Text

Initial Exam 2012-301 Final SRO Written Exam
	ML13017A366
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Site:	Saint Lucie
Issue date:	01/14/2013
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1 PSLHLC21NRCEXAM ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: 12/17/12 Facility/Unit: St. Lucie Plant Region:

I [1 II [Xl Ill [1 IV LI Reactor Type: W El CE BW El 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 overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to complete the combined examination, and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months if you are only taking the SRO portion.

Applicant Certification All work done on this examination is my own.

I have neither given nor received aid.

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

PSL HLC 21 NRC EXAM Question 76 Given the following:

Unit 1 is cooling down and has just placed SDC in service using the 1 B LPSI pump.

Pressurizer pressure and level started lowering rapidly and the lB LPSI pump was stopped.

The RCS has heated up to 340° F.

Which ONE of the following states:

1) The Tech. Spec. ACCIDENT MONITORING INSTRUMENTATION that should be used to monitor Pressurizer level?

2) Based on the current conditions, the Tech. Spec. action that is applicable if ONE CHANNEL of that instrumentation is NOT operable I available AND is unable to be restored?

A.

1) Pressurizer level transmitter LT-1 11 OX AND LT-1 11 OY.

2) Be in Hot Shutdown in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

B.

1) Pressurizer level transmitter LT-1 103 AND LT-1 104, LT-1 105.

2) Be in Hot Shutdown in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

C.

1) Pressurizer level transmitter LT-1 11 OX AND LT-1 11 OY.

2) Be in Hot Shutdown in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

D.

1) Pressurizer level transmitter LT-1 103 AND LT-1 104, LT-1 105.

2) Be in Hot Shutdown in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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PSL HLC 21 NRC EXAM Question 77 Unit 1 is combating a LARGE SGTR on the 1 B SG. All Reactor Coolant Pumps have been stopped.

1 -EOP-04, Steam Generator Tube Rupture is being implemented with the following conditions:

Pressurizer pressure is 900 psia Pressurizer level is offscale low 1 B SG pressure indicates 650 psia lB SG level indicates 95% Narrow Range and slowly rising.

1 B SG has been isolated lAW Appendix R Which ONE of the following is the PREFFERED method of lowering the 1 B SG level to within the Safety Function range?

A.

Line up the 1 B SG blowdown system to the Monitored Storage Tank (MST).

B.

Reducing RCS pressure to less then the SG pressure (backflow).

C. Steaming the 1 B SG to the condenser.

D. Steaming the 1 B SG to the atmosphere.

- 77

PSL HLC 21 NRC EXAM Question 78 Unit 2 is performing a Reactor startup following a refueling outage. The Reactor is critical with a stable power level of 6%. A positive Moderator Temperature Coefficient (MTC) exists.

SBCS valve PCV-8802 fails to the full open position. Efforts to close the valve from the control room have failed.

RCS TaveiS currently 515°F and lowering.

RCS pressure is 2220 psia and lowering.

Pressurizer level is 25% and lowering.

1) Which ONE of the following would be observed that requires a manual Reactor trip?

2) When the Reactor is tripped, which ONE of the following Tech. Spec action statement applies?

A.

1) 2 of 4 high startup rate channel pre-trips illuminated.

2) Restore Pressurizer level 27% to 68% within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

B.

1) 2 of 4 high startup rate channel pre-trips illuminated.

2) Restore RCS pressure to greater than 2225 psia within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

C.

1)RCSTave.

2) Restore Pressurizer level 27% to 68% within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

D.

1) RCS Tave

2) Restore RCS pressure to greater than 2225 psia within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

- 78

PSL HLC 21 NRC EXAM Question 79 Given the following:

At time 0020 both Units tripped due to a LOOP (loss of offsite power)

On the trip, both Unit 1 Diesel generators failed to start and ONE Unit 2 Diesel generator is running on its respective bus.

The E-Plan classification was made at time 0025

1) Which of the following states the basis for the HIGHEST classification and

2) The LATEST time the NRC must be notified A.

1) Station Blackout

2) Time 0125 B.

1) Station Blackout

2) Time 0120 C.

1) LOOP

2) Time 0125 D.

1) LOOP

2) Time 0120

- 79

PSL HLC 21 NRC EXAM Question 80 Unit 2 is at 100% power with the 2C Auxiliary Feedwater (AFW) Pump being out of service for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months At time 2230 the Unit tripped due to a Loss of Offsite power o

The 2A Diesel generator automatically started and loaded on the bus o

The 2B Diesel generator started but its output breaker failed to close At time 2231 2A and 2B Steam Generator (SG) narrow range levels indicated 17 and 20% respectively At time 2235 the 2B Diesel generator breaker was manually closed. 2A and 2B SG levels indicate 16 and 19% respectively.

1) Which ONE of the following states the Tech. Spec Action statement applicable for the 2C AFW pump?

2) Assuming NO further Operator actions, which of the following states the AFW status at time 2236?

A. 1) Restore the 2C AFW pump to operable status within 66 hours7.638889e-4 days 0.0183 hours 1.09127e-4 weeks 2.5113e-5 months .

2) The 2A AFW pump is running feeding the 2A SG. The 2B AFW pump is NOT running.

B. 1) Restore the 2C AFW pump to operable status within 66 hours7.638889e-4 days 0.0183 hours 1.09127e-4 weeks 2.5113e-5 months .

2) The 2A AFW pump is running feeding only the A SG. The 2B AFW pump is running but NOT feeding the 2B SG.

C. 1) Restore the 2C AFW pump to operable status within 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

2) The 2A AFW pump is running feeding the 2A SG. The 2B AFW pump is NOT running.

D. 1) Restore the 2C AFW pump to operable status within 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

2) The 2A AFW pump is running feeding only the A SG. The 2B AFW pump is running but NOT feeding the 2B SG.

- 80

PSL HLC 21 NRC EXAM Question 81 Given the following conditions on Unit 2:

The Containment Atmosphere PARTICULATE radioactivity monitor has been out of service for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

1) If a loss of instrument air occurred after the unit was shutdown, which RCS leakage detection subsystems would be operable?

2) Based on that determination, what surveillances, if any, will be required to be performed to satisfy the RCS Leakage Detection system LCO per Ops Policy 503, Technical Specification Guidance? Perform an RCS leak rate:

A. 1) ONLY the Reactor Cavity Leakage Alarm is operable.

2) OR a containment atmosphere grab sample analysis every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

B. 1) The Reactor Cavity Leakage Alarm AND the Containment Atmosphere GASEOUS Radioactivity monitor are operable.

2) OR a containment atmosphere grab sample analysis every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

C. 1) ONLY the Reactor Cavity Leakage Alarm is operable.

2) AND a containment atmosphere grab sample analysis every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D. 1) The Reactor Cavity Leakage Alarm AND the Containment Atmosphere GASEOUS Radioactivity monitor are operable.

2) AND a containment atmosphere grab sample analysis every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

- 81

PSL HLC 21 NRC EXAM Question 82 Unit 1 was operating at 100% power (1050 MW) when an influx of jellyfish occurred, causing a degradation of condenser vacuum.

At 0800, a down power is commenced at 1%/Mm; condenser backpressure is 7.2 Hg.

Time Condenser Backpressure ( Hg A)

MWe 0810 6.8 945 0820 6.6 840 0835 6.3 683 0850 6.1 525 Which ONE of the following states:

1) The procedural requirements of 1-AOP-1 2.01, Loss of Condenser Vacuum at time 0850?

At time 0853, Condenser Backpressure rose to 8.5 HgA.

2) Assuming no Operator actions, an automatic Reactor trip will occur:

A. 1) Continue the downpower until backpressure lowers to <5.9 in HgA.

2) immediately.

B. 1) Continue the downpower until backpressure lowers to <5.9 in HgA.

2) in 5 minutes.

C. 1) Stabilize reactor power at the current level.

2) immediately.

D. 1) Stabilize reactor power at the current level.

2) in 5 minutes.

- 82

PSL HLC 21 NRC EXAM Question 83 Unit I 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.

Chemistry has reported that samples taken just offshore of the discharge canal were over 20 times the applicable concentrations specified in 1 OCFR2O part B.

lAW 1-AOP-06.02, Uncontrolled Release Of Radioactive Liquids which ONE of the following is a required SUBSEQUENT Operator action AND what are the reportability requirements per 10CFR50.72 and 10CFR5O.73?

1)

Stop the 1A Waste Monitor pump _(1).

2)

Initiate an _(2)_.

A. 1) from the Liquid Waste Control panel, AND close FCV-6627X locally

2) LER within 60 days B. 1) locally AND lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve

2) LER within 60 days C. 1) locally AND lock closed V21462, Waste Monitor Pumps Discharge to Discharge Canal Isolation valve

2) Emergency Notification System (ENS) notification within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

D. I) from the Liquid Waste Control panel, AND close FCV-6627X locally

2) Emergency Notification System (ENS) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

- 83

PSL HLC 21 NRC EXAM Question 84 The Waste Gas Surge Tank has been aligned to the Plant Vent for the past 180 days with the Waste Gas System taken out of service lAW 2-0530020, Waste Gas System Operation.

Unit 2 is at 100% power preparing to perform a VCT purge with Nitrogen in preparation for a refueling outage.

The SRO directed the Gas Surge Tank to be re-aligned to the 2A Gas Decay Tank for the VCT purging operation and the VCT purge to be started.

The VCT purge has been ongoing for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The SNPO reports the 2A Gas Decay Tank pressure has not changed. He also reports the 2B and 2C Gas Decay Tank pressures have not changed.

The RAB general area dose rates have not changed. (no Area Radiation Monitors are in alarm or increasing)

Which of the following should be performed?

1) Stop the VCT purge and:

2) the above condition is:

A.

1) Direct the SNPO to realign the Gas Surge Tank to the Plant Vent until a valve alignment check can be performed.

2) considered an UNPLANNED GAS RELEASE lAW C-200 ODCM.

B.

1) Direct the SNPO to realign the Gas Surge Tank to the Plant Vent until a valve alignment check can be performed.

2) NOT considered an UNPLANNED GAS RELEASE lAW C-200 ODCM.

C

1) Direct RP to perform a survey of the Waste Gas Decay Tank rooms and the SNPO to perform a valve alignment check.

2) considered an UNPLANNED GAS RELEASE lAW C-200 ODCM.

D.

1) Direct RP to perform a survey of the Waste Gas Decay Tank rooms and the SNPO to perform a valve alignment check.

2) NOT considered an UNPLANNED GAS RELEASE lAW C-200 ODCM.

PSL HLC 21 NRC EXAM Question 85 Given the following conditions on Unit 2:

The unit is shutdown in Mode 3 with Reactor Coolant System (RCS) temperature at 532°F and pressure at 2250 psia.

A CEDM housing leak has resulted in the following annuciator:

Rx CAVITY LEAKAGE HIGH N-46 In accordance with 2-AOP-01.08, RCS Leakage Abnormal Operations the initial determination of the RCS leak rate should be done by _(1 )_.

The Tech Spec action that applies for this event is _(2)_.

A.

1) observing FR-07-03, Reactor Cavity Leakage Flow

2) reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B.

1) observing FR-07-03, Reactor Cavity Leakage Flow

2) be in COLD SHUTDOWN within 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months C.

1) gross Charging and Letdown mismatch

2) reduce the leakage rate to within limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months D.

1) gross Charging and Letdown mismatch

2) be in COLD SHUTDOWN within 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months PSL HLC 21 NRC EXAM Question 86 Unit 1 has experienced a LOCA with the following conditions:

At time 0006 the Unit tripped At time 0021 RCS pressure indicated 1580 psia and the crew entered 1-EOP-03, LOCA.

The current time is 0053.

Which ONE of the following states the procedural actions that are taken to ensure equipment reliability and maintainability of the RCPs.

A. Verify CCW to the RCPs and the alternate RCP bleedoff flow has been established.

B.

Ensure CCW remains isolated by placing the four CCW Containment isolation valves To/From the RCPs to close.

C. Ensure the RCPs are off and remove the RCP breaker trip and close fuses.

D. Verifying RCP NPSH requirements are met in accordance with EOP-99 Figure 1A or 1B, RCS Pressure Temperature.

- 86

PSL HLC 21 NRC EXAM Question 87 Given the following conditions on Unit 2:

The unit is operating at 90% power.

The AB bus is aligned to the B train.

The 2A Charging and 2B Charging pumps are operating. The 2C Charging pump is in Standby.

The following annunciator has just alarmed due to a relay failure in the SA ESFAS Actuation Cabinet:

SIAS CHANNEL NB ACTUATION R-6 ONLY the Chg and Letdown systems were affected by the SIAS actuation signal.

Assume immediate Operator actions have been taken In accordance with 2-AOP-69.01, Inadvertent ESFAS Actuation.

(1) control switch should be in AUTO.

This event, perAP 00010721, NRC Required Non-Routine Notifications and Reports, _(2)_.

A. 1) All three Charging pumps

2) is not reportable B. 1) All three Charging pumps

2) would require a 60 day LER C. 1) The 2B and 2C Charging pumps

2) is not reportable D. 1) The 2B and 2C Charging pumps

2) would require a 60 day LER

- 87

PSL HLC 21 NRC EXAM Question 88 Given the following conditions on Unit 1:

The unit is at 100% power The 1 C Auxiliary Feedwater Pump (AFW) is out of service.

Time 10:00:00: a unit trip occurs.

10:03:00: both Steam Generators (SGs) NR levels were observed to be <15% on all safety channels.

10:07:15: prior to any Operator actions, the RCO reports that ONLY AFAS-2 has actuated.

10:12:00: the crew exited 1-EOP-01 SPTAs Which ONE of the following states why AFAS-1 did not actuate and what procedure would be entered?

1) AFAS-1 did not actuate due to a malfunction of the

2) The crew should enter 1-EOP-02 Post Trip recovery AND use the guidance in 1-AOP-09.02 Auxiliary Feedwater to A. 1) time delay relay failure

2) manually actuate AFAS-1 B. 1) AFAS-1 lockout relay actuation

2) manually actuate AFAS-1 C. 1) time delay relay failure

2) cross-tie the AFW headers to feed both SGs with the 1 B AFW pump D. 1) AFAS-1 lockout relay actuation

2) cross-tie the AFW headers to feed both SCs with the 1 B AFW pump

- 88

PSL HLC 21 NRC EXAM Question 89 Given the following conditions:

The A 120 Vital AC Instrument Bus has just de-energized due to an internal fault in its inverter.

The affected instrument bus has been aligned to the Isolimiter.

For the actions that were taken, this event has occurred on _(1 )_.

For the current conditions, the Tech Spec Action is _(2)_.

(Assume Mode 1)

A. 1) Unit 1

2) with the instrument inverter not connected to its associated DC bus, re-energize the Instrument bus from its associated inverter and DC bus within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B. 1) Unit 1

2) complete; the instrument bus may remain in the current alignment indefinitely.

C. 1)Unit2

2) complete; the instrument bus may remain in the current alignment indefinitely.

D. 1)Unit2

2) with one instrument inverter not connected to its associated DC bus, re-energize the Instrument bus from its associated inverter and DC bus within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

- 89

PSL HLC 21 NRC EXAM Question 90 The following Unit 1 Control Room Outside Air Intake (CROAI) Radiation Monitor has failed high:

RIS-26-84, North CROAI Train SA Which ONE of the following states the response of the CROAJ Intake ducts?

1)

CROAI intake duct(s) isolate(s).

2) The required actions would be to enter A.

1) BOTH the North and South 2)1-AOP-26.01, Process Radiation Monitors and operate the Control Room Ventilation system in the recirculation mode.

B.

1) ONLY the North 2)1-AOP-26.01, Process Radiation Monitors and operate the Control Room Ventilation system in the recirculation mode.

C.

1) BOTH the North and South

2) 1-AOP-25.02 Ventilation Systems and operate the Control Room Ventilation system in the recirculation mode.

D

1) ONLY the North

2) 1-AOP-25.02 Ventilation Systems and operate the Control Room Ventilation system in the recirculation mode.

- 90

PSL HLC 21 NRC EXAM Question 91 Unit 1 is at 100% power. All CEAs were at 136 when CEA 56 slipped to the lower electrical limit (LEL), indicating 1 on the CEAPDS.

Efforts to re-align CEA 56 have been ongoing for 60 minutes, but CEA 56 still indicates.

Which ONE of the following states:

1)

CEA 56 position indication on the DCS.

2) The procedure requirements of 1-AOP-66.01, Dropped or Misaligned CEA Abnormal Operations A.

1) DCS would indicate 136

2) Continue efforts to re-align CEA 56 while concurrently reducing power to 70% lAW 1-AOP-22.01, Rapid Downpower B

1) DCS would indicate 136

2) Suspend efforts to re-align CEA 56 and reduce power to 70% lAW 1-AOP-22.01, Rapid Downpower C.

1) DCS would indicate 1

2) Continue efforts to re-align CEA 56 while concurrently reducing power to 70% lAW 1-AOP-22.01, Rapid Downpower D.

1) DCS would indicate 1

2) Suspend efforts to re-align CEA 56 and reduce power to 70% lAW 1-AOP-22.01, Rapid Downpower

- 91

PSL HLC 21 NRC EXAM Question 92 Unit 1 has entered 1-EOP-03, LOCA with the following conditions:

Containment pressure is 12 psig.

All Containment coolers and Containment Spray pumps are operating.

Containment Hydrogen concentration is 4.5%

The Technical Support Center (TSC) is fully manned and plant conditions have been communicated to the TSC.

Which ONE of the following states the status of the Containment Temperature & Pressure Safety function AND when should the H2 purge system or Hydrogen Recombiners be placed in service?

1) Containment Temperature & Pressure Safety function is:

2) The H2 purge system or Hydrogen Recombiners should be placed in service:

A.

1)MET

2) only as directed by the Technical Support Center.

B.

1)MET

2) when the Unit Supervisor deems it necessary based on the Containment Hydrogen concentration.

C. 1)NOTMET

2) only as directed by the Technical Support Center.

D. 1)NOTMET

2) when the Unit Supervisor deems it necessary based on the Containment Hydrogen concentration.

- 92

PSL HLC 21 NRC EXAM Question 93 Which ONE of the following states:

1) The Tech Spec bases for the quantity of radioactivity for each Waste Gas Decay Tank?

2) The Tech Spec LCO for Oxygen concentration (by volume) in the Waste Gas Decay tank if Hydrogen concentration exceeds 4% (by volume).

A.

1) The number of curies of noble gas is limited for each tank based on limiting the dose rates to acceptable levels within the plant protected area.

2) Maximum of 2% Oxygen.

B.

1) The number of curies of noble gas is limited for each tank based on limiting the dose rates to acceptable levels within the plant protected area.

2) Maximum of 4% Oxygen.

C.

1) The number of curies of noble gas is limited for each tank based on limiting the dose at the exclusion boundary in the event of an uncontrolled release.

2) Maximum of 2% Oxygen.

D.

1) The number of curies of noble gas is limited for each tank based on limiting the dose at the exclusion boundary in the event of an uncontrolled release.

2) Maximum of 4% Oxygen.

- 93

PSL HLC 21 NRC EXAM Question 9)4 Unit 2 has tripped due to a LOOP. The 2A Diesel Generator did not start but the 2B Diesel Generator started and loaded on the 2B3 4.16KV bus.

1)

Prior to formal implementation of 2-EOP-01, Standard Post Trip Actions which of the following would be expected for operation of the Atmospheric Dump valves?

2) Which of the following actions is the Unit Supervisor ALLOWED to take while implementing 2-EOP-01?

A. 1) One ADV on the A side operated in AUTO I AUTO from the PACB and one ADV on the B side operated in AUTO I AUTO from RTGB 202.

2) Approach the control board to visually determine if the ADV configuration is correct.

B. 1) One ADV on the A side operated in AUTO I AUTO from the PACB and one ADV on the B side operated in AUTO I AUTO from RTGB 202.

2) Perform a peer check while the RCO is lining up the ADVs.

C. 1) One ADV on the A side operated in MANUAL I MANUAL from RTGB 202 and one ADV on the B side operated in AUTO / AUTO from RTGB 202.

2) Approach the control board to visually determine if the ADV configuration is correct.

D. 1) One ADV on the A side operated in MANUAL / MANUAL from RTGB 202 and one ADV on the B side operated in AUTO / AUTO from RTGB 202.

2) Perform a peer check while the RCO is lining up the ADVs.

- 94

PSL HLC 21 NRC EXAM Question 95 Unit 1 is in Mode 3, Normal operating temperature and pressure.

The solenoid vent valve for the actuator on HCV-14-1 failed open causing HCV-14-1, CCW to the RCPs to close.

1-NOP-O1.02, Reactor Coolant Pump Operation section 5.2, Local Restoration of CCW to RCPs is being performed to re-open HCV-14-1.

Which ONE of the following states ALL the actions necessary to control this process PRIOR TO the solenoid vent valve repair?

A.

Perform an operability test of HCV-14-1 per OP-i -0010125A, Surveillance Data Sheets once HCV-i4-i is opened.

B.

Document temporary hose connection lAW ADM-17.i8, Temporary Modifications.

C. Document temporary hose connection lAW ADM-1 7.18, Temporary Modifications AND follow the Tech. Spec. actions due to HCV-14-i not closing in the event a SIAS were to occur.

D. Document temporary hose connection lAW ADM-1 7.18, Temporary Modifications AND once HCV-14-1 is opened perform operability test per OP-i -0010125A, Surveillance Data Sheets.

- 95

PSL HLC 21 NRC EXAM Question 96 Unit 1 is in Mode 6 performing a core re-load.

An underload condition occurred while attempting to lower a spent fuel bundle into the core.

As Refueling Supervisor, which ONE of the following would you direct to troubleshoot this condition?

A. Conduct the troubleshooting process as described in 1-NOP-67.04, Refueling Machine Operation.

B. Initiate a NPWO lAW ADM-0010432 Control of Plant Work Orders for the equipment vendor to conduct an alignment check of the Refueling Machine.

C. Contact Mechanical Maintenance and the equipment vendor and perform O-GMP-21 Troubleshooting Process D. Implement NAP-412, Operational Decision Making and gather an Operational Decision Making team to determine the course of action.

- 96

PSL HLC 21 NRC EXAM Question 97 Unit 1 performed a down power and manually tripped the Unit at 0700 on August 6, 2012 in preparation for a refueling outage.

Which ONE of the following states:

1) The EARLIEST time that Tech. Specs state fuel movement within the reactor pressure vessel can be performed.

2) The Tech. Spec basis for this time A. 1)0700 August 9, 2012

2) fuel handling accident analysis assumes the radioactive decay of the short lived fission products.

B. 1)0700 August 9,2012

2) fuel handling accident analysis assumes 99% of the assumed gas gap activity released to have decayed.

C. 1)0700 August 13, 2012

2) fuel handling accident analysis assumes the radioactive decay of the short lived fission products D. 1)0700 August 13, 2012

2) fuel handling accident analysis assumes 99% of the assumed gas gap activity released to have decayed.

- 97

PSL HLC 21 NRC EXAM Question 98 Unit 2 is at 100% power. At 0030 on April 3, 2012 the Unit 2, 2B SG, RM-80 for the Main Steam Line radiation monitor was not communicating with the PC-i 1 in the Control Room.

At timel300 on April 3, 2012, the RM-23P was installed locally for the 2B Main Steam Line monitor lAW 2-NOP-26.01, Radiation Monitors

1) The Tech. Spec. Action Statement for the Main Steam line monitor was:

2) This was due to:

A.

1)NOTmet

2) the RM-23P was not installed within the Tech. Spec. Action statement time requirements.

B.

1)NOTmet

2) the RM-23P is not powered from a Vital bus, thus it would not be available in the event of a LOOP/SGTR.

C. 1)met

2) the RM-23P was installed within the Tech Spec Action statement time requirement AND the RM-23P meets the requirement of a Temporary Modification lAW ADM-1 7.18, Temporary Modifications.

D. 1)met

2) the RM-23P was installed within the Tech Spec Action statement time requirement AND the RM-23P meets the preplanned alternate method of monitoring.

- 98

PSL HLC 21 NRC EXAM Question 99 At time 0021, Unit 2 evacuated the Control Room due to a fire. 2-ONP-1 00.02, Control Room Inaccessibility is in progress.

At time 0034 critical actions from all Appendices are reported complete.

Which ONE of the following states the responsibilities of:

1) Shift Manager (SM) 2)RCOA A.

1) Classify the event as Alert

2) Establish communications with the HSP from the AFW area and perform actions as directed by the US.

B. 1) Classify the event as Site Area Emergency

2) Establish communications with the HSP from the AFW area and perform actions as directed by the US.

C. 1) Classify the event as Alert

2) Establish communications with the SM and monitor plant parameters on the HSP.

D. 1) Classify the event as Site Area Emergency

2) Establish communications with the SM and monitor plant parameters on the HSP.

- 99

PSL HLC 21 NRC EXAM Question 100 Unit 1 has completed 1-EOP-01, Standard Post Trip Actions.

The Unit supervisor is analyzing Chart 1, Diagnostic Flow Chart, to determine the subsequent EOP to enter.

The following indications and alarms are observed:

Containment pressure is 0.1 psig.

RCS pressure is 1580 psia and rising.

1 B SC Blowdown monitor and Air Ejector radiation monitor alarms are in.

Main Steam Line radiation monitors are NOT in alarm.

A Steam Safety valve was open and has reseated on the 1A SC. 1A SG pressure lowered to 580 psia and is now 700 psia and rising.

1 B SG pressure is 800 psia and stable.

RCS Thot is 513°F and rising.

1) Which of the following states the SG that is the MOST AFFECTED?

2) What EOP will be implemented after 1-EOP-01?

A.1) 1ASG

2) 1-EOP-04, SGTR.

B. 1) 1ASG

2) 1 -EOP-1 5, Functional Recovery.

C. 1) lB SG

2) 1-EOP-04, SGTR.

D. 1) lB SC

2) 1-EOP-15, Functional Recovery.

- 100

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)

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 ft3 volume per Table 2:

(minutes /100 ft 3

).

D.

RECORD additional 100 ft3 volumes above mid-loop per Table 3:

(100 ft3)

E.

CALCULATE Time to Boil as follows:

+

=

mm Time to boil Additional time to boil Time to Boil Stepl.B Stepl.C 2.

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

Step 1.D Time Boiling Will Occur

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(i.35)

=

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

REVISION NO.:

PROCEDURE TITLE:

PAGE:

SHUTDOWN COOLING ABNORMAL OPERATIONS 21 cf 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 (°F 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

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 (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 0.917 0.834 0.752 0.669 0.587 0.103 60 1.35 1.17 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 22 of 31 PROCEDURE NO.:

1-AOP 03 02 ST LUCIE UNIT 1

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5 SHUTDOWN COOLING ABNORMAL OPERATIONS 23 of1 PROCEDURE NO.:

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

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 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 I

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:

SHUTDOWN COOLING ABNORMAL OPERATIONS 24 of 31 PROCEDURE NO.:

1-AOP-03.02 ST. LUCIE UNIT 1 ATTACHMENT 2 RCS Level Indications versus Elevation (Page 1 of 1)

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

- 48 (0

- 400 (ft, LI-i 103 (ft, inches)

LOCATION inches) inches) inches) 387 57%

60 Refueling Operations 375 53%

23 ft Above Reactor Vessel Flange 363 N/A 50%

58 Remove Hook from UGS Rig When in Lower Cavity 327 40%

55 UGS Lift to Core 291 30%

52 UGS Lift to Laydown Area N/A 248 48, 5 18%

48, 5 23 ft Above Fuel 239 47 8 16%

47 8 CEA Extension Shafts Below 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 Top ofHotLeg 33 33 30, 6 30, 6 Bottom of S/G Primary Manway 27 27 30 0 Max level for Nozzle Dam

N/A 30, 0 Installation 24 4 24 4 29 9 %

29 9 Mm level for LPSI pump operation for SDC 24 %

24 4 29, 9 %

29, 9 4 Low Level Annunciator Z-1 9 21 21 29, 6 29, 6 Centerline of Hot Leg 0

0 27, 9 27, 9 Bottom of Hot Leg 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.

REVISION NO.:

PROCEDURE TITLE:

PAGE; 47 PPENDlCES / FIGURES / TABLES! DATA SHEETS 131 of173 PROCEDURE NO.:

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.

a.

4, a.

C, 4

C, C,

a.

C, (0

C RCS Pressure Range Required QSPDS Subcooled Margin Reading (Rep CET) J 2250 psia to 1000 psia 40 to 1 80 0

F 1000 psia to 500 psia 50 to 170 0

F Less than 500 psia 80 to 160 0

F 0

100 200 00 400 500 600 700 800 Indicated RCS Temperature (F)

FIGURE lB RCS PRESSURE TEMPERATURE 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.

A I

NOTE 2 00 An Op.rIor

. bn piatd i.k I Cnroi& Room R T[

Coi<. Ar.y romom, t Eon sootmo 04 tho proonouro £0i vErity ttio votOpnrtErAJd04.4cnEcGcnoco0cryn04itythcI j

EOPCoordbioiO.)

2200 Acceptable /

Range

[

2000 1800 Maximum SubcooIed.

1600 or I

00 1400

/

RCPNPSH I

400 Minimum Subcooled° 200 0

0 100 200 300 r I REVISION NO.:

PROCEDURE TITLE:

PAGE:

47 PPEN DICES I FIGURES I TABLES I DATA SHEETS 132 of 173 PROCEDURE NO.:

1-EOP-99 ST. LUCIE UNIT 1 (Page 1 of 1)

(Containment Temperature Greater Than 200° F)

I, lncludes insirurneni Unceritintie 400 500 600 700 800 Indicated RCS Temperature (F)

P.EOocç

REVISION NO.:

PROCEDURE TITLE:

PAGE:

47

\\PPENDICES I FIGURES / TABLES I DATA SHEETS 133 of 173 PROCEDURE NO.:

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

P R

E S

S U

z E

R P

R E

S S

U A

E p

a 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0

NOTE This curve represents minimum expected SI Flow.

If measured flow is less than this

figure, Then SI System lineup should be

verified.

1 Full Train in Operation A

2 Full Trains in Operation EL::::

U 1000 2000 3000 4000 TOTAL SAFETY INJECTION FLOW (gpm) 5000 6000 (P/EOP/1-EOP.99-F2-AO)

REVISION NO.:

PROCEDURE TITLE:

PAGE:.

44 APPENDICES/FIGURES/TABLES/DATA

122 of 159,J PROCEDURE NO.:

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 curve assumes one pump is operating in each ioop. RCP instrumentation should be monitored for seal and pump pertormance in accordance with 2-EOP-99, Table 13.

1 RCS Pressure Range Required QSPDS Subcooled Margin Reading (Rep CET) 2250 psia to 1000 psia 40 to 1 80F 1000 psia to 500 psia 50 to 170F Less than 500 psia 80 to 160F 2400 2200 2000 11111 1M OpNorAld h bece paccd In Ucc Un)12 Ce*oI Rnnm RC0

I cnk. (My rnnIco In INn nceicn n(Ihc riYI I

I vhdItyoI the OpeIeM end.

hnaen neNy I

Acceptabe Range I

I H

0.

C 0

N U,

0 0

I)

ii I

if I

1200 1000 800 600 400 200

z:z

Minimum J

/

RCPNPSH/

1

Requirernent*

z.:

1/

es Instrument Uncertair,U 0

100 200 300 400 500 Indicated RCS Temperature (F)

.5 I 600 700 800 P.ceSs.nop.esc 4

Iwsz1

REVISION NO.:

PROCEDURE TiTLE:

PAGE:-

44 APPENDICES I FIGURES I TABLES / DATA 123of159-_

PROCEDURENO.:

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.

a).

a) c-aa, C)

C)

N C,

U)a) 0

-C)

C) a)

C)

-C) 600 700 800 (PlOP 2-P-U 1UIRec.Zdr) 0 100 200 300 400 500 hidicated RCS Temperature (F)

REVISION NO.:

PROCEDURE TITLE:

PAGE:.:;:,

44 APPENDICES I FIGURES I TABLES / DATA 1.24 of 1 PROCEDURE NO.:

SHEETS 2-EOP-99 ST LUCIE UNIT 2 FIGURE 2 SAFETY INJECTION FLOW VS. RCS PRESSURE p

R E

S S

U z

E R

P R

E S

U R

E p

S a

(Page 1 of 1)

TOTAL SAFETY INJECTION FLOW (gpm)

(PIOPSI2-EOP-99!F1g2!Rev.OtUf)

REVISION NO.:

PROCEDURE TITLE:

PAGE:.

44 APPENDICES/FIGURES/TABLES/DATA 155 of 159 PROCEDURE NO.:

SHEETS 2EOP-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 / 490 amps Maximum 2000 hour0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months rated load 3730 KW / 530 amps r

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 KWIAMPS EDG KW/AMPS LESS THAN:

ICW Pump 474.6 I 68 2450 /346 Cntmt. Spray Pump 347.1 I 50 2650 / 375 CCW Pump 362.9 I 51 2800 I 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 I 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 13.0 I 16 3250 / 460 Battery Charger 52.0 / 7 3450 I 488 ECCS Exhaust HVE-9NB 50.8 I 7 3350 / 474 Inst. Air Compressor 54.0 I 8 3350 I 473 InverterRm.AICACC-4 11.7/2 3450/488 Fuel Pool Cooling Pump 28.8 I 4 3400 I 480 Control Rm. NC ACC-3 A (B) (C) 36.0 I 5 3400 I 480 RAB Elect. Equip. Rm. Supply HVS-5A (B) 77.2 I 11 3350 I 474

REVISION NO.:

PROCEDURE TITLE:

PAGE:

44 APPENDICES/FIGURES/TABLES/DATA 156 of 159 PROCEDURE NO.:

SHEETS 2-EOP-99 ST LUCIE UNIT 2 TABLEII EMERGENCY DIESEL GENERATOR LOADING (SBO)

(Page2of2)

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 Inverter 30.0 I 4 3450 / 488 Vital SUPS Inverter 20.0 / 3 3450 / 488 Rx Cavity Cool Fan HVS-2A (B) 13.7 I 2 3450 / 488 BAMUPump 13.1/2 3450/488 RCP Oil Lift Pump 9.0 I 1 3450 /488 Sec. Bldg. Comp. Rm.

5.0 I 1 3450 I 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 / 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 I 488 Elect. Equip. Rm. Roof 4.5 I 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 PPENDICES I FIGURES I TABLES! DATA SHEETS 168 of 173 PROCEDURE NO.:

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 0.556 hours 0.00331 weeks 7.61e-4 months rated load 3935 KW I 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:

lOW Pump 449.2 / 64 3000 Cntmt. Spray Pump 403.2/58 3100 COW Pump 354.9 / 51 3200 HPSI Pump 324.4 I 46 3250 AFWPump 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-IOA (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-9AIB 38.1 I 5 3750 30.4/4 3750 Inst. Air Compressor 32.8 / 5 3750 Cable Spread Rm. A/C 31.5 / 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 I FIGURES I TABLES! DATA SHEETS 169 of 173 PROCEDURE NO.:

1-EOP-99 ST LUCIE UNIT 1 TABLE 11 EMERGENCY DIESEL GENERATOR LOADING (SBO)

(Page 2 of 2)

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 I 3 3750 Rx Cavity Cool Fan HVS-2A (B) 15.5! 2 3750 BA MU Pump 13.1 I 2 3750 RCP Oil Lift Pump 9.0 / 1 3750 Computer Rm. NC ACC-1OA (B) 8.1 I 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! 1 3750 Computer Rm. Fan HVA-1 OA (B) 2.7 I 1 3750 EDG Fuel Transfer Pump 2.3 I 1 3750 Inst. Air Cool Pump 1.8! 1 3750 RAB Elect. Equip. Rm. Roof Vent RV-314 1.3 / 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 USING LPSI 83 of 96 PROCEDURE NO.:

1-NOP-03.06 ST. LUCIE UNIT 1 ATTACHMENT 3 SDC & LPSI Pump Flow Requirements (Page 1 of 1) 265 psia 1 Pump4117 pm Minonum Flow o 1200 9pm 500sn505s

, /

(owng sum of P1.3312, 3322, 3332, 3342) 3322. 3332. 3342)

> /

15a.

//,

Mode 6 Mnimow Flow MuFloW

60

2 7000 gpm 2 pp 4155 gpm /

//

/ / / ////

1PP341175pm 5

1PP34905P/

[

1 PP3i20gpm Operation /

2PPs°3S3lgpm 2PPS332399pm

.i Operation Restricted

[\\

\\\\////

2995 lPP312Ogpm_°//r;

/

80 120 135 80 100 120 135 140 150 200 325 4

RCS Temperature I

NOTE:

1>

LPSI Pump Minimum Flow 2)

Dunng performance of Safeguards Testing in Mode 5, (at all limes)

RCS temperatures < 100° F and level greater than or

< 40 gpm 20 mins.

equal to 35 ft., it is acceptable for flow to increase

> 1200 gpm continuous above and specified limits. At the conclusion of testing,

> 1000 gpm continuous (using sum of Fl-3312, 3322, 3332, 3342) adherence to the specified limits should resume.

This ISAN O4°ERATORAID (OA)

IF This FIGURE It, REVISED THE tORi WILLALSO HAVETO BE REVISED iPi005il NOP.o3OeFC.1iRou2,3mi

ATTACHMENT 4 Condenser Pressure Limitations (Page 1 of 2) ll6psig

1

=5.9D6inHgA 35.6 psig 3.5 inHg REVISION NO.:

PROCEDURE TITLE:

PAGE:

1 LOSS OF CONDENSER VACUUM 26 of 27 PROCEDURE NO.:

V 1-AOP-12.O1 ST. LUCJEUNIT1 LP In Jet Pressure (psig) 0 7.1 29.0 50.8 72.7 94.5 116.4 138.2 160.1 181.9 203.7 210 10 V

10

=8.859 InHQA V

V

=8.859 inHoA 8

7.9 psig cZ V

7.

ai6 a) a)

4 0

C) 3 9

8 7

2 0

Trip

Alarm 4

3 2

300 400 500 400 700 800 900 598 0

1000 1030 230 Generator Load (MW)

St. Lucie NRC Exam HLC-21 SRO Exam 76.

A 77.

B 78.

C 79.

A 80.

A 81.

A 82.

B 83.

B-84.

D 85.

D 86.

B 87.

D 88.

A 89.

D 90.

C 91.

B 92.

C 93.

C 94.

A 95 C

96.

A 97.

A 98.

D 99.

C 100.

B Final Score SRO Final Score Total

ML13017A366

Text

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