ML15097A264

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301 Final RO Written Exam
ML15097A264
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 04/07/2015
From:
NRC/RGN-II
To:
Florida Power & Light Co
References
50-335/15-301, 50-389/15-301
Download: ML15097A264 (94)
v • d • e


Text

HLC 22 RO NRC EXAM Question 1 Unit 1 is at 45% power steady state. A leak on the upper instrument tap (reference leg) associated with the SELECTED Pressurizer (Pzr) Level Transmitter, LT-1110X occurs.

Assuming NO Operator actions, which ONE of the following would be the response of the Pressurizer Pressure Level Control System?

Indicated Pzr Level Actual Pzr Level A. lowers rises B. rises rises C. rises lowers D. lowers lowers Page 1 of 75

HLC 22 RO NRC EXAM Question 2 Given the following conditions on Unit 1:

  • The reactor has been manually tripped and the crew is implementing 1-EOP-01, Standard Post Trip Actions
  • The Core Heat Removal Safety Function has JUST been completed.
  • Pressurizer pressure is 1590 psia
  • Containment pressure is 5.5 psig Which ONE of the following completes the statements below:

A Safety Injection Actuation signal __(1)__ occurred.

The required status of the Reactor Coolant pumps at this time is __(2)__ should be secured.

A. 1) HAS

2) ONE RCP in each loop B. 1) HAS
2) ALL four RCPs C. 1) HAS NOT
2) ONE RCP in each loop D. 1) HAS NOT
2) ALL four RCPs Page 2 of 75

HLC 22 RO NRC EXAM Question 3 Given the following conditions on Unit 2:

  • A Loss of Coolant Accident (LOCA) has occurred
  • Reactor Coolant System pressure is 75 psia Which ONE of the following is monitored or performed with regards to Short and Long Term Core Cooling given the above conditions?

Short Term Cooling Long Term Cooling A. Low Pressure Safety Injection operation/ Align Shutdown Cooling Safety Injection Tanks discharge B. Low Pressure Safety Injection operation/ Align High Pressure Safety Injection Safety Injection Tanks discharge hot and cold leg injection with a Recirculation Actuation Signal C. High Pressure Safety Injection operation/ Align Shutdown cooling Steam Generator steaming D. High Pressure Safety Injection operation/ Align High Pressure Safety Injection Steam Generator steaming hot and cold leg injection with a Recirculation Actuation Signal Page 3 of 75

HLC 22 RO NRC EXAM Question 4 Unit 2 is at 100% power Given the following indications on the 2A1 Reactor Coolant Pump (RCP):

  • Controlled Bleedoff (CBO) temperature is 225oF
  • CBO flow is 2.5 gpm
  • Vapor Seal Cavity pressure is 80 psia
  • Upper Seal Cavity pressure is 2235 psia
  • Middle Seal Cavity pressure is 2235 psia Which ONE of the following describes the status of the RCP seals and required action?

A. ONLY One RCP seal has failed; perform a controlled shutdown then secure the 2A1 RCP.

B. ONLY Two RCP seals have failed; trip the reactor and secure the 2A1 RCP.

C. ONLY Two RCP seals have failed; perform a controlled shutdown then secure the 2A1 RCP.

D. Three RCP seals have failed; trip the reactor and secure the 2A1 RCP.

Page 4 of 75

HLC 22 RO NRC EXAM Question 5 Unit 1 is operating at 100% power.

The SNPO reports that a break in the Charging header has occurred.

The following indications noted on the RTGB:

  • Charging Header pressure is 0 psig
  • Reactor Cavity leakage is 0.1 gpm and steady Which ONE of the following completes the statements below:

Annunciator __(1)__ should be in alarm for this condition.

Due to the leak location, __(2)___ Charging pump(s) can be used when aligning per 1-AOP-02.03, Alternate Charging Flow Path Through the Auxiliary HPSI Header.

(Reference Provided)

A. 1) M-7, Regenerative Heat Exchanger Letdown P High

2) either the 1A, 1B OR 1C B. 1) M-28, Regenerative Heat Exchanger Outlet Temp High
2) either the 1A, 1B OR 1C C. 1) M-7, Regenerative Heat Exchanger Letdown P High
2) ONLY the 1A D. 1) M-28, Regenerative Heat Exchanger Outlet Temp High
2) ONLY the 1A Page 5 of 75

HLC 22 RO NRC EXAM Question 6 Given the following conditions on Unit 1:

  • The unit is currently shutdown for a refueling outage
  • The Reactor Head is being removed
  • The RCS level 35 feet
  • Time since reactor shutdown is 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br />

If all SDC was lost, with the conditions given above, the Time to Boil is approximately____ minutes.

(References Provided)

A. 28 B. 30 C. 37 D. 40 Page 6 of 75

HLC 22 RO NRC EXAM Question 7 Given the following conditions on Unit 1:

  • The 1A and 1B Component Cooling Water (CCW) pumps are running
  • The 1C CCW pump is in standby in accordance with 1-NOP-14.02, CCW System Operation, and is aligned to the B train electrically and mechanically
  • A Loss of Offsite Power (LOOP) has just occurred
  • The 1B CCW pump failed to start following the LOOP
  • 1 minute later, a Loss of Coolant Accident (LOCA) with SIAS and CIAS actuation occurred Which ONE of the following describes the configuration of the CCW system at this time?

(Assume no operator actions)

A. ONLY 1 CCW pump supplying all CCW loads due to the failure of 1B CCW pump to start.

B. Two CCW pumps supplying all CCW loads due to SIAS start of the 1C CCW pump.

C. ONLY 1 CCW pump supplying its own safety header due to ESFAS isolation of the Non-Essential header.

D. Two CCW pumps supplying all CCW loads due to SIAS start of the 1C CCW pump until the Non-Essential header isolates on a loss of instrument air.

Page 7 of 75

HLC 22 RO NRC EXAM Question 8 Given the following conditions on Unit 1:

  • The unit is operating at 100% power
  • PIC-1110X, Pressurizer (Pzr) pressure controller is selected
  • Pzr pressure is being maintained at 2250 psia with Pzr Backup Heaters B1, B2, and B5 ON with a 10% output to the Pzr Proportional Heaters
  • PT-1110Y is out of service for I&C calibration PT-1110X begins to slowly fail high.

Which ONE of the following choices completes the statement below:

IAW 1-AOP-01.10 Pressurizer Pressure and Level, the operator is directed to take manual control of HIC-1100, Spray Valve controller and __(1)__ its output in order to

__(2)__ ACTUAL Pzr Pressure.

A. 1) lower

2) lower B. 1) lower
2) raise C. 1) raise
2) raise D. 1) raise
2) lower Page 8 of 75

HLC 22 RO NRC EXAM Question 9 Given the following conditions on Unit 1:

  • Reactor power is 100%
  • No operator actions have been taken Which ONE of the following describes the expected reactivity change AND the impact on the Reactor Coolant System (RCS) Pressure from this event?

Over the next 5 minutes, reactor power will:

A. Stay the same; an RCS over pressure condition will be prevented due to the event being within the design bases of the Pressurizer Safety valves.

B. Stay the same; an RCS pressure excursion that could potentially challenge the RCS pressure boundary integrity will be prevented by the Diverse Scram System.

C. Lower; an RCS over pressure condition will be prevented due to the event being within the design bases of the Pressurizer Safety valves.

D. Lower; an RCS pressure excursion that could potentially challenge the RCS pressure boundary integrity will be prevented by the Diverse Scram System.

Page 9 of 75

HLC 22 RO NRC EXAM Question 10 Given the following conditions on Unit 1:

  • The unit was operating at 100% power
  • 1-EOP-04, SGTR is being implemented
  • SIAS actuation has occurred
  • A Reactor Coolant System (RCS) cool down and depressurization is in progress The crew is evaluating RCS Void Elimination per 1-EOP-99, Appendix K, RCS Fill and Drain Method of Void Elimination.

Which ONE of the following is an indication that voids are present in the Reactor Vessel Head?

A. RVLMS indicates segments voided.

B. Pressurizer Level lowering while spraying.

C. Pressurizer level rising while charging to the RCS.

D. The saturation temperature of the RCS is higher than the temperature in the upper Rx Head region.

Page 10 of 75

HLC 22 RO NRC EXAM Question 11 Given the following:

  • The Unit 1 reactor tripped from 100% power 15 minutes ago
  • The 1C AFW pump header flow control valves were closed

The 1A and 1B AFW pump header flow control valves __(1)___.

The 1C AFW pump header flow control valves __(2)__.

A. 1) require throttling closed

2) require throttling closed B. 1) remain throttled
2) require throttling closed C. 1) require throttling closed
2) remain closed D. 1) remain throttled
2) remain closed Page 11 of 75

HLC 22 RO NRC EXAM Question 12 Given the following conditions on Unit 1:

  • A Station Blackout has occurred and 1-EOP-10, Station Blackout, is being implemented
  • The crew is evaluating Single Phase Natural Circulation criteria
  • The BRCO reports the T between REP CET and T hot is 18oF and increasing Which ONE of the following choices describes:
1. The contingency action, in 1-EOP-10, Station Blackout, that is to be taken if Single Phase Natural Circulation criteria is BEING challenged?

AND

2. The operational implications if the temperature difference between T hot and REP CET exceeds the Single Phase Natural Circulation criteria limits?

A. 1) Verify Two Phase Natural Circulation CRITERIA.

2) The Hot Legs are becoming thermodynamically uncoupled from the core.

B. 1) Verify Two Phase Natural Circulation CRITERIA.

2) The Reactor Coolant System is approaching saturated conditions.

C. 1) Ensure proper control of Steam Generator feeding and steaming.

2) The Hot Legs are becoming thermodynamically uncoupled from the core.

D. 1) Ensure proper control of Steam Generator feeding and steaming.

2) The Reactor Coolant System is approaching saturated conditions.

Page 12 of 75

HLC 22 RO NRC EXAM Question 13 Given the following conditions for Unit 2:

  • The unit is operating at 100% power
  • The 2AB 4.16kVAC bus is aligned to the 2B3 4.16kVAC bus
  • HVA/ACC-3C is the running air conditioning unit
  • HVA/ACC-3A and HVA/ACC-3B control switches are aligned as required per 2-NOP-25.07, Control Room Ventilation System
  • A Loss of Offsite Power (LOOP) has occurred Which ONE of the following describes the final configuration of HVA/ACC-3A and HVA/ACC-3B Air Conditioning units AFTER the EDG loading sequence is complete?

HVA/ACC-3A is __(1)__.

HVA/ACC-3B is __(2)__.

A. 1) running

2) not running B. 1) not running
2) not running C. 1) not running
2) running D. 1) running
2) running Page 13 of 75

HLC 22 RO NRC EXAM Question 14 Given the following conditions on Unit 1:

  • The unit is operating at 100% power
  • A loss of the 1MB 120VAC Vital Instrument Inverter occurs Which ONE of the following choices completes the statements below:

The B Channel Steam Generator (SG) Pressure and Level Safety channel indication will be affected on the __(1)__ .

The Reactor Protection System coincidence for a reactor trip will now be __(2)__ on Low SG Pressure or Level.

A. 1) A and B SGs

2) 1 out of 3 B. 1) A and B SGs
2) 2 out of 3 C. 1) B SG ONLY
2) 1 out of 3 D. 1) B SG ONLY
2) 2 out of 3 Page 14 of 75

HLC 22 RO NRC EXAM Question 15 Given the following conditions on Unit 1

  • Unit 1 was operating at 100% power
  • The 1AB busses are aligned to the A train
  • The unit tripped and the crew is carrying out actions of EOP-01, Standard Post Trip Actions
  • During the Maintenance of Vital Auxiliaries Safety Function, the DRCO reports that the 1AB DC bus is de-energized Which ONE of the following actions are required in accordance with EOP-01 AND also satisfies the design basis:

Within ______ , re-energize the 1AB DC bus from the ________.

A. 10 minutes; 1AB Battery Charger B. 10 minutes; 1B DC bus C. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; 1AB Battery Charger D. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; 1B DC bus Page 15 of 75

HLC 22 RO NRC EXAM Question 16 Given the following:

  • Unit 2 is operating at 100% power.
  • The 2B3 4.16kVAC bus has been de-energized due to a differential current lockout
  • The 2AB 4.16kVAC bus is aligned to the A train
  • The crew was UNSUCCESSFUL in resetting the differential current lockout relay
  • The US directed that the 2B Intake Cooling Water (ICW) pump control switch be placed in Pull-to-Lock AND the 2C ICW pump MECHANICALLY aligned to the B train
  • The US also directed that the 2B Component Cooling Water pump (CCW) pump control switch be placed in Pull-to-Lock AND the 2C CCW pump MECHANICALLY aligned to the B train
  • The 2C ICW pump and the 2C CCW pump were then started as directed by 2-AOP-47.01B, Loss of a Safety Related AC Bus-Train B Which ONE of the following statements describes ALL of the consequences associated with the ICW system AND the CCW system being in this configuration per Ops Policy 503?

A. Offsite Power Operability for two ICW pumps running on the same electrical bus; Offsite Power Operability for two CCW pumps running on the same electrical bus.

B. Offsite Power Operability for two ICW pumps running on the same electrical bus.

C. Offsite Power Operability for two ICW pumps running on the same electrical bus; Offsite Power Operability AND Emergency Diesel Generator Operability for two CCW pumps running on the same electrical bus.

D. Offsite Power Operability AND Emergency Diesel Generator Operability for two CCW pumps running on the same electrical bus.

Page 16 of 75

HLC 22 RO NRC EXAM Question 17 Given the following:

  • An uncomplicated trip from 100% power has occurred on Unit 2
  • 2-EOP-01, Standard Post Trip Actions is being implemented
  • Reactor power is 1.0E-6% and lowering as indicated on Wide Range Instrumentation Which ONE of the following describes the status of the Nuclear Startup Channels?

A. Energized. They automatically energized at 1.0 E-5% power.

B. NOT energized. They will be manually energized while implementing 2-EOP-01, Standard Post Trip Actions.

C. Energized. They automatically energized on the reactor trip signal.

D. NOT energized. They will be manually energized after 2-EOP-02, Reactor Trip Recovery is entered.

Page 17 of 75

HLC 22 RO NRC EXAM Question 18 Given the following:

  • Unit 1 Reactor is at a stable power level of 2% in preparation for plant start up
  • RCS pressure is 2220 psia and lowering
  • Pressurizer level is 25% and lowering
  • Both Atmospheric Dump Valves (ADVs) are in service operating in Auto After the reactor is tripped, which ONE of the following describes:
1) The expected plant response.

AND

2) After the 1A SG dries out, operate the 1B ADV at a saturation pressure for A. 1) BOTH SGs will depressurize at the same rate until MSIS.
2) RCS T avg of 525oF to 535oF B. 1) ONLY the 1A SG will depressurize.
2) the lowest RCS T COLD C. 1) BOTH SGs will depressurize at the same rate until MSIS.
2) the lowest RCS T COLD D. 1) ONLY the 1A SG will depressurize.
2) RCS T avg of 525oF to 535oF Page 18 of 75

HLC 22 RO NRC EXAM Question 19 Unit 2 is in Mode 2 with the following:

  • A reactor startup is in progress using 2-GOP-302, Reactor Plant Startup - Mode 3 to Mode 2
  • Reactor power is 1.0E-5%
  • CEA group 5 is at 52 inches and being withdrawn in manual sequential to a planned stopping height of 60 inches
  • CEA #59 does not move with the rest of the Group 5 CEAs If the CEAs were continued to be withdrawn, which ONE of the following alarms are expected during this evolution?

A. K-29, CEA PDIL (ADS).

B. K-18, Auto Withdraw Prohibit.

C. K-11, CEA Motion Inhibit.

D. K-26, CEA Withdrawal Prohibit.

Page 19 of 75

HLC 22 RO NRC EXAM Question 20 Given the following:

  • Unit 2 tripped from 100% due to a Loss of Offsite Power (LOOP)
  • All AB electrical busses are aligned to the B side
  • The 2B Charging pump is out of service with its control switch in stop Following the trip:

If a condition requiring the crew to emergency borate existed, operators would be required to start the 2C Chg pump and emergency borate via the ___(1)____ to establish a flowpath.

If a SIAS were to subsequently occur, the 2C Chg pump breaker would __(2)__.

A. 1) 2B Boric Acid Makeup pump and Emergency Borate valve (V2514)

2) open then reclose on the load block sequencer B. 1) Gravity Feed valves (V2508 and V2509)
2) remain closed C. 1) 2B Boric Acid Makeup pump and Emergency Borate valve (V2514)
2) remain closed D. 1) Gravity Feed valves (V2508 and V2509)
2) open then reclose on the load block sequencer Page 20 of 75

HLC 22 RO NRC EXAM Question 21 Given the following conditions on Unit 2:

  • The reactor is operating at 100% power
  • Channel X for Pressurizer (Pzr) Level control is SELECTED
  • Channel Y for Pzr Level control, LT-1110Y, failed LOW Which ONE of the following states:
1) the CURRENT status of the Pzr Heaters AND
2) after selecting the LEVEL position on the Back Up Interlock Bypass Key Switch (B/U INTLK BP Key), which Pzr heaters are available?

A. 1) All Pzr heaters off

2) All B. 1) All Pzr heaters off
2) A side Pzr heaters ONLY C. 1) ONLY B side Pzr heaters off
2) A side Pzr heaters D. 1) ONLY B side Pzr heaters off
2) All Page 21 of 75

HLC 22 RO NRC EXAM Question 22 Given the following:

  • Core Reload is in progress on Unit 2
  • 32 Fuel Assemblies have been loaded into the core
  • During insertion of the 33rd assembly, the BRCO reports that count rate has increased from 10 CPS to 24 CPS Which ONE of the following describes the action required in accordance with 0-NOP-67.05, Refueling Operation, for the stated conditions?

A. Direct Reactor Engineering to assess the nuclear instrument readings used for the 1/M plot and verify that they do NOT extrapolate to 0 when fuel movement resumes.

B. Direct Reactor Engineering to validate the method being used to calculate the 1/M and renormalize the 1/M prior to inserting the next fuel assembly.

C. Stop inserting the fuel assembly and verify Shutdown Margin while maintaining the fuel assembly at the current position.

D. Stop inserting the fuel assembly and withdraw it into the Refueling Machine Hoist/Mast then verify Shutdown Margin.

Page 22 of 75

HLC 22 RO NRC EXAM Question 23 Unit 1 is performing a Liquid Release of the 1A Waste Monitor Tank when the following alarm is received:

LIQUID WASTE RAD HIGH N-37 LIQUID RELEASE FLOW CONTROL VALVE, FCV-6627X, indicates open and will not close from the RTGB.

IAW 1-AOP-06.02, Uncontrolled Release Of Radioactive Liquids, which ONE of the following is a required SUBSEQUENT Operator action?

A. At the 1A Waste Monitor Storage Tank, stop the 1A Waste Monitor pump from the local control box AND at the CCW platform, lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve.

B. At the 1A Waste Monitor Storage Tank, close FCV-6627X AND at the CCW platform, lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve.

C. From the Liquid Waste Control panel ONLY, stop the 1A Waste Monitor pump AND close V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve.

D. From the Liquid Waste Control panel, close FCV-6627X AND at the Waste Monitor Storage Tanks, stop the 1A Waste Monitor pump from the local control box.

Page 23 of 75

HLC 22 RO NRC EXAM Question 24 Given the following on Unit 1:

  • Several fire detectors have alarmed in the Cable Spreading Room Which ONE of the following describes the expected actuation?

A. Halon will charge the header, but only discharge into the room when the header fuseable link melts.

B. Halon will charge the header and then automatically discharge into the room.

C. Pre-action dry pipe header will be charged with water, and then automatically discharge into the room.

D. Pre-action dry pipe header will be charged with water, but only discharge into the room when the header fuseable link melts.

Page 24 of 75

HLC 22 RO NRC EXAM Question 25 Given the following conditions on Unit 1:

  • The reactor is operating at 100% power
  • A full B train INADVERTENT CIAS occurred
  • 1-AOP-69.01 Inadvertent ESFAS Actuation was entered
  • Section 4.2.2 Recovery from Inadvertent CIAS is being performed for B train CIAS components
  • B train valve V6555 Waste Gas Containment Isolation valve (downstream) is indicating OPEN on the RTGB
  • A train valve V6554 Waste Gas Containment Isolation valve (upstream) is indicating OPEN on the RTGB
  • The affected Containment Penetration is #31 Which ONE of the following MEETS the required action, if any, per 3.6.3.1, Containment Isolation Valves? (consider each selection independently)

A. NONE since V6554 is OPERABLE.

B. V6554 must be CLOSED ONLY.

C. V6555 must be CLOSED AND DE-ENERGIZED.

D. V6555 must be CLOSED ONLY.

Page 25 of 75

HLC 22 RO NRC EXAM Question 26 Given the following conditions on Unit 1:

  • The reactor is at 100% power
  • The specific activity of the RCS has stabilized at 0.15 uCi/gram Dose Equivalent (DEQ) Iodine 131
  • DEQ XE-133 is at normal levels IAW 1-AOP-01.06, which ONE of the following is a required action based on the current level of DEQ I-131 and the reason for the action?

A. Isolate letdown to prevent high gamma radiation areas in the RCA.

B. Position V6307, Flash Tank Divert Valve, to the Flash Tank to strip fission product gasses.

C. Commence a plant shutdown due to RCS chemistry limits being exceeded.

D. Place all available CVCS Ion Exchangers in service to provide additional mechanical filtration to reduce RCS activity.

Page 26 of 75

HLC 22 RO NRC EXAM Question 27 Given the following:

  • Unit 2 is operating at 100% power
  • The 2A Charging (Chg) pump is running
  • The 2B Chg pump switch is in AUTO
  • The Chg pump selector switch is in the 2A-2B position A Small Break Loss of Coolant Accident then occurs with the following:
  • The Reactor is manually tripped
  • Pressurizer level is 25% and slowly rising
  • All Charging pumps are now running Complete the following statements:

(consider each statement independently)

The 2C CHG pump ___(1)____ following the SIAS signal.

Later in the event, if Pressurizer Level rises above Chg pump cut off set point, the 2B CHG pump (back-up) will __(2)___.

A. 1) was manually started

2) remain running B. 1) was manually started
2) auto stop C. 1) automatically started
2) remain running D. 1) remains running
2) auto stop Page 27 of 75

HLC 22 RO NRC EXAM Question 28 The following conditions exist on Unit 1:

  • RCS temperature is 130°F
  • RCS pressure is 310 psia
  • Secondary side of the Steam Generator (SG) is 165°F Based upon the given conditions, which ONE of the following results could occur if an RCP is started?

A. Excessive core uplift.

B. No adverse results should be expected.

C. An RCS pressure transient outside the LTOP system capacity.

D. Allowable brittle fracture stress limits for the SG could be exceeded.

Page 28 of 75

HLC 22 RO NRC EXAM Question 29 Given the following:

  • BOTH LCV-2210P & Q, Letdown Level Control Valves, are open with their controller in MANUAL
  • BOTH PCV-2201P & Q, Letdown Pressure Control Valves, are throttled with their controller in AUTO set at 100 psig Which ONE of the following choices completes the statement below:

If HCV-3657, SDC Temp Control Valve, is throttled OPEN, what is the effect on RCS temperature AND how would the Letdown Pressure Control valves respond to maintain letdown pressure on setpoint?

RCS temperature will:

A. rise causing PCV-2201P&Q to throttle open.

B. lower causing PCV-2201P&Q to throttle closed.

C. rise causing PCV-2201P&Q to throttle closed.

D. lower causing PCV-2201P&Q to throttle open.

Page 29 of 75

HLC 22 RO NRC EXAM Question 30 Given the following:

  • The B SDC train is in service
  • The A SDC train is in standby

4.16KV SWGR 2B2 CURRENT TRIP A-13 Which ONE of the following describes the response of the 2B Low Pressure Safety Injection pump?

A. Continues in operation.

B. Its control breaker opens, but can be manually closed.

C. Its control breaker opens, but recloses following a time delay.

D. Stops due to loss of AC power and its breaker cannot be reclosed.

Page 30 of 75

HLC 22 RO NRC EXAM Question 31 Given the following conditions:

  • Unit 1 is in MODE 4
  • SDC flow rate returning to the core is 3400 gpm as indicated on FI-3306
  • RCS temperature is 295°F and being held constant for shift turnover
  • HCV-3657 SDC Temp Control Valve, is open and FCV-3306 SDC Return Flow Valve, is closed
  • The air supply line breaks on HCV-3657 Which ONE of the following choices completes the statement below:

As a result of the loss of air, HCV-3657 will __(1)__and SDC flow rate returning to the core will __(2)___.

A. 1) close

2) lower to approximately 0 gpm B. 1) fail as is
2) remain unchanged C. 1) close
2) lower then return to 3400 gpm D. 1) open
2) rise to approximately 4600 gpm Page 31 of 75

HLC 22 RO NRC EXAM Question 32 Unit 2 is performing a cooldown per 2-GOP-305, Reactor Plant Cooldown - Hot Standby To Cold Shutdown, for a refueling outage with the following conditions:

Time: 11:30

  • RCS pressure is 1750 psia
  • RCS temperature is 504°F
  • 2A & 2B S/Gs are 740 psia Time: 11:32
  • 2A Steam Line ruptures outside Containment and just upstream of the MSIV
  • RCS pressure is 1630 psia and rapidly lowering
  • SG pressures are 580 psia and rapidly lowering Which ONE of the following states:
1) What ESFAS actuation(s) must be MANUALLY actuated?
2) Which procedure will be implemented to mitigate the event?

A. 1) BOTH MSIS, and SIAS.

2) 2-EOP-05, ESDE.

B. 1) ONLY SIAS.

2) 2-EOP-05, ESDE.

C. 1) BOTH MSIS, and SIAS.

2) 2-ONP-01.01 Plant Condition 1 Steam Generator Heat Removal LTOP Not in Effect.

D. 1) ONLY SIAS.

2) 2-ONP-01.01 Plant Condition 1 Steam Generator Heat Removal LTOP Not in Effect.

Page 32 of 75

HLC 22 RO NRC EXAM Question 33 Given the following on Unit 1:

  • The unit has just completed drawing a bubble from a solid plant condition
  • Quench Tank pressure was noted to be 1 psig
  • Pressurizer (Pzr) is being maintained at 200 psia by cycling backup Pzr heaters
  • RCS temperature is 205°F If a PORV is venting fluid to the Quench Tank (QT), which ONE of the following would apply to both the expected PORV tailpipe temperature AND the Technical Specification Limiting Condition for Operation leakage limit for this type of leakage?

(Assume 100% quality. References provided)

A. ~310ºF; 1 gpm B. ~310ºF; 10 gpm C. ~380ºF; 1 gpm D. ~380ºF; 10 gpm Page 33 of 75

HLC 22 RO NRC EXAM Question 34 Given the following on Unit 1:

  • Unit 1 is operating at 100% power
  • LS-14-1A (A side CCW Surge Tank Level Switch) on the Component Cooling Water (CCW) surge tank fails low causing the following annunciator CCW SURGE TANK LEVEL HIGH/

COMPARTMENT A LEVEL LOW S-6 Which ONE of the following describes the impact on CCW operation and Reactor Coolant Pump (RCP) Cooling:

A. No Non-Essential header valves isolate, A and B CCW header supplies flow to the RCPs.

B. A side Non-Essential header valves auto close; B CCW header supplies flow to the RCPs.

C. A side Non-Essential header valves should be manually closed; All RCPs should be secured.

D. All four Non-Essential header valves auto close; All RCPs should be secured.

Page 34 of 75

HLC 22 RO NRC EXAM Question 35 On Unit 1, which ONE of the following DIRECTLY feeds the Pressurizer PORV OPEN signal when the PORV selector switch is in:

1) NORMAL RANGE
2) LOW RANGE DIRECTLY from the:

A. 1) RPS high pressurizer pressure trip bistables

2) Pressurizer pressure instruments PT-1103, 1104 B. 1) Pressurizer pressure instruments PT-1102 A through D
2) Pressurizer pressure instruments PT-1102 A through D C. 1) RPS high pressurizer pressure trip bistables
2) Pressurizer pressure instruments PT-1102 A through D D. 1) Pressurizer pressure instruments PT-1102 A through D
2) Pressurizer pressure instruments PT-1103, 1104 Page 35 of 75

HLC 22 RO NRC EXAM Question 36 Given the following conditions on Unit 1:

The unit is operating at 100% power.

Reactor Protection System (RPS) Channel A Tcold RTD (TE-1112CA) has been inadvertently set to the MAXIMUM value of the Tcold range.

Which ONE of the following describes the effect of this adjustment on the given parameters?

Channel A : TM/LP Trip Setpoint Delta-T Power Indication A. Lowers Lowers B. Lowers Raises C. Raises Raises D. Raises Lowers Page 36 of 75

HLC 22 RO NRC EXAM Question 37 Given the following conditions on Unit 2:

  • Unit 2 is at 18% power
  • The Main Generator is on-line
  • The crew is raising turbine load at 1 MW/min IAW 2-GOP-201, Reactor Plant Startup - Mode 2 to Mode 1 The Main Transformer 2A Differential Current Alarm has annunciated resulting in:
  • Turbine tripping on a generator lockout Which ONE of the following describes the expected plant response and subsequent actions?

The Reactor should _________.

A. remain CRITICAL; Verify SBCS quick opens to remove reactor heat and enter 2-AOP-53.03, Main Generator B. remain CRITICAL; Ensure SBCS responds in pressure control mode to remove reactor heat and enter 2-AOP-53.03, Main Generator C. have automatically TRIPPED; Manually trip the reactor and enter EOP-01, Standard Post Trip Actions D. have automatically TRIPPED; Manually trip the reactor then enter EOP-15, Functional Recovery, due to the Reactivity Control Safety Function not being met Page 37 of 75

HLC 22 RO NRC EXAM Question 38 Given the following conditions on Unit 2:

The crew has entered 2-EOP-03, LOCA with the following:

  • 2-HVS-1A and 2-HVS-1C, Containment Fan Coolers, are running
  • 2B CS pump failed to auto start
  • Containment Pressure is 7 psig and rising
  • Containment Temperature is 220°F and rising
  • Hydrogen Analyzers have just been placed in service Which ONE of the following describes the status of the Containment Temperature and Pressure Safety Function and required actions (if any) per 2-EOP-03, LOCA?

A. Met; based on current Containment Temperature and Pressure.

B. Not Met; but will be if the HVS-1B Containment Fan Cooler is started.

C. Not Met; but will be if the 2B CS pump is started with a flow rate of 2700 gpm.

D. Met; based on ONLY 2 Containment Fan Coolers running and the 2A CS pump at its current flow rate.

Page 38 of 75

HLC 22 RO NRC EXAM Question 39 Given the following events and conditions:

  • Unit 2 is operating at 100%
  • A loss of off-site power (LOOP) occurred
  • The 2B EDG started but its output breaker DID NOT auto close

A train of Auxiliary Feedwater (AFW) is feeding the 2A SG Time: 0205:

The 2B EDG output breaker was manually closed Which ONE of the following statements correctly describes the B Train AFW status at Time 0206, and any subsequent actions (if any)?

The 2B AFW pump:

A. is running and feeding the 2B SG. No further action is required.

B. is running but NOT feeding the 2B SG. Open the 2B AFW flow control valves to establish the desired flow rate.

C. is NOT running. Manually initiate AFAS-2 using all 4 Manual Initiation switches on RTGB-202.

D. is NOT running. Manually start the B train of AFW in accordance with the operator hard card.

Page 39 of 75

HLC 22 RO NRC EXAM Question 40 Given the following condition on Unit 2:

Time: 0200

  • A Small Break Loss of Coolant Accident has occurred
  • A loss of offsite power (LOOP) occurs
  • Safety Injection Signal Actuates (SIAS)

Which ONE of the following describes the expected condition of the Containment Fan Coolers following the LOOP, then following the SIAS?

__(1)__ Containment Cooling Fans running in ___(2)___ speed.

0200 0220 A. 1) Three Four

2) Fast Fast B. 1) Three Four
2) Fast Slow C. 1) Four Four
2) Fast Fast D. 1) Four Four
2) Fast Slow Page 40 of 75

HLC 22 RO NRC EXAM Question 41 Given the following conditions on Unit 2:

  • A Large Break LOCA has occurred
  • The 2B Containment Spray pump was manually started by the RCO Which ONE of the following identifies the status of the B Train Iodine Removal System at this time?

2B Hydrazine Pump SE-07-3B, 2B Hydrazine Pump Discharge Valve A. OFF CLOSED B. ON CLOSED C. ON OPEN D. OFF OPEN Page 41 of 75

HLC 22 RO NRC EXAM Question 42 The REGULARLY scheduled QUARTERLY Code Run Test has just been performed on the 2A Containment Spray (CS) pump IAW 2-OSP-07.04A, 2A Containment Spray and 2A Hydrazine Pump Code Run.

Which ONE of the following describes the specific parameter, from this particular surveillance, that must be satisfied in order to be in compliance with the Unit 2 CONTAINMENT SPRAY and COOLING SYSTEM Technical Specification LCO, 4.6.2.1?

A. 2A Hydrazine Pump flow as indicated on RTGB-206 B. 2A CS Pump developed head by a locally installed pressure gauge C. 2A CS Pump vibration by local vibrometer D. 2A CS Pump discharge flow as indicated on RTGB 206 Page 42 of 75

HLC 22 RO NRC EXAM Question 43 Which ONE of the following is the function of the 103% Turbine Overspeed Protection Circuit (OPC)?

A. Reheat stop valves and extraction non-return valves are maintained closed to prevent LP turbine overspeed following a turbine trip.

B. Reheat stop valves and extraction non-return valves momentarily close to prevent LP turbine overspeed following a turbine trip.

C. Governor valves and intercept valves are maintained closed to prevent turbine overspeed following a complete loss of electrical load.

D. Governor valves and intercept valves momentarily close to prevent turbine overspeed following a complete loss of electrical load.

Page 43 of 75

HLC 22 RO NRC EXAM Question 44 Given the following:

  • Unit 1 reactor is at 65% power

(Assume no operator action)

Reactor Coolant System (RCS) Pressure will:

A. increase because the RCS delta T power increases.

B. increase because the RCS temperature increases due to increased SG temperatures.

C. decrease because the increased boiling rate in the SG tube bundle region decreases Tavg.

D. decrease because the SG level initially increases due to swell, causing a contraction of the RCS inventory.

Page 44 of 75

HLC 22 RO NRC EXAM Question 45 Given the following conditions on Unit 2:

  • The unit has just tripped from 100% power due to a loss of the 2A 125VDC bus
  • The 2AB 125VDC bus is aligned to the B train
  • 2-EOP-01, Standard Post Trip Actions is being implemented
  • No contingency actions have been taken Which ONE of the following completes the statements below with regards to the configuration of the 2B and 2C Auxiliary Feedwater pumps (AFW) immediately following AFAS actuation?

The 2B AFW pump is __(1)__. The 2C AFW pump is running feeding __(2)__.

A. 1) running feeding the 2B Steam Generator

2) ONLY the 2A Steam Generator B. 1) locked out due to a Feedwater Header Rupture ID;
2) ONLY the 2A Steam Generator.

C. 1) running feeding the 2B Steam Generator;

2) BOTH the 2A and 2B Steam Generator.

D. 1) locked out due to a Feedwater Header Rupture ID;

2) BOTH the 2A and 2B Steam Generator.

Page 45 of 75

HLC 22 RO NRC EXAM Question 46 Given the following on Unit 2:

  • The reactor is operating at 100% power
  • The 2A3 4.16kVAC bus has been de-energized due to an inadvertent trip of the 2A3-2A2 bus tie breaker, 4.16 KV BUS TIE 2A3-2A2
  • 2-AOP-47.01A, Loss of a Safety Related AC Bus-Train-A, is being implemented
  • The SNPO reports that there is NO apparent damage found on the 2A3-2A2 bus tie breaker For the stated conditions, which ONE of the following completes the statements below:

IAW 2-AOP-47.01A Attachment 7, Restoration of Offsite Power with 2A EDG in Operation, the 2A EDG synchroscope should be slowly rotating in the __(1)__

direction.

If NON-EMERGENCY EDG trips were locked in AT THIS TIME, they would actuate when the __(2)__.

A. 1) clockwise (fast)

2) 2A3 to 2A2, 4.16kVAC bus tie breaker is closed B. 1) clockwise (fast)
2) Synch Plug switch is placed into the TIE 2A3/2B3 position C. 1) counterclockwise (slow)
2) 2A3 to 2A2, 4.16kVAC bus tie breaker is closed D. 1) counterclockwise (slow)
2) Synch Plug switch is placed into the TIE 2A3/2B3 position Page 46 of 75

HLC 22 RO NRC EXAM Question 47 Given the following conditions on Unit 1:

The unit is at 100%

An automatic reactor trip occurs Which ONE of the following completes the statement below:

The __(1)___ signal DIRECTLY generates the __(2)__ bus automatic transfer from the auxiliary transformers to the Start-up transformers.

A. 1) TDM-1 and TDM-2

2) Live B. 1) TDM-1 and TDM-2
2) Dead C. 1) Generator Lockout
2) Live D. 1) Generator Lockout
2) Dead Page 47 of 75

HLC 22 RO NRC EXAM Question 48 Given the following conditions on Unit 1:

  • Unit 1 is at 100%
  • The 1AA Battery Charger is out of service
  • Annunciator B-20, "125V DC Bus/ 1A Batt Chgr/ Batt Rm Fan Trouble" has just alarmed
  • The SNPO has been dispatched to verify the status of the 1A battery charger Which ONE of the following describes an indication(s), FROM THE CONTROL ROOM, that can be used to determine if the 1A vital DC bus is powered from the Battery ONLY?

A. ONLY the 1A DC Bus voltmeter on RTGB-101 indicates 130VDC slowly lowering.

B. ONLY the 1A DC Bus ammeter on RTGB-101 indicates a discharge rate.

C. Both an ammeter on RTGB-101 indicates a discharge rate AND the voltmeter on RTGB-101 indicates 130VDC slowly lowering.

D. A white light above the 1A DC Bus voltmeter on RTGB-101 is lit signifying potential is being supplied from a battery charger.

Page 48 of 75

HLC 22 RO NRC EXAM Question 49 The Unit 2 SNPO has reported the following local alarm on the 2A Emergency Diesel Generator (EDG)

STARTING AIR PRESS LOW 5-1 The SNPO reports a relief valve lifted and has reseated on the two Air Receiver Tanks with the following pressures being reported:

  • 2A1: 45 psig, 2A2: 50 psig, 2A3: 152 psig, 2A4: 155 psig Which ONE of the following describes the effect of this condition on the 2A EDG OPERABILITY AND if a start signal occurs prior to any operator action?

A. INOPERABLE; 2A EDG would start.

B. OPERABLE; 2A EDG would NOT start.

C. OPERABLE; 2A EDG would start.

D. INOPERABLE; 2A EDG would NOT start.

Page 49 of 75

HLC 22 RO NRC EXAM Question 50 Given the following:

  • Unit 1 is at 100% power
  • The SNPO reports that the 1A Diesel Fuel Oil Transfer (DFOT) pump has tripped
  • The Diesel Oil Storage Tanks (DOST) are above the Technical Specification minimum levels For the stated conditions, which ONE of the following completes the statements below:

Technical Specification Limiting Condition for Operation 3.8.1.1, Electrical Power Systems - AC Sources, is __(1)__.

AND If a Loss of Offsite Power were to occur, the expected system response would be

__(2)__.

(Assume no operator action)

A. 1) MET

2) The 1A EDG would run for ~47 minutes before running out of fuel B. 1) MET
2) The 1A EDG would run with make-up via gravity feed C. 1) NOT MET
2) The 1A EDG would run for ~47 minutes before running out of fuel D. 1) NOT MET
2) The 1A EDG would run with make-up via gravity feed Page 50 of 75

HLC 22 RO NRC EXAM Question 51 Given the following on Unit 1:

Unit 1 is at 100% power Unit 2 is at 100% power The Unit 1 in-service waste gas decay tank has ruptured with a gas release in progress Which ONE of the following completes the statements below:

A MINIMUM of___(1)_____ Unit 1 Control Room Outside Air Intake Rad Monitor(s) in HIGH alarm, causes ___(2)_____ control room(s) to go into recirc mode?

A. 1) One

2) ONLY the Unit 1 B. 1) Two
2) ONLY the Unit 1 C. 1) One
2) BOTH Unit 1 and Unit 2 D. 1) Two
2) BOTH Unit 1 and Unit 2 Page 51 of 75

HLC 22 RO NRC EXAM Question 52 Which ONE of the following describes the function of the TCV-13-2A & 2B, 1A & 1B Turbine Cooling Water Heat Exchanger Outlet Valves, AND MV-21-2 & 3, Intake Cooling Water A & B Train to Turbine Cooling Water Heat Exchanger Valves?

TCV-13-2A & 2B controls __(1)__flow through the Turbine Cooling Water heat exchanger.

MV-21-2 & 3 close, to isolate TCW, on receipt of a SIAS signal to __(2)__.

A. 1) Intake Cooling Water

2) provide backpressure for Intake Cooling Water pumps to prevent run-out flow during accident conditions B. 1) Turbine Cooling Water
2) provide backpressure for Intake Cooling Water pumps to prevent run-out flow during accident conditions C. 1) Turbine Cooling Water
2) ensure sufficient cooling flow is available to the Component Cooling Water Heat Exchangers D. 1) Intake Cooling Water
2) ensure sufficient cooling flow is available to the Component Cooling Water Heat Exchangers Page 52 of 75

HLC 22 RO NRC EXAM Question 53 Given the following:

Unit 1 is at 100% power The following Control Room annunciators and indications are received:

INSTR AIR INSTR AIR PRESS COMPR HIGH/LOW AUTO START F-5 F-21

  • Instrument Air Pressure indication on RTGB-102, Pl-18-9, indicates 97 psig, lowering slowly The NPO reports that the1C and 1D Instrument Air Compressors are running.

For the stated conditions, which ONE of the following completes the statements below:

IAW 1-AOP-18.01, Instrument Air Malfunction:

If Instrument Air header pressure continued to lower, the unit to unit cross-tie from Unit 2 would open at __(1)__.

If Instrument Air header pressure continued to degrade, the crew should evaluate the need to perform a controlled shutdown when Instrument Air header pressure reaches a MINIMUM of __(2)__.

A. 1) 95 psig

2) 75 psig B. 1) 85 psig
2) 75 psig C. 1) 95 psig
2) 60 psig D. 1) 85 psig
2) 60 psig Page 53 of 75

HLC 22 RO NRC EXAM Question 54 Given the following conditions on Unit 1:

  • A loss of offsite power (LOOP) has occurred on Unit 1
  • The crew is performing actions of 1-EOP-09, Loss of Off Site Power / Loss of Forced Circulation
  • The SM directs the crew to perform a controlled cooldown to 350°F in accordance with 1-AOP-01.13, Natural Circulation Cooldown Which ONE of the following local (field) operator action(s) must be completed to DIRECTLY support the cooldown from the CONTROL ROOM?

A. Reset Non-Essential Load Breakers IAW 1-EOP-99, Appendix P, Restoration of Components Actuated by ESFAS.

B. Crosstie Unit 1 Condensate Storage Tank with Unit 2 Condensate Storage Tank IAW 1-AOP-09.02, Auxiliary Feedwater.

C. Perform 1-EOP-99, Appendix X, Secondary Plant Post Trip Actions, Section 2.

D. Perform 1-EOP-99, Appendix H, Operation of the 1A and 1B Instrument Air Compressors.

Page 54 of 75

HLC 22 RO NRC EXAM Question 55 Which ONE of the following completes the statements below:

IAW 2-NOP-68.01, Containment Building Access Hatches-Operation, interlocks that are installed to prevent both airlock doors from being open at the same time must be functional __(1)__. A control room annunciator alarms to alert the control room operators if __(2)__ door(s) is(are) open.

A. 1) in Modes 1 thru 4 AND Mode 6

2) EITHER the inner OR outer B. 1) in Modes 1 thru 4 AND Mode 6
2) BOTH the inner AND outer C. 1) ONLY in Modes 1 thru 4
2) EITHER the inner OR outer D. 1) ONLY in Modes 1 thru 4
2) BOTH the inner AND outer Page 55 of 75

HLC 22 RO NRC EXAM Question 56 Given the following on Unit 1:

  • A plant start-up is in progress with power stable at 15%
  • The Main Generator is on line
  • CEAs are at 110 inches on group 7
  • One CEA in group 7 is 3 inches below the remainder of CEAs
  • The CEDS control is placed in Manual Individual mode to realign the CEA
  • When the RCO initially withdraws the CEA, the CEA moves outward but it continues to WITHDRAW when the control switch is released due to a control switch failure As a result, which ONE of the following will occur?

(Assume NO Operator action)

As power rises:

A. BOTH T avg and T ref will increase at the same rate and the CEA withdrawal should stop when a group deviation occurs.

B. BOTH T avg and T ref will increase at the same rate and the CEA withdrawal should stop when an Automatic CEA Withdrawal Prohibit occurs.

C. ONLY T avg will increase and the CEA withdrawal should stop when a group deviation occurs.

D. ONLY T avg will increase and the CEA withdrawal should stop when an Automatic CEA Withdrawal Prohibit occurs.

Page 56 of 75

HLC 22 RO NRC EXAM Question 57 Which ONE of the following completes the statements below:

If the external leads of a Core Exit Thermocouple short together, a __(1)___

temperature than actual would be indicated.

In accordance with Ops Policy-503, Technical Specification Guidance, a TOTAL of

__(2)___ Core Exit Thermocouples per core quadrant are required to be OPERABLE for Mode 1 - 3 operation.

A. 1) higher

2) 2 B. 1) lower
2) 2 C. 1) lower
2) 4 D. 1) higher
2) 4 Page 57 of 75

HLC 22 RO NRC EXAM Question 58 Given the following conditions on Unit 2:

  • The plant is currently in Mode 3
  • Radiation Protection has requested that a containment purge be performed to reduce particulate activity in Containment Which ONE of the following describes the required method of purging the Containment atmosphere under these conditions?

Operation of:

A. HVE-1&2, airborne radioactivity removal system IAW 2-NOP-25.05, Containment Ventilation Systems.

B. HVE-7A/B through the Continuous Purge (mini-purge) mode filter train IAW 2-NOP-25.02, Continuous Containment / Hydrogen Purge System Operation.

C. HVE-6A/B through the Shield Building Ventilation filter train IAW 2-NOP-25.01, Shield Building Ventilation System Operation.

D. HVE-8A/B through the normal Containment Purge (main-purge) System filter train IAW 2-NOP-06.20, Controlled Gaseous Batch Release to Atmosphere.

Page 58 of 75

HLC 22 RO NRC EXAM Question 59 Given the following on Unit 1:

  • A small break LOCA has occurred
  • 1-EOP-03, LOCA, was entered and the direction to place both Hydrogen Analyzers in service was given Which ONE of the following completes the statements below:

IAW with 1-EOP-99, Appendix L, Placing a Hydrogen Analyzer in Service, aligning the sampling point for the Hydrogen Analyzer requires positioning valves at (in) the __(1)__.

AFTER 1-EOP-99, Appendix L, Placing a Hydrogen Analyzer in Service, had been performed, a Loss of Offsite (LOOP) occurred resulting in BOTH Emergency Diesel Generators starting and energizing the 1A3 and 1B3 4.16 kv busses.

Without any operator action, Hydrogen Analyzer panel operation IN THE CONTROL ROOM __(2)__ be affected.

A. 1) Hydrogen Analyzer Cubicle on the 43 foot elevation in the Fan Room

2) WOULD B. 1) Control Room
2) WOULD C. 1) Hydrogen Analyzer Cubicle on the 43 foot elevation in the Fan Room
2) WOULD NOT D. 1) Control Room
2) WOULD NOT Page 59 of 75

HLC 22 RO NRC EXAM Question 60 IAW 1-NOP-67.04, Refueling Machine Operation, which ONE of the following would be expected while operating the Refueling Machine (RFM) during a core onload?

A. A Bridge and Trolley lockout interlock is present any time the RFM Hoist is being lowered or raised, while on index at a core location, to prevent RFM movement.

B. If fuel movement had to be suspended, the RFM operator should ensure that the fuel transfer carriage is placed in its stored position on the Spent Fuel Pool side.

C. When lowering the RFM Hoist over the core with a fuel assembly grappled on, hoist motion is automatically stopped when the Lower Grapple operate zone is reached.

D. Operation with the Programmable Logic Controller (PLC) switch in the OVRD position is permitted to override an OVERLOAD condition on a fuel assembly that is being raised out of the core.

Page 60 of 75

HLC 22 RO NRC EXAM Question 61 Given the following conditions on Unit 1:

  • The Unit is in Mode 3
  • Control Element Assembly testing is planned
  • 1-GOP-302, Reactor Plant Startup - Mode 3 to Mode 2 Which ONE of the following Reactor Protection System RPS trips is NOT bypassed during this testing?

A. Low Steam Generator Level B. Thermal Margin / Low Pressure C. Low Steam Generator Pressure D. Low Reactor Coolant System Flow Page 61 of 75

HLC 22 RO NRC EXAM Question 62 Given the following Unit 1:

  • Unit 1 is at 12% power with Tavg at 535°F and Steam Generator pressure at 900 psia
  • The Main Generator has just been synchronized to the grid
  • The Main Generator picked up 40 MWe and then TRIPPED 5 seconds later Which ONE of the following states the expected plant response?

A. Reactor power indicates 12% with Steam Bypass Control System valves opening to control steam generator pressure at 940 psia for 4 minutes then ramp to 900 psia over the next 5 minutes.

B. Reactor power indicates 12% with Steam Bypass Control System valves opening to control steam generator pressure at 900 psia ONLY.

C. Reactor trips with Steam Bypass Control System closing to control steam generator pressure at 940 psia for 4 minutes then ramp to 900 psia over the next 5 minutes.

D. Reactor trips with both Atmospheric Dump Valves opening to control steam generator pressure at 900 psia.

Page 62 of 75

HLC 22 RO NRC EXAM Question 63 Given the following conditions on Unit 2:

  • The gas analyzer local panel oxygen monitor and Chemistry samples on the in-service gas decay tank indicate 2.2%

IAW 2-AOP-06.03, Waste Gas System, which ONE of the following actions should be taken?

Suspend all additions of waste gases and _______.

A. ensure the Gas Surge header inlet to the Gas SURGE Tank auto closes and the nitrogen purge supply to the Gas SURGE Tank auto opens B. manually align nitrogen to the Gas SURGE Tank C. ensure the Gas Surge header inlet to the Gas DECAY Tank auto closes and the nitrogen purge supply to the Gas DECAY Tank auto opens D. manually align nitrogen to the in-service Gas DECAY Tank Page 63 of 75

HLC 22 RO NRC EXAM Question 64 Given the following conditions on Unit 2:

TIME 1200: The unit had to be manually tripped due to a severe DEH leak on Governor Valve #1 1202: A 350 gpm tube rupture developed in the 2A Steam Generator (SG) 1205: SIAS & CIAS actuations occurred on low Reactor Coolant System (RCS) pressure 1210: 2-EOP-01, SPTAs are in progress and the crew has just begun to evaluate the Containment Conditions safety function Which ONE of the following rad monitor alarms and trend indications would be AVAILABLE AT THIS TIME to determine the status of the Containment Conditions safety function (Secondary Activity)?

(ASSUME NO OPERATOR ACTIONS HAVE BEEN TAKEN and no other complications exist post trip)

A. Main Steam Line Rad Monitor AND SG Blowdown Rad Monitor B. Steam Jet Air Ejector AND SG Blowdown Rad Monitor C. ONLY Main Steam Line Rad Monitor D. ONLY Steam Jet Air Ejector Page 64 of 75

HLC 22 RO NRC EXAM Question 65 Unit 1 is at 100% power, steady state.

  • The 1B Intake Cooling Water (ICW) pump has just tripped unexpectedly
  • It is desired to START the 1C ICW pump to replace the 1B ICW pump In accordance with 1-AOP-21-03B, 1B INTAKE COOLING WATER SYSTEM HEADER, which ONE of the following answers the questions below:
1) What is the MINIMUM electrical alignment to start the 1C ICW pump for the given plant conditions?
2) Prior to starting the 1C ICW pump, if Main Generator Average Cold Gas Temperature were to rise to 47.7°C, what is the required action the crew must take at that point in time?

A. 1) The 1AB 4.16 kVAC bus, 1AB 480 V bus AND the 1AB DC bus aligned to the B side.

2) Reduce MVARS to minimum.

B. 1) The 1AB 4.16 kVAC bus, 1AB 480 V bus AND the 1AB DC bus aligned to the B side.

2) Reduce power as necessary to stabilize main generator cold gas temperature.

C. 1) ONLY the 1AB 4.16 kVAC bus aligned to the B 4.16 KV side.

2) Reduce MVARS to minimum.

D. 1) ONLY the 1AB 4.16 kVAC bus aligned to the B 4.16 KV side

2) Reduce power as necessary to stabilize main generator cold gas temperature.

Page 65 of 75

HLC 22 RO NRC EXAM Question 66 Given the following on Unit 2:

  • A Core Reload is in progress
  • Both BF 3 Log Startup Channels are in service with the B Channel selected for audible count rate monitoring (control room and containment)
  • While Reactor Engineering was monitoring the indicated count rates for a 1/M plot, it was determined that the B Log Startup Channel had failed low IAW 0-NOP-67.05, Refueling Operation, which ONE of following describes the impact on the fuel movement?

A. With the B Log Startup Channel inoperable, the core reload MUST STOP until it is returned to service.

B. With the A Log Startup Channel operable, the core reload can continue as long as audible is selected for that channel.

C. The core reload can continue by substituting a Wide Range Log Safety Channel and selecting the audible count rate to that channel.

D. The core reload can continue by substituting an Appendix R Wide Range (Excore) and selecting the audible count rate to channel A.

Page 66 of 75

HLC 22 RO NRC EXAM Question 67 Unit 1 is operating at 100% when the following annunciator alarmed due to a loss of power to the MA Instrument Inverter:

120V AC INSTR BUS MA INVERTER TROUBLE B-43 Which ONE of the following Control Room alarms would NOT be expected to annunciate for this event?

A. Q-19, 1B S/G PRESS MSIS CHANNEL TRIP B. Q-16, CNTMT RAD HIGH CIS CHANNEL TRIP C. R-10, ENGINEERED SAFEGUARDS ATI FAULT D. R-11, CNTMT PRESS HIGH CSAS CHANNEL TRIP Page 67 of 75

HLC 22 RO NRC EXAM Question 68 Given the following on Unit 2:

  • Reactor start-up is in progress
  • Mode 2 has just been declared Reactor Engineering predicts that the reactor will become critical approximately 600 pcm earlier than the ECC calculation.

Which ONE of the following describes the correct course of action IAW 2-GOP-302, Reactor Plant Startup - Mode 3 to Mode 2?

Stop CEA withdrawal, _________.

A. and immediately initiate emergency boration B. and ensure CEAs are inserted to a position equivalent to (-) 500 pcm from the apparent critical position C. maintain the present rod height, and verify that the 1/M predicted rod position is greater than minimum rod height for criticality D. raise the Reactor Coolant System boron concentration until criticality can be predicted within the proper +/-pcm band. Recalculate the ECC prior to continuing CEA withdrawal Page 68 of 75

HLC 22 RO NRC EXAM Question 69 Given the following:

  • Unit 1 is at 100% power
  • An equipment clearance order (ECO) is being developed for a system with the following parameters: pressure - 100 psia and temperature - 130°F
  • Due to an equipment deficiency, only a SINGLE CHECK VALVE is available as an isolation boundary IAW OP-AA-101-1000, Clearance and Tagging, at a minimum, which ONE of the following describes the Energy classification and whose approval is required for the clearance to allow use of a SINGLE CHECK VALVE as an isolation boundary?

A. High Energy; Nuclear Joint Safety Committee B. Low Energy; Nuclear Joint Safety Committee C. Low Energy; Shift Manager D. High Energy; Shift Manager Page 69 of 75

HLC 22 RO NRC EXAM Question 70 Given the following conditions on Unit 1:

Due to equipment unavailability, the Containment Fan Cooler flow weekly surveillance check must be delayed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

To ensure compliance with the Technical Specification Limiting Condition of Operation (LCO), which ONE of the following describes how the surveillance must be tracked?

A. With an Action Request (AR) ONLY.

B. the Equipment Out Of Service program AND an Action Request (AR).

C. 1-OP-0010125A, Data Sheet 29, Surveillance Tracker (Data Sheet Pink).

D. 1-OP-0010125A, Data Sheet 30, Unscheduled Surveillances and Evolution Tracking (Data Sheet Green).

Page 70 of 75

HLC 22 RO NRC EXAM Question 71 Given the following conditions on Unit 1:

  • 1-GOP-302, Reactor Plant Startup - Mode 3 to Mode 2 is being implemented
  • Reactor power is at 1.0E-2% and slowly increasing
  • A containment entry is required to check the RCP Oil Collection Tank level
  • No Management Exemptions have been authorized for this entry IAW ADM- 09.05, Containment Entries Mode 1-4, which ONE of the following conditions apply?

A Containment entry:

A. cannot occur because reactor power level is beyond the administrative limit for entry inside the biological shield wall.

B. can occur ONLY IF reactor power is lowered to <1.0E-3%.

C. can occur ONLY IF ALL Regulating Group CEAs are inserted.

D. can occur IF power level is stabilized at the current value.

Page 71 of 75

HLC 22 RO NRC EXAM Question 72 Given the following:

  • The Unit 2 reactor is operating 100%
  • The Unit Supervisor directs use of the Portable RM-23P at the B MSL line RM-80 Microprocessor When the RM-23P is placed in service, which ONE of the following describes:
1) the Control Room (CR) Alarm Function AND
2) the location where the B MSL radiation levels can be read CR Alarm function B MSL radiation reading A. None ONLY Local at RM-23P B. RMCS Local at RM-23P AND RM-23 at PACB-2 C. None Local at RM-23P AND RM-23 at PACB-2 D RMCS RMCS AND Local at RM-23P Page 72 of 75

HLC 22 RO NRC EXAM Question 73 Given the following:

  • Unit 1 tripped from 100% power
  • The B SG has a sheared U-tube
  • The crew has entered 1-EOP-15, Functional Recovery Which ONE of the following completes the following statement:

The MOST AFFECTED SG is the __(1)__ SG. It will remain the MOST AFFECTED SG until __(2)__.

A. 1) A

2) the failed open MSSV on the A SG is gagged B. 1) A
2) 1-EOP-99, Appendix R, Steam Generator Isolation, is complete on the A SG C. 1) B
2) 1-EOP-99, Appendix R, Steam Generator Isolation, is complete on the B SG D. 1) B
2) Reactor Coolant System pressure is reduced within 50 psia of the B SG pressure.

Page 73 of 75

HLC 22 RO NRC EXAM Question 74 Given the following on Unit 1:

Time 0010:

  • The Unit is at 100% power
  • Pressurizer level is 66%
  • Pressurizer pressure is 2250 psia
  • 2 Charging pumps are running
  • Letdown flow is 84 gpm
  • A containment particulate radiation monitor is reading 210 cpm Time 0020:
  • Pressurizer level is at 64%
  • Pressurizer pressure is 2235 psia
  • 2 Charging pumps are running
  • Letdown flow is 50 gpm
  • A containment particulate radiation monitor is reading 400 cpm Which ONE of the following completes the following statements:
1) The type of event that is occurring at time 0020 is a __(1)__
2) For the purposes of Emergency Plan classification, the increased RCS leakage at time 0020 is considered __(2)__ leakage.

A. 1) Steam Generator Tube Leak

2) IDENTIFIED B. 1) Steam Generator Tube Leak
2) UNIDENTIFIED C. 1) Reactor Coolant System Leak
2) IDENTIFIED D. 1) Reactor Coolant System Leak
2) UNIDENTIFIED Page 74 of 75

HLC 22 RO NRC EXAM Question 75 Given the following conditions on Unit 1:

  • 1-EOP-03, LOCA is being implemented
  • Pressurizer Pressure 900 psia and slowly lowering
  • T HOT is 508°F and slowly lowering
  • REP CET 515°F and slowly lowering
  • Pressurizer Level is 55% and slowly rising
  • ECCS flow is 650 gpm
  • Containment Temperature is 185°F and slowly lowering Which ONE of the following states the strategy that should be implemented AT THIS TIME? (Consider each selection independently)

(References Provided)

Cooldown and ___________.

A. depressurize to maximize ECCS flow B. ensure 1-EOP-99, Figure 2 is being maintained C. allow Pressurizer level to rise to 68% then throttle ECCS flow and secure Charging D. throttle ECCS flow and cycle a Charging pump to allow Pressurizer level to stabilize and be maintained between 30% to 68%

Page 75 of 75

St. Lucie NRC Exam HLC-22 ROISRO Answer Key Question Answer

1. C
2. B
3. B
4. C
5. D
6. B
7. C
8. B
9. D
10. A
11. C
12. C
13. A
14. A
15. B
16. A
17. D
18. B
19. C
20. B
21. B
22. D
23. A
24. B
25. C
26. B
27. A
28. C
29. B
30. B
31. A 32.
33. B
34. A
35. A
36. D
37. C
38. C 5jei 1 tes+i-.. U 3 cJ..&-jcd 1 i

c C LCrriz*S.

Rev 13/23/20158:13:17 AM

St. Lucie NRC Exam HLC-22 Question Answer New PSL Modified Comp Memory Bank PSL Bank

39. C
40. D
41. B
42. B
43. D
44. B
45. A
46. C
47. D
48. A
49. C
50. D
51. A
52. D
53. B
54. D
55. C
56. C
57. C
58. B
59. B
60. A
61. A
62. B
63. A
64. D
65. C
66. D
67. D
68. B
69. B
70. C
71. D
72. A
73. A
74. D
75. B SRO Exam Rev 13/23/20158:40:24 AM
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REVISION NO.: PROCEDURE TITLE: PAGE:

SHUTDOWN COOLING ABNORMAL OPERATIONS 19 of 31 PROCEDURE NO.:

1-AOP-03.02 ST. LUCIE UNIT 1 ATTACHMENT I Estimated Time to Core Boiling (Page 1 of 5)

DETERMINE estimated time to core boiling as follows (Section 6.2 Commitment 2):

A. RECORD the following information at the time SDC was lost:

Time Shutdown Cooling Lost from Section 4.2 Step 2 RCS Temperature from Section 4.2 Step 2 °F Vessel / Cavity Level ft Time since shutdown (hours)

B. RECORD time to boil at mid-loop per Table 1:

(minutes)

C. RECORD additional time to boil for a 100 ft 3 volume per Table 2:

(minutes /100 ft ).

3 D. RECORD additional 100 ft 3 volumes above mid-loop per Table 3:

(100 ft

)

3 E. CALCULATE Time to Boil as follows:

+ x = *min Time to boil Additional time to boil Additionall00 3 ft volumes Time to Boil Stepl.B Stepl.C Stepl.D

2. IF core shuffle or reload has NOT been competed, THEN CALCULATE time boiling will occur as follows:

+ =

Time SDC Lost Time to Boil Time Boiling Will Occur Stepl.A Stepl.E

REVISION NO.: PROCEDURE TITLE: PAGE:

SHUTDOWN COOLING ABNORMAL OPERATIONS 20 of 31 PROCEDURE NO.:

1-AOP-03.02 ST. LUCIE UNIT 1 ATTACHMENT I Estimated Time to Core Boiling (Page 2 of 5)

3. IF core shuffle or reload has been completed, THEN CALCULATE time boiling will occur as follows (Section 6.1 .3 Management Directive 1):

x(1.35) =

Time SDC Lost Time Boiling Will Occur Stepl.A

REVISION NO.: PROCEDURE TITLE: PAGE:

SHUTDOWN COOLING ABNORMAL OPERATIONS 21 of 31 PROCEDURE NO.:

1-AOP-03.02 ST. LUCIE UNIT 1 ATTACHMENT I Estimated Time to Core Boiling (Page 3of5)

NOTE

. Temperatures between columns, select higher temperature.

  • Time since shutdown between rows, select the lesser time.

Table 1 Time to Boil (minutes) at Mid-Loop RCS Temperature °F)

Shutdown Time 60 80 90 100 110 120 130 140 200 (Hours) 24 13.1 11.4 10.5 9.64 8.77 7.90 7.03 6.17 1.08 48 16.0 13.9 12.8 11.8 10.7 9.66 8.60 7.54 1.32 60 17.3 15.0 13.9 12.7 11.6 10.4 9.30 8.16 1.43 72 18.6 16.1 14.9 137 12.4 11.2 9.98 8.76 1.54 90 20.4 17.7 16.4 15.0 13.7 12.3 11.0 9.62 1.69 102 21.6 18.7 17.3 15.9 14.4 13.0 11.6 10.2 1.78 120 23.2 20.1 18.6 17.0 15.5 14.0 12.4 10.9 1.91 132 24.2 21.0 19.4 17.8 16.2 14.6 13.0 11.4 2.00 144 25.1 21.8 20.1 185 16.8 15.1 13.5 11.8 2.07 240 31.0 26.9 24.8 22.8 20.7 18.7 16.6 14.6 2.56 300 33.8 29.3 27.0 24.8 22.6 20.3 18.1 15.9 2.79 360 36.3 31.5 29.0 26.6 24.2 21.8 19.4 17.1 2.99 480 40.9 35.5 32.8 30.1 27.3 24.6 21.9 19.3 3.38 600 45.4 39.4 36.4 33.3 30.4 27.3 24.3 21.4 3.75 840 54.2 47.0 43.4 39.8 36.2 32.6 29.0 25.5 4.47 1440 73.9 64.1 59.2 54.3 49.4 44.5 39.6 34.8 6.10

REVISION NO.: PROCEDURE TITLE: PAGE:

SHUTDOWN COOLING ABNORMAL OPERATIONS 22 of 31 PROCEDURE NO.:

1-AOP-03.02 ST. LUCIE UNIT 1 ATTACHMENT I Estimated Time to Core Boiling (Page 4 of 5)

NOTE Temperatures between columns, select higher temperature.

Time since shutdown between rows, select the lesser time.

Table 2 Additional Time To Boil (minutes) for Each 100 cubic feet of RCS Volume (Section 6.1.3 Management Directive 2)

RCS Temperature (°F Shutdown Time 60 80 90 100 110 120 130 140 200 (Hours) 24 0.913 0.792 0.731 0.671 0.610 0.550 0.490 0.430 0.0754 48 1.12 0.968 0.893 0.819 0.746 0.672 0.598 0.525 0.0921 60 1.21 1.05 0.967 0.887 0.807 0.727 0.647 0.568 0.0996 72 1.30 1.12 1.04 0.952 0.866 0.781 0.695 0.610 0.107 90 1.42 1.23 1.14 1.04 0.951 0.857 0.763 0.669 0.117 102 1.50 1.30 1.20 1.10 1.00 0.905 0.805 0.707 0.124 120 1.61 1.40 1.29 1.19 1.08 0.972 0.865 0.760 0.133 132 1.68 1.46 1.35 1.24 1.13 1.01 0.902 0.792 0.139 144 1.75 1.52 1.40 1.28 1.17 1.05 0.937 0.823 0.144 240 2.16 1.87 1.73 1.58 1.44 1.30 1.16 1.01 0.178 300 2.35 2.04 1.88 1.73 1.57 1.42 1.26 1.11 0.194 360 2.52 2.19 2.02 1.85 1.69 1.52 1.35 1.19 0.208 480 2.85 2.47 2.28 2.09 1.90 1.71 1.53 1.34 0.235 600 3.16 2.74 2.53 2.32 2.11 1.90 1.69 1.49 0.261 840 3.77 3.27 3.02 2.77 2.52 2.27 2.02 1.77 0.311 1440 5.14 4.46 4.12 3.78 3.44 3.10 2.76 2.42 0.424

REVISION NO.: PROCEDURE TITLE: PAGE:

SHUTDOWN COOLING ABNORMAL OPERATIONS 23 of 31 PROCEDURE NO.:

1-AOP-03.02 ST. LUCIE UNIT 1 ATTACHMENT I Estimated Time to Core Boiling (Page 5of5)

NOTE If elevation is between rows, select the lesser value.

Table 3 Additional Volume (100 cubic feet) Above Mid-Loop (Section 6.1.3 Management Directive 2)

Vessel Head Vessel Head Vessel Head Installed or Not Installed Not Installed Not Installed Elevation Additional Elevation Additional Elevation Additional Volume Volume Volume Feet 100 ft3 Feet 100 ft3 Feet 100 ft3 29.5 0.00 36.5 14.20 48.5 229.00 30.0 0.40 37.0 23.15 49.0 237.95 30.5 0.81 37.5 32.10 49.5 246.90 31.0 1.21 38.0 41.05 50.0 255.85 31.5 1.61 38.5 50.00 50.5 264.80 32.0 2.02 39.0 58.95 51.0 273.75 32.5 2.42 39.5 67.90 51.5 282.70 33.0 2.82 40.0 76.85 52.0 291.65 33.5 3.23 40.5 85.80 52.5 300.60 34.0 3.63 41.0 94.75 53.0 309.55 34.5 4.04 41.5 103.70 53.5 318.50 35.0 4.44 42.0 112.65 54.0 327.45 35.5 4.84 42.5 121.60 54.5 336.40 36.0 5.25 43.0 130.55 55.0 345.35 43.5 139.50 55.5 354.30 44.0 148.45 56.0 363.25 44.5 157.40 56.5 372.70 45.0 166.35 57.0 381.15 45.5 175.30 57.5 390.10 46.0 184.25 58.0 399.05 46.5 193.20 58.5 408.00 47.0 202.15 59.0 416.95 47.5 211.10 59.5 425.90 48.0 220.05 60.0 434.85

REVISION NO.: PROCEDURE TITLE: PAGE:

SHUTDOWN COOLING ABNORMAL OPERATIONS 18 of 37 PROCEDURE NO.:

2-AOP-03.02 ST. LUCIE UNIT 2 ATTACHMENT I Estimated Time to Core Boiling (Page 1 of 4)

I. DETERMINE estimated time to core boiling as follows (Section 6.2 Commitment 3):

A. RECORD the following information at the time SDC was lost:

Time Shutdown Cooling Lost from Section 4.2 Step 2 RCS Temperature from Section 4.2 Step 2 °F Vessel / Cavity Level ft Time since shutdown (hours)

B. RECORD time to boil at mid-loop per Table 1:

(minutes)

C. RECORD additional time to boil for a 100 ft 3 volume per Table 2:

(minutes /100 ft ).

3 D. RECORD additional 100 3 ft volumes above mid-loop per Table 3:

(100 ft

)

3 E. CALCULATE Time to Boil as follows:

+ .. . . x mm Time to boil Additional time to boil Additional 100 ft 3 volumes Time to Boil Step 1 .B Step! .C Step 1 .D

2. IF core shuffle or reload has NOT been competed, THEN CALCULATE time boiling will occur as follows:

+ =

Time SDC Lost Time Boiling Will Occur Stepl.A

REVISION NO.: PROCEDURE TITLE: PAGE:

SHUTDOWN COOLING ABNORMAL OPERATIONS 19 of 37 PROCEDURE NO.:

2-AOP-03.02 ST. LUCIE UNIT 2 ATTACHMENT I Estimated Time to Core Boiling (Page 2 of 4)

3. IF core shuffle or reload has been completed, THEN CALCULATE time boiling will occur as follows (Section 6.1 .3 Management Directive 1):

+ x(l.35) =

Time SDC Lost Time to Boil Time Boiling Will Occur Stepl.A Step i.E NOTE Temperatures between columns, select higher temperature.

Time since shutdown between rows, select the lesser time.

Table 1 Time to Boil (minutes) at Mid-Loop RCS Temperature (°F)

Shutdown Time (Hours) 60 80 90 100 110 120 130 140 200 24 11.9 10.4 9.57 8.77 7.99 7.20 6.40 5.62 0.986 48 14.6 12.7 11.7 10.7 9.76 8.79 7.83 6.87 1.20 60 15.8 13.7 12.6 11.6 10.6 9.51 8.47 7.43 1.30 72 17.0 14.7 13.6 12.5 11.3 10.2 9.09 7.98 1.40 90 18.6 16.1 14.9 13.7 12.4 11.2 9.98 8.76 1.54 102 19.7 17.0 15.7 14.4 13.1 11.8 10.5 9.25 1.62 120 21.1 18.3 16.9 15.5 14.1 12.7 11.3 9.94 1.74 132 22.0 19.1 17.6 16.2 14.7 13.3 11.8 10.4 1.82 144 22.9 19.8 18.3 16.8 15.3 13.8 12.3 10.8 1.89 240 28.2 24.5 22.6 20.7 18.9 17.0 15.1 13.3 2.33 300 30.7 26.7 24.6 22.6 20.6 18.5 16.5 14.5 2.54 360 33.0 28.6 26.4 24.3 22.1 19.9 17.7 15.5 2.73 480 37.2 32.3 29.8 27.4 24.9 22.4 20.0 17.5 3.07 600 41.3 35.9 33.1 30.4 27.6 24.9 22.2 19.5 3.41 840 49.3 42.8 39.5 36.2 33.0 29.7 26.4 23.2 4.07 1440 67.3 58.4 53.9 49.4 45.0 40.5 36.1 31.7 5.55

REVISION NO.: PROCEDURE TITLE: PAGE:

SHUTDOWN COOLING ABNORMAL OPERATIONS 20 Of 37 PROCEDURE NO.:

2-AOP-03.02 ST. LUCIE UNIT 2 ATTACHMENT I Estimated Time to Core Boiling (Page 3 of 4)

NOTE

  • Temperatures between columns, select higher temperature.
  • Time since shutdown between rows, select the lesser time.

Table 2 Additional Time To Boil (minutes) for Each 100 cuc feet of RCS Volume RCS Temperature (°F Shutdown Time (hours) 60 80 90 100 110 120 130 140 200 24 0.913 0.792 0.731 0.671 0.610 0.550 0.490 0.430 0.0754 48 1.12 0.968 0.893 0.819 0.746 0.672 0.598 0.525 0.0921 60 1.21 1.05 0.967 0.887 0.807 0.727 0.647 0.568 0.0996 72 1.30 1.12 1.04 0.952 0.866 0.781 0.695 0.610 0.107 90 1.42 1.23 1.14 1.04 0.951 0.857 0.763 0.669 0.117 102 1.50 1.30 1.20 1.10 1.00 0.905 0.805 0.707 0.124 120 1.61 1.40 1.29 1.19 1.08 0.972 0.865 0.760 0.133 132 1.68 1.46 1.35 1.24 1.13 1.01 0.902 0.792 0.139 144 1.75 1.52 1.40 1.28 1.17 1.05 0.937 0.823 0.144 240 2.16 1.87 1.73 1.58 1.44 1.30 1.16 1.01 0.178 300 2.35 2.04 1.88 1.73 1.57 1.42 1.26 1.11 0.194 360 2.52 2.19 2.02 1.85 1.69 1.52 1.35 1.19 0.208 480 2.85 2.47 2.28 2.09 1.90 1.71 1.53 1.34 0.235 600 3.16 2.74 2.53 2.32 2.11 1.90 1.69 1.49 0.261 840 3.77 3.27 3.02 2.77 2.52 2.27 2.02 1.77 0.311 1440 5.14 4.46 4.12 3.78 3.44 3.10 2.76 2.42 0.424

REVISION NO.: PROCEDURE TITLE: PAGE:

SHUTDOWN COOLING ABNORMAL OPERATIONS 21 of 37 PROCEDURE NO.:

2-AOP-03.02 ST. LUCIE UNIT 2 ATTACHMENT I Estimated Time to Core Boiling (Page 4of4)

NOTE If elevation is between rows, select the lesser value.

Table 3 Additional Volume (100 cubic feet) Above Mid-Loop Vessel Head Installed Vessel Head Not Vessel Head Not or Not Installed Installed Installed Additional Additional Additional Elevation Elevation .

Elevation Volume Volume Volume Feet 100 ft3 Feet 100 ft3 Feet 100 ft3 29.5 0.00 36.5 14.20 48.5 229.00 30 0.40 37 23.15 49 237.95 30.5 0.81 37.5 32.10 49.5 246.90 31 1.21 38 41.05 50 255.85 31.5 1.61 38.5 50.00 50.5 264.80 32 2.02 39 58.95 51 273.75 32.5 2.42 39.5 67.90 51.5 282.70 33 2.82 40 76.85 52 291.65 33.5 3.23 40.5 85.80 52.5 300.60 34 3.63 41 94.75 53 309.55 34.5 4.04 41.5 103.70 53.5 318.50 35 4.44 42 112.65 54 327.45 35.5 4.84 42.5 121.60 54.5 336.40 36 5.25 43 130.55 55 345.35 43.5 139.50 55.5 354.30 44 148.45 56 363.25 44.5 157.40 56.5 372.70 45 166.35 57 381.15 45.5 175.30 57.5 390.10 46 184.25 58 399.05 46.5 193.20 58.5 408.00 47 202.15 59 416.95 47.5 211.10 59.5 425.90 48 220.05 60 434.85

a C

3 0

C C

a aI in I

REVISION NO.: PROCEDURE TITLE: PAGE:

53 PPENDICES I FIGURES I TABLES I DATA SHEETS PROCEDURE NO.: 132 of 176 1-EOP-99 ST. LUCIE UNIT 1 FIGURE IA RCS PRESSURE TEMPERATURE (Page 1 of 1)

(Containment Temperature Less Than or Equal to 200°F)

CAUTION The RCP NPSH curve assumes instrumentation should be monito pp

[dance with tEOP99, Table 13.

2200 . An Operator Aid has been placed in the Unit I Control Room RCO desk (Any revision to this section of the procedure shall verify the validity 2000 of the Operator Aid and, if changes are necessary, notify the EOP Coordinator).

1800 1600 .

Acceptable Range z 140n 0.

. 1200 -

I I

Maximum Minimum Subcooled° Subcooled 0.

- 1000

  • 0

.E 800-

/ 1/

600 400 200 Shut

°Includcs Instrument Uncertainties 0

0 100 I I 4 200 300 400 500 600 700 800 Indicated RCS Temperature (°F)

RCS Pressure Range Required QSPDS Subcooled Margin Reading (Rep CET) 2250 psia to 1000 psia 40 to 180°F 1000 psia to 500 psia 50 to 170°F Less than 500 psia 80 to 160°F

REVISION NO.: PROCEDURE TITLE:

53 PPENDICES I FIGURES / TABLES I DATA SHEETSI PROCEDURE NO.: I 133 of 176 1-EOP-99 ST. LUCIE UNIT 1 FIGURE lB RCS PRESSURE TEMPERATURE (Page 1 of 1)

(Containment Temperature Greater Than 200°F)

CAUTION The RCP NPSH curve assumes one pump is operating in each loop. RCP instrumentation should be monitored for seal and pump performance in accordance with 1-EOP-99, Table 13.

U U,

a z

U, I

a, 0

a, N

U, U,

a, 0

a, U

I 0 100 200 300 400 500 600 700 800 Indicated RCS Temperature (°F) .001S SQl S0.,a OR:. S

REVISION NO.: PROCEDURE TITLE: PAGE:

53 PPEND ICES / FIGURES I TABLES I DATA SHEETS PROCEDURE NO.: 134 of 176 1-EOP-99 ST. LUCIE UNIT 1 FIGURE 2 SAFETY INJECTION FLOW VS. RCS PRESSURE (Page 1 of 1) 1300 1200 1100 1000 900 VI U 800 VI VI U

I 0

700 U

N I 600 VI VI w 500 0

400 300 200 100 0

0 1000 2000 3000 4000 5000 6000 Total Safety Injection Flow (gpm) P/FQP/-FOP 9FlJ2,.lncV

REVISION NO.: PROCEDURE TITLE: PAGE:

50 APPENDICES / FIGURES I TABLES / DATA PROCEDURE NO.: 126 of 171 SHEETS 2-EOP-99 ST. LUCIE UNIT 2 FIGURE IA RCS PRESSURE TEMPERATURE (Page 1 ofi)

(Containment Temperature Less Than or Equal to 200°F)

CAUTION The RCP NPSH cue assumes instrumentation should be monit

[dance with 2EOP, Tab 13.

NUtS 2400 An Operator Ard ha, been placed or hp Un) 2 Control Ronnr RCO dock (Any rcpeion 1° tb, section piPe procedure shall perrfy the validry of the Operator Aid and, if chaegeo are necencary. noldy foe EOP Coordirurtor, 2200 2000 1800 Maximum Subcooled 1600 a

a) 1400 a

C) 1200 a) a

  • 0 a) 1000 0

Minimum Subcooled 800 600 400 lpciudes Instrument Uncertarettes 200 0

0 100 200 300 400 500 600 700 800 nica1ed RCS Temperature (F) 1 prCpSQ.cc.p.har CRC RCS Pressure Range Required QSPDS Subcooled Margin Reading (Rep CET) 2250 psia to 1000 psia 40 to 180°F 1000 psia to 500 psia 50 to 170°F Less than 500 psia 80 to 160°F

REVISION NO.: PROCEDURE TITLE: PAGE:

50 APPENDICES / FIGURES I TABLES I DATA 127 of 171 PROCEDURE NO.: SHEETS 2-EOP-99 ST. LUCIE UNIT 2 FIGURE lB RCS PRESSURE TEMPERATURE (Page 1 of 1)

(Containment Temperature Greater Than 200°F)

CAUTION The RCP NPSH curve assumes one pump is operating in each loop. RCP instrumentation should be monitored for seal and pump performance in accordance with 2-EOP-99, Table 13.

2400 NOTE An Operator Aid has been placed in the Unit 2 Control Room RCO desk. (Any revoron to this section of the procedure shall verify the vakdity of the Operator Aid arid, if changes are necessary, notify I EOP Coordinator.(

2200 2000 1800

  • 1.

1600 U) ci.

0) ci 0)

U) 11) 1400 0

0)

N ci U.)

1200 U) 0)

ci

  • 0 0)

CD 1000 C.) Minimum

-o RCP NPSH Subcooled*

C 800 600 400 1ncludes Instrument Uncertainties 200 0

0 100 200 300 400 500 600 700 800 Indicated RCS Temperature (F) P.CPS EQP90g 8,Re2xf

REVISION NO.: PROCEDURE TITLE: PAGE:

50 APPENDICES I FIGURES / TABLES / DATA 128 of 171 PROCEDURE NO.: SHEETS 2-EOP-99 ST. LUCIE UNIT 2 FIGURE 2 SAFETY INJECTION FLOW VS. RCS PRESSURE (Page 1 of 1) 1200 NOTE 1100 This curve represents minimum expected SI Flow. If measured flow 1000 is less than this figure, then SI System lineup should be verified.

900 l1 a

w 800 z

a, I 700 0

I a,

N 600 Ill a, 500 a.

400 2 Full Trains

.-ln Operation 300 200 100 1 FullTrain :7 in Operation 0

0 1000 2000 3000 4000 5000 6000 Total Safety Injection Flow (gpm)

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