ML13017A371

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Initial Exam 2012-301 Final RO Written Exam
ML13017A371
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Site: Saint Lucie  NextEra Energy icon.png
Issue date: 01/14/2013
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PSL HLC 21 NRC EXAM

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ES-401 Site-Specific ROWritten Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:

Date: 12/17/12 Facility/Unit: St. Lucie Plant Region: I El II Ill [1 IV [1 Reactor Type: W El CE BW [1 GE El 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 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicants Signature Results Examination Value Points Applicants Score Points Applicants Grade Percent

PSL HLC 21 NRC EXAM Question 1 Given the following conditions:

  • The Unit 1 and Unit 2 reactors have experienced a reactor trip.

While performing EOP-01 Standard Post Trip Actions which ONE of the following annunciators, should be addressed FIRST?

(Evaluate each choice independently)

A. Unit 1: AnnunciatorA-60, 125VDC BUS lAB UV.

B. Unit 2: Annunciator G-24, 15% BYPASS LCV 9005/9006 5% FLOW.

C. Unit 1: Annunciator J-19, 1A1 RCP SEAL TROUBLE COOLING WATER FLOW LOW.

D. Unit 2: Annunciator A-43, 120V AC INVTR 2B / INSTR BUS 2MB/2MB-1 TROUBLE.

1

PSL HLC 21 NRC EXAM Question 2 Given the following:

  • 2 LEDs are lit on the Acoustic Monitor display for PORV Vi 402.
  • Pressurizer Pressure is 2000 psia.
  • Pressurizer Temperature is 636°F
  • Quench Tank Pressure is being maintained at 5 psig.

Which ONE of the following is:

1) the condition of the fluid downstream of the relief valve AND
2) the approximate temperature on TIA-1 106, Relief Valves?

A. 1) Superheated Steam

2) 245°F B. 1) Superheated Steam
2) 230°F C. 1) Wet Vapor
2) 230°F D. 1) Wet Vapor
2) 245°F PSL HLC 21 NRC EXAM Question 3 Unit 1 is conducting a heatup lAW 1-GOP-303, Reactor Plant Heatup Mode 3<1750 to Mode 3 >1750. RCS pressure is 1680 psia. Pressurizer level is 28%.

Ten minutes later a 200 gpm RCS leak develops. RCS pressure is 1580 psia and lowering rapidly. Pressurizer level is 20% and lowering. The mitigating procedure(s) for the RCS leak has been entered.

For the above conditions, SIAS should:

A. NOT be manually actuated because automatic actuation has already occurred.

B. NOT be manually actuated because conditions for manual actuation have not been reached.

C. be manually actuated because automatic actuation did not occur but should have for the stated conditions.

D. be manually actuated because signals that would result in automatic actuation are currently blocked.

PSL HLC 21 NRC EXAM Question 4 Unit 1 is performing a cooldown for a refueling outage with the following initial conditions:

  • RCS pressure is 1420 psia
  • Pressurizer level is 35%
  • Tave is 470°F Pressurizer pressure and level are now dropping rapidly and currently indicate:
  • RCS pressure is 620 psia
  • Pressurizer level is 0%
  • Tave is 468°F Which ONE of the following states the procedure(s) that will be implemented and I or referenced?

A. ONLY 1-EOP-03, LOCA.

B. ONLY 1-AOP-01.08, RCS Leakage Abnormal Operations.

C. 1-AOP-01.08, RCS Leakage Abnormal Operations. AND 1-ONP-01.01, Plant Condition 1 Steam Generator Heat Removal LTOP Not in Effect.

D. 1-AOP-01.08, RCS Leakage Abnormal Operations. AND 1-ONP-01.02, Plant Condition 2 Steam Generator Heat Removal LTOP in Effect.

PSL HLC 21 NRC EXAM Question 5 Unit 1 is operating at 100% power with the following:

TIME 1306: R-26-56, CCW radiation monitor, has just gone into alarm.

1307: Due to rising Controlled Bleedoff temperature on 1A1 RCP, 1-AOP-01.09A1, 1A1 Reactor Coolant Pump was entered.

Based on the given conditions, which ONE of the following describes:

1) The actions taken for HCV-14-11A1, Seal Cooler HX Isolation Valve?
2) Subsequent actions the crew should take?

Ensure the reactor is tripped and the 1A1 RCP is secured if:

A. 1) Place the control switch for HCV-1 4-11 Al in CLOSE.

2) EITHER Controlled Bleedoff temperature exceeds 250° F OR CCW not restored within 10 minutes.

B. 1) Place the control switch for HCV-14-11A1 in CLOSE.

2) BOTH Controlled Bleedoff temperature exceeds 250° F AND CCW not restored within 10 minutes.

C. 1) Verify HCV-14-11A1 is OPEN, if not go to OPEN RESET then AUTO.

2) EITHER Controlled Bleedoff temperature exceeds 250°F OR CCW not restored within 10 minutes.

D. 1) Verify HCV-14-1 1A1 is OPEN, if not go to OPEN RESET then AUTO.

2) BOTH Controlled Bleedoff temperature exceeds 250°F AND CCW not restored within 10 minutes.

PSL HLC 21 NRC EXAM Question 6 A RCS leak is in progress on Unit 1. Given the following at time 12:30:

  • 50% power steady state.
  • V2504, RWT to Charging pumps, is closed and racked out.
  • Pressurizer Level is 58% and steady.
  • Letdown Flow is 29 gpm.
  • Two Charging Pumps are running
  • VCT Level is 40% and lowering.
  • RCP 1A1 CBO: 1.4gpm
  • RCP 1B1 CBO: 1.4gpm
  • RCP1A2 CBO: 1.4gpm
  • RCP1B2 CBO: 1.3gpm Which ONE of the following would be the expected time that a loss of Charging would occur?

(Assume NO Operator actions are taken)

A. 12:54 - 12:55 B. 12:51 - 12:52 C. 12:49 - 12:50 D. 12:45 12:46 PSL HLC 21 NRC EXAM Question 7 Given the following conditions on Unit 1:

  • The unit is currently in Mode 6, shutdown for a refueling outage.
  • Time since reactor shutdown is 500 hrs.
  • The Reactor Head is being de-tensioned.
  • The RCS level 35 feet.
  • A Loss of Offsite Power (LOOP) has just occurred.
1) AT THIS TIME, the LPSI pumps_(1)_.
2) If the LPSI pumps did NOT start, the Time to Boil is approximately_(2)_ minutes.

A. 1) require manual re-start after the vital busses are re-energized 2)30 B. 1) auto started on EDG load sequencing 2)30 C. 1) require manual re-start after the vital busses are re-energized 2)41 D. 1) auto started on EDG load sequencing 2)41 PSL HLC 21 NRC EXAM Question 8 Unit 1 is operating at 100% power with the following conditions:

  • Pressurizer (Pzr) Pressure controller PIC-1100Y is selected for control.
  • The Pzr has been placed on recirc in preparation for a downpower.

Pzr Pressure transmitter, PT-i 1 OOY failed high.

Which ONE of the following describes the expected response of the Pressurizer Pressure control system?

Pzr Main Spray valves go fully_(1)_ and ALL Pzr Backup heaters are_(2).

A. 1)Closed

2) DE-ENERGIZED B. 1)Closed
2) ENERGIZED C. 1)Open
2) DE-ENERGIZED D. 1)Open
2) ENERGIZED PSL HLC 21 NRC EXAM Question 9 Given the following conditions on Unit 1:
  • The turbine automatically tripped due an electrical disturbance on the grid.

For this event, other than emergency boration, which ONE of the following describes the specific actions to be performed, as necessary, in EOP-O1, S PTAs?

A. 1) manually insert the CEAs at the RTGB

2) open the Rx Trip Swgr TCBs near the MG Set Control Panels B. 1) open the Rx Trip Swgr TCBs in the Cable Spreading Room
2) open the CEDM MG Set Load Center Bkrs in the Electrical Swgr Room C. 1) manually insert the CEAs at the RTGB
2) open both CEDM MG Set contactors in the Electrical Swgr Room D. 1) open the CEDM MG Set Load Center Bkrs in the Cable Spreading Room
2) open both CEDM MG Set contactors near the MG Set Control Panels PSL HLC 21 NRC EXAM Question 10 Given the following conditions on Unit 1:
  • The 1A SG NR level is 71% NR and slowly rising.
  • The lB SG NR level is 62% NR and constant.
  • Pressurizer (Pzr) level is 33% and stable.
  • RCS Thot is 448°F and stable.
  • REP CET temperature is 440°F slowly rising.

For the given conditions, HPSI throttling criteria is (1 )_.

The reasons for throttling ECCS is _(2)_.

A. 1)met

2) to maintain the RCS Inventory Control and Pressure Control Safety Functions and establish RCS Heat Removal via the SG(s)

B. 1) met

2) to maintain the RCS Inventory Control and Pressure Control Safety Functions and prevent overfilling the ruptured SG due to RCS in-leakage C. 1)NOT met
2) once throttling criteria is met, to maintain the RCS Inventory Control and Pressure Control Safety Functions and establish RCS Heat Removal via the SG(s)

D. 1) NOT met

2) once throttling criteria is met, to maintain the RCS Inventory Control and Pressure Control Safety Functions and prevent overfilling the ruptured SG due to RCS in-leakage PSL HLC 21 NRC EXAM Question 11 While performing a reactor start up on Unit 2, a Steam Line Rupture occurred on the 2B Steam Generator (SG) upstream of the Main Steam Isolation Valve.

At the onset of the event, the 2A SG depressurizes at a rate determined by the _(1)_.

Immediately after MSIS actuates, the 2A SG pressure will _(2)_.

A. 1) reactor coolant system cooldown

2) initially increase then lower due to the reactor coolant system cooldown B. 1) reactor coolant system cooldown
2) stabilize due to the rupture being isolated C. 1) size of the steam line rupture
2) initially increase then lower due to the reactor coolant system cooldown D. 1) size of the steam line rupture
2) stabilize due to the rupture being isolated PSL HLC 21 NRC EXAM Question 12 Given the following conditions:
  • A Loss of Offsite Power has occurred at the St. Lucie Plant.
  • Only the 2A EDG is operating on Unit 2 with the load on the 2A EDG at 2550 kW.
  • The 1A3 4.16 kV bus has been energized on Unit 1 by the Unit 2 2A EDG, followed by the lAB 480V Load Center.
  • The 1A Charging (Chg) pump was started on Unit 1 and the 2A Auxiliary Feedwater (AFW) pump was started on Unit 2.
  • The load on the 2A EDG is now 3310 kW.

Which of the following is the MOST ADDITIONAL equipment that is allowed to be operated lAW 1-EOP-10, Station Blackout, EOP-99, Appdx V and EOP-99 Table 11?

(Assume the load start sequence is the order listed in each selection)

A. The 1A Battery Charger and the 1A Component Cooling Water pump.

B. The 1A Battery Charger, the 1C Charging pump, 1 bank of Pressurizer Heaters and Containment Fan Cooler HVS-1A.

C. The 1A AFW pump and ONE bank of Pressurizer heaters.

D. The 1A AFW pump, Containment Fan Cooler HVS-1A and theiC Charging pump.

PSL HLC 21 NRC EXAM Question 13 Given the following conditions:

  • A Loss of Offsite Power (LOOP) has occurred on Unit 1
  • 30 minutes later, the SNPO reports that the oil pressure on the 1A EDG 16 cylinder engine is 4 psig.
  • One minute after the SNPO report, thel B EDG received a Differential Current trip alarm on the local EDG annunciator panel.

Which ONE of the following describes the status of the 1A and 1 B EDGs at this time?

1)The 1A EDG is____________

2)The1BEDGis__________

A. 1)running

2) running B. 1)tripped
2) running C. 1) tripped
2) tripped D. 1)running
2) tripped PSL HLC 21 NRC EXAM Question 14 Unit 1 is in EOP-15 Functional Recovery and is not meeting the minimum requirement for 120V Instrument AC busses.

To meet the minimum requirement for 120V Instrument AC busses energize a MINIMUM of ONE 120V Instrument bus from its respective:

A. DC bus to ensure availability of essential instrumentation used for monitoring and control of other safety functions.

B. DC bus so channel checks can be performed to monitor and verify safety functions.

C. maintenance bypass bus to ensure availability of essential instrumentation used for monitoring and control of other safety functions.

D. maintenance bypass bus so channel checks can be performed to monitor and verify safety functions.

PSL HLC 21 NRC EXAM Question 15 Unit 1 is operating at 100% power with the following:

  • Annunciators B-b, 125V DC Bus 1A Ground and A-40, 125V DC Bus lAB Ground are in alarm.
  • The lAB DC Bus is aligned to the 1A DC bus.
  • The lAB Battery Charger was placed in service on the lAB 125V DC Bus in accordance with 1-AOP-50.01, 125V DC Ground Diagnostic.
  • When the 1A to lAB cross tie breakers were opened, the lAB Battery Charger output breaker tripped.
1) When the AB Battery Charger output breaker tripped, what would place the Unit in a Tech.

Spec action statement?

2) PRIOR to separating the lAB 125V DC Bus from the 1A 125V DC bus, what indication on thelAB Battery Charger could be used to diagnose an operational problem with the battery charger?

A. 1) lAB Battery Charger.

2) The lAB Battery Charger ground light indications would be dim while performing a ground test.

B. 1)AFWPP1C.

2) The lAB Battery Charger ground light indications would be dim while performing a ground test.

C. 1) lAB Battery Charger.

2) Failure of amps to rise on the lAB Battery Charger ammeter local indication after the 1 AB Battery Charger output breaker was closed onto the lAB 1 25V DC bus.

D. l)AFWPP1C.

2) Failure of amps to rise on the lAB Battery Charger ammeter local indication after the lAB Battery Charger output breaker was closed onto the lAB 125V DC bus.

PSL HLC 21 NRC EXAM Question 16 Unit 2 is operating at 100% power when the following alarm occurred:

2A CCW HX lOW FLOW LOW S-3 Which ONE of the following could be the cause of the low flow condition?

A. A tube rupture in the Component Cooling Water Heat Exchanger has occurred.

B. HCV-21-7A, Component Cooling Water HX Strainer Debris Discharge Isolation valve (backwash outlet) has failed open.

C. The instrument air line for TCV-14-4A, A CCW HX Outlet valve has become disconnected.

D. While backwashing the A Turbine Cooling Water Heat Exchanger strainer, SS-21-4A, a rupture occurred at the Intake Cooling Water inlet to the strainer.

PSL HLC 21 NRC EXAM Question 17 Given the following conditions on Unit 1:

  • A Loss of Offsite Power (LOOP) has occurred concurrent with a Loss of Coolant Accident (LOCA).
  • 1-EOP-99, Appdendix H, Operation of the lA/lB Instrument Air Compressors has been performed and the 1A and I B Instrument Air Compressors are running.
  • SIAS has just occurred.

Which ONE of the following describes the response of the Emergency Instrument Air Compressors?

The lAand lB Instrument Air Compressors A. will auto start when their designated Emergency Diesel Generator load block times out after load shed.

B. will auto start when the 1A6/1B6 MCC non-essential load breakers are reset C. can be manually re-started after the start circuit is reset from the control room D. can be manually re-started after the start circuit is reset locally PSL HLC 21 NRC EXAM Question 18 Given the following conditions:

  • AFAS and MSIS actuation has occurred.

Which ONE of the following describes ALL the required actions to restore Main Feedwater flow?

A. On Unit 2, reset MSIS.

B. On Unit 1, override AFAS to the MFIVs C. On Unit 2, override AFAS to the MFIVs AND reset MSIS.

D. On Unit 1, override AFAS to the MFIVs AND reset MSIS.

PSL HLC 21 NRC EXAM Question 19 Unit 1 is performing an up power with the following:

  • The Unit Supervisor has directed the RCO to withdraw Group 7 Control Element Assemblies (CEAs) in manual sequential from 124 withdrawn to 127 withdrawn for the power ascension.
  • When Group 7 CEAs reached 127 withdrawn, the RCO released the CEA manual control switch but the Group 7 CEAs continued to move outward.

Assuming NO operator actions, which ONE of the following describes the CEA Control Motion Interlock that will stop CEA motion?

Group 7 CEA rod motion will be automatically stopped by the_(1) motion interlock generated from the _(2)_.

A. 1) Upper Group Stop

2) CEA reed switch position transmitters B. 1) Upper Group Stop
2) Distributed Control System C. 1) CEA Position Deviation
2) Distributed Control System D. 1) CEA Position Deviation
2) CEA reed switch position transmitters PSL HLC 21 NRC EXAM Question 20 Unit 2 is operating at 60% power.

Condenser backpressure is 4.5 hg absolute and slowly rising.

The NPO is directed to perform local actions lAW 2-AOP-1 2.01, Loss of Condenser Vacuum Which of the following NPO actions could result in Condenser backpressure RISING?

A. While placing a Hogging Ejector in service by adjusting steam pressure to 200 psig, intermittent steam flow from the Hogging ejector exhaust is observed.

B. Throttling the Turbine Seal PCV bypass valves to a value ofi .5 to 5.0 psig.

C. Increasing condensate flow to the Condenser vacuum breakers.

D. Adjusting PlC-i 2-29, SJAE Steam Pressure to 400 psig steam pressure on the A and B Steam Jet Air Ejectors.

PSL HLC 21 NRC EXAM Question 21 A Waste gas release is in progress lAW OP 1-0530021, Controlled Gaseous Batch Release to Atmosphere.

1) The Blue Fail light on Channel 42 Gaseous Waste Radiation Monitor should remain to be considered operable.
2) The EARLIEST the gas release is required to be manually terminated?

A. 1) de-energized

2) the Plant Vent Radiation Monitor trending up.

B. 1) de-energized

2) a High Alarm condition is received on an Plant Vent Radiation Monitor Channel.

C. 1)energized

2) the Plant Vent Radiation Monitor trending up.

D. 1)energized

2) a High Alarm condition is received on an Plant Vent Radiation Monitor Channel.

PSL HLC 21 NRC EXAM Question 22 Which ONE of the following describes:

1 r

1) The type of detector that is used for thContainment Isolation Area Radiation Monitors (CIS)

AND

2) The operational implications associated with the detector limitation(s)?

A. 1)GM-tube.

2) In low radiation fields, the detector output signal is weak thereby requiring amplification before being sent to the ratemeter I alarm electronic circuit.

B. 1) Ion Chamber.

2) In low radiation fields, the detector output signal is weak thereby requiring amplification before being sent to the ratemeter I alarm electronic circuit.

C. 1)GM-tube.

2) A weak ionizing event produces the same output as a much stronger ionizing event so if the detector is in a strong radiation field, it will become saturated.

D. 1) Ion Chamber.

2) A weak ionizing event produces the same output as a much stronger ionizing event so if the detector is in a strong radiation field, it will become saturated.

- 22 -

PSL HLC 21 NRC EXAM Question 23 A Fire Watch patrol has been assigned to monitor a specific fire zone once per hour on Unit 2.

This action is being done in order to comply with compensatory actions in accordance with AP 1800022, Fire Protection Plan.

Assume no other actions have been taken.

Which ONE of the following describes the Fire Protection Feature(s) that is (are) inoperable?

The is inoperable.

A. fixed water spray system for the 2A and 2B Startup Transformers B. pre-action sprinkler system for the Cable Spread room (43.0 elev. RAB)

C. fire door that separates the A and B Electrical Switchgear rooms (43.0 elev. RAB)

D. minimum required amount of fire detection instrumentation for the Fuel Handling Building New Fuel Area PSL HLC 21 NRC EXAM Question 24 Given the following:

  • Unit 2 has evacuated the Control Room due to the presence of toxic fumes
  • All Operator actions in the Control Room were performed prior to evacuation.
  • Critical actions from Appendix A through D of 2-ONP-1 00.02 Control Room Inaccessibility have been completed
  • RCO A is maintaining Hot Standby conditions at the Remote Shutdown Panel Which ONE of the following describes how RCS pressure is controlled and how subcooling is monitored?

Control pressurizer pressure between 1800 and 1850 psia by operating Auxiliary Spray valves along with (1)

Determine subcooling margin using 2-ONP-1 00.02 Control Room Inaccessibility, Figure 1 using Reactor Coolant System (2) and Pressurizer pressure.

A. 1) Proportional and backup heaters

2) T-hot B. 1) backup heaters ONLY
2) T-cold + 50°F C. 1) Proportional and backup heaters 2)T-cold + 50°F D. 1) backup heaters ONLY
2) T-hot PSL HLC 21 NRC EXAM Question 25 A Large Break LOCA has occurred on Unit 1. Onsite and offsite doses are higher than expected. It is suspected that a breach of Containment has occurred.

Containment pressure is currently 35 psig.

Which ONE of the following would have the LARGEST effect on reducing the Containment leak rate?

Reduce:

A. the energy release into the Containment by cooling down the RCS at maximum allowable rate by maximizing ECCS flow.

B. the energy release into the Containment by cooling down the RCS at maximum allowable rate by maximizing SG steaming and feeding.

C. Containment pressure by ensuring all available Hydrogen Purge and Containment Coolers are operating.

D. Containment temperature by ensuring all available Containment coolers and Containment Spray pumps are operating.

PSL HLC 21 NRC EXAM Question 26 Which ONE of the following Unit 1 Letdown Monitor radiation trends would be indicative of fuel failure?

A. ONLY Iodine increases and remains significantly above prior levels during steady state operation.

B. ONLY Iodine increases and remains significantly above prior levels during a plant load change.

C. Iodine remains constant while gross activity increases during steady state operation.

D. Iodine AND gross activity increase during a plant load change.

PSL HLC 21 NRC EXAM Question 27 Unit I is in 1-EOP-15, Functional Recovery due to Feedwater problems. Which ONE of the following states when Once Through Cooling (OTC) is to be initiated?

A. TCOLD rises 5°F with all ADVs fully open.

B. THQ-I- rises 5°F with all ADVs fully open.

C. The 1A wide range SG level indicates 14% and the lB wide range SG level indicates 16%.

D. Both SG wide range levels indicate 15% with MAXIMUM available feedwater flow of 150 gpm.

PSL HLC 21 NRC EXAM Question 28 Given the following on Unit 2:

  • Unit was at 100% power for 210 days when a trip occurred.
  • Unit is offline for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with RCS at normal operating temperature and pressure.
  • AFWflowtoeachSGisllogpm.

A loss of CCW occurs requiring all RCPs to be stopped. Ten (10) minutes after stopping the RCPs, which of the following would be expected? (assume NO Operator actions)

SG pressure:

A. lowers. AFW flow remains the same.

B. rises. AFW flow lowers.

C. lowers. AFW flow rises.

D. rises. AFW flow remains the same.

PSL HLC 21 NRC EXAM Question 29 Unit 2 is in Mode 3 at 1810 psia and 502F Tave. with three RCPs operating.

  • The 2A2 RCP has just been started.

Which of the following would require an IMMEDIATE stopping of the 2A2 RCP?

A. Upper seal cavity pressure indicates 600 psia.

B. Lower seal cavity temperature indicates 305°F.

C. Controlled bleedoff flow indicates 2 gpm.

D. RCS pressure drops 30 psia below the minimum RCS pressure for RCP operation.

PSL HLC 21 NRC EXAM Question 30 Unit 1 is operating at 100% power.

Which ONE of the following conditions could result in the Charging Pump(s) not meeting the design Net Positive Suction Head?

(assume NO Operator actions)

Volume Control Tank:

A. pressure lowers tolO psig.

B. level lowers to 10% level.

C. level transmitter LT2227 failing LOW.

D. level transmitter LT2227 failing HIGH.

PSL HLC 21 NRC EXAM Question 31 Unit 1 has tripped due to a LOOP. Both Emergency Diesel Generators (EDG) started and loaded on their respective busses, however the feeder breaker to the 1 B5 MCC tripped opened when the 1 B EDG output breaker closed.

On the trip three CEAs failed to fully insert.

Which ONE of the following states the available emergency boration flowpath?

Charging pump suction aligned from the:

A. RWT isolation, V2504.

B. BAMTs through the Gravity feed isolations, V2508 and V2509.

C. discharge of A OR B BAM pump through the emergency borate valve MV-2514.

D. discharge of ONLY the A BAM pump through the emergency borate valve MV-2514.

PSL HLC 21 NRC EXAM Question 32 Unit 1 has just placed SDC in service and is cooling down at 30°F / hour.

A loss of Instrument air occurs and air pressure indicates 20 psig.

Which ONE of the following states the effect on RCS temperature on the loss of instrument air?

(assuming NO Operator actions)

RCS temperature will:

A. lower due to TCV-14-4A, 1A CCW HX Outlet and TCV-14-4B, lB CCW HX Outlet going full OPEN.

B. lower due to HCV-14-3A, CCW to Shutdown HX IA and HCV-14-3B, CCW to Shutdown HX 1 B going full OPEN.

C. rise due to FCV-3306, SDC Return Flow, going full CLOSED.

D. rise due to HCV-3657, SDC TEMP Control, going full CLOSED.

PSL HLC 21 NRC EXAM Question 33 Unit 1 is on Shutdown cooling with the following conditions:

  • RCS temperature is 105°F
  • RCS level is 41 feet.
  • The IA LPSI pump is aligned for SDC and the lB LPSI pump is in standby.
  • The RCS is being drained to the 34 foot level via the 1A LPSI pump recirc, V3204, at a rate of 50 gpm.
  • SDC flow is 3450 gpm.

It is desired to increase the drain down rate to 100 gpm.

Which ONE of the following states the actions needed to raise the drain down flow rate, to drain from 41 feet to 34 feet, and the bases for these actions?

1) Throttle open V3204, 1 A LPSI pump recirc. to the RWT, and reduce SDC flow to no more than:
2) If Amps on the 1A LPSI pump start swinging, what is the FIRST Immediate Operator Action lAW 1-AOP-03.02, Shutdown Cooling Abnormal Operations A. 1)3160 gpm. This is the minimum SDC flow that will limit the RCS from heating up.
2) Stop the 1A LPSI pump.

B. 1) 3400 gpm. This is the minimum SDC flow that will limit the RCS from heating up.

2) Stop the 1A LPSI pump.

C. 1) 3160 gpm. This is the maximum LPSI flow requirements to prevent suction line voiding and possible water hammer.

2) Throttle closed the LPSI header isolation valves.

D. 1)3400 gpm. This is the maximum LPSI flow requirements to prevent suction line voiding and possible water hammer.

2) Throttle closed the LPSI header isolation valves.

PSL HLC 21 NRC EXAM Question 34 Unit 2 has tripped from 100% power due to a Main Feedwater problem. The following conditions exist:

  • Pressurizer level is 22% and slowly lowering.
  • RCS TAVE is 530° F and stable.
  • 2A and 2B Charging pumps are running with Charging header pressure indicating 420 psia.
  • Reactor cavity leakage recorder is off scale high.

Which of the following states the Operator actions and the appropriate procedure implementation?

A. Start the 2C Charging pump in addition to the 2A and 2B Charging pumps to restore Pressurizer level to 27-35%. Implement 2-AOP-01 .06, Excessive RCS Leakage.

B. Start the 2C Charging pump in addition to the 2A and 2B Charging pumps and align to the A HPSI Header lAW 2-AOP-02.03, Charging and Letdown Attachment 2, Alternate Charging Flow Path Through the A HPSI Header.

C. Stop the 2A and 2B Charging pumps and align the 2A or 2B Charging pump to the A HPSI header lAW 2-AOP-02.03, Charging and Letdown Attachment 2, Alternate Charging Flow Path Through the A HPSI Header.

D. Stop the 2A and 2B Charging pumps and start the 2C Charging pump to restore Pressurizer level to 27-35%. Implement 2-AOP-01 .06, Excessive RCS Leakage.

- 34 -

PSL HLC 21 NRC EXAM Question 35 Unit 1 is implementing 1-EOP-02, Reactor Trip Recovery due to an inadvertent SIAS.

Thirty (30) minutes into the event the Quench Tank High level alarm is received.

Which ONE of the following states the most likely reason for the Quench Tank high level alarm?

A. Operator actions have aligned the alternate RCP bleedoff flow.

B. CIAS has aligned the alternate RCP bleedoff flow.

C. Pressurizer relief or Safety valve leakage.

D. Quench Tank cooling heat exchanger has developed a leak.

PSL HLC 21 NRC EXAM Question 36 On Unit 1, which ONE of the following Quench Tank conditions could result is increasing radioactivity to the Containment atmosphere during a Quench Tank design event?

Quench Tank:

A. pressure is allowed to lower to 0.9 psig.

B. temperature is allowed to rise to 117°F.

C. temperature is allowed to lower to 110°F.

D. level is allowed to lower to 38%.

PSL HLC 21 NRC EXAM Question 37 Given the following conditions:

  • After the N header automatically isolated, the operators manually tripped the reactor and turbine
  • The N header leak has been isolated
  • LA-.1O, CCW SURGE TANK COMPARTMENT A LEVEL LOW, locked in
  • LB-b, COW SURGE TANK LEVEL HIGH/COMPARTMENT B LEVEL LOW, locked in
  • Chemistry has requested that cooling be restored to the sample heat exchangers to allow S/G samples to be taken Based on the above conditions, which ONE of the following describes the MINIMUM action(s)/conditions that must occur to open the CCW N header isolation valves?

The CCW N header valves:

A. will open if the control switches are placed in closed/override and then placed in open.

B. can be locally opened by failing the air supply to the valves.

C. will open if the control switches are placed in the open position.

D. cannot be opened until level is restored to the surge tank.

PSL HLC 21 NRC EXAM Question 38 On Unit 2, which ONE of the following states how the Pressurizer PORV open signal is achieved when the PORV selector switch is in:

1) NORMAL RANGE
2) LTOP Directly from the:

A. 1) RPS high pressure trip bistables.

2) Pressurizer pressure instruments PT-i 103, 1104 B. 1) Pressurizer pressure instruments PT-i 102 A through D
2) Pressurizer pressure instruments PT-i 102 A through D C. 1) RPS high pressure trip bistables.
2) Pressurizer pressure instruments PT-i i 02 A through D D. 1) Pressurizer pressure instruments PT-i 102 A through D
2) Pressurizer pressure instruments PT-i 103, 1104 PSL HLC 21 NRC EXAM Question 39 Unit 1 is at 100% power with the following:

The DC power supply to ONE RPS K Relay has failed (de-energized).

Which ONE of the following states:

1) The number of TCBs that has opened?
2) The procedure that CAN be used to close the TCBs when the fault is corrected?

A. 1) 2 Trip Circuit Breakers (TCBs open)

2) 1-AOP-49.02, 120V INSTRUMENT AC SYSTEM (CLASS 1E)

B. 1) 2 Trip Circuit Breakers (TCBs open)

2) 1-AOP-50.07A(B) LOSS OF OR DEGRADED SAFETY RELATED DC BUS 1A (1B)

C. 1) 4 Trip Circuit Breakers (TCBs open)

2) 1-AOP-49.02, 120V INSTRUMENT AC SYSTEM (CLASS 1E)

D. 1) 4 Trip Circuit Breakers (TCBs open)

2) 1-AOP-50.07A(B) LOSS OF OR DEGRADED SAFETY RELATED DC BUS 1A (1B)

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PSL HLC 21 NRC EXAM Question 40 Unit 1 is at 100% power when the following SINGLE annunciator is received:

ENGINEERED SAFEGUARDS ATI FAULT R-10 Upon observation of the ESFAS panel, it is observed the Containment Pressure individual ATI Test Panel light is NOT illuminating during the test sequence.

Which ONE of the following states:

1) the significance of the observation.
2) the actuation logic for SIAS on high Containment pressure.

A. 1) The Containment pressure bistable did not trip at 5% ABOVE setpoint during the testing sequence.

2) SIAS on high Containment pressure is 1/3 logic B. 1) The Containment pressure bistable did not trip at 5% ABOVE setpoint during the testing sequence.
2) SIAS on high Containment pressure is 2/4 logic C. 1) The Containment pressure bistable tripped at 5% BELOW setpoint during the testing sequence.
2) SIAS on high Containment pressure is 1/3 logic D. 1) The Containment pressure bistable tripped at 5% BELOW setpoint during the testing sequence.
2) SIAS on high Containment pressure is 2/4 logic PSL HLC 21 NRC EXAM Question 41 Unit 2 has experienced a LOCA. RCS pressure is 1580 psia and the crew has entered 2-EOP-03, LOCA.

On the trip, feeder breakers to MCC 2B9 tripped.

Which ONE of the following states the RUNNING Containment Fan Coolers?

A. C and D Containment Fan Coolers.

B. A and C Containment Fan Coolers.

C. A and B Containment Fan Coolers.

D. B and D Containment Fan Coolers.

PSL HLC 21 NRC EXAM Question42 Unit 1 is at 100% power with CEDM cooling fan HVE -21B out of service and HVE-21A running.

HVE-21A trips and cannot be started.

Which ONE of the following states the time to restore a CEDM cooling fan and the basis for this time?

Restore a CEDM cooling fan within:

A. 45 minutes to limit the possibility of dropping CEAs due to overheated CEDM coils.

B. 45 minutes to prevent the reactor vessel support structure from exceeding its design limits.

C. 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to limit the possibility of dropping CEAs due to overheated CEDM coils.

D. 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to prevent the reactor vessel support structure from exceeding its design limits.

PSL HLC 21 NRC EXAM Question 43 Unit 2 has experienced a large break Loss of Coolant accident with the following conditions:

  • Two (2) Containment fan coolers are operating.
  • Containment temperature is 245°F.
  • Containment pressure is 22 psig.

Which of the following MINIMUM actions are necessary to meet the Containment Temperature and Pressure control safety function?

A. Start an additional Containment Spray pump and ensure Spray flow is 2550 gpm or greater.

B. Increase the flow rate on the running Containment Spray pump to 2550 gpm or greater.

C. Start one additional Containment Cooler.

D. Start two additional Containment Coolers.

PSL HLC 21 NRC EXAM Question 44 During start of the 1[2]C Auxiliary Feedwater pump for a surveillance run the following annunciator was received and locked in:

1 [2]C AFW Pump Turbine Failure/Trip!

SS Isol G-46 The Red and Green lights for MV-08-3, 1 [2] C AFW Pump Trip and Throttle valve are both illuminated.

This is an indication of on Unit A. Electrical, Unit 1.

B. Mechanical, Unit 1.

C. Electrical, Unit 2.

D. Mechanical, Unit 2.

PSL HLC 21 NRC EXAM Question 45 Unit 2 is in Mode 3 with the following:

  • A condenser backpressure pressure transmitter (PS-i 0-9) briefly spiked to 14 Hg absolute then returned to 5.7 Hg absolute.

SBCS valves:

A. close until the SBCS PERMISSIVE SWITCH is taken to MANUAL.

B. close until the SBCS VACUUM INTERLOCK PUSHBUTTON is depressed.

C. close and automatically reopen as backpressure returned to 5.7 Hg absolute.

D. remained controlling in Automatic due to the low vacuum setpoint NOT reached.

PSL HLC 21 NRC EXAM Question 46 On Unit 1, which ONE of the following will terminate Main Feedwater to the Steam Generators?

A trip from 100% power and:

A. Containment pressure rises to 4 psig 5 minutes after the trip.

B. Steam Generator levels lower to 19% NR 6 minutes after the trip.

C. Steam Generator levels rise to 90% NR 5 minutes after the trip.

D. A complete loss of Nitrogen supply pressure to the Main Feedwater Isolation valves.

PSL HLC 21 NRC EXAM Question 47 Given the following conditions:

  • Unit 2 is in Mode 3 maintaining Hot Standby conditions
  • The following annunciator has just been received on Unit 2:

CST LEVEL LOW LA-i 3 The alarm is in due to the Unit 2 Condensate Storage Tank (CST) level approaching the MINIMUM _(1) level.

One of the design bases for the Unit 2 CST is to have additional capacity available to supply makeup to Unit 1 in the event that a _(2)_ damages the Unit 1 CST.

A. 1)tech spec

2) vertical tornado missile B. 1) usable water
2) vertical tornado missile C. 1)tech spec
2) seismic category I earthquake D. 1) usable water
2) seismic category I earthquake PSL HLC 21 NRC EXAM Question 48 Unit 1 is operating at 100% power when the following alarm is received:

4KV SWGR 1A3 ti CURRENT TRIP B-i 4 Which ONE of the following states the status of the iA Diesel Generator?

The 1A Diesel Generator:

A. has started and sequenced loads that were previously running on the 1A3 4.16 KV bus.

B. has started but does NOT load on the 4.16 KV bus until the A Current relay is reset.

C. does NOT start until the A Current relay is reset.

D. does NOT start until the 1A2 to 1A3 4.16 KV tie breaker is Green Flagged.

PSL HLC 21 NRC EXAM Question 49 Unit 2 was at 100% power when a loss of the 2A DC bus occurs.

Which ONE of the following indicates the AFW availability?

(assume AB DC bus aligned to the A side)

1) The 2B AFW pump to the:
2) the 2C AFW pump steam from the:

A. 1) 2A Steam Generator.

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

B. 1) 2A Steam Generator.

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

C. 1) 2B Steam Generator.

2) 2A Steam Generator and feeding the 2A Steam Generator.

D. 1) 2B Steam Generator.

2) 2B Steam Generator and feeding the 2B Steam Generator.

PSL HLC 21 NRC EXAM Question 50 Unit 2 has experienced a LOOP. Both Emergency Diesel Generators (EDGs) are loaded on their respective busses.

Which ONE of the following EDG parameters can be manually controlled from the EDG controls on the RTGB for this condition AND which load is NOT shed for the above condition?

A. Voltage, 2A and 2B CCW pumps B. Voltage, 2A and 2B HPSI pumps C. Frequency, 2A and 2B CCW pumps D. Frequency, 2A and 2B HPSI pumps PSL HLC 21 NRC EXAM Question 51 Unit us at 100% power with the following conditions:

  • The 1A Emergency Diesel Generator air dryers have been issued a clearance which included taking the air dryer switch to the OFF position.
  • Air pressure on all the air receivers is 175 psig.

An inadvertent Channel A CIAS occurs.

Which ONE of the following states the status of the:

1) 1A Emergency Diesel Generator (EDG)
2) 1A Diesel Generator Air Start system?

A. 1) The IA EDG is NOT running.

2) The electric driven air compressor IS running.

B. 1)The IAEDG IS running.

2) The electric driven air compressor IS running.

C. 1) The 1A EDG is NOT running.

2) The electric driven air compressor is NOT running.

D. 1) The 1A EDG IS running.

2) The electric driven air compressor is NOT running.

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PSL HLC 21 NRC EXAM Question 52 A steam generator tube leak of about 50 gpm has occurred on Unit 1. The crew is performing a downpower and is at 90% power. Steam Generator Blowdown Monitor PT 6, CHNL 44 is in HIGH alarm.

As the downpower reaches 60%, the leak increases to 70 gpm.

Which ONE of the following states the expected indication of the Steam Generator Blowdown indication PT 6, CHNL 44 for this increased leak rate?

Blowdown activity will:

A. NOT change due to the monitored sample being in a stagnant fluid.

B. NOT change at the lower power level because of the higher leak rate.

C. INCREASE due to the increased leak rate.

D. DECREASE due to the lower power level.

PSL HLC 21 NRC EXAM Question 53 Unit 1 is at 100% power with the CCW HX, ICW strainers in an automatic backwash cycle.

Unit 1 then tripped due to a large break loss of coolant accident (LOCA).

Shortly after SIAS actuation the below alarm annunciated.

A ICW HDR MV-21 -3 OVRLD I SIAS FAIL TO CLOSE E-22

1) What position would HCV-21-7A and HCV-21-7B, Debris Disch. Isol. indicate on RTGB 102?
2) What affect could the above alarm have?

A. 1)Closed.

2) Reduction of ICW flow / heat removal capability through the CCW heat exchanger.

B. 1)Closed

2) ICW header flow exceeding design basis C. 1)Open
2) Reduction of ICW flow / heat removal capability through the CCW heat exchanger.

D. 1)Open

2) ICW header flow exceeding design basis PSL HLC 21 NRC EXAM Question 54 Unit I is at 100% power with the 1 C Instrument Air compressor in RUN and the 1 D Instrument air compressor is in AUTO.

Which of the following conditions requires a MANUAL RESET and MANUAL START of the standby 1 D Instrument Air Compressor?

The 1 C Instrument Air Compressor tripped on:

A. Motor overload.

B. High temperature.

C. Low oil pressure.

D. High Instrument Air pressure.

PSL HLC 21 NRC EXAM Question 55 Which ONE of the following would result in a VIOLATION of Containment Integrity while the Unit is in Mode 1?

A. Stroke testing the Containment Vacuum Reliefs.

B. A Containment Isolation valve stroke time is in the Alert range.

C. A motor operated Containment Isolation valve will NOT fully close with the motor but is closed manually and is de-energized.

D. Opening a locked manual Containment Isolation valve in the penetration room and stationing an operator in the Control Room to close this valve in the event of an accident.

PSL HLC 21 NRC EXAM Question 56 Unit 2 is experiencing a Large Break Loss of Coolant accident.

Which ONE of the following is the MOST DEFINITIVE system used to determine a possible superheat condition in the core and how can this parameter be monitored from the RTGB?

A. Heated Junction Thermocouples (HJTCs) by selecting RCS on QSPDS.

B. Core Exit Thermocouples (CETs) by selecting IN CORE on ERDADS.

C. Heated Junction Thermocouples (HJTCs) by selecting INCORE on ERDADS.

D. Core Exit Thermocouples (CETs) by selecting RCS on QSPDS.

PSL HLC 21 NRC EXAM Question 57 Unit us in Mode 5 with a Containment Purge in progress.

Channel MD CIAS radiation monitor fails high.

Which ONE of the following states the status of the Containment Purge system and Containment evacuation alarm?

Containment Purge:

A. isolates and the Containment evacuation alarm actuates.

B. continues to operate and the Containment evacuation alarm actuates.

C. isolates and the Containment evacuation alarm remains silent.

D. continues to operate and the Containment evacuation alarm remains silent.

PSL HLC 21 NRC EXAM Question 58 St. Lucie plant has experienced a catastrophic natural event that has resulted in Unit 2 Spent fuel pool structure damage with an estimated leak rate of 400 gpm.

2-AOP-04.01, Fuel Pool Cooling System has been entered.

Which ONE of the following states the significance of the leak rate AND the Fuel Pool makeup source that would be used to compensate for the above leakage? (assume Spent Fuel Pool is accessible)

A. The above leak rate is WITHIN the normal makeup flow rate. The makeup flowpath will be from the Fuel Pool purification system with suction from the RWT.

B. The above leak rate is WITHIN the normal makeup flow rate. Primary Water pumps with suction from the Primary Water tank.

C. The above leak rate is OUTSIDE the normal makeup flow rate. Portable Fire pump with suction from the City Water Storage Tanks.

D. The above leak rate is OUTSIDE the normal makeup flow rate. Intake Cooling water from the discharge of the Intake Cooling Water header.

PSL HLC 21 NRC EXAM Question 59 Unit 1 is at 90% power, increasing power to 100% at 3MWe I mm. The 1A Main Feedwater Regulating valve (HPFRV) stops responding to the power increase and has failed as is.

Assuming NO Operator actions and the power increase progresses, which of the following states the 1A SG level response?

1A SG level will initially:

A. lower from setpoint until the Low Power FRV opens to return SC level to setpoint.

B. lower from setpoint and continue to lower resulting in 1A SG level low alarm.

C. lower from setpoint until the 100% FW Bypass initially opens to control SG level at setpoint.

D. remain at setpoint with the Low Power FRV controlling SG level.

PSL HLC 21 NRC EXAM Question 60 Unit 2 is at 12% power and has just synchronized the Main Generator to the grid. The Generator picked up 40 MWe and then tripped 5 seconds later.

Which ONE of the following states the expected plant indication?

A. Reactor power indicates 12% with SBCS opening to control temperature.

B. Reactor power indicates 12% with ADVs opening to control temperature.

C. Trip Circuit Breaker (TCB) lights indicate GREEN with ADVs closing to control temperature.

D. Trip Circuit Breaker (TCB) lights indicate GREEN with SBCS closing to control temperature.

PSL HLC 21 NRC EXAM Question 61 Unit I is at 2% power performing a plant startup with the following:

  • The Hogging Ejectors have just been placed in service to initially draw a vacuum in the condenser.

If a Steam Generator tube leak developed, which ONE of the following states the secondary radiation monitor(s) that would indicate the Steam Generator tube leakage?

A. ONLY Main Steam Line monitors and SG Blowdown monitors.

B. ONLY SG Blowdown monitors.

C. ONLY SJAE monitor and Main Steam Line monitors.

D. SJAE, Main Steam Line monitors and SG Blowdown monitors.

PSL HLC 21 NRC EXAM Question 62 Unit 1 is at 40% power with the following conditions:

  • lAand 1C Condensate pump running Condensate header recirc. valve, FCV-12-1 opens to a flow of 10,000 gpm.

Which of the following would be the FIRST procedure to enter?

A. 1-AOP-09.04, Feedwater, Condensate, and Heater Drain Pump Abnormal Operations B. 1-AOP-12.01, Loss of Condenser Vacuum C. 1-AOP-22.01, Rapid Downpower D. 1-EOP-01, Standard Post Trip Actions PSL HLC 21 NRC EXAM Question 63 On Unit 1, Liquid Waste Radiation Monitor R-6627 has been declared out of service.

lAW 1-NOP-06.O1, Controlled Liquid Release to the Circulating Water Discharge, which ONE of the following states the MINIMUM required actions to perform a controlled liquid release to the Circulating Water Discharge?

A. An independent verification of the Initial valve alignment AND two independent release rate calculations.

B. An independent verification of the Initial valve alignment AND two independent radioactivity analysis of the tank to be released.

C. Two independent radioactivity analysis of the tank to be released AND two independent release rate calculations.

D. An independent verification of the Initial valve alignment AND two independent radioactivity analysis of the tank to be released AND two independent release rate calculations.

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PSL HLC 21 NRC EXAM Question 64 Unit 2 is at 100% power, steady state.

  • An Equipment Clearance order is being executed to remove 2B Intake Cooling Water (ICW) pump from service for a motor inspection.
  • It is desired to align 20 ICW pump to replace 2B.

Which ONE of the following describes the MINIMUM electrical alignment that will meet the requirements of the Technical Specifications LCO for the 2C ICW pump?

A. ONLY the 2AB 4.16 KV bus aligned to the B 4.16 KV side.

B. ONLY the 2AB 4.16 KV AND 2AB DC bus aligned to the B 4.16 KV and B DC side.

C. The 2AB 4.16 KV bus aligned to the B 4.16 KV side and the 2AB 480 V bus and the 2AB DC bus aligned to either the B side OR the A side.

D. The 2AB 4.16 KV bus, 2AB 480 V bus AND the 2AB DC bus aligned to the B side.

PSL HLC 21 NRC EXAM Question 65 Unit I is at 100% power when the following alarm is received:

INST AIR PRESS HIGH I LOW F-5 The crew has implemented 1-AOP-1 8.01, Instrument Air Malfunction.

The Instrument air pressure indicates 99 psig and slowly lowering. The 1 C Instrument air compressor has tripped and the 1 D compressor is out of service on a clearance.

Which ONE of the following Operator actions, as directed in 1-AOP-18.01, would be the FIRST step to mitigate the lowering of Instrument air pressure?

A. Open the Unit to Unit Instrument air cross-ties.

B. Start the lAand or lB Instrument air compressor(s).

C. Open the Station air to Instrument air crosstie.

D. Swap air dryers, place the standby air dryer in service.

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PSL HLC 21 NRC EXAM Question 66 The plant has been at 100% power for 210 days. You have been on vacation for 10 days. Upon return to work you will be the Licensed RO OATC (Operator At The Controls). ONE other Licensed RO is assigned to your shift and he is in the Operator At the Controls Area (QACA).

Three RCO Trainees have been assigned to your shift.

Which ONE of the following states the review of Station Log requirement AND the allowable number of Trainees in the OACA?

A. Review the Station Logs back to 10 days ago. ONE (1) Trainee in the OACA.

B. Review the Station Logs back to 3 days ago. ONE (1) Trainee in the QACA C. Review the Station Logs back to 10 days ago. TWO (2) Trainees in the QACA.

D. Review the Station Logs back to 3 days ago. TWO (2) Trainees in the OACA.

PSL HLC 21 NRC EXAM Question 67 Which ONE of the following does NOT require a plant wide announcement over the paging system as defined in Ops policy OPS-106, Communication:

A. Performing a resin transfer in the RAB.

B. Latching the turbine prior to performing a Turbine Startup.

C. Reducing power from 100% to 99.5% for Tave coast down at end of core life.

D. Performing the Control Element Assembly Full Length periodic surveillance.

PSL HLC 21 NRC EXAM Question 68 Unit 1 is coming out of a refueling outage. Which ONE of the following is the MINIMUM Plant condition (i.e. lowest Mode) that would require implementation of ADM-01 .01, Confined Space Entry?

Entering the Containment after the Unit has just:

A. reached normal operating temperature and pressure.

B. announced Reactor is critical.

C. entered Mode 3 from a Mode 4 condition.

D. entered Mode 4 from a Mode 5 condition.

PSL HLC 21 NRC EXAM Question 69 The Control Rooms have been evacuated and 1(2)-ONP-100.02, Control Room Inaccessibility is being implemented.

A plant cooldown and depressurization to Shutdown Cooling is being conducted from the Hot Shutdown panel lAW Appendix E.

As the cooldown and depressurization progresses, which ONE of the following states how ECCS pumps are controlled, prior to reaching SIAS setpoint during the depressurization?

A. On Unit 1, RACK OUT ALL ECCS pumps.

B. On Unit 2, RACK OUT ALL ECCS pumps.

C. On Unit 1, BLOCK SIAS by placing the SIAS keyswitch, to SIAS BLOCK for SIAS Channel Aand B.

D. On Unit 2, BLOCK SIAS by placing the SIAS keyswitch, to SIAS BLOCK for SIAS Channel Aand B.

PSL HLC 21 NRC EXAM Question 70 Which ONE of the foflowing is used to administratively control an annunciator that has been out of service for 10 days?

A. ADM-09.03, Administrative Control Of Defeated Annunciators B. ADM-001 0432, Control Of Plant Work Orders C. ADM-17.18, Temporary Modifications D. OP-AA-101-1000, Clearance and Tagging PSL HLC 21 NRC EXAM Question 71 Unit 1 is at 100% power preparing for unit shutdown for a refueling outage. The 1A Charging pump is running and the RCO is preparing to start the 1 B Charging pump.

Which ONE of the following lAW 1-NOP-02.02, Charging and Letdown is the correct order to start the 1 B Charging Pump?

A. 1) Start the 1 B Charging pump.

2) Contact the SNPO within 15 minutes to ensure the 1 B Charging pump is operating properly.
3) Notify RP the 1 B Charging pump is running.

B. 1) Contact RP at least 15 minutes prior to starting charging pump.

2) Direct SNPO to perform a local inspection and verify charging pump is ready to be started.
3) Start the 1 B Charging pump.

C. 1) Contact RP at least 15 minutes prior to starting charging pump.

2) Start the 1 B Charging pump.
3) Contact the SNPO to ensure the lB Charging pump is operating properly.

D. 1) Direct SNPO to perform a local inspection and verify charging pump is ready to be started.

2) Approximately 15 minutes later, start the lB Charging pump.
3) Notify RP the 1 B Charging pump is running.

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PSL HLC 21 NRC EXAM Question 72 As an FPL employee, tomorrow you are scheduled to perform valve lineups in the RAB. Its December 22 and your TEDE exposure to date is 775 mrem. Assignment 1 is a 65 minute job to be performed in an area that is 200 mrem/hr.

On Jan 2, you are scheduled for Assignment 2, to work in an area that is 115 mrem/hr for four (4) hours, but the new year updated NRC form 4 has not been filled out.

Which assignment or assignments, if any, can you complete without a dose extension and without exceeding the FPL TEDE administrative dose limits lAW HP-2, FPL Radiation Protection Manual?

A. CAN complete BOTH assignments.

B. CAN complete assignment 1 ONLY.

C. CAN complete assignment 2 ONLY.

D. CANNOT complete ANY assignment.

PSL HLC 21 NRC EXAM Question 73 Unit 1 is in Mode 6 performing refueling operations. A UGS lift is scheduled and you have been assigned to move the Refueling Machine in preparation for this lift. It is expected to take 5 minutes to move the Refueling Machine.

The dose rate on the bridge of the refueling machine is 115 mr/hr.

What type of RWP would be expected and what RP coverage would be REQUIRED.

A. ONLY A Job specific RWP with continuous RP coverage.

B. ONLY A Job specific RWP with periodic RP coverage.

C. A general entry RWP for entry into the RCA AND a Job specific RWP for the RCB with continuous RP coverage.

D. A general entry RWP for entry into the RCA AND a Job specific RWP for the RCB with periodic RP coverage.

PSL HLC 21 NRC EXAM Question 74 The Unit has just tripped.

Prior to formal implementation of EOP-O1, Standard Post Trip Actions, which ONE of the following CAN BE performed by the RO WITHOUT concurrence of the Unit Supervisor?

A. Starting an additional Charging Pump with Pressurizer level lowering rapidly.

B. Closing the Diesel output breaker if it didnt close on a LOOP.

C. Closing the MSR TCVs due to the MSR Block valves not closing.

D. Closing the MSIVs due to the Turbine not tripping.

PSL HLC 21 NRC EXAM Question 75 Unit 1 Unit Supervisor is directing implementation of 1-EOP-15, Functional Recovery.

Which ONE of the following identifies the instrumentation that is to be used FIRST by the Operators to assess the status of Safety Functions?

A. ERDADS instrumentation B. DCS instrumentation C. Instrumentation ALSO designated as Remote Shutdown instrumentation D. Instrumentation identified by White Bezel around the face of the instrument REVISION NO.: PROCEDURE TITLE: PAGE:;

SHUTDOWN COOLING ABNORMAL OPERATIONS 1 9 of 31 PROCEDURE NO.:

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

I. 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 I 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 = mm Time to boil Additional time to boil Additional 100 ft 3 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 Stepi.A Step i.E

REVISION NO.: PROCEDURE TITLE: PAGE:

SHUTDOWN COOLING ABNORMAL OPERATIONS 20 f 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):

.35) =

Time Boiling Will Occur LA

REVISION NO.: PROCEDURE TITLE: PAGE:,.

SHUTDOWN COOLING ABNORMAL OPERATIONS 21 of 31 PROCEDURE NO.:

1-AOP-03 02 ST LUCIE UNIT I ATTACHMENT I Estimated Time to Core Boiling (Page 3 of 5)

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 (°P Shutdown 60 80 90 100 110 120 130 140 200 Time (Hours) 24 14.7 12.7 11.8 10.8 9.81 8.84 7.87 6.91 1.21 48 17.9 15.6 14.4 13.2 12.0 10.8 9.61 8.44 1.48 60 19.4 16.8 15.5 14.3 13.0 11.7 10.4 9.13 1.60 72 20.8 18.1 16.7 15.3 13.9 12.5 11.2 9.80 1.72 90 22.9 19.8 18.3 16.8 15.3 13.8 12.3 10.8 1.89 102 24.1 20.9 19.3 17.7 16.1 14.5 12.9 11.4 1.99 120 25.9 22.5 20.8 19.1 17.3 15.6 13.9 12.2 2.14 132 27.1 23.5 21.7 19.9 18.1 16.3 14.5 12.7 2.23 144 28.1 24.4 22.5 20.6 18.8 16.9 15.1 13.2 2.32 240 34.7 30.1 27.8 25.5 23.2 20.9 18.6 16.3 2.86 300 37.8 32.8 30.3 27.7 25.3 22.8 20.3 17.8 3.12 360 40.6 35.2 32.5 29.8 27.1 24.4 21.7 19.1 3.35 480 45.8 39.7 36.6 33.6 30.6 27.6 24.5 21.5 3.78 600 50.8 44.0 40.7 37.3 33.9 30.6 27.2 23.9 4.19 840 60.6 52.5 48.5 44.5 40.5 36.5 32.5 28.5 5.00 1440 82.7 71.7 66.2 60.7 55.3 49.8 44.3 38.9 6.82

REVISION NO.: PROCEDURE TITLE: PAGE:

5 SHUTDOWN COOLING ABNORMAL OPERATIONS 22 of 31 PROCEDURE NO.:

V*

1-AOP-03 02 ST LUCIE UNIT 1 i:

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 Manaqement Directive 2)

RCS Temperature (°F Shutdown Time (Hours) 60 80 90 100 110 120 130 140 200 24 1.02 0.886 0.818 0.750 0.683 0.615 0.548 0.481 0.0843 48 1.25 1.08 0.999 0917 0.834 0.752 0.669 0.587 0.103 60 1.35 117 1.08 0.992 0.903 0.813 0.724 0.635 0.111 72 1.45 1.26 1.16 1.06 0.969 0.873 0.777 0.682 0.120 90 1.59 1.38 1.27 1.17 1.06 0.958 0.853 0.749 0.131 102 1.68 1.46 1.35 1.23 1.12 1.01 0.901 0.791 0.139 120 1.81 1.57 1.45 1.33 1.21 1.09 0.968 0.850 0.149 132 1.88 1.63 1.51 1.38 1.26 1.13 1.01 0.886 0.155 144 1.96 1.70 1.57 1.44 1.31 1.18 1.05 0.920 0.161 240 2.41 2.09 1.93 1.77 1.61 1.45 1.29 1.014 0.199 300 2.63 2.28 2.11 1.93 1.76 1.58 1.41 1.024 0.217 360 2.82 2.45 2.26 2.07 1.89 1.70 1.51 1.33 0.233 480 3.18 2.76 2.55 2.34 2.13 1.92 1.71 1.50 0.263 600 3.53 3.07 2.83 2.60 2.36 2.13 1.89 1.66 0.292 840 4.22 3.66 3.38 3.10 2.82 2.54 2.26 1.98 0.348 1440 5.75 4.99 4.61 4.23 3.85 3.46 3.08 2.71 0.475

REVISION NO.: PROCEDURE TITLE: PAGE:

SHUTDOWN COOLING ABNORMAL OPERATIONS 23of 31 PROCEDURE NO.:

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

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

II Table 3 Additional Volume (100 cubic feet) Above Mid-Loop (Section 6.1.3 Manaqement 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 ff3 Feet 100 ff3 Feet 100 ff3 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 39.50 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; 5

SHUTDOWN COOLING ABNORMAL OPERATIONS 24 of 31 PROCEDURE NO.:

1-AOP-03.02 ST. LUCIE UNIT 1

.1:

ATTACHMENT 2 RCS Level Indications versus Elevation (Page 1 of 1)

NOTE The following information is posted as an Operator Aid at the CRAC Panel.

Any changes to this section must be included in the Operator Aid per 0010140, Control of Operator Aids.

INSTRUMENT ELEV Ll-1117 LI-1117-1 Tygon (0 48

- (0 400

- (ft, LI-i 103 (if, inches) LOCATION inches) inches) inches) 387 57% 60 Refueling Operations 23 ft Above Reactor Vessel 375 53%

Flange N/A Remove Hook from UGS Rig 363 50% 58 When in Lower Cavity 327 40% 55 UGS Lift to Core 291 30% 52 UGS Lift to Layd own Area N/A 248 48, 5 18% 48, 5 23 ft Above Fuel CEA Extension Shafts Below 239 47, 8 16% 47, 8 Water 186 43, 3 0% 43, 3 ICI Flanges 183 43 0% 43 Bottom of Pressurizer 123 38 <0% 38 2 inches Above Instrument Plate 99 36 36 Reactor Vessel Flange 63 33 33 RCP Seal Cartridge 42 42 31,3 31,3 TopofHotLeg 33 33 30, 6 30, 6 Bottom of S/G Primary Manway Max level for Nozzle Dam 27 27 30, 0 N/A Installation Mm level for LPSI pump 24 1,4 24 1,4 29 9 % 29 9 operation for SDC 24 4 24 4 29, 9 % 29, 9 4 Low Level Annunciator Z-19 21 21 29, 6 29, 6 Centerline of Hot Leg 0 0 27, 9 27, 9 Bottom of Hot Leg

REVISION NO.: PROCEDURE TITLE: PAGE:

47 PPENDICES I FIGURES / TABLES I DATA SHEETS PROCEDURE NO.:

131 of 173 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 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.

2400 H An .,nlaAe ha been pbsedn the l.k I Co,U Roenn RO I /

desk (Ant ,n,.,esn a lids sense., olin, n.e dns shall ns.*y the 54 he Opn.etosAid ens. CnUonçns cnn nssensomy. nhUy tine Cod CehnMtsn.l 2200 Acceptable

/ -:

Range 2000 1800 -; . Maximum I Subcooled 1800 C.

U

  • 3 1400 C

4)

C 1200 U,

a C

a 1000 -

Minimum 800 / 47 Subcooled° RCPNPSII I Requiremenr 600

-7c;---

400--

__,////

InclUdeS nest Uincen!a,nnnes f?V 0

0 100 200 300 400 500 600 700 800 Indicated RCS Temperature (F) nA U 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:

47 PPENDlCES I FIGURES! TABLES I DATA SHEETS PROCEDURE NO.:

132 of 173 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.

NOTE I do<. AIy r0on 707770 S000fl 07700 p100007770 00377700777 v70ny 07700 OpOrolor Aid 000, 000370700370 000070ary, 007077 070 EOP Co07fretof) 2200

/

Acceptable Range 2000 1800 Maxmum Subcooed..

1600 07 a

1400 1200 E:ZZZLZZZ 1000 800 RCP NPSH Requirements 1

/,

I

/ K Minimum SubcooIed 200 lncludes noirument Uncertainties 0

0 100 200 300 400 500 600 700 800 Indicated RCS Temperature (F) P .77 0Rcc r700c72

REVISION NO.: PROCEDURE TITLE:

PAGE:

47 APPENDICES I FIGURES I TABLES I DATA SHEETS PROCEDURE NO.: 133 of 173 1-EOP-99 ST. LUCIE UNIT I FIGURE 2 SAFETY INJECTION FLOW VS. RCS PRESSURE (Page 1 of 1) 1300 1200 P

A 1100 E

S 1000 S

U 900 z

E 800 R

P 700 A

E 600 S

S U 500 R

E 400 300 p

S 200 a

100 0

TOTAL SAFETY INJECTION FLOW (gpm)

(P/EOP/1-EOP-99-F2-RO)

REVS0N NO.: PROCEDURE JJTLE: PAGE:;.

44 APPENDICES I FIGURES ITABLES I DATA i22 of 1 59.

PROCEDURE NO.: SHEETS 2-EOP-99 ST. LUCIE UNIT 2 FIGURE IA RCS PRESSURE TEMPERATURE (Page 1 of 1)

(Containment Temperature Less Than or Equal to 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.

C 4,

C) r.J 4,

  • 0 0 100 200 300 400 500 600 700 800 Indicated ECS Temperature (F)

RCS Pressure Range Required QSPDS Subcooled Margin Reading (Rep CET) 2250 psia to 1000 psia 40 to 180 F

4 1000 psia to 500 psia 50 to 1 70 F

4 Less than 500 psia 80 to 160 F

4

PROCEDURE TITLE: PAGE:

REVISION NO.:

44 DlcE:iURiTABLEs/DATA 123f19:

FIGURE lB RCS PRESSURE TEMPERATURE (Page 1 of 1)

(Containment Temperature Greater Than 200°F) 1 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.

I I I I I L I

_j Lceptie F NOTE 2400 An OperatcrAtd has been placed in the Unit 2 Coolest Room RCO desk. (Arry rmtslon to thIs sect,afl of the piocedurn shall sarlfy the validity of the OparetarAid and, If nhangas are flecenvary, notify the COP Cuordinates) 2200

/ Range 2000 I<

1800 Maximum -

. SUbooole zrzzI:1zz (El 1600 En cc El) z En 1400 Ld11 (El El)

El)

N En 1200 En El) 0 El)

CO iooo C)

V 800 nzz z

1 iz z _  :

600 400 200 - J 0

0 100 200 300 400 500 600 700 800 piOPs.mP-9g.1eR.zri ndicated RCS Temperature (F)

REVISION NO.: PROCEDURE TITLE: PAGE::

44 APPENDICES/FIGURES/TABLES/DATA 124 of 159 SHEETS PROCEDURE NO -

2-EOP-99 ST LUCIE UNIT 2 FIGURE 2 SAFETY INJECTION FLOW VS. RCS PRESSURE (Page 1 of 1)

P R

F S

S U

z F

R P

R F

S s-:..

U R

F p

S a

TOTAL SAFETY INJECTION FLOW (gpm) P/OPS/2-EDP-99/Fia2/Rev.OftiI

REVISION NO.: PROCEDURE TITLE: PAGE*

44 APPENDICES I FIGURES / TABLES I DATA 155 of 159 PROCEDURE NO.: SHEETS 2-EOP-99 ST LUCIE UNIT 2 TABLE 11 EMERGENCY DIESEL GENERATOR LOADING (SBO)

(Page 1 of 2)

CAUTION Unit I EDG Load Limits are as follows:

. Maximum continuous load 3500 KW I 490 amps

. Maximum 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rated load 3730 KW / 530 amps NOTE KW indication is the preferred method of controlling EDG loading. Amp values are provided in the event that KW indication is NOT available.

UNIT 2 COMPONENT RUNNING START PERMITTED IF UNIT I KW!AMPS EDG KW/AMPS LESS THAN:

ICW Pump 474.6 I 68 2450 /346 Cntmt. Spray Pump 347.1 / 50 2650 / 375 CCW Pump 362.9 / 51 2800 / 396 HPSI Pump 324.3/46 2900 /410 AFWPump 246.8/35 2950/417 LPSI Pump 280.4/40 2900/410 Pzr. Heater Backup Bank 200 / 29 3300 / 466 Hydrazine Pump 2.7 / 1 3450 / 488 Charging Pump 51.6 / 7 3300 / 466 RAB Exhaust HVE-1 OA (B) 205 / 29 3150 / 445 Cont. Purge Fan HVE-8A (B) 82.0 / 12 3350 / 474 Cntmt. Fan Cooler 69.0 / 10 3300 / 466 RAB Supply Fan HVS-4A (B) 1 1 3.0 / 16 3250 / 460 Battery Charger 52.0/7 3450/488 ECCS Exhaust HVE-9AIB 50.8 / 7 3350 / 474 Inst. Air Compressor 54.0 / 8 3350 / 473 Inverter Rm. A/C ACC-4 11.7 / 2 3450 / 488 Fuel Pool Cooling Pump 28.8 / 4 3400 / 480 Control Rm. NC ACC-3 A (B) (C) 36.0 / 5 3400 / 480 RAB Elect. Equip. Rm. Supply HVS-5A (B) 77.2 / 11 3350 / 474

REVISION NO.: PROCEDURE TITLE: PAGE:

1 44 APPENDICES I FIGURES /TABLES / DATA 156 of 159 PROCEDURE NO.: SHEETS 2-EOP-99 ST LUCIE UNIT 2 TABLE 11 EMERGENCY DIESEL GENERATOR LOADING (SBO)

(Page 2 of 2)

UNIT 2 COMPONENT RUNNING START PERMITTED IF UNIT I KW/AMPS EDG KW I AMPS LESS THAN:

Shield Bldg. Exh Fan HVE-6A (B) 45.3 I 6 3350 / 474 Rx Support Cool Fan HVE-3A (B) 21.8 / 3 3400 / 480 Fire and Security lnverter 30.0 / 4 3450 / 488 Vital SUPS lnverter 20.0 / 3 3450 / 488 Rx Cavity Cool Fan HVS-2A (B) 13.7 / 2 3450 / 488 BAMU Pump 13.1/2 3450/488 RCP Oil Lift Pump 9.0 / 1 3450 / 488 Sec. Bldg. Comp. Rm. 5.0 / 1 3450 / 488 A/C ACC-1 OA (B)

Control Rm. Fan HVA-3A (B) 13.4 / 2 3450 / 488 EDG Air Compressor 6.7/ 1 3450 I 488 Inst. Air Cool Fan 4.5 / 1 3450 / 488 Intake Bldg. Fan HVE-41 6.7! 1 3450 / 488 RAB Elect. Equip. Exh HVE-11!12 41.7/6 3350/474 Control Rm. Emerg. HVE-1 3A (B) 9.0 / 1 3450 / 488 Sec. Bldg. Comp. Rm. 2.7 / 1 3450 / 488 Fan_HVA-1OA_(B)

EDG Fuel Transfer Pump 1.6! 1 3450 / 488 Inst. Air Cool Pump 6.7 / 1 3450 / 488 Elect. Equip. Rm. Roof 4.5 / 6 3450 / 488 Vent RV 3/4 EDG Oil Pump 1.8 / 1 3450 / 488 Battery Room Roof Vent RV-1!2 0.7! 1 3450 / 488 END OF TABLE II

REVISION NO.: PROCEDURE TITLE: PAGE:.

47 APPENDICES I FIGURES! TABLES! DATA SHEETS PROCEDURE NO.: 168 of 173 1-EOP-99 ST. LUCIE UNIT 1 TABLE 11 EMERGENCY DIESEL GENERATOR LOADING (SBO)

(Page 1 of 2)

CAUTION Unit 2 EDG Load Limits are as follows:

. Maximum continuous load 3685 KW/510 amps

. Maximum 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rated load 3935 KW / 550 amps NOTE KW indication is the preferred method of controlling EDG loading. Amp values are provided in the event that KW indication is NOT available.

UNIT I COMPONENT RUNNING START PERMITTED IF UNIT 2 KW I AMPS EDG KW LESS THAN:

ICW Pump 449.2 I 64 3000 Cntmt. Spray Pump 403.2/58 3100 COW Pump 354.9 / 51 3200 HPSI Pump 324.4/46 3250 AFW Pump 286.3 / 41 3350 LPSI Pump 270.2 / 39 3250 Pzr. Heater Backup Bank 208.5 / 30 3600 Fire Pump 198.4 / 28 3450 Charging Pump 71.3 / 10 3650 RAB Exhaust HVE-1OA (B) 68.0 / 10 3600 Rx Purge Fan HVE-8A (B) 67.0 / 10 3650 Cntmt. Fan Cooler 61.8 / 9 3600 RAB Supply Fan HVS-4A (B) 53.9 / 8 3700 Battery Charger 52.0 / 7 3750 RAB ECCS Exhaust HVE-9A/B 38.1 /5 3750 30.4/4 3750 Inst. Air Compressor 32.8 / 5 3750 Cable Spread Rm. NC 31.5 I 5 3750 Fuel Pool Pump 29.7 / 4 3750 Control Rm. A/C ACC-3 A (B) (C) 29.3 / 4 3750 (continued on next page)

REVISION NO.: PROCEDURE TITLE:

PAGE:

47 \PPENDICES/FIGURES/TABLES/DATA SHEETS PROCEDURE NO.: 169 of 173 1-EOP-99 ST. LUCIE UNIT I TABLEII EMERGENCY DIESEL GENERATOR LOADING (SBO)

(Page 2of2)

UNIT I COMPONENT RUNNING START PERMITTED IF UNIT 2 KW I AMPS EDG KW LESS THAN:

RAB Elect. Equip. Rm. Supply HVS-5A (B) 27.0 / 4 3750 Shield Bldg. Exh Fan HVE-6A (B) 27.0 / 4 3700 Rx Support Cool Fan HVE-3A (B) 21.6 / 3 3750 Fire or Security Inverter 20.0 / 3 3750 Vital SUPS Inverter 20.0 / 3 3750 Rx Cavity Cool Fan HVS-2A (B) 15.5 / 2 3750 BA MU Pump 13.1 / 2 3750 RCP Oil Lift Pump 9.0 / 1 3750 Computer Rm. NC ACC-1OA (B) 8.1/1 3750 Control Rm. Fan HVA-3A (B) 6.7 / 1 3750 EDG Air Compressor 6.7 / 1 3750 Inst. Air Cool Fan 6.7 I 1 3750 Cable Spread Rm. Fan 4.5 / 1 3750 RAB Elect. Equip. Exh HVE-11/12 4.1 / 1 3750 Control Rm. Emerg. HVE-13A (B) 2.7 I 1 3750 Computer Rm. Fan HVA-1OA (B) 2.7 / 1 3750 EDG Fuel Transfer Pump 2.3 / 1 3750 Inst. Air Cool Pump 1.8 I 1 3750 RAB Elect. Equip. Rm. Roof Vent RV-3/4 1.3 I 1 3750 EDG Oil Pump 0.9 / 1 3750 END OF TABLE II

REVISION NO.: PROCEDURE TITLE:

PAGE:

34 FILLING AND DRAINING THE RCS AND REFUELING CAVITY PROCEDURE NO.: USING LPSI 83 of 96 1-NOP-03.06 ST. LUCIE UNIT 1 ATTACHMENT 3 SDC & LPSI Pump Flow Requirements (Page 1 of 1)

IIL gpm

- /1PP35?Opm d I Ma<men Plow irW ji 53145 m V,2PP3778Qpml S

\ /7///. /72: I Maxtinum Poe 2 PPs s.3 37 gpm 0

1 ///*.. 7//A lrw 1 PP 3120 pm Operation /1 Plow reaies 2PPs3637gpm

\\

Syatemllow \4 Restricted /1 1PP312Oa0m 30OOgpm 1/////////:

135 140 1 RCS Temperature NOTE: 1) LPSI Pump Minimum Flaw 2) During performance of Safeguards Testing in Mode 5 (at all times) RCS temperatures 100° F and level greater than or 40 gpm <20 reins. equal to 35 ft., it is acceptable for flow to increase

> 1200 gpm continuous above and specified limits. Al the conclusion of testing, 1000 gpm continuous (using sum of P1-3312, 3322, 3332, 3342) adherence to the specified limits should resume.

This 1SAN Ol°ERATOR AID (GA) iF ThIS FIGURE iS REVISED THE (OA) WILLALSO HAVE TO BE REVISED lPIOvSIINOPO3.O6fFiglIRo2.fl

St. Lucie NRC Exam HLC-21 Question Answer

1. A
2. C
3. D
4. C
5. A
6. B
7. C.
8. D
9. B
10. A
11. C
12. C
13. D
14. A
15. D
16. B
17. D
18. C
19. B
20. A
21. D
22. C
23. D
24. B
25. D
26. A
27. A
28. B
29. B
30. D
31. C
32. D
33. C
34. C
35. A
36. D
37. D
38. A
39. A
40. D
41. C
42. B
43. D

CI) r C

C) m z

C) m x

B I

r

-

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