembly.
B.
- R-5 OR R-25A
- The offsite dose may be as high as but not more than the 10 CFR 100 limit.
C.
- R-5 AND R-25A
- The activity release will be limited to that contained in a single fuel assembly.
D.
- R-5 AND R-25A
- The offsite dose may be as high as but not more than the 10 CFR 100 limit.
- 87. Unit 1 was operating at 100% power with the following conditions:
At 1000: A Loss of Offsite Power occurs.
At 1015: The following conditions exist -
- DG-02, 1G 4160 V bus tie to 1L 4160 V bus, has AMBER and GREEN Lights LIT.
Which one of the following completes the statements below?
At 1015: The 1B DG (1) have cooling water supplied.
At 1015: The REQUIRED ACTION(S) of Tech Spec(s) (2) is(are) required to be performed.
Tech Spec nomenclature: 3.8.9, Distribution Systems - Operating 3.7.8, Service Water System (SWS)
(1) (2)
A. WILL 3.8.9 AND 3.7.8 B. will NOT 3.8.9 AND 3.7.8 C. WILL 3.8.9 ONLY D. will NOT 3.8.9 ONLY
- 88. Unit 1 is in Mode 3 with the following conditions:
- Pressurizer level is 22% and stable.
Subsequently, a rupture occurs on the Instrument Air header piping in the MSVR and AOP-6.0, Loss of Instrument Air, is in progress.
Which one of the following completes the statements below?
Pressurizer level will (1) .
Per AOP-6.0, to maintain Pressurizer level, the operating crew is required to perform actions of (2) in conjunction with AOP-6.0.
Procedure Names: AOP-16.0, CVCS Malfunction SOP-2.1, CVCS Plant Startup and Operation (1) (2)
A. lower AOP-16.0 B. rise AOP-16.0 C. lower SOP-2.1 D. rise SOP-2.1
- 89. Unit 1 is operating at 100% power when the following occurs:
- R-27B, CTMT HIGH RANGE, is tagged out.
- The instrument power supply fuse to R-27A, CTMT HIGH RANGE, blows.
Which one of the following completes the statements below?
R-27A indication will fail (1) .
Per Tech Spec 3.3.3, Post Accident Monitoring Instrumentation, the REQUIRED ACTION is to (2) .
Reference Provided A. (1) HIGH (2) immediately initiate action in accordance with Specification 5.6.8 B. (1) HIGH (2) restore R-27A OR R-27B to OPERABLE status in 7 days C. (1) LOW (2) immediately initiate action in accordance with Specification 5.6.8 D. (1) LOW (2) restore R-27A OR R-27B to OPERABLE status in 7 days
- 90. Unit 1 is operating at 100% power and the following occurs:
- R-15A, SJAE EXH, power supply becomes erratic causing its indication to become unreliable but it does not alarm.
Per the ODCM, which one of the following actions are required to continue the release via this pathway, if any?
A. No actions are required.
B. Continuously collect samples using auxiliary equipment.
C. Place SJAE filtration in service until R-15A is restored to operable.
D. Perform grab samples at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyze them within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 91. Unit 1 is in MODE 6 with the following conditions:
- Core reload is complete.
- Control Rod Drive Shaft Latching and RCCA Drag Testing is about to begin per FHP-5.1, Control Rod Drive Shaft Latching/Unlatching Tool Operating Instruction.
Which one of the following completes the statements below?
Per FHP-0.0, Refueling Organization, the Fuel Handling Supervisor (1) .
Per UOP-4.1, Controlling Procedure for Refueling, two Source Range Nuclear Instruments (2) required to be OPERABLE.
A. (1) is required to be in Containment (2) are NOT B. (1) is required to be in Containment (2) ARE C. (1) may be in the Control Room in direct Communication with Containment (2) are NOT D. (1) may be in the Control Room in direct Communication with Containment (2) ARE
- 92. A tagout is required to be cleared during night shift and the Work Document Holder is not on site and cannot be contacted to gain their approval.
Per NMP-AD-003, Equipment Clearance and Tagging, which one of the following can sign off the Work Document Holder?
A. Shift Manager B. Operations Director C. Maintenance Director D. Maintenance Manager
- 93. Unit 1 is at 6% power with the following conditions:
- The 1A SGFP has been started.
- AFW is secured.
- The Main Feed Regulating Valves are closed.
At 1000 on January 1, 2015:
- MOV-3232B, MAIN FW TO 1B SG STOP VLV , is declared INOPERABLE.
At 1200 on January 1, 2015:
- FCV-489, 1B SG FW BYP FLOW, is declared INOPERABLE.
Subsequently it is determined that repairs will take 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> for each valve.
Which one of the following completes the statement below?
Per Tech Spec 3.7.3, Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves, the earliest time that feed flow to the 1B SG must be isolated is .
Reference Provided A. 1800 on January 1, 2015 B. 2000 on January 1, 2015 C. 1000 on January 4, 2015 D. 1200 on January 4, 2015
- 94. A General Emergency on Unit 1 has been declared with following conditions:
- An Emergency Response Team is required to be dispatched to isolate an offsite release source.
- The TSC has not yet been manned.
Which one of the following completes the statements below?
To receive the dose listed above, operators (1) required to be volunteers.
The (2) will authorize the exposure.
(1) (2)
A. are NOT RP Supervisor B. are NOT Shift Manager C. ARE RP Supervisor D. ARE Shift Manager
- 95. Unit 1 is in MODE 6 with core offload in progress with the following condition:
- A spent fuel assembly is being moved from its assigned location in the core to the upender.
Subsequently, AOP-30.0, Refueling Accident, is entered Which one of the following completes the statements below?
Per AOP-30.0, the Refueling SRO will direct the fuel assembly to be (1) .
Per the BASES of Tech Spec 3.9.6, Refueling Cavity Water Level, 23 ft of water is required to be maintained above the fuel to (2) .
A. (1) placed in any empty fuel location in the core (2) provide back up decay heat removal B. (1) placed in any empty fuel location in the core (2) retain iodine fission product activity in the water during a fuel handling accident C. (1) returned to its assigned location in the core (2) provide back up decay heat removal D. (1) returned to its assigned location in the core (2) retain iodine fission product activity in the water during a fuel handling accident
- 96. Unit 2 reactor startup is in progress and the following conditions exist:
- NI31, SR1 COUNT RATE is 106 cps and stable.
- NI32, SR2 COUNT RATE is 104 cps and stable.
- TSLB-3 1-1, SR HI Q NC-31D is lit.
- TSLB-3 1-2, SR HI Q NC-32D is NOT lit.
- GA1, SR HI FLUX TRIP, is in alarm.
- The Reactor Trip breakers are closed.
Subsequently, The Shift Supervisor directs a manual Reactor trip.
- The Reactor Trip breakers open.
Which one of the following completes the statements below?
An emergency classification threshold value (1) been exceeded per NMP-EP-110-GL01, FNP EALS - ICs, Threshold Values And Basis.
The latest time the NRC can be notified is (2) hour(s) after the event / emergency declaration.
(1) (2)
A. has NOT 4 B. HAS 4 C. has NOT 1 D. HAS 1
- 97. Unit 1 is performing the actions of EEP-0.0, Reactor Trip or Safety Injection, and AOP-9, Loss of Component Cooling Water. Conditions are as follows:
- 1F 4160V bus is de-energized.
- B Train CCW is the on service Train.
- 1B CCW pump is Tagged Out.
- 1A CCW pump tripped.
- 1C CHG PUMP is running.
Subsequently, the Shift Supervisor determines that Firewater is required to be aligned to the 1B Charging pump.
Which one of the following completes the statements below?
The 1C Charging pump will be (1) while aligning Firewater to the 1B Charging pump.
(2) Charging pump CCW oil cooler piping will become chemically contaminated.
(1) (2)
A. secured ONLY the 1B B. secured BOTH 1B and 1C C. maintained running ONLY the 1B D. maintained running BOTH 1B and 1C
- 98. Unit 1 operating crew has exited EEP-0.0, Reactor Trip or Safety Injection, and is now performing ECP-1.2, LOCA Outside Containment with the following conditions:
- The leak isolation steps are completed.
- RWST level is 12.5 ft.
- RCS pressure continues to lower.
Which one of the following completes the statement below?
The next procedure the operating crew is required to transition to is .
A. EEP-0.0, Reactor Trip or Safety Injection B. ESP-1.3, Transfer to Cold Leg Recirculation C. EEP-1.0, Loss of Reactor or Secondary Coolant D. ECP-1.1, Loss of Emergency Coolant Recirculation
- 99. Unit 2 is performing the actions of FRP-H.1, Response to Loss of Secondary Heat Sink, and the following conditions exist:
- The TDAFW pump has been returned to service.
- Containment pressure is 0 psig.
- RCS Bleed and Feed was initiated, but has now been secured.
- RCS pressure is 1600 psig and rising.
- Pressurizer level is 23% and rising.
Which one of the following completes the statements below?
The minimum SG level that permitted securing Bleed and Feed was at least one SG (1) .
The operating crew will transition to (2) from FRP-H.1.
A. (1) Wide Range level at 14%
(2) ESP-1.1, SI Termination B. (1) Wide Range level at 14%
(2) EEP-1, Loss of Reactor or Secondary Coolant C. (1) Narrow Range level at 33%
(2) ESP-1.1, SI Termination D. (1) Narrow Range level at 33%
(2) EEP-1, Loss of Reactor or Secondary Coolant
100. Unit 1 is cooling down per ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding, and the following conditions exist:
- RVLIS is not available.
- RCS Hot leg is 450°F and slowly lowering.
- RCS Cold leg is 425°F and slowly lowering.
- The crew is cooling down at the maximum rate allowed by procedure.
- Pressurizer level has just rapidly risen to 78% and is stable
- RCS pressure reduction is not required.
- CST level is 9ft.
Which one of the following completes the statements below?
The operating crew will transition to ESP-0.4, Natural Circulation Cooldown with Allowance for Reactor Vessel Head Steam Voiding (Without RVLIS), based on (1) .
The maximum allowable cooldown rate in ESP-0.4 is (2) .
Reference Provided A. (1) CST Level (2) <100°F in any 60 minute period B. (1) CST Level (2) <50°F/hr C. (1) Reactor Vessel void formation being indicated (2) <100°F in any 60 minute period D. (1) Reactor Vessel void formation being indicated (2) <50°F/hr
PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS
NOTE--------------------------------------------------------
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required channel 30 days with one required to OPERABLE status.
channel inoperable.
B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A Specification 5.6.8.
not met.
C. One or more Functions C.1 Restore one channel to 7 days with two required OPERABLE status.
channels inoperable.
Farley Units 1 and 2 3.3.3-1 Amendment No. 170 (Unit 1)
Amendment No. 163 (Unit 2)
PAM Instrumentation 3.3.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.3-1 for the not met. channel.
E. As required by Required E.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 /> Action D.1 and referenced in AND Table 3.3.3-1.
E.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> F. As required by Required F.1 Initiate action in Immediately Action D.1 and accordance with referenced in Specification 5.6.8.
Table 3.3.3-1.
SURVEILLANCE REQUIREMENTS
NOTE--------------------------------------------------------------
SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1.
SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required In accordance with instrumentation channel that is normally energized. the Surveillance Frequency Control Program SR 3.3.3.2 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.3.3-2 Amendment No. 185 (Unit 1)
Amendment No. 180 (Unit 2)
PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 1)
Post Accident Monitoring Instrumentation CONDITION REFERENCED FROM REQUIRED REQUIRED FUNCTION CHANNELS ACTION D.1
- 1. RCS Hot Leg Temperature (Wide Range) 2 E
- 2. RCS Cold Leg Temperature (Wide Range) 2 E
- 3. RCS Pressure (Wide Range) 2 E
- 4. Steam Generator (SG) Water Level (Wide or 2/SG E Narrow Range)
- 5. Refueling Water Storage Tank Level 2 E
- 6. Containment Pressure (Narrow Range) 2 E
- 7. Pressurizer Water Level 2 E
- 8. Steam Line Pressure 2/SG E
- 9. Auxiliary Feedwater Flow Rate 2 E
- 10. RCS Subcooling Margin Monitor 2 E
- 11. Containment Water Level (Wide Range) 2 E
- 12. Core Exit Temperature - Quadrant 1 2 (a) E
- 13. Core Exit Temperature - Quadrant 2 2(a) E
- 14. Core Exit Temperature - Quadrant 3 2(a) E
- 15. Core Exit Temperature - Quadrant 4 2(a) E
- 16. Reactor Vessel Level Indicating System 2 F
- 17. Condensate Storage Tank Level 2 E
- 18. Deleted
- 19. Containment Area Radiation (High Range) 2 F (a) A channel consists of two core exit thermocouples.
Farley Units 1 and 2 3.3.3-3 Amendment No. 167 (Unit 1)
Amendment No. 159 (Unit 2)
Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves LCO 3.7.3 Three Main FW Stop Valves, three MFRVs, and associated bypass valves shall be OPERABLE.
APPLICABILITY: MODES 1 and 2, except when all main feedwater lines are isolated by either a Main FW Stop Valve, a MFRV and its associated bypass valve or by a closed manual valve.
ACTIONS
NOTE-------------------------------------------------------------
Separate Condition entry is allowed for each valve.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Main FW A.1 Close or isolate Main FW 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Stop Valves inoperable. Stop Valve.
AND A.2 Verify Main FW Stop Valve Once per 7 days is closed or isolated.
B. One or more MFRVs B.1 Close or isolate MFRV. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable.
AND B.2 Verify MFRV is closed or Once per 7 days isolated.
Farley Units 1 and 2 3.7.3-1 Amendment No. 146 (Unit 1)
Amendment No. 137 (Unit 2)
Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One or more MFRV C.1 Close or isolate bypass 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> bypass valves valve.
AND C.2 Verify bypass valve is closed Once per 7 days or isolated.
D. Two valves in the same D.1 Isolate affected flow path. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> flow path inoperable.
E. Required Action and E.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.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each Main FW Stop Valve, In accordance with MFRV, and associated bypass valve is in accordance the Inservice with the time requirement in the Inservice Testing Testing Program.
Plan.
Farley Units 1 and 2 3.7.3-2 Amendment No. 146 (Unit 1)
Amendment No. 137 (Unit 2)
1/22/2013 14:30
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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: 20 OCT 2015 Facility / Unit FARLEY 1 & 2 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 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results RO/SRO-Only/Total Examination Values 75 / ______
______ 25 / ______
100 Points Applicant's Score ______ / ______ / ______
Points Applicant's Grade ______ / ______ / ______
Percent ES-401, Page 38 of 50
- 1. Unit 1 is starting up IAW UOP-1.2, Startup of Unit from Hot Standby to Minimum Load, with the following condition:
- Reactor Power is 13%.
The CONTROL ROD MOTION switch has been released following a rod withdrawal when the following occurs:
- Rods step out continuously.
Which one of the following completes the statements below?
The first action directed by AOP-19.0, Malfunction of Rod Control System, is to (1) .
With NO operator action the C-1, IR Hi Flux Rod Stop, (2) stop the outward rod motion.
A. (1) manually Trip the Reactor (2) will NOT B. (1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) will NOT C. (1) manually Trip the Reactor (2) WILL D. (1) place ROD CONTROL BANK SELECTOR SWITCH in AUTO (2) WILL
- 2. Unit 1 is performing a Reactor startup at MOL with the following conditions:
- UOP-1.2, Startup of Unit From Hot Standby to Minimum Load, is in progress.
- The OATC has stabilized Reactor power.
- NI-35 and NI-36, INTERMEDIATE RANGE, indicate 1x10-8 AMPS.
Subsequently, control rods are withdrawn 3 steps.
Which one of the following completes the statements below?
Reactor Power will rise then stablize (1) the POAH.
The first indication of reaching the POAH is rising (2) .
(1) (2)
A. below Pressurizer Level B. at Pressurizer Level C. below S/G Pressure D. at S/G Pressure
- 3. Unit 1 is at 25% power when the following conditions occur:
At 1000:
- 1A RX COOLANT PUMP AMPS indicates 700 AMPS.
At 1002:
- The 1A RCP motor experiences a Sheared Shaft.
Which one of the following completes the statements below?
At 1002 the 1A RCP will draw (1) electrical current than it did at 1000.
The crew is required to immediately enter (2) .
(1) (2)
A. More EEP-0.0, Reactor Trip and Safety Injection B. Less EEP-0.0, Reactor Trip and Safety Injection C. More AOP-4.0, Loss of Reactor Coolant Flow D. Less AOP-4.0, Loss of Reactor Coolant Flow
- 4. Unit 1 is operating at 100% power with the following conditions:
- PK-145, LP LTDN PRESS, is set to maintain Letdown Pressure at 275 psig.
Subsequently, the RCS filter becomes completely clogged and does not allow any flow.
Which one of the following completes the statements below?
PK-145 controller demand will (1) .
AOP-16.0, CVCS Malfunction, entry conditions (2) been met.
(1) (2)
A. Rise HAVE B. Rise have NOT C. Lower HAVE D. Lower have NOT
- 5. Which one of the following completes the statement below?
Charging Pump Suctions will automatically align to the RWST when (1) sense(s) (2) VCT Level.
Level Transmitter Nomenclature LT-115, VCT LVL LT-112, VCT LVL (1) (2)
A. either LT-115 or LT-112 5%
B. both LT-115 and LT-112 5%
C. either LT-115 or LT-112 15%
D. both LT-115 and LT-112 15%
- 6. Unit 1 is in MODE 4 with the following conditions:
- Plant cooldown is in progress with the 'A' Train of RHR .
Which one of the following completes the statements below?
Raising demand on FK-605A will (1) CCW temperature.
Per SOP-23.0, Component Cooling Water System, the maximum allowable CCW outlet temperature for the CCW HX used for cooldown is (2) .
(1) (2)
A. raise 120°F B. raise 135°F C. lower 120°F D. lower 135°F
- 7. Unit 1 is shutdown when the following conditions occur:
- The 1A CCW pump tripped.
- The 'A' Train is the ON SERVICE Train.
Which one of the following completes the statement below?
Cooling is lost to the (1) RHR Heat Exchanger.
The affected RHR train (2) available for transfer to Cold Leg Recirculation.
(1) (2)
A. 1A is NOT B. 1A IS C. 1B is NOT D. 1B IS
- 8. Unit 1 has experienced a tube rupture on the 1A SG with the following conditions:
- A Loss of All Offsite Power has occurred.
- The operating crew is performing EEP-3, Steam Generator Tube Rupture.
- RCS cooldown is in progress.
- INTEGRITY Critical Safety Function Status Tree has turned ORANGE due to the 1A RCS LOOP cold leg temperature dropping rapidly.
Which one of the following completes the statements below?
The 1A RCS LOOP cold leg temperature drop was caused by increased (1) flow over the 1A RCS LOOP cold leg instrument.
(2) is the highest listed cold leg temperature that could lead to this ORANGE INTEGRITY condition.
(1) (2)
A. Natural Circulation 270°F B. Natural Circulation 225°F C. High Head Safety Injection 270°F D. High Head Safety Injection 225°F
- 9. A Safety Injection has just occurred on Unit 1.
Which one of the following completes the statement below?
The minimum valve actuations that would lead to HHSI Pump cavitation are .
Valve Nomenclature:
LCV-115C, VCT OUTLET ISO LCV-115E, VCT OUTLET ISO LCV-115D, RWST TO CHG PUMP LCV-115B, RWST TO CHG PUMP A. LCV-115C or LCV-115E opening B. LCV-115C and LCV-115E opening C. LCV-115B or LCV-115D closing D. LCV-115B and LCV-115D closing
- PI-472, PRT PRESS, stablizes at 15.0 psig.
Which one of the following completes the statements below?
HE5, PRT PRESS HI, (1) in alarm.
Per SOP-1.2, Reactor Coolant Pressure Relief System, normal nitrogen pressure prevents (2) .
(1) (2)
A. IS excessive corrosion due to oxygen B. is NOT excessive corrosion due to oxygen C. IS an explosive mixture of oxygen and hydrogen D. is NOT an explosive mixture of oxygen and hydrogen
- 11. Unit 1 is operating at 100% power when the following conditions occur:
- A large break has occurred at the inlet of a Pressurizer Safety Valve.
Subsequently, the following condition exists:
- Pressurizer Pressure is 1600 psig.
- Charging Pump miniflow valves are open.
Which one of the following completes the statements below?
Per EEP-0, Reactor Trip or Safety Injection, the crew (1) required to close the Charging Pump miniflow valves.
Closing the Charging Pump miniflow valves when required will ensure (2) .
(1) (2)
A. IS HHSI pump injection flow is maximized B. is NOT HHSI pump injection flow is maximized C. IS HHSI pump heat is removed D. is NOT HHSI pump heat is removed
- 12. Unit 1 is operating at 100% power with the following conditions:
- A dual unit LOSP occurs.
Subsequently, Unit 2 experiences a Safety Injection.
Which one of the following completes the statement below for Unit 1?
The (1) CCW pump is being powered by the (2) DG.
(1) (2)
A. 1A 1-2A B. 1A 1C C. 1C 1-2A D. 1C 1C
- 13. Unit 1 is in MODE 5 with the following conditions:
- A cooldown is in progress.
- RHR is on service.
Subsequently, the following conditions occur:
- V-8708A, RHR SUCTION RELIEF, has lifted and is stuck open.
Which of the following tank levels will immediately rise due to the malfunction?
- 14. A Design Basis Large Break LOCA has occurred on Unit 1.
Which one of the following completes the statements below?
The Accumulators will inject directly to the (1) .
The purpose of the Accumulator design capacity is to (2) refill the Reactor Vessel following a design basis accident.
(1) (2)
A. Hot Legs partially B. Hot Legs completely C. Cold Legs partially D. Cold Legs completely
- 15. Unit 1 is operating at 100% power and the following conditions exist:
- Pressurizer Pressure is 2240 psig.
- Tavg is 572°F.
- Pressurizer Level Control is in manual.
- Pressurizer Level is 60%.
- 600V LCC 1M has lost power.
Which one of the following completes the statements below?
Power has been lost to the (1) Pressurizer Heater Group.
Pressurizer Heater Groups A and B are currently (2) .
(1) (2)
A. D Energized B. D De-Energized C. E Energized D. E De-Energized
- 16. Unit 1 is operating at 100% Power when the following conditions occur:
- A short circuit occurs in PT-445, PRZR PRESS.
- Pressurizer Pressure remains stable.
Which one of the following completes the statement below?
The Pressurizer Pressure input to the Reactor Protection System will NOT be affected by this malfunction due to the use of .
A. an independent control channel B. a median signal selector C. isolation devices D. de-energize to actuate bistables
- 17. Unit 1 is operating at 100% power and the following occurs:
- A Safety Injection followed by an LOSP on Unit 1.
Several minutes following the safety injection the following condition exists:
- The 1B DG is running with the output breaker open.
Which one of the following completes the statements below?
SOP-0.8, Transient Response Procedure User's Guide, (1) require a procedure be used prior to closing the 1B DG output breaker.
The B1G sequencer (2) energize the 1C Air Compressor.
(1) (2)
A. DOES DOES B. DOES does NOT C. does NOT DOES D. does NOT does NOT
- 18. The 1D Vital Panel becomes de-energized on Unit 1.
Which one of the following completes the statements below.
The 'B' Train SI actuated MOVs (1) automatically stroke upon an SI actuation.
'B' Train ESF pumps (2) be started in LOCAL at the HSDP.
(1) (2)
A. WILL CAN B. WILL CANNOT C. will NOT CAN D. will NOT CANNOT
- 19. Which one of the following completes the statements below?
The C-11, Bank D Stop, is actuated by input from (1) at a Bank D rod height of (2) steps.
(1) (2)
A. Digital Rod Position Indication 220 B. Digital Rod Position Indication 228 C. the Pulse-to-Analog Converter 220 D. the Pulse-to-Analog Converter 228
- 20. Unit 1 is in MODE 3 and the following RCP temperatures are observed:
Motor Bearing Temperature Motor Stator Temperature 1A RCP 190°F 235°F 1B RCP 200°F 220°F 1C RCP 190°F 230°F Which one of the following completes the statement below?
Only the is (are) required to be secured.
A. 1A RCP B. 1B RCP C. 1A and 1B RCPs D. 1A and 1C RCPs
- 21. Which one of the following conditions would cause a Core Exit Thermocouple (CETC) monitor alarm?
- 1. ANY CETC input disconnected.
- 2. ONLY 10 valid CETCs.
- 3. ANY CETC temperature at 650°F.
A. 1 ONLY B. 1 AND 3 ONLY C. 2 ONLY D. 1, 2, AND 3
- 22. Unit 1 is operating at 100% power when the following conditions occurred:
- 1B Charging Pump is started.
- 1A Charging Pump is secured.
- 1B CHG PUMP AMPS, begins to oscillate.
- FI-122A, CHG FLOW, begins to oscillate.
Subsequently, the following annunciators come into alarm:
- EA2, CHG HDR FLOW HI-LO.
- DE1, REGEN HX LTDN FLOW DISCH TEMP HI.
Which one of the following completes the statements below?
The alarms above are indicative of (1) .
The maximum 1A RCP seal injection flowrate that would cause DD1 to alarm is (2) .
(1) (2)
A. FCV-122 closing 6 gpm B. 1B Charging Pump Cavitation 6 gpm C. FCV-122 closing 3 gpm D. 1B Charging Pump Cavitation 3 gpm
- 23. Unit 1 is operating at 100% power with the following conditions:
- A Large Break LOCA occurs.
Subsequently, a Loss of Offsite Power occurs.
Which one of the following completes the statement below 5 minutes after the Loss of Offsite Power?
(1) Containment Cooler Fans are running in slow speed.
The reduced speed prevents CTMT cooler (2) due to high moisture content in the Containment atmosphere.
(1) (2)
A. 2 fan motor overload B. 4 fan motor overload C. 2 cooling coil impingement damage D. 4 cooling coil impingement damage
- 24. Unit 1 is in MODE 5 and the following condition exists:
- Both Trains of RHR are operating in the cooldown alignment.
- Power is aligned to the RHR suction valves.
- Tavg is 195°F.
Subsequently, the following condition occurs:
Which one of the following completes the statements below?
MOV-8701A, 1C RCS LOOP TO 1A RHR PUMP, (1) automatically close.
IF MOV-8701A closes, then AOP-12.0, Residual Heat Removal System Malfunction, entry (2) required.
(1) (2)
A. DOES is NOT B. does NOT is NOT C. DOES IS D. does NOT IS
- 25. Unit 1 is Shutdown following a LOCA with the following conditions:
- PR-950, CTMT PRESS, peaked at 3.2 psig.
- ECP-1.1, Loss of Emergency Coolant Recirculation, is in progress.
Which one of the following completes the statments below:
Per ECP-1.1, the minimum CTMT Sump Level that can support Containment Spray pump operation is .
A. 2.0 ft B. 3.8 ft C. 4.5 ft D. 5.3 ft
- 26. Unit 1 is operating at 100% power when the following condition occurs:
- PK-444A, PRZR PRESS REFERENCE, demand fails to 0%.
Which one of the following completes the statements below?
Initially, (1) PORV(s) will OPEN automatically.
PCV-444C, 1A LOOP SPRAY VLV, will (2) .
(1) (2)
A. only ONE CLOSE B. only ONE OPEN C. BOTH CLOSE D. BOTH OPEN
- 27. Unit 1 is operating at 100% power with the following conditions:
- Containment Mini-Purge is in operation Subsequently, the following conditions occur:
- A Main Steam Line breaks inside Containment
- PR-950Z, CTMT PRESS, stablizes at 14.5 psig.
Which one of the following completes the statements below?
CTMT Mini-Purge supply and exhaust fans (1) tripped automatically due to a Containment Ventilation Isolation signal.
CTMT Mini-Purge supply and exhaust dampers (2) closed automatically due to a Containment Ventilation Isolation signal.
(1) (2)
A. HAVE HAVE B. HAVE have NOT C. have NOT HAVE D. have NOT have NOT
- 28. Unit 1 is operating at 100% power with the following conditions:
- STP-33.2A, Reactor Trip Breaker Train A Operability Test, is in progress.
- Reactor Trip Breaker A is OPEN.
- Reactor Trip Bypass Breaker A is CLOSED.
- Reactor Trip Breaker B is CLOSED.
Subsequently, the following conditions occur:
- An automatic reactor trip signal is generated.
- The Reactor does NOT trip.
Which one of the following completes the statements below?
When the RX TRIP ACTUATION switch is taken to TRIP (1) will OPEN.
Per EEP-0, Reactor Trip or Safety Injection, if the RX TRIP ACTUATION switches fail to trip the Reactor, the next action required is to (2) .
A. (1) ONLY Reactor Trip Breaker B (2) trip the MG set supply breakers B. (1) BOTH Reactor Trip Bypass Breaker A and Reactor Trip Breaker B (2) trip the MG set supply breakers C. (1) ONLY Reactor Trip Breaker B (2) insert Control Rods manually D. (1) BOTH Reactor Trip Bypass Breaker A and Reactor Trip Breaker B (2) insert Control Rods manually
- 29. Unit 2 is starting up per UOP-1.2, Startup of Unit From Hot Standby To Minimum Load, with the following conditions:
- Main Steam Header Warm Up is in Progress.
Which one of the following actions would cause the 2B SG Pressure to lower due to increased steam demand from the 2B SG?
A. Lower PC-3371B, 2B MS ATMOS REL VLV, SETPT in AUTO.
B. Lower PC-3371B, 2B MS ATMOS REL VLV, OUTPUT in MAN.
C. Lower PK-464, STM HDR PRESS, OUTPUT in MAN.
D. Lower PK-464, STM HDR PRESS, SETPT in AUTO.
At 1000:
- HIGHEST CORE EXIT TEMP CHAN A and B on the IPC, indicates 530°F.
- 1A SG PRESS is 810 psig.
- RCS cooldown is in progress.
At 1045:
- HIGHEST CORE EXIT TEMP CHAN A and B, on the IPC indicates 450°F.
- 1A SG PRESS is 300 psig.
Which one of the following completes the statements below?
Compared to the conditions at 1000, RCS subcooling at 1045 has (1) .
Compared to the conditions at 1000, SG tube leakage rate at 1045 has (2) .
Reference Provided (1) (2)
A. risen risen B. risen lowered C. lowered lowered D. lowered risen
- 31. Unit 1 is in Mode 3 at EOL with the following conditions:
- A Reactor Startup is being planned for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a reactor trip.
- Tavg is being maintained by the Atmospheric Relief Valves (ARVs).
- The Estimated Critical Condition (ECC) calculation predicts criticality at 100 steps on Control Bank D.
Which one of the following conditions will result in critical rod height being HIGHER than the value predicted by the ECC?
For your answer, consider that no operator actions are taken to mitigate or compensate for the below events.
A. A dilution of 500 gallons is performed.
B. Auxiliary Feedwater flow is RAISED to all SGs.
C. A post maintenance test results in the closure of all ARVs.
D. Reactor startup occurs 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> after the reactor trip.
- 32. Unit 2 is at 68% power ramping down due to a problem with #4 Governor Valve with the following conditions:
- EH is isolated to #4 Governor valve.
- A subsequent failure causes #2 Governor Valve to fail closed.
- Turbine load drops to 450 MW.
Which one of the following completes the statements below?
The #2 governor valve closure results in (1) .
Per SOP-72.0, General Instructions for DEH Operators Console, the operating crew is required to (2) .
A. (1) automatic removal of the IMP Press Loop (2) trip the Main Turbine B. (1) automatic removal of the IMP Press Loop (2) match reactor power with turbine load C. (1) opposed governor valve closure (2) trip the Main Turbine D. (1) opposed governor valve closure (2) match reactor power with turbine load
- 33. Unit 1 is operating at 100% power with the following conditions:
AT 1000:
AT 1005:
- KK1, TURB COND VAC LO, comes into alarm Which one of the following completes the statements below?
(1) is the earliest time AOP-8.0, Partial Loss of Condenser Vacuum, entry is required.
At 100% Reactor power, (2) is the lowest condenser pressure a manual Reactor Trip is required.
(1) (2)
A. 1000 3.800 psia B. 1005 3.800 psia C. 1000 2.901 psia D. 1005 2.901 psia
- 34. Unit 1 entered FRP-H.1, Response to Loss of Secondary Heat Sink, with the following conditions:
Time 1000 1015 1030 1100 1A S/G WR LVL (%) 37.00 28.00 18.00 11.00 1B S/G WR LVL (%) 32.00 20.00 10.00 6.00 1C S/G WR LVL (%) 29.00 19.00 9.00 3.00 CNMT PRESS (PSIG) 1.50 2.00 3.00 4.50 AFW TOTAL FLOW (GPM) 0 0 0 0 Which one of the following is the EARLIEST time that a manual Safety Injection is required due to meeting Bleed and Feed criteria per FRP-H.1?
A. 1000 B. 1015 C. 1030 D. 1100
- 35. Which one of the following is the purpose of depressurizing all intact SGs during the performance of ECP-0.0, Loss of All AC Power?
A. Rapidly reduces DP across SG U-tubes to minimize RCS inventory loss from a potential tube rupture.
B. Cools RCP seals in a controlled manner and minimizes loss of RCS inventory.
C. Maximizes Natural Circulation flow before reflux cooling begins as the RCS becomes saturated.
D. Maximizes Natural Circulation flow to allow reactor vessel head to cool since CRDM cooling fans are unavailable.
- 36. Unit 1 is operating at 100% power and the following condition exists:
- Main Condenser Pressure is rising due to a failure of the 1A SJAE.
Which one of the following completes the statements below?
Main Condenser Hotwell Temperature will initially (1) .
AOP-8.0, Partial Loss of Condenser Vacuum, will direct placing (2) on service.
(1) (2)
A. RISE a Hogger B. LOWER a Hogger C. RISE the 1B SJAE D. LOWER the 1B SJAE
- 37. The following conditions exist:
- Unit 1 is in MODE 5.
- Unit 2 is operating at 100% power.
- The 1B DG is INOPERABLE.
Subsequently, the following occurs simultaneously:
- 4160V busses 1F, 1K, 1G, and 1L de-energize.
- 4160V busses 2F, 2K, 2G, and 2L de-energize.
- The 1-2A DG Trips and cannot be restored.
Which one of the following completes the statement below?
The first procedure the Unit 1 Operating Crew is required to enter is (1) .
The Operating Crew will restore power to Unit 1 with the (2) .
A. (1) AOP-5.0, Loss of A or B Train Electrical Power (2) 1C DG B. (1) ECP-0.0, Loss of All AC Power (2) 1C DG C. (1) AOP-5.0, Loss of A or B Train Electrical Power (2) 2C DG D. (1) ECP-0.0, Loss of All AC Power (2) 2C DG
- 38. Which one of the following completes the statement below?
The Main Turbine exhaust hood sprays use (1) to automatically prevent excessive temperatures at the exhaust of the LP Turbine (2) 15% Turbine Load.
(1) (2)
A. demin water above B. demin water below C. condensate above D. condensate below
- 39. Unit 1 is operating at 100% power when the following occurs:
- The 1C 120 VAC Vital Instrumentation Panel is de-energized.
Which one of the following completes the statements below?
LCV-459, LTDN LINE ISO, (1) automatically close if a Pressurizer Low Level condition occurs.
LCV-115A (2) immediately divert to the RHT.
(1) (2)
A. WILL WILL B. WILL will NOT C. will NOT WILL D. will NOT will NOT
- 40. Unit 1 is operating at 8% power and the following conditions occur:
- The Battery Input Breaker on the 1B inverter trips.
- WD2, 1B INV FAULT, annunciator alarms.
- No Other Annunciators are in Alarm due to the fault.
Subsequently, the Rover reports the following indications from the 1B Inverter.
- INVERTER POWERING LOAD lamp NOT lit.
- BYPASS SOURCE AVAILABLE lamp is LIT.
Which one of the following completes the statements below?
The 1B 120V Vital AC panel is (1) .
The 1B INVERTER AMPERES meter on the EPB indicates (2) .
A. (1) Energized (2) 0 Amps B. (1) Energized (2) Full Load Amps C. (1) De-energized (2) 0 Amps. When the MANUAL BYPASS SWITCH is taken to BYPASS SOURCE TO LOAD position it will indicate Full Load Amps.
D. (1) De-energized (2) 0 Amps. When the MANUAL BYPASS SWITCH is taken to BYPASS SOURCE TO LOAD position it will continue to indicate 0 Amps.
- 41. Unit 1 is operating at 100% power when the following conditions occur:
- Annunciator KB4, SGFP SUCT PRESS LO, alarms
- PR-4039, SGFP SUCT PRESS, indicates 300 psig and lowering.
Which one of the following completes the statement below?
The earliest time the standby condensate pump will start is when .
A. KB4 has been in alarm for 10 seconds B. KB4 has been in alarm for 30 seconds C. SGFP suction pressure has remained below 275 PSIG for 10 seconds D. SGFP suction pressure has remained below 275 PSIG for 30 seconds
- 42. A gas transfer is in progress to the #8 Waste Gas Decay Tank on Unit 1 when the following conditions occur:
- The #8 Waste Gas Decay Tank relief valve lifts.
- The relief valve fails to reseat.
Which one of the following completes the statements below?
The relief valve lifting will initially be detected by (1) .
The release (2) be automatically isolated from the environment if an alarm condition exists.
(1) (2)
A. R-13, WASTE GAS MONITOR WILL B. R-13, WASTE GAS MONITOR will NOT C. R-14, PLANT VENT MONITOR WILL D. R-14, PLANT VENT MONITOR will NOT
- 43. Unit 1 is Operating at 100% Reactor Power when the following conditions occur:
Time 1000 1005 1010 1015 1A S/G NR LVL (%) 26.00 23.00 21.00 7.00 1B S/G NR LVL (%) 34.00 27.00 25.00 8.00 1C S/G NR LVL (%) 35.00 33.00 31.00 12.00 1A SGFP STATUS Running Running Tripped Tripped 1B SGFP STATUS Running Running Tripped Tripped Which one of the following is the earliest time when all AFW Pumps have recieved an AUTO START signal?
A. 1000 B. 1005 C. 1010 D. 1015
- 44. Unit 1 is operating at 100% power with the following condition:
- An LOSP occurs.
Which one of the following completes the statements below?
10 seconds after power is restored to the 1F 4160V bus:
1A CHG PUMP AMPS will indicate (1) AMPS.
1A MDAFWP AMPS will indicate (2) AMPS.
(1) (2)
A. greater than zero greater than zero B. greater than zero zero C. zero greater than zero D. zero zero
- 45. Unit 1 is operating at 100% power when the following condition occurs:
- The Reactor Trips Subsequently, the following indications are displayed continously on the MCB.
Which one of the following completes the statement below?
The valve actuation was initiated by a (1) .
The valve position prevents (2) .
A. (1) Safety Injection (2) damage to turbine building auxiliaries.
B. (1) Loss of Offsite Power (2) complete isolation of SW flow to the Air Compressors C. (1) Safety Injection (2) complete isolation of SW flow to the Air Compressors D. (1) Loss of Offsite Power (2) damage to turbine building auxiliaries.
- 46. Which one of the following completes the statements below?
The (1) RCP(s) can be powered from the 1A Startup Transformer.
The (2) RCP(s) can be powered from the 2B Startup Transformer.
(1) (2)
A. 1A RCP 2A RCP B. 1A RCP 2B and 2C RCPs C. 1B and 1C RCPs 2A RCP D. 1B and 1C RCPs 2B and 2C RCPs
- 47. Unit 1 is at 100% power when the following condition occurs in the Aux Bldg DC distribution system:
- The 125V DC Bus 1B has been de-energized.
Subsequently, an LOSP occurs on Unit 1.
Which one of the following completes the statements below?
The 1B DG (1) be started from the EPB.
The B1G Sequencer (2) automatically sequence loads.
(1) (2)
A. CAN WILL B. CANNOT will NOT C. CANNOT WILL D. CAN will NOT
- 48. Which one of the following completes the statement below for the 1B DG Air Recievers?
The maximum Air Receiver pressure that will cause an alarm on the 1B DG Local Control Panel is (1) .
At the alarm setpoint there is enough air pressure to ensure a maximum of (2) start attempts are available.
(1) (2)
A. 200 psig 3 B. 200 psig 5 C. 350 psig 3 D. 350 psig 5
- 49. Unit 1 is operating at 100% power when the following conditions occur:
- MH1, FIRE, annunciator on the Unit 1 Main Control Board (MCB) alarms.
- Aux Bldg El 139 W Side Det 1A-39, 43, 46, 53 1A-55, 59, 106", light is lit on the Control Room Fire Panel.
- The Rover reports that the window for 1A-59 at the PYR-A-LARM panel is lit.
What is (are) the minimum required action(s) to ensure MH1, FIRE, will alarm again if 1A-39 comes into alarm?
A. The Control Room Fire Panel alarm must be acknowledged.
and 1A-59 must be placed in OVERRIDE on the PYR-A-LARM panel.
B. The Control Room Fire Panel alarm must be acknowledged.
and The Reflash Panel alarm for detection system 1A-59 must be acknowledged.
C. ONLY 1A-59 must be placed in OVERRIDE on the PYR-A-LARM panel.
D. ONLY the Reflash Panel alarm for detection system 1A-59 must be acknowledged.
- 50. AOP-28.0, Control Room Inaccessibility, is in progress on Unit 1.
Which one of the following completes the statements below?
The 1A MDAFWP will be operated in LOCAL at the (1) HSDP.
Operator action is required to control the MDAFWP FCVs in LOCAL at the HSDP in order to prevent (2) .
(1) (2)
A. F low SG water level due to valve position B. F isolating letdown due to cooldown C. A low SG water level due to valve position D. A isolating letdown due to cooldown
- 51. Unit 2 is at 100% power with the following conditions:
- A #1 Waste Monitor Tank (WMT) release is in progress with the #1 WMT pump running.
- RCV-18, WMT DISCH TO ENVIRONMENT, is open.
Subsequently R-18, LIQ WASTE DISCH, alarms HIGH.
Which one of the following completes the statements below?
RCV-18 will (1) .
The #1 WMT pump will (2) .
(1) (2)
A. remain open trip B. remain open continue to run C. close trip D. close continue to run
- 52. Unit 1 is operating at 100% power with the following condition:
- A SG Tube Leak is in progress.
Which one of the following radiation monitors is able to automatically stop a release to the environment due to the SG Tube Rupture?
A. R-23A, SGBD SRG TK INLET B. R-23B, SGBD SRG TK DISCH C. R-19, SGBD SAMPLE D. R-70A, SG TUBE LEAK DET
- 53. Unit 1 is operating at 100% power when the following occurs:
- A Large Break LOCA occurs inside containment.
- Containment Pressure reaches 35 psig.
Which one of the following completes the statements below?
MOV-3024A, EMERG SW FROM 1A CTMT CLR, opened due to a(n)
(1) signal.
Each CTMT Cooler will be supplied with approximately (2) GPM of Service Water flow.
(1) (2)
A. Safety Injection 2000 B. Safety Injection 800 C. Containment Spray 2000 D. Containment Spray 800
- 54. Unit 1 experienced a Safety Injection with LOSP.
Which one of the following completes the statements below?
The 1A Charging Pump Room Cooler will automatically start due to a signal generated by the 1A Charging Pump (1) .
Controls for starting the Charging Pump Room Coolers (2) located on the BOP Panel.
(1) (2)
A. Breaker ARE B. Breaker are NOT C. Room Thermostat ARE D. Room Thermostat are NOT
- 55. Unit 1 is operating at 100% power with the following conditions:
- The Gross Failed Fuel Detector (GFFD) has steadily indicated 2500 cpm during the entire fuel cycle.
Subsequently, the following readings are recorded:
Time 1000 1100 1200 1300 GFFD Indication (cpm) 1.1 X 104 1.5 X 104 4.4 X 104 1.3 X 105 Which one of the following is the earliest time the GFFD will be in High Alarm?
A. 1000 B. 1100 C. 1200 D. 1300
- 56. Unit 1 is operating at 100% power with the following conditions:
- AOP-5.2, Degraded Grid, has just been entered.
- Voltage on all emergency busses for both units is reading 3875 volts.
- MEGAVARS are reading (+) 100 on the MCB.
- The Shift Supervisor has directed the UO to maintain (+) 400 MVARs in accordance with the voltage schedule.
- The Unit 2 UO maintains MVARS stable on Unit 2 during the adjustment.
Which one of the following will occur when the Unit 1 UO performs the adjustment as directed by the Shift Supervisor?
The operator will (1) Voltage, to reach (+) 400 MVARs.
After adjusting voltage, the temperature of large pump motors, such as the RCP or CW pump motors, will (2) .
(1) (2)
A. raise lower B. raise rise C. lower lower D. lower rise
- 57. Unit 1 was manually tripped from 100% power and the following conditions exist:
- AOP-6.0, Loss of Instrument Air, is in progress.
- The TDAFW pump automatically started.
- BOTH MDAFW pumps failed to start.
- The MSVR is not accessible.
Subsequently, the following report is received from Mechanical Maintenance:
- Restoration of Instrument Air will take 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
Which one of the following describes the required AOP-6.0 operator action(s), if any, and the reason?
A. No action is required because the TDAFWP steam admission valves fail to the "as is" position.
B. Manually close the TDAFWP steam admission valves to avoid causing an uncontrolled cooldown.
C. Manually open the TDAFWP steam admission valves to provide an adequate heat sink.
D. Manually align emergency air to the TDAFW pump steam admission valves to provide an adequate heat sink.
- 58. Unit 1 is operating at 100% power when the following occurs:
At 1000
- An Instrument Air malfunction occurs.
At 1015
- PI-4004B, INST AIR PRESS, indicates 50 psig and stable Which one of the following completes the statements below?
At 1015 V904, Instrument Air to the Service Building, is (1) .
A(n) (2) maintains MSIV air pressure following loss of instrument air pressure.
(1) (2)
A. OPEN accumulator B. OPEN compressed nitrogen cylinder C. CLOSED accumulator D. CLOSED compressed nitrogen cylinder
- 59. Unit 1 is shutdown following a LOCA with the following conditions:
- PR-950Z, CTMT PRESS, indicates 32 psig and slowly lowering.
Subsequently, ONLY the following actions are taken:
- SI BLOCK RESET A TRN pushbutton is depressed.
- SI BLOCK RESET B TRN pushbutton is depressed.
Which one of the following completes the statements below:
(1) (2)
A. IS is NOT B. IS IS C. is NOT is NOT D. is NOT IS
- 60. Unit 1 is operating at 100% power when the following conditions occur:
- Phase A is actuated using the MCB handswitches.
How has the Phase A signal affected the following valve positions?
Valve Nomenclature:
HV-8152, LTDN LINE CTMT ISO MOV-8112, RCP SEAL WTR RTN ISO HV-8149A, LTDN ORIF ISO 45 GPM MOV-3052, CCW TO RCP CLRS A. Only HV-8152, HV-8149A, and MOV-8112 have closed.
B. Only HV-8152, MOV-8112, and MOV-3052 have closed.
C. Only HV-8152, and HV-8149A have closed.
D. Only HV-8152 has closed.
- 61. A Main Control Board Deficiency related to a MCB handswitch has been identified.
Which one of the following completes the statements below IAW SOP-0.10, FNP Operations Site Specific Policies?
A (1) is required to be created to identify the deficiency.
The identifier (Deficiency Tag/Control Room DOT) will be (2) .
(1) (2)
A. Deficiency Tag affixed to the MCB handswitch B. Deficiency Tag placed in the deficiency notebook C. Control Room DOT affixed to the MCB handswitch D. Control Room DOT placed in the deficiency notebook
- 62. Unit 1 experiences a Reactor Trip with Safety injection.
Subsequently, the following occurs:
- The UO directs the Turbine Building Systems Operator (TB SO) to perform the TB SO Actions Following a Reactor Trip or Safety Injection.
Which one of the following completes the statements below per SOP-0.0, Appendix A, TB SO Actions Following a Reactor Trip and/or Safety Injection?
The TB SO is required to close V-503A, 1A MSR 2ND STG STM SUPP ISO (1) .
The TB SO is required to close V-905A, 1A MS LINE DRN POT TO COND ISO (2) .
(1) (2)
A. following any Reactor trip following any Reactor trip B. following any Reactor trip only when specifically directed C. only when specifically directed following any Reactor trip D. only when specifically directed only when specifically directed
- 63. Which one of the following completes the statements below per NMP-AP-001-003, Review and Approval of Site Procedures?
The "Pen and Ink" Change Process may be used for (1) changes.
A Condition Report (2) required following use of a procedure with "Pen and Ink" changes.
(1) (2)
A. editorial IS B. editorial is NOT C. temporary IS D. temporary is NOT
- 64. Unit 1 is in a Refueling Outage with fuel being loaded into the core.
Which one of the following completes the statements below?
Per TRM 13.1.6, Borated Water Source - Shutdown, the minimum operable BAT Tank Temperature is (1) .
Per TRM 13.1.6, the minimum operable BAT Tank Volume is (2) .
(1) (2)
A. 35°F 2000 gallons B. 35°F 11336 gallons C. 65°F 2000 gallons D. 65°F 11336 gallons
- 65. Unit 1 is exiting a refueling outage with the following conditions:
Time 1000 1200 1400 1600 Average Coolant Temp (°F) 300 450 547 547 Rated Thermal Power (%) 0 0 2 6 Keff <.99 <.99 1.00 1.00 Which one of the following completes the statements below?
The earliest time Unit 1 is in MODE 4 is at (1) .
The earliest time Unit 1 is in MODE 1 is at (2) .
(1) (2)
A. 1000 1400 B. 1000 1600 C. 1200 1400 D. 1200 1600
- 66. A Plant Operator has been assigned a portable RAM 100 frisker for personnel monitoring when exiting the dry cask storage area with the following condition:
- The Frisker Response Checks were last performed 7 days ago.
Which one of the following completes the statements below?
The frisker detects (1) .
The Frisker Response Checks for the assigned frisker are required to be performed (2) .
A. (1) Beta and Gamma radiation (2) prior to use B. (1) Beta and Gamma radiation (2) 6 months from the date of the last response check C. (1) ONLY Gamma radiation (2) prior to use D. (1) ONLY Gamma radiation (2) 6 months from the date of the last response check
- 67. You are assigned a task:
- Your current TEDE is 1500 mrem.
- Dose rate in the area you are required to work is 1500 mr/hr.
Which one of the following is the maximum amount of time you can stay in the area without exceeding Farley Administrative TEDE limits with no additional approval?
A. 20 minutes B. 100 minutes C. 120 minutes D. 140 minutes
- 68. EEP-0.0, Reactor Trip or Safety Injection, provides specific Reactor Coolant Pump (RCP) trip criteria on the foldout page.
Which one of the following is the reason for tripping the RCPs when these conditions occur?
A. Conserves RCS inventory during a Small Break LOCA with subsequent LOSP.
B. Prevents RCP seal damage following a Small Break LOCA.
C. Prevents pump runout following a Large Break LOCA.
D. Ensures core reflood following a Large Break LOCA.
- 69. Unit 1 and Unit 2 are operating at 100% power when the following condition occurs:
- The Outside System Operator reports a fire in the Liquid hydrogen storage tank vent stack.
Which one of the following completes the statement below?
Per AOP-29.0, Plant Fire, and SOP-34.0, Hydrogen-Oxygen System the fire will be extinguished by .
A. spraying water directly on the vent stack and isolating the leak.
B. discharging a portable fire extinguisher into the vent stack and isolating the leak.
C. establishing a helium purge and isolating the leak.
D. isolating the leak ONLY.
- 70. The following condition exist on Unit 1:
Subsequently, the following occurs:
- The Emergency Director declares a SITE AREA EMERGENCY.
Which one of the following completes the statements below?
Per NMP-EP-111, Emergency Notifications, a (1) tone will be sounded prior to the onsite notification announcement.
Per NMP-EP-111, Emergency Notifications, the (2) is responsible for approving notifcations to State and Local Authorities of the emergency condition.
(1) (2)
A. YELP Emergency Director B. WARBLE Emergency Director C. YELP Shift Manager D. WARBLE Shift Manager
- 71. An RCS soak is in progress per FRP-P.1, Response to Imminent Pressurized Thermal Shock Condition, on Unit 1.
Which one of the following actions is permitted?
A. Start a Charging Pump.
B. Energize PZR heaters.
C. Start an RCP.
D. Isolate Accumulators.
- 72. Unit 1 is shutdown following a Large Break LOCA followed by an LOSP. The following conditions occur:
At 1000:
- WA2, 1-2A DG GEN FAULT TRIP, alarms.
At 1015:
- RWST level is 3 ft.
- Containment Spray pump suctions are aligned to the RWST.
Which one of the following completes the statements below?
At 1015 (1) train(s) of emergency coolant recirculation capability has(have) been lost.
The operating crew (2) required to secure all CTMT Spray at 1015.
(1) (2)
A. ONLY one IS B. ONLY one is NOT C. BOTH IS D. BOTH is NOT
- 73. Unit 1 is shutdown with ECP-2.1, Uncontrolled Depressurization of All Steam Generators in progress. The following conditions exist:
- All MSIV - TRIP handswitches have been taken to CLOSE.
Which one of the following completes the statements below?
The next action the crew is required to take per ECP-2.1 is (1) .
If an MSIV is closed, ECP-2.1 directs use of (2) to determine if a Steam Generator has been isolated.
A. (1) Place the MSIV -TEST handswitch to TEST (2) Cold Leg Temperature B. (1) Place the MSIV - TEST handswitch to TEST (2) SG Pressure C. (1) Manually remove air pressure from the MSIVs (2) Cold Leg Temperature D. (1) Manually remove air pressure from the MSIVs (2) SG Pressure
- 74. Unit 1 is shutdown with the following conditions:
- 1A SG Pressure is 1145 psig and rising.
- The 1A Atmospheric Relief Valve is mechanically bound and cannot be opened.
Which one of the following completes the statements below?
Entry conditions for FRP-H.2, Response to Steam Generator Overpressure (1) been met When FRP-H.2 is entered, the crew would be directed to lower 1A SG Pressure by (2) .
(1) (2)
A. have NOT dumping steam to the TDAFWP B. HAVE dumping steam to the TDAFWP C. have NOT opening MSIV bypasses D. HAVE opening MSIV bypasses
- 75. Unit 1 has experienced a Large Break LOCA with the following conditions:
- PR-0950Z, CTMT PRESS NR, indicates 30 psig.
- FI-958 A and B, CS FLOW, indicate 1200 GPM each.
Which one of the following completes the statements below?
Per CSF-0.5, Containment, the crew is required to enter a(n) (1) path FRP due to (2) .
(1) (2)
A. RED CTMT Pressure B. RED CTMT Sump Level C. ORANGE CTMT Pressure D. ORANGE CTMT Sump Level
- 76. Unit 1 was operating at 100% power when the following occurred:
At 1000:
- All Control Banks are at 231 steps.
At 1010:
- Rod K4 fell to 130 steps.
- Rod M6 fell to 150 steps.
- RCS Tavg lowered.
- Pressurizer pressure lowered.
Which one of the following completes the statement below?
Per AOP-19, Malfunction of Rod Control System, the operating crew is required to .
A. shutdown the unit using UOP-3.1, Power Operation B. trip the Reactor and go to EEP-0.0, Reactor Trip and Safety Injection C. reduce power to less than 75% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using UOP-3.1, Power Operation D. address restoration of rods using SOP-41.0, Control Rod Drive and Position Indication System
- 77. Unit 1 is operating at 100% power when the following occurs:
At 1000:
- HH4, RCP VIB TRBL (WHITE annunciator window), comes into alarm.
- 1A RCP shaft vibration is reported as 21 mils and stable.
- DC2, RCP #1 SEAL LKOF FLOW HI (YELLOW annunciator window),
comes into alarm.
At 1600:
- The Unit is in MODE 3.
- The Reactor Trip Breakers are open.
- 1B and 1C RCPs are running.
- 1A RCP is tagged out.
Which one of the following completes the statements below?
At 1000, the operating crew is required to (1) , then secure the 1A RCP.
At 1600, RCS pressure control is via (2) .
A. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Normal Spray B. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Normal Spray C. (1) trip the Reactor and go to EEP-0.0, Reactor Trip or Safety Injection (2) Auxiliary Spray D. (1) perform a controlled shutdown per the appropriate Unit Operating Procedures (2) Auxiliary Spray
- 78. Unit 1 is operating at 100% power when the following occurs:
- Due to a Pressurizer pressure control malfunction, PCV-445A, PRZR PORV opens and reseats several times.
- PRT parameters are:
- Level: 84% and is stable.
- Temperature: 180°F and stable.
- Pressure: 30 psig and stable.
Which one of the following completes the statements below?
HE4, PRT LVL HI-LO, (1) in alarm.
Draining the PRT using the RCDT pump per Section 4.3, Filling and Draining the PRT, of SOP-1.2 (2) restore all PRT parameters to within normal log specifications.
Procedure name: SOP-1.2, Reactor Coolant Pressure Relief System (1) (2)
A. is NOT will NOT B. IS will NOT C. is NOT WILL D. IS WILL
- 79. Unit 1 is in MODE 3 with the following conditions:
At 1000:
- The Shutdown Banks are withdrawn.
At 1005:
- A complete loss of offsite power occurs.
Which one of the following completes the statements below?
At 1005, manual action (1) required to generate a P-4 signal.
Per the BASES of Tech Spec 3.3.2, ESFAS Instrumentation, P-4 is required to be OPERABLE to prevent (2) .
A. (1) IS (2) excessive Containment pressure due to a steamline break B. (1) is NOT (2) excessive Containment pressure due to a steamline break C. (1) IS (2) damage to the Main Steam lines and SG safeties due to SG overfill D. (1) is NOT (2) damage to the Main Steam lines and SG safeties due to SG overfill
- 80. Unit 1 is operating at 100% power with the following conditions:
- A malfunction occurred resulting in PCV-444B, PRZR PORV, opening.
Subsequently, the immediate operator actions of AOP-100, Instrumentation Malfunction, were performed and the following conditions exist:
- PCV-444B GREEN light is LIT.
- RCS pressure is 2180 psig and stable.
- PRT pressure, level and temperature are stable.
- HA4, PRZR SAFETY VLV TEMP HI, is in alarm.
- HA5, PRZR PORV TEMP HI, is in alarm.
Which one of the following completes the statements below?
PCV-444B (1) leaking by.
Per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs), PCV-444B (2) OPERABLE.
(1) (2)
A. IS IS B. IS is NOT C. is NOT IS D. is NOT is NOT
- 81. Unit 1 is at 100% power with the following conditions:
- PT-950, CTMT PRESS (Channel 1), was declared INOPERABLE.
- PT-950 bistables were positioned as required by Tech Spec 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, for continuous operation with an inoperable channel.
Which one of the following completes the statements below?
The Safety Injection function (1) affected by the PT-950 malfunction.
Per Tech Spec 3.3.2, the REQUIRED ACTION is to place the PT-950 bistables in (2) .
(1) (2)
A. IS TRIP B. IS BYPASS C. is NOT TRIP D. is NOT BYPASS
- 82. Unit 1 is in MODE 3 with the following conditions:
- All RCPs are running.
Which one of the following completes the statements below?
The method used in the Main Control Room (MCR) to isolate the CCW leak is to (1) .
Per the BASES of Tech Spec 3.7.7 - CCW System, once the CCW leak is isolated from the MCR, the CCW System is (2) .
A. (1) isolate CCW to ALL RCPs (2) INOPERABLE B. (1) isolate CCW to the 1A RCP ONLY (2) INOPERABLE C. (1) isolate CCW to ALL RCPs (2) OPERABLE D. (1) isolate CCW to the 1A RCP ONLY (2) OPERABLE
- 83. Unit 1 has experienced a LOCA. The following conditions exist:
- EEP-1.0, Loss of Reactor or Secondary Coolant, is in progress.
- Containment Hydrogen is 6% by volume of dry air.
Which one of the following completes the statements below?
The hydrogen concentration (1) exceed the lower FLAMMABILITY limit.
Hydrogen concentration will be lowered using (2) .
A. (1) DOES (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System B. (1) DOES (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation C. (1) does NOT (2) SOP-10.0, POST LOCA Containment Pressurization and Vent System D. (1) does NOT (2) Attachment 3 of EEP-1.0, Post LOCA Hydrogen Recombiner Operation
- 84. Unit 1 is operating at 100% when a Pressurizer level control malfunction occurs and the following conditions exist:
- Pressurizer level is 70% and rising.
- Charging flow is 120 gpm.
- Letdown is 60 gpm.
- RCP seal leakoff is 3 gpm per pump.
- Actions in the field are being taken to regain control of Charging.
- It will take 8 minutes to regain control of Charging.
Which one of the following completes the statements below?
An automatic reactor trip (1) occur before control of Charging is regained.
Per the BASES of Tech Spec 3.3.1, Reactor Trip System (RTS)
Instrumentation, the purpose of the automatic Reactor Trip on Pressurizer Water Level - High is to (2) .
Reference Provided A. (1) WILL (2) provide protection against water relief through the PORV's B. (1) WILL (2) prevent thermal shock of the Spray Nozzle C. (1) will NOT (2) provide protection against water relief through the PORV's D. (1) will NOT (2) prevent thermal shock of the Spray Nozzle
- 85. Unit 1 is conducting a fuel reload and the following occurs:
At 1015: An Intermediate Leg leak is in progress on the 1A RCS loop with the following conditions.
- R-2, CTMT 155 FT, is in alarm.
- EH2, SFP LVL HI-LO is in alarm.
- Both RHR pumps have been secured due to cavitation.
Which one of the following completes the statements below?
At 1030, an emergency classification, per NMP-EP-110, Emergency Classification Determination and Initial Action, (1) required.
Per AOP-12, Residual Heat Removal System Malfunction, the maximum time to complete Containment closure is (2) hour(s).
(1) (2)
A. IS 1 B. IS 2 C. is NOT 1 D. is NOT 2
- 86. A fuel shuffle is in progress in the Unit 1 SFP with the following conditions:
At 1000:
- An 1800 lb. load is being moved over spent fuel.
At 1015:
- The load is dropped causing damage to the spent fuel.
At 1015, which one of the following describes the minimum Radiation Monitor(s) required to be in alarm to meet AOP-30, Refueling Accident, entry conditions?
AND Which one of the following describes the the expected worst case consequences of dropping an 1800 lb. load onto the spent fuel Per the Bases of TR 13.9.4, Crane Travel-Spent Fuel Storage Building?
A.
- R-5 OR R-25A
- The activity release will be limited to that contained in a single fuel assembly.
B.
- R-5 OR R-25A
- The offsite dose may be as high as but not more than the 10 CFR 100 limit.
C.
- R-5 AND R-25A
- The activity release will be limited to that contained in a single fuel assembly.
D.
- R-5 AND R-25A
- The offsite dose may be as high as but not more than the 10 CFR 100 limit.
- 87. Unit 1 was operating at 100% power with the following conditions:
At 1000: A Loss of Offsite Power occurs.
At 1015: The following conditions exist -
- DG-02, 1G 4160 V bus tie to 1L 4160 V bus, has AMBER and GREEN Lights LIT.
Which one of the following completes the statements below?
At 1015: The 1B DG (1) have cooling water supplied.
At 1015: The REQUIRED ACTION(S) of Tech Spec(s) (2) is(are) required to be performed.
Tech Spec nomenclature: 3.8.9, Distribution Systems - Operating 3.7.8, Service Water System (SWS)
(1) (2)
A. WILL 3.8.9 AND 3.7.8 B. will NOT 3.8.9 AND 3.7.8 C. WILL 3.8.9 ONLY D. will NOT 3.8.9 ONLY
- 88. Unit 1 is in Mode 3 with the following conditions:
- Pressurizer level is 22% and stable.
Subsequently, a rupture occurs on the Instrument Air header piping in the MSVR and AOP-6.0, Loss of Instrument Air, is in progress.
Which one of the following completes the statements below?
Pressurizer level will (1) .
Per AOP-6.0, to maintain Pressurizer level, the operating crew is required to perform actions of (2) in conjunction with AOP-6.0.
Procedure Names: AOP-16.0, CVCS Malfunction SOP-2.1, CVCS Plant Startup and Operation (1) (2)
A. lower AOP-16.0 B. rise AOP-16.0 C. lower SOP-2.1 D. rise SOP-2.1
- 89. Unit 1 is operating at 100% power when the following occurs:
- R-27B, CTMT HIGH RANGE, is tagged out.
- The instrument power supply fuse to R-27A, CTMT HIGH RANGE, blows.
Which one of the following completes the statements below?
R-27A indication will fail (1) .
Per Tech Spec 3.3.3, Post Accident Monitoring Instrumentation, the REQUIRED ACTION is to (2) .
Reference Provided A. (1) HIGH (2) immediately initiate action in accordance with Specification 5.6.8 B. (1) HIGH (2) restore R-27A OR R-27B to OPERABLE status in 7 days C. (1) LOW (2) immediately initiate action in accordance with Specification 5.6.8 D. (1) LOW (2) restore R-27A OR R-27B to OPERABLE status in 7 days
- 90. Unit 1 is operating at 100% power and the following occurs:
- R-15A, SJAE EXH, power supply becomes erratic causing its indication to become unreliable but it does not alarm.
Per the ODCM, which one of the following actions are required to continue the release via this pathway, if any?
A. No actions are required.
B. Continuously collect samples using auxiliary equipment.
C. Place SJAE filtration in service until R-15A is restored to operable.
D. Perform grab samples at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and analyze them within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 91. Unit 1 is in MODE 6 with the following conditions:
- Core reload is complete.
- Control Rod Drive Shaft Latching and RCCA Drag Testing is about to begin per FHP-5.1, Control Rod Drive Shaft Latching/Unlatching Tool Operating Instruction.
Which one of the following completes the statements below?
Per FHP-0.0, Refueling Organization, the Fuel Handling Supervisor (1) .
Per UOP-4.1, Controlling Procedure for Refueling, two Source Range Nuclear Instruments (2) required to be OPERABLE.
A. (1) is required to be in Containment (2) are NOT B. (1) is required to be in Containment (2) ARE C. (1) may be in the Control Room in direct Communication with Containment (2) are NOT D. (1) may be in the Control Room in direct Communication with Containment (2) ARE
- 92. A tagout is required to be cleared during night shift and the Work Document Holder is not on site and cannot be contacted to gain their approval.
Per NMP-AD-003, Equipment Clearance and Tagging, which one of the following can sign off the Work Document Holder?
A. Shift Manager B. Operations Director C. Maintenance Director D. Maintenance Manager
- 93. Unit 1 is at 6% power with the following conditions:
- The 1A SGFP has been started.
- AFW is secured.
- The Main Feed Regulating Valves are closed.
At 1000 on January 1, 2015:
- MOV-3232B, MAIN FW TO 1B SG STOP VLV , is declared INOPERABLE.
At 1200 on January 1, 2015:
- FCV-489, 1B SG FW BYP FLOW, is declared INOPERABLE.
Subsequently it is determined that repairs will take 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> for each valve.
Which one of the following completes the statement below?
Per Tech Spec 3.7.3, Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves, the earliest time that feed flow to the 1B SG must be isolated is .
Reference Provided A. 1800 on January 1, 2015 B. 2000 on January 1, 2015 C. 1000 on January 4, 2015 D. 1200 on January 4, 2015
- 94. A General Emergency on Unit 1 has been declared with following conditions:
- An Emergency Response Team is required to be dispatched to isolate an offsite release source.
- The TSC has not yet been manned.
Which one of the following completes the statements below?
To receive the dose listed above, operators (1) required to be volunteers.
The (2) will authorize the exposure.
(1) (2)
A. are NOT RP Supervisor B. are NOT Shift Manager C. ARE RP Supervisor D. ARE Shift Manager
- 95. Unit 1 is in MODE 6 with core offload in progress with the following condition:
- A spent fuel assembly is being moved from its assigned location in the core to the upender.
Subsequently, AOP-30.0, Refueling Accident, is entered Which one of the following completes the statements below?
Per AOP-30.0, the Refueling SRO will direct the fuel assembly to be (1) .
Per the BASES of Tech Spec 3.9.6, Refueling Cavity Water Level, 23 ft of water is required to be maintained above the fuel to (2) .
A. (1) placed in any empty fuel location in the core (2) provide back up decay heat removal B. (1) placed in any empty fuel location in the core (2) retain iodine fission product activity in the water during a fuel handling accident C. (1) returned to its assigned location in the core (2) provide back up decay heat removal D. (1) returned to its assigned location in the core (2) retain iodine fission product activity in the water during a fuel handling accident
- 96. Unit 2 reactor startup is in progress and the following conditions exist:
- NI31, SR1 COUNT RATE is 106 cps and stable.
- NI32, SR2 COUNT RATE is 104 cps and stable.
- TSLB-3 1-1, SR HI Q NC-31D is lit.
- TSLB-3 1-2, SR HI Q NC-32D is NOT lit.
- GA1, SR HI FLUX TRIP, is in alarm.
- The Reactor Trip breakers are closed.
Subsequently, The Shift Supervisor directs a manual Reactor trip.
- The Reactor Trip breakers open.
Which one of the following completes the statements below?
An emergency classification threshold value (1) been exceeded per NMP-EP-110-GL01, FNP EALS - ICs, Threshold Values And Basis.
The latest time the NRC can be notified is (2) hour(s) after the event / emergency declaration.
(1) (2)
A. has NOT 4 B. HAS 4 C. has NOT 1 D. HAS 1
- 97. Unit 1 is performing the actions of EEP-0.0, Reactor Trip or Safety Injection, and AOP-9, Loss of Component Cooling Water. Conditions are as follows:
- 1F 4160V bus is de-energized.
- B Train CCW is the on service Train.
- 1B CCW pump is Tagged Out.
- 1A CCW pump tripped.
- 1C CHG PUMP is running.
Subsequently, the Shift Supervisor determines that Firewater is required to be aligned to the 1B Charging pump.
Which one of the following completes the statements below?
The 1C Charging pump will be (1) while aligning Firewater to the 1B Charging pump.
(2) Charging pump CCW oil cooler piping will become chemically contaminated.
(1) (2)
A. secured ONLY the 1B B. secured BOTH 1B and 1C C. maintained running ONLY the 1B D. maintained running BOTH 1B and 1C
- 98. Unit 1 operating crew has exited EEP-0.0, Reactor Trip or Safety Injection, and is now performing ECP-1.2, LOCA Outside Containment with the following conditions:
- The leak isolation steps are completed.
- RWST level is 12.5 ft.
- RCS pressure continues to lower.
Which one of the following completes the statement below?
The next procedure the operating crew is required to transition to is .
A. EEP-0.0, Reactor Trip or Safety Injection B. ESP-1.3, Transfer to Cold Leg Recirculation C. EEP-1.0, Loss of Reactor or Secondary Coolant D. ECP-1.1, Loss of Emergency Coolant Recirculation
- 99. Unit 2 is performing the actions of FRP-H.1, Response to Loss of Secondary Heat Sink, and the following conditions exist:
- The TDAFW pump has been returned to service.
- Containment pressure is 0 psig.
- RCS Bleed and Feed was initiated, but has now been secured.
- RCS pressure is 1600 psig and rising.
- Pressurizer level is 23% and rising.
Which one of the following completes the statements below?
The minimum SG level that permitted securing Bleed and Feed was at least one SG (1) .
The operating crew will transition to (2) from FRP-H.1.
A. (1) Wide Range level at 14%
(2) ESP-1.1, SI Termination B. (1) Wide Range level at 14%
(2) EEP-1, Loss of Reactor or Secondary Coolant C. (1) Narrow Range level at 33%
(2) ESP-1.1, SI Termination D. (1) Narrow Range level at 33%
(2) EEP-1, Loss of Reactor or Secondary Coolant
100. Unit 1 is cooling down per ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding, and the following conditions exist:
- RVLIS is not available.
- RCS Hot leg is 450°F and slowly lowering.
- RCS Cold leg is 425°F and slowly lowering.
- The crew is cooling down at the maximum rate allowed by procedure.
- Pressurizer level has just rapidly risen to 78% and is stable
- RCS pressure reduction is not required.
- CST level is 9ft.
Which one of the following completes the statements below?
The operating crew will transition to ESP-0.4, Natural Circulation Cooldown with Allowance for Reactor Vessel Head Steam Voiding (Without RVLIS), based on (1) .
The maximum allowable cooldown rate in ESP-0.4 is (2) .
Reference Provided A. (1) CST Level (2) <100°F in any 60 minute period B. (1) CST Level (2) <50°F/hr C. (1) Reactor Vessel void formation being indicated (2) <100°F in any 60 minute period D. (1) Reactor Vessel void formation being indicated (2) <50°F/hr
PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS
NOTE--------------------------------------------------------
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required channel 30 days with one required to OPERABLE status.
channel inoperable.
B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A Specification 5.6.8.
not met.
C. One or more Functions C.1 Restore one channel to 7 days with two required OPERABLE status.
channels inoperable.
Farley Units 1 and 2 3.3.3-1 Amendment No. 170 (Unit 1)
Amendment No. 163 (Unit 2)
PAM Instrumentation 3.3.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.3-1 for the not met. channel.
E. As required by Required E.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 /> Action D.1 and referenced in AND Table 3.3.3-1.
E.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> F. As required by Required F.1 Initiate action in Immediately Action D.1 and accordance with referenced in Specification 5.6.8.
Table 3.3.3-1.
SURVEILLANCE REQUIREMENTS
NOTE--------------------------------------------------------------
SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1.
SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required In accordance with instrumentation channel that is normally energized. the Surveillance Frequency Control Program SR 3.3.3.2 Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.3.3-2 Amendment No. 185 (Unit 1)
Amendment No. 180 (Unit 2)
PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 1)
Post Accident Monitoring Instrumentation CONDITION REFERENCED FROM REQUIRED REQUIRED FUNCTION CHANNELS ACTION D.1
- 1. RCS Hot Leg Temperature (Wide Range) 2 E
- 2. RCS Cold Leg Temperature (Wide Range) 2 E
- 3. RCS Pressure (Wide Range) 2 E
- 4. Steam Generator (SG) Water Level (Wide or 2/SG E Narrow Range)
- 5. Refueling Water Storage Tank Level 2 E
- 6. Containment Pressure (Narrow Range) 2 E
- 7. Pressurizer Water Level 2 E
- 8. Steam Line Pressure 2/SG E
- 9. Auxiliary Feedwater Flow Rate 2 E
- 10. RCS Subcooling Margin Monitor 2 E
- 11. Containment Water Level (Wide Range) 2 E
- 12. Core Exit Temperature - Quadrant 1 2 (a) E
- 13. Core Exit Temperature - Quadrant 2 2(a) E
- 14. Core Exit Temperature - Quadrant 3 2(a) E
- 15. Core Exit Temperature - Quadrant 4 2(a) E
- 16. Reactor Vessel Level Indicating System 2 F
- 17. Condensate Storage Tank Level 2 E
- 18. Deleted
- 19. Containment Area Radiation (High Range) 2 F (a) A channel consists of two core exit thermocouples.
Farley Units 1 and 2 3.3.3-3 Amendment No. 167 (Unit 1)
Amendment No. 159 (Unit 2)
Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Stop Valves and Main Feedwater Regulation Valves (MFRVs) and Associated Bypass Valves LCO 3.7.3 Three Main FW Stop Valves, three MFRVs, and associated bypass valves shall be OPERABLE.
APPLICABILITY: MODES 1 and 2, except when all main feedwater lines are isolated by either a Main FW Stop Valve, a MFRV and its associated bypass valve or by a closed manual valve.
ACTIONS
NOTE-------------------------------------------------------------
Separate Condition entry is allowed for each valve.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Main FW A.1 Close or isolate Main FW 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Stop Valves inoperable. Stop Valve.
AND A.2 Verify Main FW Stop Valve Once per 7 days is closed or isolated.
B. One or more MFRVs B.1 Close or isolate MFRV. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable.
AND B.2 Verify MFRV is closed or Once per 7 days isolated.
Farley Units 1 and 2 3.7.3-1 Amendment No. 146 (Unit 1)
Amendment No. 137 (Unit 2)
Main FW Stop Valves and MFRVs and Associated Bypass Valves 3.7.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. One or more MFRV C.1 Close or isolate bypass 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> bypass valves valve.
AND C.2 Verify bypass valve is closed Once per 7 days or isolated.
D. Two valves in the same D.1 Isolate affected flow path. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> flow path inoperable.
E. Required Action and E.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.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the closure time of each Main FW Stop Valve, In accordance with MFRV, and associated bypass valve is in accordance the Inservice with the time requirement in the Inservice Testing Testing Program.
Plan.
Farley Units 1 and 2 3.7.3-2 Amendment No. 146 (Unit 1)
Amendment No. 137 (Unit 2)
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