Text

1A -PSL L-20-1 RO and SRO Student Exam Final as Given with Key
	ML21034A519
Person / Time
Site:	Saint Lucie
Issue date:	02/03/2021
From:	; NRC/RGN-II
To:	;
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ML21034A519 1.

Given the following conditions:

Unit 2 is at 45% power

Pressurizer (PZR) Level Control is selected to the X position

Reactor Regulating System (RRS) Selector is in the RRS 1 position Subsequently:

LT-1110X develops a leak on the high pressure connection of the D/P cell (reference leg)

PZR Pressure is 2235 psia and slowly LOWERING Which ONE of the following completes the statements below?

Based on the given conditions, the automatic response of the Pressurizer Level Control system is that letdown flow will ____(1)____.

In accordance with 2-AOP-01.10, Pressurizer Pressure And Level, operators are required to place the ____(2)____ to mitigate the event.

A. (1) RISE (2) RRS selector switch to the RRS-2 position B. (1) RISE (2) PZR level control selector switch to the Y position C. (1) LOWER (2) RRS selector switch to the RRS-2 position D. (1) LOWER (2) PZR level control selector switch to the Y position

2.

Given the following conditions:

Unit 2 was tripped from 100% power due to rapidly lowering Pressurizer Level

Following the Reactor trip, a LOOP occurred

Pressurizer Pressure is 1350 psia and slowly lowering

Core Exit Thermocouples indicate 530°F

2-EOP-03, LOCA is in progress Which ONE of the following completes the statements below?

Based on the conditions above, the primary mechanism of RCS heat removal is being provided by ____(1)____.

In accordance with 2-EOP-03, LOCA the STABLE MINIMUM required NR S/G level is

____(2)____.

A. (1) S/Gs (2) 35%

B. (1) S/Gs (2) 60%

C. (1) RCS Break Flow (2) 35%

D. (1) RCS Break Flow (2) 60%

3.

Given the following conditions:

Unit 1 has experienced a Large Break LOCA

RWT Level is 8 ft and lowering

1-EOP-03, LOCA is in progress at Step 37, In preparation for RAS Which ONE of the following completes the statements below?

IAW 1-EOP-03, the crew is required to REMOVE the power inhibit from SI Recirc valves V3659, SI PUMP MINIFLOW ISOL and V3660, SI PUMP MINIFLOW ISOL by operating the SI Recirc Valves ____(1)____.

An inadvertent closure of a single valve will isolate recirc flow for ____(2)____ ECCS train(s).

A. (1) supply breakers (2) BOTH B. (1) supply breakers (2) a SINGLE C. (1) RTGB key switches (2) BOTH D. (1) RTGB key switches (2) a SINGLE

4.

Given the following conditions:

12:00:00 Unit 1 is at 100% power 12:07:00 TE-1151, 1A1 RCP Lower Seal temperature is 180 °F and RISING 12:07:30 1-AOP-01.09A1, 1A1 Reactor Coolant Pump was entered Which ONE of the following completes the statements below?

As TE-1151 continues to RISE, HCV-14-11A1, Seal Cooler HX Isolation Valve ____(1)____

AUTOMATICALLY CLOSE.

In accordance with 1-AOP-01.09A1, the crew will be required to trip the Reactor and secure the RCP, if the Lower Seal Cavity Temperature exceeds the setpoint of ____(2)____.

A. (1) will (2) 200 °F B. (1) will (2) 250 °F C. (1) will NOT (2) 200 °F D. (1) will NOT (2) 250 °F

5.

Given the following conditions:

Unit 2 is in Mode 3

Pressurizer level control system malfunction occurs

2-AOP-01.10, Pressurizer Pressure and Level has been entered

At time 1415 charging and letdown were secured

RCS temperature is 532°F

RCS pressure is 2250 psia

RCP Controlled Bleedoff (CBO) is 1.1 gpm per RCP

Pressurizer level is 33%

Last Unidentified RCS leak rate was 0.05 gpm

No operator actions were taken, and all RCS leakage parameters remained constant for the next two hours Which ONE of the following describes the EARLIEST time that the Pressurizer will be at the MINIMUM Tech. Spec. 3.4.3, Pressurizer limit?

A. 1501 B. 1531 C. 1537 D. 1546

6.

Given the following conditions:

Unit 1 is currently shutdown for a refueling outage

The Reactor Head studs have been detensioned

The RCS level 35 feet

Time since reactor shutdown is 250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months

Reactor Coolant System (RCS) temperature is 95º F Subsequently:

All Shutdown Cooling (SDC) flow was lost due to a piping rupture just downstream of the SDC Heat Exchanger

1-AOP-03.02, Shutdown Cooling Abnormal Operations was entered Which ONE of the following describes the calculated Time to Boil in accordance with 1-AOP-03.02, Attachment 1, Estimated Time to Core Boiling?

The Time to Boil is approximately ________ minutes.

REFERENCE PROVIDED A. 23 B. 30 C. 33 D. 42

7.

Given the following conditions:

Unit 1 is at 100% power Subsequently:

Annunciator S-6, CCW Surge Tank Compartment A Level Low ALARMS

Annunciator S-16, CCW Surge Tank Compartment B Level Low ALARMS

1-AOP-14.01, Component Cooling Water Abnormal Operations is entered

LG-14-2A, CCW Surge Tank Level indicates 29 inches and SLOWLY LOWERING

LG-14-2B, CCW Surge Tank Level indicates 29 inches and SLOWLY LOWERING

LCV-14-1, Demin Water to CCW Surge Tank, is CLOSED Which ONE of the following completes the statements below?

In accordance with 1-AOP-14.01, if V14103, LCV-14-1 Bypass Valve is mechanically bound closed and will not operate; the crew is required to FIRST attempt to locally align the _____(1)_____ Header to restore CCW Surge Tank Level.

The CCW N Header Isolation Valves _____(2)_____ AUTOMATICALLY CLOSE.

A. (1) Fire Water (2) will B. (1) Fire Water (2) will NOT C. (1) Service Water (2) will D. (1) Service Water (2) will NOT

8.

Given the following conditions:

Unit 2 has experienced a LOCA

PORV 1474 is stuck OPEN

2-EOP-01, SPTA is in progress

Containment Pressure is 7.2 psig and RISING

Containment Temperature is 203 °F and RISING USING THE PICTURES ON THE NEXT PAGE Which ONE of the following completes the statements below?

If the US asks the RO to report current RCS pressure, the RO is required to answer

____(1)____.

In accordance with 2-EOP-01, the Crew is required to CLOSE ____(2)____

REFERENCE PICTURES PROVIDED (NEXT PAGE)

A. (1) 1504 psia (2) BOTH the Block Valve AND OVERRIDE the PORV B. (1) 1504 psia (2) EITHER the Block Valve OR OVERRIDE the PORV C. (1) 1506 psia (2) BOTH the Block Valve AND OVERRIDE the PORV D. (1) 1506 psia (2) EITHER the Block Valve OR OVERRIDE the PORV

9.

Given the following conditions:

Unit 1 is at 100% power

A total loss of feedwater event occurred

The Reactor Protection System FAILED TO AUTOMATICALLY TRIP the reactor when trip conditions were present Which ONE of the following completes the statements below?

With NO operator actions, Reactor Power 5 minutes after the ATWS will be

____(1)____ Reactor Power just before the ATWS occurred.

The FSAR credits the ____(2)____ to mitigate a complete loss of feedwater with ATWS accident.

A. (1) lower than (2) Diverse Scram System B. (1) lower than (2) Pressurizer Safety Valves C. (1) approximately the same as (2) Diverse Scram System D. (1) approximately the same as (2) Pressurizer Safety Valves

10.

Given the following conditions:

Unit 1 has experienced a SGTR

1-EOP-04, SGTR is in progress at step 10 INITIATE lowering RCS Temperature Which ONE of following completes the statement below?

Isolate the ruptured S/G when the RCS is cooled down to a procedurally directed

____(1)____ less than ____(2)____, in accordance with 1-EOP-04.

A. (1) Thot (2) 510 °F B. (1) Thot (2) 500 °F C. (1) REP CET (2) 510 °F D. (1) REP CET (2) 500 °F

11.

Which ONE of the following completes the statement below?

A CAUTION in 2-EOP-10, Station Blackout (SBO), states the following:

Do NOT Restart ____(1)____; if power is from ___(2)___, to prevent exceeding component amperage limits A. (1) ICW Pumps (ONLY)

(2) the Station Blackout Crosstie B. (1) ICW Pumps (ONLY)

(2) the ONLY operating EDG on Unit 1 C. (1) ICW or CCW Pumps (2) the Station Blackout Crosstie D. (1) ICW or CCW Pumps (2) the ONLY operating EDG on Unit 1

12.

Given the following timeline:

HH:MM:SS 00:00:00 Unit 1 tripped from 100% due to a LOCA 1A, 1B and 1C Charging Pumps are running post trip 00:03:00 SIAS Actuates 00:05:00 A Loss of Offsite Power (LOOP) occurs 00:05:10 Both the 1A and 1B EDGs have started and output breakers are CLOSED Which ONE of the following completes the statements below?

At time 00:05:10, 1A/1B HPSI pumps ____(1)____ running and 1C Charging Pump is NOT running due to ____(2)___ .

A. (1) are (2) load sequencing timer B. (1) are (2) RTGB Control Switch Position C. (1) are NOT (2) load sequencing timer D. (1) are NOT (2) RTGB Control Switch Position

13.

Given the following conditions:

Unit 2 is at 100% power

LIC-9023A, B S/G Level Safety Channel is bypassed

Pressurizer Level Control is in the X position Subsequently:

Containment Evacuation alarm sounds

BRCO reports Multiple alarms

Trip Circuit Breakers (TCB) Indications as follows:

o TCBs 1, 2, 5 and 6 OPEN o TCBs 3, 4, 7, and 8 CLOSED Which ONE of the following describes (1) the event that occurred and (2) what component will require manual control?

A. (1) Loss of the 2A 125V Vital DC Bus (2) Pressurizer Level Control System B. (1) Loss of the 2A 125V Vital DC Bus (2) Steam Generator Water Level Control System C. (1) Loss of the 2MA 120VAC Instrument Bus (2) Pressurizer Level Control System D. (1) Loss of the 2MA 120VAC Instrument Bus (2) Steam Generator Water Level Control System

14.

Given the following conditions:

Unit 1 is at 100% power

The 1AB busses are aligned to the A train Subsequently:

The Unit tripped

A loss of the 1A DC bus occurs

1-EOP-01, Standard Post Trip Actions is in progress Which ONE of the completes the statements below?

IAW 1-EOP-01, the 1AB DC bus will be re-energized from the ____(1)____.

Feedwater flow to the 1A S/G will be restored using the ____(2)____.

A. (1) 1B DC bus (2) 1B AFW Pump via the AFW cross-tie valves B. (1) 1B DC bus (2) 1C AFW Pump C. (1) 1AB Battery Charger (2) 1B AFW Pump via the AFW cross-tie valves D. (1) 1AB Battery Charger (2) 1C AFW Pump

15.

Given the following conditions:

Unit 2 tripped due to a SGTR

2-EOP-04, SGTR is in progress

SIAS has actuated

NPO reports the following Intake Cooling Water (ICW) parameters:

o A Turbine Cooling Water (TCW) Hx flowrate is 6000 gpm o B Turbine Cooling Water (TCW) Hx flowrate is 0 gpm IAW 2-EOP-99, Table 1, SIAS SIGNAL, the crew is required to ____(1)____

ISOLATION VALVE.

____(2)____ will experience a temperature change due to the ICW alignment.

A. (1) OPEN MV-21-2, HEADER B (2) Instrument Air Compressors B. (1) OPEN MV-21-2, HEADER B (2) Circulating Water Pump seal coolers C. (1) CLOSE MV-21-3, HEADER A (2) Instrument Air Compressors D. (1) CLOSE MV-21-3, HEADER A (2) Circulating Water Pump seal coolers

16.

Given the following conditions:

Unit 1 is at 100% power

Instrument Air Pressure, Pl-18-9, is 97 psig, slowly LOWERING Which ONE of the following completes the statements below, in accordance with 1-AOP-18.01, Instrument Air Malfunction, if Instrument Air header pressure continues to LOWER?

The Unit to Unit cross-tie from Unit 2 will OPEN at a setpoint of ____(1)____.

1-AOP-18.01 states the following: IF Instrument Air header pressure indicates less than

____(2)____ and lowering, THEN PERFORM the following: A. TRIP reactor. B. GO TO 1-EOP-01, Standard Post Trip Actions.

A. (1) 95 psig (2) 75 psig B. (1) 95 psig (2) 60 psig C. (1) 85 psig (2) 75 psig D. (1) 85 psig (2) 60 psig

17.

Given the following conditions:

Unit 2 has tripped from 100% power

2-EOP-01, SPTAs are complete

2-EOP-02, Reactor Trip Recovery has been entered Which ONE of the following completes the statement below?

IAW 2-EOP-02, the crew is required to maintain RCS Tavg between ________.

A. 505 and 515 °F B. 515 and 525 °F C. 525 and 535 °F D. 535 and 545 °F

18.

Given the following conditions:

10:00 Unit 2 was tripped due to an Excess Steam Demand Event (ESDE) inside Containment 10:01 the crew recognized that the ESDE in progress was from the 2A S/G 10:09 the crew FIRST noticed 2A S/G had reached dryout by observing the Tcold trend below:

USING THE GRAPH ON THE NEXT PAGE Which ONE of the following completes the statements below in accordance with the requirements of ADM-11.16, Transient Procedure Use and Adherence, Section 4.3.1.N, RCS Temperature Stabilization Guidance following an ESDE?

The crew is required to establish a pressure band on the 2B S/G of ____(1)____.

Stabilization of the 2B S/G was required to be commenced____(2)____.

REFERENCE PROVIDED (GRAPH ON NEXT PAGE)

A. (1) 300-350 psia (2) as soon as the crew verified that ONLY the 2A S/G is faulted B. (1) 300-350 psia (2) when the ESDE was terminated, or the 2A S/G was blown dry C. (1) 525-575 psia (2) as soon as the crew verified that ONLY the 2A S/G is faulted D. (1) 525-575 psia (2) when the ESDE was terminated, or the 2A S/G was blown dry

19.

Given the following conditions:

Unit 1 is at 100% power

AB Busses are aligned to the B train

1AA Battery Charger is OOS Subsequently:

1A Battery Charger trips

1-AOP-50.08, Loss of 125 VDC Station Battery Charger has been entered

The crew completes the following actions:

1AB Charger is aligned to the 1AB DC Bus

Divorced the 1AB DC Bus from the 1B DC bus by opening 60135, TIE 1AB-1A (inside) and 60130, TIE 1A-1AB (outside)

Which ONE of the following completes the statements below?

TS 3.8.2.3 - DC Distribution - Operating, Surveillance Requirement 4.8.2.3.1, D.C. bus train shall be determined OPERABLE and energized, is required to be performed within a MAXIMUM of ____(1)____.

In accordance with 1-AOP-50.08, the operator is required to FIRST CLOSE

____(2)____ breakers to now align the 1AB DC Bus to 1A DC bus.

A. (1) 30 minutes (2) 60135, TIE 1AB-1A (inside) THEN 60130, TIE 1A-1AB (outside)

B. (1) 30 minutes (2) 60130, TIE 1A-1AB (outside) THEN 60135, TIE 1AB-1A (inside)

C. (1) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (2) 60135, TIE 1AB-1A (inside) THEN 60130, TIE 1A-1AB (outside)

D. (1) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (2) 60130, TIE 1A-1AB (outside) THEN 60135, TIE 1AB-1A (inside)

20.

Given the following conditions:

Unit 2 is at 100% power Subsequently:

CEA #1, Reg Group 5 dropped to the bottom of the core

2-AOP-66.01, Dropped or Misaligned CEA Abnormal Operations is in progress Which ONE of the following completes the statements below?

The Core Mimic (Display 6801) for CEA #1 would indicate ____(1)____.

During the recovery of CEA #1, CEA Motion Inhibit (CMI) ____(2)____ be required to be bypassed.

A. (1) GREEN (2) will B. (1) GREEN (2) will NOT C. (1) ORANGE (2) will D. (1) ORANGE (2) will NOT

21.

Given the following conditions:

Unit 2 is performing a Reactor Startup in accordance with 2-GOP-302, Reactor Plant Startup - Mode 3 to Mode 2 at Step 4.5.2, Critical Approach

Below is the listed initial power levels power to commence approach to criticality and the power when the reactor was announced critical SU Channel BF3 (CPS) WRNI (% Power)

A B A B

-8 INITIAL 50 50 3 x 10 3 x 10-8 CRITICAL 3200 400 4 x 10-7 3 x 10-7 Which ONE of the following describes the status of the BF3 detectors and can the startup continue?

SU Channel ____(1)____ is indicating AS EXPECTED.

In accordance with 2-GOP-302, the Reactor Startup ____(2)____ continue?

A. (1) A ONLY (2) can B. (1) A ONLY (2) can NOT C. (1) B ONLY (2) can D. (1) B ONLY (2) can NOT

22.

Given the following conditions:

Unit 1 is at 11% power

The condenser has developed a small air leak

The crew has entered 1-AOP-12.01, Loss of Condenser Vacuum

Condenser vacuum indicates 3.5 inHgA and DEGRADING Which ONE of the following completes the statements below?

In accordance with 1-AOP-12.01, the crew is required to trip the turbine at a setpoint of

____(1)____ inHgA. If the vacuum continues to degrade, the Steam Bypass Control System will become unavailable at a setpoint of ____(2)____ inHgA.

A. (1) 5.9 (2) 8.859 B. (1) 5.9 (2) 12 C. (1) 8.5 (2) 8.859 D. (1) 8.5 (2) 12

23.

Given the following conditions:

Unit 1 automatically tripped due to a Small Break LOCA

The crew is performing the actions of 1-EOP-01, SPTAs Subsequently:

RIS-26-3-1, Channel #3 Containment Isolation Radiation Monitor Hi Hi alarm condition occurs

The extra RCO is performing the actions of 1-AOP-26.02, Area Radiation Monitors Which ONE of the following completes the statement below?

In accordance with 1-AOP-26.02 step 4.2.2.4.A, verifying alarm validity, the BLUE fail safe light ____(1)____ LIT for a VALID alarm.

RIS-26-3-1 utilizes a ____(2)____ detector.

A. (1) is (2) Scintillation B. (1) is (2) Geiger-Mueller C. (1) is NOT (2) Scintillation D. (1) is NOT (2) Geiger-Mueller

24.

Given the following conditions:

Unit 1 tripped due to a LOOP

ALL AFW has been LOST

1-EOP-06, Total Loss of Feed has been entered Subsequently:

Offsite power has been restored to the B train

Annunciator A-3, 6.9 kV Swgr 1B1 Current Trip is LIT Which ONE of the following completes the statements below?

In accordance with 1-EOP-06, the ____(1)____ pump will be FIRST used to restore Feedwater flow.

In order to successfully establish Once Through Cooling ____(2)____ Pump(s) is/are required to be running.

A. (1) 1B Condensate (2) ALL available Charging (NO HPSI)

B. (1) 1B Condensate (2) at Least 1 High Pressure Safety Injection (HPSI)

C. (1) 1B Main Feed Water (2) ALL available Charging (NO HPSI)

D. (1) 1B Main Feed Water (2) at Least 1 High Pressure Safety Injection (HPSI)

25.

Given the following conditions:

Unit 2 has tripped

2-EOP-01, SPTAs are in progress

Pressurizer pressure is 1800 psia and LOWERING

Pressurizer level is 15% and LOWERING

RCS 495 °F and LOWERING

2A SG is 800 psia and LOWERING

2B SG is 800 psia and LOWERING

Containment pressure is 1.5 psig and RISING Which ONE of the following describes the required actions and procedure selection?

Emergency Boration ____(1)____ required and the crew will transition to ____(2)____.

A. (1) is (2) 2-EOP-03, LOCA B. (1) is (2) 2-EOP-05, ESDE C. (1) is NOT (2) 2-EOP-03, LOCA D. (1) is NOT (2) 2-EOP-05, ESDE

26.

Given the following conditions:

Unit 2 tripped from 100% power due to a Loss of Offsite Power (LOOP)

2-EOP-09, LOOP/LOFC is in progress

30 minutes post trip, the crew commenced a Natural Circulation Cooldown per 2-AOP-01.13, Natural Circulation Cooldown

The crew cooled down the RCS to 325 °F in 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Which ONE of the following completes the statements below?

During the RCS cooldown, the S/G ADVs were operated in ____(1)____.

An RCS soak ____(2)____ required to performed IAW 2-AOP-01.13.

A. (1) manual/manual ONLY (2) is B. (1) manual/manual ONLY (2) is NOT C. (1) auto/manual OR manual/manual (2) is D. (1) auto/manual OR manual/manual (2) is NOT

27.

Given the following conditions:

Unit 1 has a SGTR in the 1A S/G

1-EOP-04, SGTR is in progress

LOOP has occurred

EDGs are supplying power

MINIMUM Subcooling is MET

1-EOP-99, Appendix R, Steam Generator Isolation is in progress

HCV-08-2A, S/G 1A Atmospheric Dump Valve, will NOT CLOSE Which ONE of the following completes the statements below?

Appendix R, Steam Generator Isolation directs the Crew to isolate HCV-08-2A ADV by closing the isolation valve ____(1)____.

Based on the given conditions, 1-EOP-04 directs the Crew to COOLDOWN at a rate NOT to exceed ___(2)___ in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period.

A. (1) LOCALLY ONLY (2) 30 °F B. (1) LOCALLY ONLY (2) 100 °F C. (1) at RTGB-102 or LOCALLY (2) 30 °F D. (1) at RTGB-102 or LOCALLY (2) 100 °F

28.

Given the following conditions:

Unit 1 is in Mode 2 performing a Reactor Startup

Critical Rod Height Data is being taken

Reactor Power is 5 X 10-4%

The Board RCO notes:

RCP 1A1 amps are 500 amps slowly RISING

RCP 1A2 amps are 425

RCP 1B1 amps are 415

RCP 1B2 amps are 420 Which ONE of the following completes the statements below?

Based on these continuing degrading conditions, and no operator action, the Reactor

____(1)____ AUTOMATICALLY TRIP.

In accordance with ADM-11.16, Transient Procedure Use and Adherence, following the Reactor trip, the BRCO ____(2)____ required to perform 1-EOP-01, SPTAs step 1 from memory, PRIOR to tripping the 1A1 RCP.

A. (1) will (2) is B. (1) will NOT (2) is NOT C. (1) will (2) is D. (1) will NOT (2) is NOT

29.

Which ONE of the following describes the operation of the Reactor Coolant Pump (RCP) Oil Lift Pumps after a RCP has tripped?

____(1)____ RCP Oil Lift pump(s) will start on RCP ____(2)____.

A. (1) BOTH (2) breaker opening B. (1) BOTH (2) Low Lube Oil Pressure C. (1) ONLY the Lead (2) breaker opening D. (1) ONLY the Lead (2) Low Lube Oil Pressure

30.

Which ONE of the following completes the statements below?

As VCT level changes, V2504, RWT Suction to Charging Valve OPENS at a setpoint of ____(1)____ and LOWERING.

V2501, VCT Outlet Valve OPENS at a setpoint of ____(2)____ and RISING.

A. (1) 5%

(2) 15%

B. (1) 5%

(2) 35%

C. (1) 15%

(2) 15%

D. (1) 15%

(2) 35%

31.

Given the following conditions:

Unit 1 is at 300°F and cooling down on Shutdown Cooling (SDC)

RCS cooldown rate is 75°F/Hr

HCV-3657, SDC Temp Control is 50% OPEN

FCV-3306, SDC Return Flow is 100% OPEN

The crew enters 1-AOP-03.02, Shutdown Cooling Subsequently:

A loss of Instrument Air occurs Which ONE of the following completes the statements below?

FCV-3306, SDC Return Flow, will ____(1)____.

IAW 1-AOP-03.02, Shutdown Cooling Abnormal Operations, the crew will reestablish the cooldown rate by locally control SDC temperature by THROTTLING HCV-3657, SDC Temp Control in the ____(2)____ direction.

A. (1) be failed OPEN (2) OPEN B. (1) be failed OPEN (2) CLOSED C. (1) fail CLOSED (2) OPEN D. (1) fail CLOSED (2) CLOSED

32.Given the following conditions:

00:00 Unit 2 has experienced a LOCA 00:15 2-EOP-03, LOCA is entered 00:50 HPSI has been throttled IAW, 2-EOP-99, App S, Safety Injection Throttling and Restoration with the following flows:

Pressurizer level is 32% and slowly RISING 2A Flow is 200 gpm 2B Flow is 400 gpm 01:20 2A HPSI pump trips 01:25 Pressurizer level is 50% and slowly LOWERING Pressurizer Pressure is 700 psia SI Flow is 400 gpm ALL Available Charging Pumps are running Which ONE of the following completes the statements below?

At time 01:25:00, 2-EOP-99, Figure 2, Safety Injection Flow vs. RCS Pressure

____(1)____ being met.

The crew is required to ____(2)____.

REFERENCE PROVIDED A. (1) is (2) throttle open HPSI header injection valves ONLY B. (1) is (2) BOTH throttle open HPSI header injection valves AND attempt 1 restart of the 2A HPSI pump C. (1) is NOT (2) throttle open HPSI header injection valves ONLY D. (1) is NOT (2) BOTH throttle open HPSI header injection valves AND attempt 1 restart of the 2A HPSI pump

33.

Given the following conditions:

Unit 2 is at 100% power

Annunciator H-32, Quench Tank Level High/Low is LIT Which ONE of the following completes the statements below?

The HIGH alarm setpoint is ____(1)____ .

IAW 2-ARP-01-H32, the crew is required to reduce level by draining the Quench Tank to the ____(2)____ per 2-NOP-01.07, Quench Tank Operation.

A. (1) 60%

(2) Hold Up Tank (HUT)

B. (1) 60%

(2) Reactor Drain Tank (RDT)

C. (1) 70%

(2) Hold Up Tank (HUT)

D. (1) 70%

(2) Reactor Drain Tank (RDT)

34.

Given the following conditions:

Unit 1 has just completed drawing a bubble from a solid plant condition

Pressurizer pressure is 260 psia

RCS temperature is 185°F

A PORV is LEAKING fluid to a downstream pressure of 4.0 psig Which ONE of the following completes the statements below?

Expected PORV tailpipe temperature is ____(1)____.

Technical Specification 3.4.6.2, RCS Operational Leakage limit for RCS leakage through the PORV into the Quench Tank is ____(2)____.

A. (1) ~400 ºF (2) 1 gpm B. (1) ~400 ºF (2) 10 gpm C. (1) ~320 ºF (2) 1 gpm D. (1) ~320 ºF (2) 10 gpm

35.

Given the following conditions:

Unit 2 is at 100% power

AB Busses are aligned to the B side

2A and 2B Component Cooling Water (CCW) pumps are running Subsequently:

2A CCW pump has tripped

The crew has entered 2-AOP-14.01, Component Cooling Water Abnormal Operations

The crew completes the following actions:

o Mechanically aligns the 2C CCW pump to the A CCW Header o Annunciator S-26, 2C CCW Pump Hdr Valves/AB Bus Misalignment alarms o Electrically aligns the 2AB 4.16Kv bus to the A side (ONLY electrical swap) o Starts the 2C CCW pump Which ONE of the following completes the statements below?

Partial CCW flow ____(1)____ continue to the A Essential CCW header if all N header isolation valves are OPEN.

Unit 2 Tech Spec 3.7.3, CCW, ____(2)____ allow the Crew 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to restore proper CCW system alignment comply with the Technical Specification.

A. (1) will (2) does B. (1) will (2) does NOT C. (1) will NOT (2) does D. (1) does NOT (2) does NOT

36.

Given the following conditions:

Unit 1 is at 100% power

RCS pressure is slowly RISING due an ongoing event Which ONE of the following completes the statements below?

As RCS Pressure RISES, HIC-1100, PZR Pressure Controller, OUTPUT will

____(1)____.

IF the RCS Pressure continues to RISE, ____(2)____ PORVs will OPEN.

A. (1) INCREASE (2) ONE B. (1) INCREASE (2) TWO C. (1) DECREASE (2) ONE D. (1) DECREASE (2) TWO

37.

Given the following conditions:

Unit 1 is performing a plant startup in accordance with 1-GOP-201, Reactor Plant Startup - Mode 2 to Mode 1

Power ascension is in progress Which ONE of the following completes the statements below?

The Reactor Protection System (RPS) Hi Startup Rate Trip Bypass setpoint is

____(1)____ power.

The RPS Hi Startup Rate trip is bypassed ____(2)____.

A. (1) 1%

(2) automatically B. (1) 1%

(2) via operator action C. (1) 15 %

(2) automatically D. (1) 15 %

(2) via operator action

38.

Given the following conditions:

Unit 2 is at 100% power

The AB electrics are aligned to the B Train

2A HPSI Pump is OOS

2B Charging Pump is OOS Subsequently:

Unit 2 has experienced a LOCA

2-EOP-03, LOCA is in progress

B ESFAS Cabinet FAILED to actuate

2A and 2C Charging Pumps are operating

2A LPSI Pump is operating

RCS Pressure is 500 psia

RCS CETs are 492 °F Which ONE of the following completes the statements below?

Core Heat Removal Safety Function ____(1)____ MET.

Safety Injection Tanks ____(2)____ injecting to the RCS REFERENCE PROVIDED A. (1) is (2) are B. (1) is (2) are NOT C. (1) is NOT (2) are D. (1) is NOT (2) are NOT

39.

Given the following conditions:

Unit 1 is at 100% power

The 1C CCW Pump is out of service Subsequently:

The 1A CCW Pump trips and cannot be restarted

1-AOP-14.01, CCW Abnormal Ops has been entered Which ONE of the following completes the statements below?

1-AOP-14.01, directs the securing of the A train Containment Fan Coolers (CFC).

CFC 1A and ____(1)____ are required to be stopped.

If Containment Temperature exceeds 120F, the unit must be removed from service within a MAXIMUM OF ____(2)____ minutes.

A. (1) 1B (2) 45 B. (1) 1B (2) 60 C. (1) 1C (2) 45 D. (1) 1C (2) 60

40.

Given the following timeline:

0000 Unit 2 has tripped from 100% power 0015 Containment temperature is 130°F Containment Pressure is 3.8 psig Which ONE of the following describes the status of the Containment Coolers at time 0000 and time 0015?

of Containment Fan TIME Coolers Running Speed A. (1) 0000 THREE (3) FAST (2) 0015 THREE (3) FAST B. (1) 0000 FOUR (4) FAST (2) 0015 FOUR (4) SLOW C. (1) 0000 THREE (3) FAST (2) 0015 FOUR (4) SLOW D. (1) 0000 FOUR (4) FAST (2) 0015 FOUR (4) FAST

41.

Which ONE of the following completes the statements below?

Unit 2 Containment Spray Pumps ____(1)____ have CCW seal cooling water supply.

Following actuation of RAS, Unit 2 Containment Spray flow ____(2)____ cooled by the Shutdown Cooling (SDC) Heat Exchangers.

A. (1) do (2) is B. (1) do (2) is NOT C. (1) do NOT (2) is D. (1) do NOT (2) is NOT

42.

Which ONE of the following completes the statements below?

Unit 1 experienced a Turbine Trip, Moisture Separator Reheater (MSR) Block Valves, MV-08-4, MV-08-6, MV-08-8 and MV-08-10, will be ____(1)____ CLOSED.

Unit 1 MSR Block valves can be MANUALLY operated via ____(2)____.

A. (1) AUTOMATICALLY (2) an RTGB Control Switch B. (1) AUTOMATICALLY (2) the OVATION System C. (1) MANUALLY (2) an RTGB Control Switch D. (1) MANUALLY (2) the OVATION System

43.

Which ONE of the following completes the statements below?

Unit 1 Main Steam System has ____(1)____ Atmospheric Dump Valves (ADVs).

Unit 1 ADVs can be isolated from the Main Steam System via ____(2)____ operated valve.

A. (1) 2 (TWO)

(2) motor B. (1) 2 (TWO)

(2) manual (ONLY)

C. (1) 4 (FOUR)

(2) motor D. (1) 4 (FOUR)

(2) manual (ONLY)

44.

Given the following conditions:

Unit 1 is at 60% power during a plant startup

1A and 1B Main Feedwater Pumps (MFWP) are operating Subsequently:

1A Condensate Pump trips

Lowest observed MFWP Suction pressure was 300 psig Which ONE of the following completes the statements below?

The ____(1)____ will AUTOMATICALLY trip.

The DIRECT cause of the above AUTOMATIC trip signal is an interlock based on

____(2)____.

A. (1) 1A MFWP ONLY (2) LOW MFWP Suction Pressure Logic B. (1) 1A MFWP ONLY (2) 1A Condensate Pump Breaker Trip Logic C. (1) 1A and 1B MFWPs (2) LOW MFWP Suction Pressure Logic D. (1) 1A and 1B MFWPs (2) 1A Condensate Pump Breaker Trip Logic

45.

Given the following conditions:

Unit 1 is at 100% power Subsequently:

Annunciator G-9, 1B S/G Level High/Low is received

DCS Flat Panel display for FW Control indicates:

LT-9006, 1B S/G NR Level is BLUE ON WHITE

LT-9021, 1B S/G NR Level is GREEN

1B S/G FWCS MED OUTPUT IS BLACK ON CYAN

LT-9023 A-D, 1B S/G NR Water Level is 66% and STABLE Which ONE of the following completes the statements below?

The FWCS Output for the 1B S/G indicates ____(1)____.

Based on the given conditions, 1-AOP-09.01, Feedwater Control Systems Abnormal Operations, Immediate Operator actions ____(2)____ require MANUAL control of 1B MFRV to be taken.

A. (1) BAD (2) do B. (1) BAD (2) do NOT C. (1) POOR (2) do D. (1) POOR (2) do NOT

46.

Given the following conditions:

Unit 1 tripped from 100% power

1C AFW pump is out of service

AFAS-1 and AFAS-2 has actuated

AFW flows have been throttled to 250 gpm

Steam Generator Levels are 27% NR and slowly RISING

1-EOP-01, SPTAs are in progress Subsequently:

A Loss of Offsite power occurs Following the completion of EDG load sequencing:

AFW flow rates to the Steam Generators would be ____(1)_____, AND In accordance with 1-NOP-99.07 Hard Cards, the Crew ____(2)____ REQUIRED to LOWER AFW flow to 150 gpm for the next 5 (FIVE) minutes.

A. (1) ~250 gpm (2) is B. (1) ~250 gpm (2) is NOT C. (1) ~320 gpm (2) is D. (1) ~320 gpm (2) is NOT

47.

Given the following conditions:

Unit 1 is at 2% power

S/G water level is being maintained with the Motor Driven AFW pumps Subsequently:

The 1A Auxiliary Feedwater pump trips Which ONE of the following describes the expected plant response BEFORE the automatic Reactor Trip on Low Steam Generator (S/G) Level?

Reactor Coolant System (RCS) Pressure will ____________.

A. RISE, because the RCS temperature RISES B. RISE, because the RCS delta T power RISES C. LOWER, because the S/G level initially RISES (swell phenomenon)

D. LOWER, because the boiling rate in the S/G tube bundle region RISES

48.

Given the following conditions:

Unit 2 has tripped from 100% power

On the trip, the AUTO transfer of the 2A Aux Transformer FAILED Which ONE of the following describes the RUNNING Reactor Coolant Pumps?

With NO additional operator actions, the ________ Reactor Coolant Pumps are RUNNING.

A. 2A1 and 2B1 B. 2A1 and 2A2 C. 2A2 and 2B1 D. 2A2 and 2B2

49.

Given the following conditions:

Unit 2 is at 100% power

The AB busses are aligned to the A side

The crew is realigning the AB busses from A side to B side per 2-NOP-52.02, Alignment of 2AB Buses and Components

The Fire and Security SUPS and Vital AC SUPS Inverters are being removed from service Which ONE of the following completes the statements below?

The Fire and Security SUPS DC back up power supply is the ____(1)____ 125VDC Bus.

The Vital AC SUPS DC back up power supply is the ____(2)____.

A. (1) 2C (2) 2C B. (1) 2C (2) 2D C. (1) 2D (2) 2C D. (1) 2D (2) 2D

50.

Given the following conditions:

Unit 2 is at 100% power

The crew is performing the 2B EDG Monthly surveillance per 2-OSP-59.01B Which ONE of the following completes the statements below?

The 2B EDG SLOW speed start ____(1)____ be performed from the Control Room.

If an EMERGENCY stop of the 2B EDG is required during the 2-OSP-59.01B monthly surveillance run, this ____(2)____ be performed from the Control Room A. (1) can (2) can B. (1) can (2) can NOT C. (1) can NOT (2) can D. (1) can NOT (2) can NOT

51.

Given the following conditions:

Unit 1 is at 100% power

The SNPO reports that the 1A Diesel Fuel Oil Transfer pump has tripped

The Diesel Oil Storage Tanks Level is greater than Technical Specification MINIMUM levels Which ONE of the following completes the statements below?

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

If a Loss of Offsite Power were to occur, with NO operator actions, the 1A EDG would run ____(2)____.

A. (1) MET (2) for ~47 minutes before running out of fuel B. (1) MET (2) with make-up via gravity feed when Day Tank level drops below the low level set point C. (1) NOT MET (2) for ~47 minutes before running out of fuel D. (1) NOT MET (2) with make-up via gravity feed when Day Tank level drops below the low level set point

52.

Given the following conditions:

NEW fuel receipt is in progress on Unit 2

A NEW fuel assembly was dropped resulting in a clad breach

The crew has entered 2-AOP-67.01, Accidents Involving New or Spent Fuel Which ONE of the following completes the statement below?

A NOTE in 2-AOP-67.01 states that the ____(1)____ radiation associated with a damaged NEW fuel assembly ____(2)____ .

A. (1) Alpha (2) will NOT cause actuation of Area or Process Radiation Monitor high radiation alarms B. (1) Alpha may cause actuation of a high radiation signal in the control room and (2) cause isolation of the Fuel Handling Building Ventilation and activate Shield Building Ventilation C. (1) Alpha and Beta (2) will NOT cause actuation of Area or Process Radiation Monitor high radiation alarms D. (1) Alpha and Beta (2) may cause actuation of a high radiation signal in the control room and cause isolation of the Fuel Handling Building Ventilation and activate Shield Building Ventilation

53.

Given the following conditions:

Unit 1 is at 100% power Subsequently:

Unit 1 tripped due to a LOCA resulting in a SIAS

HCV-21-7A, Debris Discharge Isolation indicates:

o Green Light ON Red Light OFF

HCV-21-7B, Debris Discharge Isolation indicates:

o Green Light OFF Red Light ON Which ONE of the following completes the statements below?

____(1)____ is in the correct SIAS position.

HCV-21-7A or HCV-21-7B, must be operated ____(2)____ to place them in the required position.

A. (1) HCV-21-7A (2) on RTGB 102 B. (1) HCV-21-7A (2) LOCALLY C. (1) HCV-21-7B (2) on RTGB 102 D. (1) HCV-21-7B (2) LOCALLY

54.

Given the following conditions:

Unit 2 is at 100% power

Annunciator F-5, INSTR AIR PRESS HI/LO alarms

Instrument Air Pressure Instrument reads 100 psig and LOWERING The crew ___(1)___ start the standby Instrument Air Compressors from the Control Room If Instrument Air Pressure continues to lower, the crew is required to commence a Unit shutdown due to ____(2)____.

A. (1) can (2) MSIVs failing CLOSED B. (1) can (2) not being able to maintain S/G water level C. (1) can NOT (2) MSIVs failing CLOSED D. (1) can NOT (2) not being able to maintain S/G water level

55.

Given the following conditions:

Unit 2 is in Mode 1

Health Physics just exited containment after performing surveys via the personnel access hatch and NO additional entries will be made

0-NOP-68.00, Containment Entries, Attachment 6, Operations Department Containment Entry Checklist has been completed Which ONE of the following completes the statements below?

After exiting the containment personnel access hatch door seals ____(1)____ REQUIRED to be tested in accordance with 2-OSP-68.03, Airlock Periodic Leak Testing.

In accordance with TS 3.6.1.3, Containment Air Locks, the LOWEST Mode the personnel hatch is required to be operable is ____(2)____.

A. (1) is (2) Mode 4 B. (1) is (2) Mode 5 C. (1) is NOT (2) Mode 4 D. (1) is NOT (2) Mode 5

56.

Which ONE of the following completes the statements below?

When describing the Unit 1 and Unit 2 Reactor Coolant Systems, Unit ____(1)____

has a LARGER volume.

This difference in volume must be accounted for during ____(2)____ calculations.

A. (1) 1 (2) RCS Leak Rate B. (1) 1 (2) Boron Concentration C. (1) 2 (2) RCS Leak Rate D. (1) 2 (2) Boron Concentration

57.

Given the following conditions:

Unit 2 is at 100% power

Pressurizer Level Control is selected to X channel Subsequently:

LT-1110X fails LOW

The crew enters 2-AOP-01.10, Pressurizer Pressure and Level Which ONE of the following completes the statement below?

A Train Pressurizer Heaters will be de-energized when the power supply breaker on

____(1)____ opens.

After the Back Interlock Bypass Key Switch is placed in LEVEL, power to the A side Pressurizer Heaters ____(2)____ be restored.

A. (1) 2A3 4.16KV Switchgear (2) CAN B. (1) 2A3 4.16KV Switchgear (2) CAN NOT C. (1) 2A3 Load Center (2) CAN D. (1) 2A3 Load Center (2) CAN NOT

58.

Given the following conditions:

Unit 2 was at 100% power

The crew is performing 2-AOP-22.01, Rapid Downpower to remove a Heater Drain Pump from service Subsequently:

Reg Group 5 CEA # 69 became mechanically bound and is misaligned from the Group by 10 inches Which ONE of the following completes the statement below?

CEA # 69 ____(1)____ indication will be HIGHEST.

The ACTUAL CEA #69 position can be determined by using ____(2)____ .

A. (1) Pulse Counter (2) Ovation ONLY B. (1) Pulse Counter (2) Either Distributed Control System or Ovation C. (1) Reed Switch Position Transmitter (RSPT)

(2) Ovation ONLY D. (1) Reed Switch Position Transmitter (RSPT)

(2) Either Distributed Control System or Ovation

59.

Given the following conditions:

Unit 1 is at 98% power

CEA #66 has dropped to the bottom of the core, near Linear Range Nuclear Instrument Channel D

The crew has entered 1-AOP-66.01, Dropped or Misaligned CEA Abnormal Operations

Multiple annunciators are LIT including:

L-20, Reactor Power Range Subchannel Deviation

BEACON Azimuthal Power Tilt - Tq value is 0.060 Which ONE of the following completes the statements below?

L-20 ____(1)____ an expected alarm for this condition.

IF L-20 is VALID, Tech Spec 3.2.4, Azimuthal Power Tilt - Tq ____(2)____ REQUIRED to be entered.

A. (1) IS (2) IS B. (1) IS (2) IS NOT C. (1) IS NOT (2) IS D. (1) IS NOT (2) IS NOT

60.

Given the following conditions:

Unit 2 is in Mode 3 at Normal Operating Temperature and Pressure

P8010, SBCS Main Steam Pressure Transmitter, has failed and is out of service

P8010 input is bypassed per 2-NOP-102.01, DCS Operations

Steam Bypass (SBCS) is in service with PCV-8801 controlling RCS temperature Subsequently:

P8020, SBCS Main Steam Pressure Transmitter, RAPIDLY fails off-scale HIGH Which ONE of the following complete the statements below?

PCV-8801 position will ____(1)____. PIC-8010, SBCS Master Controller will

____(2)____,

A. (1) go FULL CLOSED (2) swap to MANUAL B. (1) go FULL CLOSED (2) remain in AUTOMATIC control C. (1) remain AS IS (2) swap to MANUAL D. (1) remain AS IS (2) remain in AUTOMATIC control

61.

Given the following conditions:

Unit 2 is at 100% power

Containment Mini Purge is in progress with HVE-7A, Continuous Cntmt/H2 Purge Fan IAW 2-NOP-25.02, Continuous Containment / Hydrogen Purge System Operation Subsequently:

Unit 2 tripped due to a SBLOCA

Crew has entered 2-EOP-03, LOCA

SIAS and CIAS has actuated Which ONE of the following completes the statements below?

Based on the above conditions FCV-25-20 and FCV-25-21, Continuous CNMT Purge ISOL (Mini Purge) Valves will CLOSE and HVE-7A, ____(1)____ AUTOMATICALLY TRIP.

The Crew ____(2)____ override the CIAS signal to OPEN the Continuous CNMT Purge ISOL (Mini Purge) Valves to facilitate hydrogen removal per App N, Hydrogen Purge System Operation.

A. (1) will (2) can B. (1) will (2) can NOT C. (1) will NOT (2) can D. (1) will NOT (2) can NOT

62.

Which ONE of the following completes the statements below?

In accordance with TS 3.9.11, Spent Fuel Storage Pool, a MINIMUM level of

____(1)____ feet over the top of irradiated fuel assemblies is required.

____(2)____ is(are) used on the SFP cooling return to prevent a passive leak from draining the Spent Fuel Pool.

A. (1) 23 (2) A check valve B. (1) 23 (2) Siphon breaker holes C. (1) 29.5 (2) A check valve D. (1) 29.5 (2) Siphon breaker holes

63.

Given the following conditions:

Unit 2 is at 12% power

The Main Generator is synchronized to the grid

The Main Generator picked up 40 MWe and then tripped after 5 seconds Which ONE of the following describes the expected plant response with NO operator actions 1 minute later?

A. Reactor power indicates 12% with SBCS opening to control pressure B. Reactor power indicates 12% with ADVs opening to control temperature C. The High Power Feed Reg Valves controlling SG levels in automatic D. Trip Circuit Breaker (TCB) lights indicate GREEN with SBCS closing to control pressure

64.

Given the following conditions:

Unit 1 Liquid Waste Radiation Monitor R-6627 has been declared out of service

The crew is performing a liquid release IAW 1-NOP-06.01, Controlled Liquid Release to the Circulating Water Discharge Which of the following LISTED actions describe the MINIMUM required to perform a controlled liquid release to the Circulating Water Discharge, IAW 1-NOP-06.01?

1. An independent verification of the Initial valve alignment

2. Two independent radioactivity analysis of the tank to be released

3. Two independent release rate calculations 1-NOP-06.01 Controlled Liquid Release to the Circulating Water Discharge ACTIONS REQUIRED ACTIONS NOT REQUIRED A. 1 AND 2 3 B. 1 AND 3 2 C. 2 AND 3 1 D. 1, 2 AND 3 NONE

65.

Given the following conditions:

Unit 2 Component Cooling Water (CCW) system has developed a leak

LA-10, CCW SURGE TANK COMPARTMENT A LEVEL LOW, is locked in

LB-10, CCW SURGE TANK LEVEL HIGH/COMPARTMENT B LEVEL LOW, alarmed but subsequently clears Which ONE of the following describes the CCW system load that is LOST and the actions needed to restore CCW to that load per 2-AOP-14.01, CCW Abnormal Operations?

CCW is LOST to the ____(1)____.

The Crew is required to place the ____(2)____.

A. (1) Fuel Pool Heat Exchanger (2) A train N Header valve control switches to CLOSE then OPEN B. (1) Fuel Pool Heat Exchanger (2) B train N Header valve control switches to CLOSE then OPEN C. (1) Letdown Heat Exchanger (2) A train N Header valve control switches to CLOSE then OPEN D. (1) Letdown Heat Exchanger (2) B train N Header valve control switches to CLOSE then OPEN

66.

Given the following conditions:

BOTH Units are at 100% power

MINIMUM Shift Crew Complement is filling ALL required positions

At 03:30 the Unit 1 Desk RCO (DRCO) had to leave site due to an emergency In accordance with OPS Policy 201, Shift Complement, which ONE of the following describes how the position can be filled.

The VACANT DRCO Position ____(1)____ remain vacant until shift turnover occurs at 06:30 and being filled by the oncoming DRCO.

If the Shift Manager fills the STA position in a dual role, the STA (SRO Licensed)

____(2)____ fill the DRCO position.

A. (1) can (2) can B. (1) can (2) can NOT C. (1) can NOT (2) can D. (1) can NOT (2) can NOT

67.

Which ONE of the following states the MINIMUM Shutdown Cooling flow necessary to reduce RCS boron concentration in accordance with Tech Spec 3.1.1.3, Boron Dilution?

A. 4117 gpm B. 3570 gpm C. 3000 gpm D. 1000 gpm

68.

Given the following conditions:

Unit 2 Core Reload is in progress

BOTH BF3 Log Startup Channels are in service

Audible count rate monitoring is selected to B Channel Subsequently:

The B BF3 Log Startup Channel has failed low IAW 0-NOP-67.05, Refueling Operation, which ONE of following describes the impact on the fuel movement?

With the B BF3 Log Startup Channel inoperable, the core reload MUST A.

STOP until it is returned to service The core reload can continue by substituting a Wide Range Log Safety B.

Channel and selecting the audible count rate to that WRNI channel The core reload can continue by substituting an Appendix R Wide Range C.

(Excore) and selecting the audible count rate to A BF3 Log Startup Channel The core reload can continue with the operable A BF3 Log Startup Channel D. as the ONLY available Source Range indication, as long as audible count rate is selected for that channel.

69.

Which ONE of the following completes the statements below?

IAW Technical Specifications, Table 1.2, Operational Modes, Mode 6 Keff is required to be less than or equal to ____(1)____.

When transitioning from Mode 6 and entering Mode 5, Mode 5 is entered when the

____(2)____ Rx Vessel Head Stud is fully tensioned.

A. (1) 0.99 (2) FIRST B. (1) 0.99 (2) LAST C. (1) 0.95 (2) FIRST D. (1) 0.95 (2) LAST

70.

Which ONE of the following completes the statements below?

In accordance with TS 3.1.1.5, Minimum Temperature for Criticality, the Reactor Coolant System lowest operating loop temperature (Tavg) shall be greater than or equal to ____(1)____ in Modes 1 and 2.

With a Reactor Coolant System operating loop temperature (Tavg) less than the value above, the crew is required to restore Tavg to within its limit within a MAXIMUM of

____(2)____.

A. (1) 515°F (2) 15 minutes B. (1) 515°F (2) 30 minutes C. (1) 525°F (2) 15 minutes D. (1) 525°F (2) 30 minutes

71.

Given the following conditions:

Unit 1 is performing a plant start up IAW 1-GOP-201, Mode 2 to Mode 1

Reactor Power is 10% on hold for turbine roll

A very small RCS leak is suspected inside containment Which ONE of the following completes the statements below IAW 0-NOP-68.00, Containment Entries Modes 1 - 4?

The Containment Evacuation Alarm is tested via ____(1)____.

Personnel ____(2)____ enter the biological shield wall to determine the location of the leak.

A. (1) Pushbutton at Unit Supervisor Desk (2) Can B. (1) Pushbutton at Unit Supervisor Desk (2) Can NOT C. (1) Key switch on the Rad Monitoring Panel D (2) Can D. (1) Key switch on the Rad Monitoring Panel D (2) Can NOT

72.

Which ONE of the following completes the statement below?

In accordance with RP-AA-101, Personnel Monitoring Program Total Effective Dose Equivalent (TEDE) Administrative limit for Radiation Workers with NO extensions is

____(1)____.

In accordance with HPP-30, Personnel Monitoring, Appendix 6, Authorization to Exceed Administrative Limits, The MAXIMUM TEDE Annual Limit can be authorized for NON-EMERGENCY situations is ____(2)_____.

A. (1) 2000 mrem / year (2) 4500 mrem / year B. (1) 2000 mrem / year (2) 5000 mrem / year C. (1) 3000 mrem / year (2) 4500 mrem / year D. (1) 3000 mrem / year (2) 5000 mrem / year

73.

Given the following conditions:

Unit 1 has just tripped Prior to procedure in hand implementation of 1-EOP-01, Standard Post Trip Actions, which ONE of the following CAN BE performed by the RO WITHOUT concurrence of the Unit Supervisor IAW ADM-11.16, Transient Procedure Use and Adherence?

A. Closing the MSIVs due to the Turbine not tripping B. Establishing Auxiliary Feedwater Flow to the Steam Generators C. Closing the MSR TCVs due to the MSR Block valves not closing D. Starting an additional Charging Pump with Pressurizer level lowering rapidly

74.

Given the following conditions:

Unit 2 has tripped from 100% power

2-EOP-01, SPTAs is in progress

Pressurizer Pressure is 1580 psia and lowering

Pressurizer Level is 38% and rising

RCS Subcooling is 18 °F and slowly lowering

The crew is performing step 4, RCS Inventory Control Which ONE of the following describes the required actions?

The crew is required to ____(1)____ Charging Pump, due to a ____(2)____ piping LOCA.

A. (1) START the 2C (2) RCS Cold Leg B. (1) START the 2C (2) Pressurizer Steam Space C. (1) SECURE the 2B (2) RCS Cold Leg D. (1) SECURE the 2B (2) Pressurizer Steam Space

75.

Given the following conditions:

Unit 2 is in Mode 5

RCS Temperature is 110°F

RCS is at mid-loop conditions

RCS Time to boil is 22 minutes

Shutdown Cooling is in operation per 2-NOP-03.05, Shutdown Cooling Subsequently:

The running Shutdown Cooling pump trips due to bearing failure

The crew enters 2-AOP-03.02, Shutdown Cooling Abnormal Operations In accordance with 2-AOP-03.02, which ONE of the following completes the statements below?

The _____(1)_____ Shutdown Cooling Train will be placed in Operation.

Containment Evacuation ____(2)____ required.

A. (1) 2A (2) is B. (1) 2A (2) Is NOT C. (1) 2B (2) is D. (1) 2B (2) Is NOT

St. Lucie December 2020 Initial Licensed Operator Final NRC Written Examination Answer Key As of January 22, 2021

1) B

2) B

3) C

4) B

5) D

6) B

7) B

8) A

9) A

10) A

11) D

12) A - change from post-exam comment

13) C

14) B

15) Q15 deleted from exam per post-exam comment

16) D

17) C

18) B

19) D

20) C 1lPage

21) A 22)D

23) B

24) B

25) B

26) C

27) A

28) A

29) A

30) A

31) A

32) A

33) D

34) D

35) A

36) B

37) C

38) C

39) A

40) C

41) A

42) A

43) B

44) B 2lPage

45)D

46) D

47) A

48) C

49) D

50) C

51) D

52) A

53) B

54) D

55) C

56) D

57) B

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REVISION NO.: PROCEDURE TITLE: PAGE:

76 SRO REF 67 APPENDICES / FIGURES / TABLES / DATA SHEETS 151 of 195 PROCEDURE NO.:

1-EOP-99 ST. LUCIE UNIT 1 FIGURE 1A RCS PRESSURE TEMPERATURE (Page 1 of 1)

(Containment Temperature Less Than or Equal to 200F)

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.

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:

76 SRO REF 67 APPENDICES / FIGURES / TABLES / DATA SHEETS 152 of 195 PROCEDURE NO.:

1-EOP-99 ST. LUCIE UNIT 1 FIGURE 1B RCS PRESSURE TEMPERATURE (Page 1 of 1)

(Containment Temperature Greater Than 200F)

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.

76.

Given the following conditions:

Unit 1 is experiencing a SBLOCA

1-EOP-03, LOCA, is in progress

CEAs 1 and 6 indicate fully withdrawn

REP CET is 550 °F

Thot is 548 °F

Pressurizer Pressure is 1600 psia

Pressurizer Level is 33% RISING slowly

BOTH S/Gs are 65% NR Level Which ONE of the following completes the statements below?

HPSI throttling criteria ____(1)____ MET.

WHEN HPSI throttling criteria is MET, AND pressurizer level remains stable when the required pumps are secured, a MINIMUM of ____(2)____ (if any) Charging / HPSI pump(s) must remain in operation.

REFERENCE PROVIDED A. (1) is (2) ZERO (0)

B. (1) is (2) ONE (1)

C. (1) is NOT (2) ZERO (0)

D. (1) is NOT (2) ONE (1)

77 SRO REF

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77 SRO REF REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two of the following three boron injection flow paths shall be OPERABLE:

a. One flow path from the boric acid makeup tank(s) with the tank meeting Specification 3.1.2.8 part a) or b), via a boric acid makeup pump through a charging pump to the Reactor Coolant System.

b. One flow path from the boric acid makeup tank(s) with the tank meeting Specification 3.1.2.8 part a) or b), via a gravity feed valve through a charging pump to the Reactor Coolant System.

c. The flow path from the refueling water storage tank via a charging pump to the Reactor Coolant System.

OR At least two of the following three boron injection flow paths shall be OPERABLE:

d. One flow path from each boric acid makeup tank with the combined tank contents meeting Specification 3.1.2.8 c),

via both boric acid makeup pumps through a charging pump to the Reactor Coolant System.

e. One flow path from each boric acid makeup tank with the combined tank contents meeting Specification 3.1.2.8 c),

via both gravity feed valves through a charging pump to the Reactor Coolant System.

f. The flow path from the refueling water storage tank, via a charging pump to the Reactor Coolant System.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two boron injection flow paths to the Reactor Coolant System to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or make the reactor subcritical within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and borate to a SHUTDOWN MARGIN equivalent to the requirements of Specification 3.1.1.2 at 200F; restore at least two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ST. LUCIE - UNIT 1 3/4 1-10 Amendment No. 48, 86, 90, 94, 171, 213

77 SRO REF REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.8 At least two of the following four borated water sources shall be OPERABLE:

a. Boric Acid Makeup Tank 1A in accordance with Figure 3.1-1.

b. Boric Acid Makeup Tank 1B in accordance with Figure 3.1-1.

c. Boric Acid Makeup Tanks 1A and 1B with a minimum combined contained borated water volume in accordance with Figure 3.1-1.

d. The refueling water tank with:

1. A minimum contained volume of 477,360 gallons of water,

2. A minimum boron concentration of 1900 ppm,

3. A maximum solution temperature of 100F,

4. A minimum solution temperature of 55F when in MODES 1 and 2, and

5. A minimum solution temperature of 40F when in MODES 3 and 4.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With only one borated water source OPERABLE, restore at least two borated water sources to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or make the reactor subcritical within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and borate to a SHUTDOWN MARGIN equivalent to the requirements of Specification 3.1.1.2 at 200F; restore at least two borated water sources to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.8 At least two borated water sources shall be demonstrated OPERABLE:

a. In accordance with the Surveillance Frequency Control Program by:

1. Verifying the boron concentration of the water source, ST. LUCIE - UNIT 1 3/4 1-17 Amendment No. 28, 48, 86, 94, 129, 171, 209, 213, 223

77 SRO REF EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of:

a. One OPERABLE high-pressure safety injection (HPSI) pump,

b. One OPERABLE low-pressure safety injection pump,

c. An independent OPERABLE flow path capable of taking suction from the refueling water tank on a Safety Injection Actuation Signal and automatically transferring suction to the containment sump on a Recirculation Actuation Signal, and NOTE One ECCS subsystem charging pump shall satisfy the flow path requirements of Specification 3.1.2.2.a or 3.1.2.2.d. The second ECCS subsystem charging pump shall satisfy the flow path requirements of Specification 3.1.2.2.b or 3.1.2.2.e.

d. One OPERABLE charging pump.

APPLICABILITY: MODES 1, 2 and 3 with pressurizer pressure 1750 psia.

ACTION:

a. 1. With one ECCS subsystem inoperable only because its associated LPSI train is inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or in accordance with the Risk Informed Completion Time Program, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

2. With one ECCS subsystem inoperable for reasons other than condition a.1.,

restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or in accordance with the Risk Informed Completion Time Program, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.

ST. LUCIE - UNIT 1 3/4 5-3 Amendment No. 28, 139, 164, 177, 213, 247

77.

Given the following conditions:

Unit 1 is at 100% power

1-OSP-02.07, Borated Water Sources, was completed with the following results:

1A Boric Acid Makeup Tank SAT

1B Boric Acid Makeup Tank UNSAT

1A/1B Boric Acid Makeup Tanks Combined SAT

Refueling Water Tank SAT Subsequently:

Annunciator M-41, Boric Acid Gravity Feed V2509 Ovrld/SS Isol Alarms

BRCO reports BOTH Lights for V2509 are NOT LIT Which ONE of the following completes the statements below?

V2509, 1A BAMT Gravity Feed Valve to Charging Pump status indications are indicative of a ____(1)____.

In accordance with Unit 1 Technical Specifications, TS 3.5.2, ECCS Subsystems -

Operating ____(2)____ met.

REFERENCE PROVIDED A. (1) Thermal Overload Trip (2) is B. (1) Thermal Overload Trip (2) is NOT C. (1) Blown Control Power Fuse (2) is D. (1) Blown Control Power Fuse (2) is NOT

78.

Given the following conditions:

Unit 1 is in Mode 6

RCS Level is 56 feet

Rod latching is in progress

Both trains of Shutdown Cooling (SDC) are in service

SDC purification is NOT in service Subsequently:

A leak occurs at the suction of the 1A LPSI pump

Annunciator R-4, A Safeguards Pump Room Sump Level HI/HI-HI is LIT

Crew enters 1-AOP-01.08, Excessive RCS Leakage Which ONE of the following completes the statements below?

To ISOLATE the 1A LPSI Pump suction leak from the RCS, LOCAL valve manipulation

____(1)___ required.

When the leak was isolated per 1-AOP-01.08 with RCS level at 55 feet, compliance with TS 3.9.8.1, Shutdown Cooling and Coolant Circulation High Water Level ____(2)____

maintained.

A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT

79.

Given the following conditions:

Unit 1 is at 100% power Subsequently:

A Loss of Power event occurs Which ONE of the following completes the statements below?

1-EOP-10, Station Blackout is entered if a Loss of all ____(1)____ occurred.

An Extended Loss of AC Power (ELAP) is declared if power is NOT expected to be restored within a MAXIMUM of ____(2)____.

A. (1) AC power ONLY (2) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B. (1) AC power ONLY (2) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. (1) AC and DC power (2) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months D. (1) AC and DC power (2) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

80.

Given the following conditions:

Unit 1 is in Mode 1

System Operator reports that grid demand is high

Main Generator VARS is 0 MVARs Subsequently:

A grid disturbance occurs, resulting in grid voltage lowering to 228 kV

0-AOP-53.02, Switchyard Voltage is entered Which ONE of the following completes the statements below?

In accordance with 0-AOP-53.02 and Tech Spec 3.8.1.1, A.C. Sources, Operating, Unit 1 AC offsite sources are ____(1)____.

With NO operator action, Unit 1 Main Generator MVARs will change in the ____(2)____

direction.

A. (1) OPERABLE (2) LAG (OUT)

B. (1) OPERABLE (2) LEAD (IN)

C. (1) INOPERABLE (2) LAG (OUT)

D. (1) INOPERABLE (2) LEAD (IN)

81.

Given the following conditions:

Unit 1 has experienced a Total Loss of Feedwater (TLOF)

1-EOP-06, TLOF is in progress at Step 12, Verify RCS Heat Removal

1A S/G level is 17% wide range

1B S/G level is 4% wide range

The Atmospheric Dump Valves (ADVs) are FULL OPEN

Tcold has RISEN steadily from 535° to 541°F over the past 3 minutes Which ONE of the following completes the statements below?

1-EOP-06, requires the operators to establish OTC based upon the given ____(1)____.

The Unit Supervisor is required to establish OTC by ____(2)____.

A. (1) S/G Levels (2) performing 1-EOP-06, Step 12 Contingency Steps B. (1) S/G Levels (2) transitioning to 1-EOP-15, Functional Recovery and performing the RCS and Core Heat Removal; HR-3 Success Path 3 - Once-Through-Cooling success path C. (1) Tcold RISE (2) performing 1-EOP-06, Step 12 Contingency Steps D. (1) Tcold RISE (2) transitioning to 1-EOP-15, Functional Recovery and performing the RCS and Core Heat Removal; HR-3 Success Path 3 - Once-Through-Cooling success path

82.

Given the following conditions:

Unit 2 is at 50% power

Group 5 CEAs RSPT and Pulse Counts are at 122 inches

Group 5 CEA 59 RSPT is at 117 inches and Pulse Count is 122 inches

Attempts to realign CEA 59 per 2-NOP-99.07, Operations Hard Cards has been unsuccessful

The crew has entered 2-AOP-66.01, Dropped or Misaligned CEA Abnormal Operations Subsequently:

I&C troubleshooting reports CEA 59 is untrippable Which ONE of the following completes the statements below?

ASI for the LRNI nearest CEA 59 will be more ____(1)____ as compared to the other LRNIs.

In accordance with 2-AOP-66.01, plant shutdown ____(2)____ required.

A. (1) negative (2) is B. (1) negative (2) is NOT C. (1) positive (2) is D. (1) positive (2) is NOT

83.

Given the following conditions:

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-AOP-100.02, Control Room Inaccessibility have been completed

RCO A is maintaining Hot Standby conditions at the Hot Shutdown Control Panel Which ONE of the following completes the statements below?

Determine subcooling margin using 2-AOP-100.02, Attachment, 10 Figure 2, using Hot Shutdown Control Panel indication for Reactor Coolant System ____(1)____ and Pressurizer pressure.

In accordance with 2-AOP-100.02, If plant control is NOT established at the Hot Shutdown Control Panel within a MAXIMUM of ____(2)____ minutes following Control Room evacuation, then this event shall be classified as a Site Area Emergency.

A. (1) Thot (2) 15 B. (1) Thot (2) 30 C. (1) Tcold + 50 °F (2) 15 D. (1) Tcold + 50 °F (2) 30

84 SRO REF REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a. < 1.0 Ci/gram DOSE EQUIVALENT I-131, and

b. < 518.9 Ci/gram DOSE EQUIVALENT XE-133.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With the specific activity of the primary coolant >1.0 Ci/gram DOSE EQUIVALENT I-131, verify DOSE EQUIVALENT I-131 is < 60.0 Ci/gram once per four hours.

b. With the specific activity of the primary coolant > 1.0 Ci/gram DOSE EQUIVALENT I-131, but < 60.0 Ci/gram DOSE EQUIVALENT I-131, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while efforts are made to restore DOSE EQUIVALENT I-131 to within the 1.0 Ci/gram limit. LCO 3.0.4.c is applicable.

c. With the specific activity of the primary coolant > 1.0 Ci/gram DOSE EQUIVALENT I-131 for greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, or > 60.0 Ci/gram DOSE EQUIVALENT I-131, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d. With the specific activity of the primary coolant > 518.9 Ci/gram DOSE EQUIVALENT XE-133, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while efforts are made to restore DOSE EQUIVALENT XE-133 to within the 518.9 Ci/gram DOSE EQUIVALENT XE-133 limit. LCO 3.0.4.c is applicable.

e. With the specific activity of the primary coolant > 518.9 Ci/gram DOSE EQUIVALENT XE-133 for greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performing sampling and analysis as described in Table 4.4-4.

ST. LUCIE - UNIT 1 3/4 4-17 Amendment No. 69, 101, 213, 220, 223

84.

Given the following conditions:

Unit 1 is at 100% power for the past 100 days

At 0600 on 12/15/2020, Chemistry reports Dose Equivalent Iodine I-131 is 25 µCi/gram

1-AOP-01.06, Excessive RCS Activity is entered

Dose Equivalent Iodine I-131 remains unchanged Subsequently:

At 0000 on 12/18/2020, Chemistry reports an increase in Dose Equivalent Iodine I-131 to 70 µCi/gram In accordance with 1-AOP-01.06, the crew is required to ENSURE V6307, Flash Tank Diverter Valve is aligned to the ____(1)____.

In accordance with TS 3.4.8, Reactor Coolant System Specific Activity, the latest time Unit 1 is required to be in Mode 3 by ____(2)____.

REFERENCE PROVIDED A. (1) Flash Tank (2) 1200, 12/17/2020 B. (1) Flash Tank (2) 0600, 12/18/2020 C. (1) Hold Up Tank (2) 1200, 12/17/2020 D. (1) Hold Up Tank (2) 0600, 12/18/2020

REVISION NO.: PROCEDURE TITLE: PAGE:

85 SRO REF 67 APPENDICES / FIGURES / TABLES / DATA SHEETS 151 of 195 PROCEDURE NO.:

1-EOP-99 ST. LUCIE UNIT 1 FIGURE 1A RCS PRESSURE TEMPERATURE (Page 1 of 1)

(Containment Temperature Less Than or Equal to 200F)

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.

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:

85 SRO REF 67 APPENDICES / FIGURES / TABLES / DATA SHEETS 152 of 195 PROCEDURE NO.:

1-EOP-99 ST. LUCIE UNIT 1 FIGURE 1B RCS PRESSURE TEMPERATURE (Page 1 of 1)

(Containment Temperature Greater Than 200F)

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.

REVISION NO.: PROCEDURE TITLE: PAGE:

85 SRO REF 67 APPENDICES / FIGURES / TABLES / DATA SHEETS 153 of 195 PROCEDURE NO.:

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

85.

Given the following conditions:

Unit 1 is experiencing a LOCA

1-EOP-03, LOCA is in progress

The following parameters are observed Time 0045 0100 0115 CET 430 °F 445 °F 446 °F RCS Pressure 550 psia 550 psia 550 psia Pzr Level 0% 0% 0%

ECCS Flow 500 gpm 350 gpm 340 gpm Containment Temp 174 °F 176 °F 178 °F Which ONE of the following completes the statement below?

In accordance with ADM-11.16, Transient Procedure Use and Adherence, based on parameters at time ___(1)____ the crew MUST exit 1-EOP-03 and implement 1-EOP-15, Functional Recovery, Success Path ____(2)____.

REFERENCE PROVIDED A. (1) 0100 (2) IC Inventory Control B. (1) 0100 (2) PC Saturated Pressure Control C. (1) 0115 (2) IC Inventory Control D. (1) 0115 (2) PC Saturated Pressure Control

86.

Given the following conditions:

Unit 1 has been shutdown for 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months and is in Mode 6

RCS Temperature is 105 °F

CCW Temperature is 85 °F

1A LPSI pump is operating

RCS level is 34 feet 10 inches Subsequently:

1A LPSI pump discharge flow is oscillating between 50 and 800 GPM

1A LPSI pump motor amps are oscillating and discharge pressure is fluctuating

RCS temperature is 110 °F and slowly RISING

The crew enters 1-AOP-03.02, Shutdown Cooling Abnormal Operations Which ONE of the following completes the statements below?

In accordance with 1-AOP-03.02. the crew is required to FIRST ____(1)____.

In accordance with TS 4.9.8.2. Refueling Operations - Low Water Level Surveillance Requirements, the MINIMUM SDC flow for this condition is ____(2)____ gpm.

A. (1) STOP the 1A LPSI Pump then START the 1B LPSI Pump (2) 1850 B. (1) STOP the 1A LPSI Pump then START the 1B LPSI Pump (2) 3000 C. (1) THROTTLE CLOSED HCV-3615/3625, LPSI header injection valves (2) 1850 D. (1) THROTTLE CLOSED HCV-3615/3625, LPSI header injection valves (2) 3000

87.

Given the following conditions:

Unit 2 is at 100% power Subsequently:

Unit 2 SNPO reports a significant Component Cooling Water (CCW) leak from the 2A HPSI Pump Seal Cooler

The SNPO has isolated the leak by isolating the 2A HPSI Pump Seal Cooler Which ONE of the following completes the statements below?

In accordance with ADM-11.16, Transient Procedure Use and Adherence, the US is required to declare the ____(1)____ inoperable.

2-EOP-03, LOCA states that during emergency situations, the 2A HPSI Pump

____(2)____ be operated for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months with CCW isolated.

A. (1) 2A HPSI pump ONLY (2) can B. (1) 2A HPSI pump ONLY (2) can NOT C. (1) 2A HPSI pump and 2A CCW Header (2) can D. (1) 2A HPSI pump and 2A CCW Header (2) can NOT

Recognition General Emergency Site Area Emergency Alert Unusual Event Category SG1 Prolonged Loss of All Off-site and All On-Site AC Power SS1 Loss of All Off-site and All On-Site AC Power to Emergency SA5 AC Power Capability To Emergency Busses Reduced To A Single Power SU1 Loss of All Off-site AC Power to Emergency Busses for 15 to Emergency Busses. Busses for 15 minutes or longer. Source For 15 Minutes or Longer Such That Any Additional Single Failure Minutes or Longer.

(GB) (GB) Would Result In Station Blackout.

Operating Mode Applicability: 1, 2, 3, 4 Operating Mode Applicability: 1, 2, 3, 4 Operating Mode Applicability: 1, 2, 3, 4 Operating Mode Applicability: 1, 2, 3, 4 EAL Values: EAL Values: EAL Value: EAL Values:

Note Note Note The Emergency Coordinator should not wait until the applicable The Emergency Coordinator should not wait until the applicable time has The Emergency Coordinator should not wait until the applicable AC POWER time has elapsed, but should declare the event as soon as it is elapsed, but should declare the event as soon as it is determined that the time has elapsed, but should declare the event as soon as it is determined that the condition has exceeded, or will likely exceed, condition has exceeded, or will likely exceed the applicable time. determined that the condition has exceeded, or will likely exceed the applicable time. the applicable time

1. Loss of all Off-site AND all On-site AC power to A3 4.16 KV 1. Loss of all Off-site AND all On-site AC Power to A3 4.16 KV AND 1. AC power capability to A3 4.16 KV AND B3 4.16 KV busses reduced to a single 1. Loss of all Off-site AC power to A3 4.16 KV AND B3 4.16 KV for AND B3 4.16 KV busses. B3 4.16 KV busses for 15 minutes or longer power source for 15 minutes or longer. 15 minutes or longer.

AND AND

a. EITHER of the following: a. ANY additional single power source failure will result in a Station Blackout.

(1) Restoration of at least one emergency bus in less than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is NOT likely OR (2) RCS and Core Heat Removal Safety function is NOT met.

S - SYSTEM MALFUNCTIONS

88 SRO REF SG2 Automatic Trip and All Manual Actions Fail to Shutdown SS2 Automatic Trip Fails to Shutdown the Reactor AND Manual SA2 Automatic Trip Fails to Shutdown the Reactor AND the Manual Actions Taken SU8 Inadvertent Criticality.

the Reactor AND Indication of an Extreme Challenge to Actions Taken from the Reactor Turbine Generator Board from the Reactor Turbine Generator Board (RTGB) are Successful in Shutting the Ability to Cool the Core Exists. (RTGB) are NOT Successful in Shutting Down the Reactor. Down the Reactor FAILURE OF RX PROTECTION /

Operating Mode Applicability: 1, 2 Operating Mode Applicability: 1, 2 Operating Mode Applicability: 1, 2 Operating Mode Applicability: 3, 4 EAL Values: EAL Values: EAL Values: EAL Values:

1. Automatic trip failed to shutdown the reactor. 1. An automatic trip failed to shutdown the reactor 1. An Automatic trip failed to shutdown the reactor 1. UNPLANNED sustained positive start-up rate observed on nuclear instrumentation.

AND AND AND

a. ALL Manual actions failed to shutdown the reactor as indicated a. Manual actions taken at the Reactor Turbine Generator Board a. Manual actions taken at the Reactor Turbine Generator Board (RTGB) by: (RTGB) DO NOT shutdown the reactor as indicated by: successfully shutdown the reactor as indicated by ALL of the following:

Reactor power is NOT dropping to less than 5% power Reactor power is NOT dropping to less than 5% power Reactor power is dropping to less than 5% power CRITICALITY All CEAs are NOT inserted ALL full strength CEAs are NOT inserted Negative start-up rate All CEAs are inserted or boration in progress AND

b. EITHER of the following exist or have occurred due to continued power generation:

(1) Core Heat Removal Safety Function NOT met.

OR (2) RCS Heat Removal Safety Function NOT met.

SS3 Loss of All Vital DC Power for 15 Minutes or Longer.

Operating Mode Applicability: 1, 2, 3, 4 DEFINITION BOX DC POWER GUIDANCE BOX FOR SG1, SS1 EAL Values:

UNPLANNED - A parameter change or an event that is not the On-site AC power may be provided by the other Units Note result of an intended evolution and requires corrective or Emergency Diesel Generator (EDG) by successful X-tie to The Emergency Coordinator should not wait until the applicable mitigative actions.

either the A3 or B3 4.16 KV bus. time has elapsed, but should declare the event as soon as it is determined that the condition has exceeded, or will likely exceed, the applicable time.

1. Less than 112 VDC on 1[2]A, 1[2]B AND 1[2]AB Vital DC busses for 15 minutes or longer.

PAGE: 18 REVISION: 2 S HOT CONDITIONS EAL - HOT BASIS ST LUCIE PLANT CLASSIFICATION TOOL

88.

Given the following conditions:

Unit 2 is at 100% power when the 2B MFW pump trips

The following annunciators have alarmed:

o L-3, S/G Level Low Channel Trip (Red) o L-11, S/G Level Low Channel Pre-trip

Control Room Reactor Trip breaker indications indicate WHITE Subsequently:

The BRCO depresses the manual reactor trip pushbuttons

Control Room Reactor Trip breaker indications indicate WHITE Which ONE of the following completes the statements below?

In accordance with 2-EOP-01, SPTAs, Step 1, Verify Reactor Trip, the NEXT required action the crew is required to take is ____(1)____.

In accordance with EPIP-01, Classification of Emergencies, this event will be classified as a / an ____(2)____.

REFERENCE PROVIDED A. (1) INITIATE Emergency Boration (2) ALERT B. (1) INITIATE Emergency Boration (2) SITE AREA EMERGENCY C. (1) open CEDM MG breakers locally at 2A2 and 2B2 Load Centers (2) ALERT D. (1) open CEDM MG breakers locally at 2A2 and 2B2 Load Centers (2) SITE AREA EMERGENCY

89.

Given the following conditions:

Unit 1 tripped from 100% power

Station Blackout (SBO) conditions exist

1-EOP-01, SPTAs is in progress at step 2, MVA Which ONE of the following completes the statements below?

The FSAR (Section 15.2.13 Station Blackout Analysis) discusses the ability of operators from both units to align the AB 4.16 Buses and supply power through the Station Blackout Crosstie within ____(1)____ hour(s).

The FSAR assumes RCS heat removal will be accomplished using ____(2)____ during the time required to crosstie power.

A. (1) 1 (2) ADVs B. (1) 1 (2) MSSVs C. (1) 4 (2) ADVs D. (1) 4 (2) MSSVs

90 SRO REF REVISION NO.: PROCEDURE TITLE: PAGE:

53 OFFSITE DOSE CALCULATION MANUAL (ODCM) 20 of 231 PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (Page 1 of 2)

MINIMUM CHANNELS INSTRUMENT ACTION OPERABLE

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release a) Liquid Radwaste Effluent Line 1 35 b) Steam Generator Blowdown Effluent Line 1/SG 36, 37

2. Flow Rate Measurement Devices a) Liquid Radwaste Effluent Line N.A 38 b) Discharge Canal N.A 38 c) Steam Generator Blowdown Effluent Lines N.A 38 SG - Denotes Steam Generator ACTION STATEMENTS ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with the Surveillance Requirement for concentration limit of Control 4.11.1.1.1.

AND

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 2.E-07 micro-Curie/ml:

a. At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (1) when the specific activity of the secondary coolant is greater than 0.01 micro-Curies/gram DOSE EQUIVALENT I-131 OR

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (1) when the specific activity of the secondary coolant is less than or equal to 0.01 micro-Curies/gram DOSE EQUIVALENT I-131.

90 SRO REF REVISION NO.: PROCEDURE TITLE: PAGE:

53 OFFSITE DOSE CALCULATION MANUAL (ODCM) 21 of 231 PROCEDURE NO.:

C-200 ST. LUCIE PLANT TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION (Page 2 of 2)

ACTION STATEMENTS (continued)

ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, isotopic grab samples shall be obtained and analyzed at a Lower Limit of Detection for I-131, Co-58, Co-60, Cs-134, and Cs-137 to achieve detection sensitivity capable of detecting a primary-to-secondary leak rate of 5 gallons per day, provided that the Reactor Coolant System has sufficient activity present.

The applicable frequency shall be:

In MODES 1, 2, 3, 4

a. At least once per day(1) for isotopic activity on the affected Steam Generator, provided that the Air Ejector Gas Activity Monitor is OPERABLE, OR

b. At least every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (1) for isotopic activity on the affected Steam Generator, if the Air Ejector Gas Activity Monitor is INOPERABLE.

This requirement is intended to meet EPRI PWR Primary-to-Secondary Leak Guidelines (TR-104788-R2) per reference PMAI 00-08-109.

ACTION 38 - Minimum system design flow of required running pumps shall be utilized for ECL calculations for discharge canal flow and maximum system design flow be utilized for ECL calculations for effluent line flow.

TABLE 3.3-12 Notation (1) - The initial sample shall be completed prior to the frequency interval specified.

Subsequent samples (of the same INOPERABLE condition) may be performed per ODCM surveillance requirement 4.0.2 (a maximum allowable extension not to exceed 25% of the surveillance interval).

90.

Given the following conditions:

Unit 2 is at 100% power

RS-26-11, Steam Jet Air Ejector (SJAE) Monitor is Out of Service

S/G Dose Equivalent I-131 is 0.0003 µCi/gm Subsequently:

RS-26-5, A S/G Blowdown Rad Monitor detector output fails HIGH Which ONE of the following completes the statements below?

S/G Blowdown flow will isolate on ____(1)____ S/G(s).

In accordance with the Off Site Dose Calculation Manual, (C-200), S/G samples are required at a MINIMUM every ____(2)____ hours.

REFERENCE PROVIDED A. (1) BOTH (2) 8 B. (1) BOTH (2) 24 C. (1) ONLY the A (2) 8 D. (1) ONLY the A (2) 24

91 SRO REFERENCE PICTURE QUESTION ON NEXT PAGE 91.

Given the following conditions:

Unit 2 is stabilizing from a rapid downpower

ASI is per the graph provided Which ONE of the following completes the statements below?

To restore ASI to the acceptable band, CEAs must be ____(1)____.

In accordance with TS 3.2.5, ASI, BASES, Operating within ASI limits will result in meeting the ____(2)____ criterion in the event of a limiting transient.

REFERENCE PROVIDED A. (1) INSERTED (2) DNBR B. (1) INSERTED (2) RADIAL POWER DISTRIBUTION C. (1) WITHDRAWN (2) DNBR D. (1) WITHDRAWN (2) RADIAL POWER DISTRIBUTION

92.

Given the following conditions:

Unit 1 has experienced a SGTR

1-EOP-04, SGTR is in progress at Step 10, INITIATE lowering RCS Temperature

Cooldown with SBCS Valve PCV-8801, is in progress Subsequently:

An Instrument Air (IA) rupture occurs, resulting in a Loss of IA Which ONE of the following completes the statements below?

PCV-8801 will fail ____(1)____.

IAW 1-EOP-04, the crew will continue the cooldown via step 10 Contingency Action, the US will be required to utilize ____(2)____ to continue the cooldown.

A. (1) as is (2) Table 12, Alternate S/G Heat Removal Paths B. (1) as is (2) Appendix U, Local Operation of Unit 1 Atmospheric Dump Valves C. (1) closed (2) Table 12, Alternate S/G Heat Removal Paths D. (1) closed (2) Appendix U, Local Operation of Unit 1 Atmospheric Dump Valves

93 SRO REF REVISION NO.: PROCEDURE TITLE: PAGE:

17 FIRE PROTECTION PLAN 86 of 142 PROCEDURE NO.:

ADM-19.00 ST. LUCIE PLANT ATTACHMENT 1 Fire Protection Features Functionality Requirements And Compensatory Measures (Page 1 of 44) 1.0 FIRE DETECTION INSTRUMENTS 1.1 Required Systems Fire Detection Instruments Table 1 Unit 1 Fire Detection Instruments Instrument Location: Required Number of Instruments (NOTE 1)

(Zone denotes detection system zone) Heat Smoke Zone-1A RAB EL. -0.50' A, West Hallway - 7 of 14 RAB El. -0.50', ECCS Pump Room - 2 of 3 (NOTE 2)

Zone-2A RAB EL. -0.50' Charging pumps, East Hallway - 5 of 9 Zone-3A RAB EL. 19.50' Cable Loft, East Hallway - 13 of 25 Zone-4 RAB EL. 19.50' Machine Shop, Locker Rooms 4 of 7 9 of 18 Zone-5A RAB EL. 19.50' M.G. SETs, East Hallway - 10 of 19 Zone-6A RAB EL. 43.00' Cable Spreading Room - 10 of 20 (NOTE 5)

Zone-7A RAB EL. 43.00' A Swgr. Rm., Cable Spreading Rm. - 10 of 19 (NOTE 5)

Zone-8A RAB EL. 62.00' Control Room (below ceiling) 1 of 1 12 of 24 Zone-9A RAB EL. 43.00' H & V Hallway - 3 of 6 Zone-10A RAB EL. 43.00' H & V Fan Room - 3 of 6 Zone-11A Elect. Penet. Rec. (Annulus) EL. 18.00' - 1 of 2 Zone-12A RAB EL. 19.50' Elect. Penetration. Rooms - 6 of 12 Zone-13A Containment Tunnel Below EL. 18,00' - 4 of 7 (NOTE 8)

Zone-14A Containment EL. 18.00' Outside Bioshield Wall - 10 of 20 (NOTE 8)

Zone-15A Containment EL. 45.00' RCPs 4 of 7 8 of 15 (NOTE 8)

Zone-16A Turbine Swgr./ICW PP./Cond. Polisher Bldg. 2 of 3 11 of 21 Zone-20A Fuel Handling Bldg. EL. 19.50'/CCW Area 3 of 5 2 of 4 Zone-Z097 RAB EL. 43.00 Cable Spread In-Cabinet - 1 of 1 per cabinet (NOTE 4)

Zone-1B RAB. EL. -0.50 B, West Hallway - 7 of 14 RAB El. -0.50', ECCS Pump Room - 2 of 4 (NOTE 2)

Zone-2B RAB. EL. -0.50' Charging Pumps, East Hallway - 8 of 16 Zone-3B RAB. EL. 19.50' Cable Loft, West Hallway - 13 of 25 Zone-HSCP RAB. EL.43.00 Hot Shutdown Control Cubicle - 1 of 1 Zone-5B RAB EL. 19.50' East Hallway - 4 of 8 Zone-6B RAB EL. 43.00' B Swgr, Cable Spreading Room - 15 of 30 (NOTE 5)

Zone-7B RAB EL. 43.00' B Swgr, Cable Spreading Room - 11 of 21 (NOTE 5)

Zone-8B RAB EL. 62.00' Control Room (above ceiling) - 15 of 30 Zone-9B RAB EL. 43.00' H & V Hallway - 3 of 6 Zone-10B RAB EL. 43.00' H & V Fan Room - 5 of 9 Zone-11B Containment Elect. Penet (Annulus) - 1 of 2 (NOTE 8)

Zone-12B RAB EL. 19.50' Elect. Penetration. Rooms - 7 of 14 Zone-13B Containment Tunnel Below EL. 18,00' - 2 of 3 (NOTE 8)

Zone-14B Containment EL. 18.00' Outside Bioshield Wall - 9 of 18 (NOTE 8)

Zone-15B Containment EL. 45.00' RCPs 3 of 5 10 of 20 (NOTE 8)

Zone-16B Turbine Bldg. Switchgear, AFW Pumps - 11 of 21 Zone-Z098 RAB EL. 43.00 Cable Spread In-Cabinet - 1 of 1 per cabinet (NOTE 4)

Zone 1D RAB El. -0.50', ECCS Pump Room IFD - (NOTE 3)

93 SRO REF REVISION NO.: PROCEDURE TITLE: PAGE:

17 FIRE PROTECTION PLAN 87 of 142 PROCEDURE NO.:

ADM-19.00 ST. LUCIE PLANT ATTACHMENT 1 Fire Protection Features Functionality Requirements And Compensatory Measures (Page 2 of 44) 1.1 Required Systems Fire Detection Instruments (continued)

Table 1 Unit 1 Fire Detection Instruments Instrument Location: Required Number of Instruments (NOTE 1)

(Zone denotes detection system zone) Heat Smoke Zone 2D RAB El. -0.50', ECCS Pump Room IFD - (NOTE 3)

Zone 4D Cable Spreading Room IFD-DET-1 - 1 of 1 (NOTE 7)

Zone 5D Cable Spreading Room IFD-DET-2 - 1 of 1 (NOTE 7) 57 Cable Spreading Room In Cabinet - 1 of 1 per cabinet (NOTE 4)

Zone 67 RAB Elevator Control Room and Hoistway 1 of 1 1 of 1 (NOTE 6) (NOTE 6)

Halon 1301 Thermal Detector Locations Cable Spreading Room-Zone-1 9 of 17 (NOTE 5)

Cable Spreading Room-Zone-2 9 of 17 (NOTE 5)

Preaction Detector Locations RAB Sprinkler System - Zone 1F 24 of 24 NOTE 1: A minimum of 50% or greater of the detectors in a detector zone and/or NO two adjacent detectors out of service in the same zone are required to be functional without implementing compensatory measures.

NOTE 2: If zone 1D or 2D is functional, then the smoke detectors located in the ECCS Pump Room are NOT required to be functional.

NOTE 3: The Incipient Fire Detection (IFD) system is the required detection system for the ECCS Pump Room. One of the two zones of the IFD shall remain functional.

NOTE 4: The in-cabinet smoke detection system is installed to support the NFPA 805 program Fire Probabilistic Risk Assessment (FPRA). Changes to any aspect of this portion of the system will require the review and approval of Fire Protection Engineering and PRA group personnel. Compensatory measures are per Attachment 1, Section 1.3.2, Step 1.D. Detector locations can be found in 0-NOP-79.01, Fire Detection System.

NOTE 5: Smoke detection or thermal detection out of service in the Unit 1 Cable Spread Room requires implementation of a continuous fire watch. Smoke detection out of service in the 1B Switchgear Room requires implementation of a continuous fire watch. These compensatory measures are required per NFPA 805 and shall NOT be changed without Fire Protection Program Engineer Consent.

NOTE 6: These fire detectors do NOT require compensatory measures when NOT in service, these are a Florida State Fire Code required system.

NOTE 7: Prior to performing any work inside a cabinet being monitored by a VESDA incipient fire detector, the sampling port associated with the sampling tube connected to the cabinet needs to be isolated (via the "Isolate" Push Button Key on the VESDA display) and compensatory measures put in place.

NOTE 8: The fire detection instruments located within Containment are not required to be functional during the performance of Type A Containment leakage rate tests.

93 SRO REF REVISION NO.: PROCEDURE TITLE: PAGE:

17 FIRE PROTECTION PLAN 93 of 142 PROCEDURE NO.:

ADM-19.00 ST. LUCIE PLANT ATTACHMENT 1 Fire Protection Features Functionality Requirements And Compensatory Measures (Page 8 of 44) 1.3 Fire Detection Systems Functionality Requirements and Compensatory Measures 1.3.1 Unit 1 Fire Detection Instrumentation - Functionality Requirements

1. The fire detection instrumentation for each fire detection zone shall be FUNCTIONAL whenever equipment in that fire detection zone is required to be FUNCTIONAL.

1.3.2 Unit 1 Fire Detection Instrumentation - Compensatory Measures

1. With the number of FUNCTIONAL fire detection instruments less than required by the minimum instruments FUNCTIONAL requirement of Attachment 1, Section 1.3.1, Step 1, the following apply:

A. Smoke detection or thermal detection out of service in the Cable Spread Room requires implementation of a continuous fire watch (Zones 6A, 6B, 7B, Cable Spread Room Zone 1 and 2). These compensatory measures are required per NFPA 805 and shall NOT be changed without Fire Protection Program Engineer Consent.

B. Smoke detection out of service in the 1B Switchgear Room requires implementation of a continuous fire watch (Zones 6B and 7B). These compensatory measures are required per NFPA 805 and shall NOT be changed without Fire Protection Program Engineer Consent.

C. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , ESTABLISH a fire watch patrol to inspect the zone(s) with the non-functional instrument(s) at least once per hour.

(1) IF the detector(s) is located inside the annulus, Zone 11A or 11B, THEN INSPECT the zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

(2) IF the non-functional instrument(s) is located inside the containment (Zones 13A, 13B, 14A, 14B, 15A or 15B),

THEN MONITOR the containment air temperature at least once per hour at the locations listed in Technical Specification 4.6.1.5.

93 SRO REF REVISION NO.: PROCEDURE TITLE: PAGE:

17 FIRE PROTECTION PLAN 94 of 142 PROCEDURE NO.:

ADM-19.00 ST. LUCIE PLANT ATTACHMENT 1 Fire Protection Features Functionality Requirements And Compensatory Measures (Page 9 of 44) 1.3.2 Unit 1 Fire Detection Instrumentation - Compensatory Measures (continued)

1. (continued)

D. Cable Spread Room Incipient Fire Detector and In-cabinet Smoke Detection:

(1) With any incipient fire detector or in-cabinet detector(s) out of service and area wide smoke detection in the Cable Spread Room FUNCTIONAL (required detectors from detection zones 6A, 6B and 7B in service) thermography of the affected cabinet(s) shall be performed every two weeks and reviewed by the Fire Protection Engineer.

(2) With any incipient fire detector or in-cabinet detector(s) out of service and Cable Spread Room smoke detection out of service, the following are required:

A continuous fire watch shall be implemented Thermography of the affected cabinet(s) shall be performed every two weeks and reviewed by the Fire Protection Program Engineer 1.3.3 Unit 1 Fire Detection Instrumentation - Surveillance Requirements

1. REFER TO Attachment 2, Unit 1 Fire Protection Schedule of Periodic Tests, for listing of Fire Protection Surveillances and Procedures.

2. Each of the REQUIRED SYSTEMS fire detection instruments which are accessible during operation shall be surveilled at least once per 12 months by performance of a CHANNEL FUNCTIONAL TEST, except for thermal detectors which shall be surveilled per Attachment 1, Section 1.3.3, Step 3. Fire detection instruments which are NOT accessible during operation shall be surveilled by performance of a CHANNEL FUNCTIONAL TEST once per 18 months.

93.

Given the following conditions:

Unit 1 is at 100% power

Fire Alarm for fire zone 6A is alarming

SNPO reports NO fire with the following four detectors alarming:

o Detectors 6A-1, 6A-8, 6A-14 and 6A-19 Subsequently:

Fire Protection determines NO Detectors are ADJACENT detectors

All four failed detectors have been bypassed per 0-NOP-79.01, Fire Detection System

Fire Zone 6A alarm has be reset and remains clear

NO other are detectors are bypassed Which ONE of the following completes the statements below?

Per ADM-19.00, Fire Protection Plan, ____(1)____ fire watch is required.

This area is protected by a ____(2)____ system.

REFERENCE PROVIDED A. (1) NO (2) Halon B. (1) NO (2) Pre-action C. (1) a CONTINUOUS (2) Halon D. (1) a CONTINUOUS (2) Pre-action

94.

Given the following conditions:

Unit 1 is at 100% power

The 1A1 Circulating Waterbox has a condenser tube leak

Annunciator G-20, Secondary Chemistry Alarm is LIT, due to sodium levels

Chemistry Reports S/G chemistry has entered Action Level 3

The crew entered 1-AOP-09.03, Secondary Chemistry

The crew commenced a rapid downpower per 1-AOP-22.01, Rapid Downpower Which ONE of the following completes the statement below in accordance with 1-AOP-09.03, Secondary Chemistry?

The 1A1 Circulating Water Pump will be secured by placing the control switch to ____(1)____.

Unit 1 is required INITIATE a shutdown to at LEAST ____(2)____.

A. (1) STOP (2) Mode 3, Hot Standby B. (1) STOP (2) Mode 5, Cold Shutdown C. (1) PULL TO DRAIN (2) Mode 3, Hot Standby D. (1) PULL TO DRAIN (2) Mode 5, Cold Shutdown

95.

Given the following conditions:

Unit 1 is performing a FULL CORE OFFLOAD Which ONE of the following completes the statements below?

In accordance with 0-NOP-67.05, Refueling Operation, the Refueling Supervisor____(1)____ direct the CORE OFFLOAD activities from the FUEL HANDLING BUILDING.

In accordance with Ops policy 202, Fuel Handling Supervisor Responsibilities, a Non-licensed Fuel Handling Supervisor ____(2)____ directly supervise fuel handling activities associated with movement of irradiated fuel assemblies in the FUEL HANDLING BUILDING.

A. (1) can (2) can B. (1) can (2) can NOT C. (1) can NOT (2) can D. (1) can NOT (2) can NOT

96.

Given the following conditions:

Unit 1 is at 100% power

The Current Time is 0900

Maintenance is scheduled for the:

1A Containment Spray pump

V1402, PORV

Maintenance is scheduled to be completed as follows:

1A Containment Spray pump operable TODAY at 1500

V1402, PORV operable TOMORROW at 0800 Which ONE of the following completes the statement below?

In accordance with ADM-09.22, Equipment Out of Service, an LCO action tracking entry

____(1)____ be omitted at the discretion of the SM or US for the 1A CS pump AND

____(2)____ be omitted at the discretion of the SM or US for V1402, PORV.

A. (1) may (2) may B. (1) may (2) may NOT C. (1) may NOT (2) may D. (1) may NOT (2) may NOT

97.

Which ONE of the following completes the statements in accordance with OP-AA-1000, Conduct of Infrequently Performed Tests or Evolutions (IPTE)?

The same individual ____(1)____ perform the duties of the IPTE Manager AND Lead Test Coordinator?

The ____(2)____ gives the final permission to start the IPTE evolution.

A. (1) can (2) Shift Manager B. (1) can (2) IPTE Manager C. (1) can NOT (2) Shift Manager D. (1) can NOT (2) IPTE Manager

98.

Given the following conditions:

0000 Unit 1 commenced a 9 hour1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months Containment Mini Purge IAW 1-NOP-25.02, Continuous Containment / Hydrogen Purge System 0800 1A gas decay tank release permit, is submitted for approval IAW 1-NOP-06.20, Controlled Batch Release to Atmosphere Based on the conditions at time 0800, which ONE of the following completes the statements below?

The Containment Mini Purge is categorized as a ____(1)____ release.

The 1A decay tank release permit ____(2)____ be approved.

A. (1) BATCH (2) can B. (1) BATCH (2) can NOT C. (1) CONTINUOUS (2) can D. (1) CONTINUOUS (2) can NOT

99.

Given the following conditions:

Unit 2 is experiencing a SGTR

2-EOP-04, SGTR is in progress

Initial Cooldown for S/G isolation is in progress using SBCS

AFAS-1 and AFAS-2 have actuated

The STA has an active SRO license Which ONE of the following completes the statements below?

IAW EPIP-02, Duties and Responsibilities of The Emergency Coordinator, a release

____(1)____ currently in progress.

IAW EPIP-02, If the SM becomes incapacitated during the event, the ____(2)____ is the NEXT designated position to assume the duties of the Emergency Coordinator (EC).

A. (1) is (2) Unit 2 Unit Supervisor B. (1) is (2) Shift Technical Advisor C. (1) is NOT (2) Unit 2 Unit Supervisor D. (1) is NOT (2) Shift Technical Advisor

100 SRO REF REVISION NO.: PROCEDURE TITLE: PAGE:

28 REGULATORY REPORTING 16 of 126 PROCEDURE NO.:

LI-AA-102-1001 NUCLEAR FLEET ADMINISTRATIVE ATTACHMENT 1 REPORTABLE EVENTS (Page 1 of 8)

Declaration of an Emergency Class (See NUREG-1022 Section 3.1.1) 1 Hour Report § 50.72(a)(1)(i) The declaration of any of the Emergency Classes specified in the licensees approved Emergency Plan.

Plant Shutdown Required by Technical Specifications (See NUREG-1022 Section 3.2.1) 4 Hour Report § 50.72(b)(2)(i) The initiation of any 60 Day LER § 50.73(a)(2)(i)(A) The completion nuclear plant shutdown required by the plants of any nuclear plant shutdown required by the Technical Specifications. plants Technical Specifications.

Operation or Condition Prohibited by Technical Specifications (See NUREG-1022 Section 3.2.2) 60 Day LER § 50.73(a)(2)(i)(B) Any operation or condition which was prohibited by the plants Technical Specifications except when:

(1) The Technical Specification is administrative in nature; (2) The event consisted solely of a case of a late surveillance test where the oversight was corrected, the test was performed, and the equipment was found to be capable of performing its specified safety functions; or (3) The Technical Specification was revised prior to discovery of the event such that the operation or condition was no longer prohibited at the time of discovery of the event.

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28 REGULATORY REPORTING 17 of 126 PROCEDURE NO.:

LI-AA-102-1001 NUCLEAR FLEET ADMINISTRATIVE ATTACHMENT 1 REPORTABLE EVENTS (Page 2 of 8)

Deviation from Technical Specifications Authorized under § 50.54(x)

(See NUREG-1022 Section 3.2.3) 1 Hour Report§ 50.72(b)(1) ... any deviation from the 60 Day LER § 50.73(a)(2)(i)(C) Any deviation from plants Technical Specifications authorized pursuant to § the plants Technical Specifications authorized 50.54(x) of this part. pursuant to § 50.54(x) of this part.

Degraded or Unanalyzed Condition (See NUREG-1022 Section 3.2.4) 8 Hour Report § 50.72(b)(3)(ii) Any event or condition 60 Day LER 50.73(a)(2)(ii) Any event or condition that results in: that resulted in:

(A) The condition of the nuclear power plant, (A) The condition of the nuclear power plant, including its principal safety barriers, being including its principal safety barriers, being seriously degraded; or seriously degraded; or (B) The nuclear power plant being in an (B) The nuclear power plant being in an unanalyzed condition that significantly unanalyzed condition that significantly degrades plant safety. degraded plant safety.

External Threat or Hampering (See NUREG-1022 Section 3.2.5) 60 Day LER § 50.73(a)(2)(iii) Any natural phenomenon or other external condition that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant.

100 SRO REF REVISION NO.: PROCEDURE TITLE: PAGE:

28 REGULATORY REPORTING 18 of 126 PROCEDURE NO.:

LI-AA-102-1001 NUCLEAR FLEET ADMINISTRATIVE ATTACHMENT 1 REPORTABLE EVENTS (Page 3 of 8)

System Actuation (See NUREG-1022 Section 3.2.6) 4 Hour Report § 50.72(b)(2)(iv)(A) Any event that results or should have resulted in emergency core cooling system (ECCS) discharge into the reactor coolant system as a result of a valid signal except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.

4 Hour Report § 50.72(b)(2)(iv)(B) Any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.

8 Hour Report § 50.72(b)(3)(iv)(A) Any event or 60 Day LER § 50.73(a)(2)(iv)(A) Any event or condition that results in valid actuation of any of the condition that resulted in manual or automatic systems listed in paragraph (b)(3)(iv)(B) of this section, actuation of any of the systems listed in paragraph except when the actuation results from and is part of a (a)(2)(iv)(B) of this section, except when:

pre-planned sequence during testing or reactor operation. (1) The actuation resulted from and was part of a pre-planned sequence during testing or reactor operation; or (2) The actuation was invalid and; (i) Occurred while the system was properly removed from service; or (ii) Occurred after the safety function had been already completed.

As indicated in 10 CFR 50.73(a)(1), in the case of an invalid actuation reported under 10 CFR 50.73(a)(2)(iv)(A) other than actuation of the RPS when the reactor is critical, the licensee may, at its option, provide a telephone notification to the NRC Operations Center within 60 days after discovery of the event instead of submitting a written LER.

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28 REGULATORY REPORTING 19 of 126 PROCEDURE NO.:

LI-AA-102-1001 NUCLEAR FLEET ADMINISTRATIVE ATTACHMENT 1 REPORTABLE EVENTS (Page 4 of 8) 8 Hour Report § 50.72(b)(3)(iv)(B) The systems to § 50.73(a)(2)(iv)(B) The systems to which the which the requirements of paragraph (b)(3)(iv)(A) of requirements of paragraph (a)(2)(iv)(A) of this this section apply are: section apply are:

(1) Reactor protection system (RPS) including: (1) Reactor protection system (RPS) including:

reactor scram and reactor trip. 5 reactor scram or reactor trip.

(2) General containment isolation signals affecting (2) General containment isolation signals affecting containment isolation valves in more than one containment isolation valves in more than one system or multiple main steam isolation valves system or multiple main steam isolation valves (MSIVs). (MSIVs).

(3) Emergency core cooling systems (ECCS) for (3) Emergency core cooling systems (ECCS) for pressurized water reactors (PWRs) including: high- pressurized water reactors (PWRs) including: high-head, intermediate-head, and low-head injection head, intermediate-head, and low-head injection systems and the low pressure injection function of systems and the low pressure injection function of residual (decay) heat removal systems. residual (decay) heat removal systems.

(4) ECCS for boiling water reactors (BWRs) including: (4) ECCS for boiling water reactors (BWRs) high-pressure and low-pressure core spray systems; including: high-pressure and low-pressure core high-pressure coolant injection system; low pressure spray systems; high-pressure coolant injection injection function of the residual heat removal system; low pressure injection function of the system. residual heat removal system.

(5) BWR reactor core isolation cooling system; (5) BWR reactor core isolation cooling system; isolation condenser system; and feedwater coolant isolation condenser system; and feedwater injection system. coolant injection system.

(6) PWR auxiliary or emergency feedwater (6) PWR auxiliary or emergency feedwater system. system.

(7) Containment heat removal and (7) Containment heat removal and depressurization depressurization systems, including systems, including containment spray and fan containment spray and fan cooler systems cooler systems.

(8) Emergency ac electrical power systems, including: (8) Emergency ac electrical power systems, emergency diesel generators (EDGs); hydroelectric including: emergency diesel generators (EDGs);

hydroelectric facilities used in lieu of EDGs at facilities used in lieu of EDGs at the Oconee Station; the Oconee Station; and BWR dedicated and BWR dedicated Division 3 EDGs.

Division 3 EDGs.

5 Actuation of the RPS when the reactor is critical is (9) Emergency service water systems that do not reportable under § 50.72(b)(2)(iv)(B) normally run and that serve as ultimate heat sinks.

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28 REGULATORY REPORTING 20 of 126 PROCEDURE NO.:

LI-AA-102-1001 NUCLEAR FLEET ADMINISTRATIVE ATTACHMENT 1 REPORTABLE EVENTS (Page 5 of 8)

Event or Condition that Could Have Prevented Fulfillment of a Safety Function (See NUREG-1022 Section 3.2.7) 8 Hour Report § 50.72(b)(3)(v) Any event or 60 Day LER § 50.73(a)(2)(v) Any event or condition condition that at the time of discovery could have that could have prevented the fulfillment of the safety prevented the fulfillment of the safety function of function of structures or systems that are needed to:

structures or systems that are needed to:

(A) Shut down the reactor and maintain it in a (A) Shut down the reactor and maintain it in a safe safe shutdown condition; shutdown condition; (B) Remove residual heat; (B) Remove residual heat; (C) Control the release of radioactive material; or (C) Control the release of radioactive material; or (D) Mitigate the consequences of an accident.

(D) Mitigate the consequences of an accident.

8 Hour Report § 50.72(b)(3)(vi) Events covered in § 50.73(a)(2)(vi) Events covered in paragraph (b)(3)(v) of this section may include one or paragraph (a)(2)(v) of this section may include one or more procedural errors, equipment failures, and/or more procedural errors, equipment failures, and/or discovery of design, analysis, fabrication, construction, discovery of design, analysis, fabrication, and/or procedural inadequacies. However, individual construction, and/or procedural inadequacies.

component failures need not be reported pursuant to However, individual component failures need not be paragraph (b)(3)(v) of this section if redundant reported pursuant to paragraph (a)(2)(v) of this equipment in the same system was operable and section if redundant equipment in the same system available to perform the required safety function. was operable and available to perform the required safety function.

Common Cause Inoperability of Independent Trains or Channels (See NUREG-1022 Section 3.2.8) 60 Day LER § 50.73(a)(2)(vii) Any event where a single cause or condition caused at least one independent train or channel to become inoperable in multiple systems or two independent trains or channels to become inoperable in a single system designed to:

(A) Shut down the reactor and maintain it in a safe shutdown condition; (B) Remove residual heat; (C) Control the release of radioactive material; or (D) Mitigate the consequences of an accident.

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LI-AA-102-1001 NUCLEAR FLEET ADMINISTRATIVE ATTACHMENT 1 REPORTABLE EVENTS (Page 6 of 8)

Radioactive Release (See NUREG-1022 Section 3.2.9) 60 Day LER § 50.73(a)(2)(viii)(A) Any airborne radioactive release that, when averaged over a time period of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , resulted in airborne radionuclide concentrations in an unrestricted area that exceeded 20 times the applicable concentration limits specified in appendix B to part 20, table 2, column 1.

60 Day LER § 50.73(a)(2)(viii)(B) Any liquid effluent release that, when averaged over a time period of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , exceeds 20 times the applicable concentrations specified in appendix B to part 20, table 2, column 2, at the point of entry into the receiving waters (i.e.,

unrestricted area) for all radionuclides except tritium and dissolved noble gases.

Internal Threat or Hampering (See NUREG-1022 Section 3.2.10) 60 Day LER § 50.73(a)(2)(x) Any event that posed an actual threat to the safety of the nuclear power plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the nuclear power plant including fires, toxic gas releases, or radioactive releases.

Transport of a Contaminated Person Offsite (See NUREG-1022 Section 3.2.11) 8 Hour Report § 50.72(b)(3)(xii) Any event requiring the transport of a radioactively contaminated person to an offsite medical facility for treatment.

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28 REGULATORY REPORTING 22 of 126 PROCEDURE NO.:

LI-AA-102-1001 NUCLEAR FLEET ADMINISTRATIVE ATTACHMENT 1 REPORTABLE EVENTS (Page 7 of 8)

News Release or Notification of Other Government Agency (See NUREG-1022 Section 3.2.12) 4 Hour Report § 50.72(b)(2)(xi) Any event or situation, related to the health and safety of the public or onsite personnel, or protection of the environment, for which a news release is planned or notification to other government agencies has been or will be made.

Such an event may include an onsite fatality or inadvertent release of radioactively contaminated materials.

Loss of Emergency Preparedness Capabilities (See NUREG-1022 Section 3.2.13) 8 Hour Report § 50.72(b)(3)(xiii) Any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, emergency notification system, or offsite notification system).

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28 REGULATORY REPORTING 23 of 126 PROCEDURE NO.:

LI-AA-102-1001 NUCLEAR FLEET ADMINISTRATIVE ATTACHMENT 1 REPORTABLE EVENTS (Page 8 of 8)

Single Cause that Could Have Prevented Fulfillment of the Safety Functions of Trains or Channels in Different Systems (See NUREG-1022 Section 3.2.14) 60 Day LER § 50.73(a)(2)(ix)(A) Any event or condition that as a result of a single cause could have prevented the fulfillment of a safety function for two or more trains or channels in different systems that are needed to:

(1) Shut down the reactor and maintain it in a safe shutdown condition; (2) Remove residual heat; (3) Control the release of radioactive material; or (4) Mitigate the consequences of an accident.

§ 50.73(a)(2)(ix)(B) Events covered in paragraph (ix)(A) of this section may include cases of procedural error, equipment failure, and/or discovery of a design, analysis, fabrication, construction, and/or procedural inadequacy. However, licensees are not required to report an event pursuant to paragraph (ix)(A) of this section if the event results from:

(1) A shared dependency among trains or channels that is a natural or expected consequence of the approved plant design; or (2) Normal and expected wear or degradation.

100.

Given the following conditions:

Unit 1 is at 100% power Subsequently:

A Pressurizer Spray Valve fails OPEN

The lowest Pressurizer Pressure observed was 1700 psia prior to event mitigation Which ONE of the following completes the statements below?

In accordance with LI-AA-102-1001, Regulatory Reporting, the most LIMITING time this event requires a ____(1)____ report.

In accordance with EPIP-08, Off-Site Notifications And Protective Action Recommendations, the report to the NRC will be made via the ____(2)____ phone.

REFERENCE PROVIDED A. (1) 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (2) Hot Ring Down (HRD)

B. (1) 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (2) Emergency Notification System (ENS)

C. (1) 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (2) Hot Ring Down (HRD)

D. (1) 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (2) Emergency Notification System (ENS)

St. Lucie December 2020 Initial Licensed Operator Final NRC Written Examination Answer Key As of January 22, 2021

1) B

2) B

3) C

4) B

5) D

6) B

7) B

8) A

9) A

10) A

11) D

12) A - change from post-exam comment

13) C

14) B

15) Q15 deleted from exam per post-exam comment

16) D

17) C

18) B

19) D

20) C 1lPage

21) A 22)D

23) B

24) B

25) B

26) C

27) A

28) A

29) A

30) A

31) A

32) A

33) D

34) D

35) A

36) B

37) C

38) C

39) A

40) C

41) A

42) A

43) B

44) B 2lPage

45)D

46) D

47) A

48) C

49) D

50) C

51) D

52) A

53) B

54) D

55) C

56) D

57) B

58) C

59) A

60) C

61) C

62) B

63) A

64) D

65) D

66) C

67) C

68) C 3lPage

69) D

70) A

71) B

72) A

73) A

74) B

75) C

76) B

77) D

78) C

79) B

80) C

81) C

82) C

83) C

84) A

85) C

86) D

87) A

88) D

89) B

90) C

91) C

92) D 4lPage

93) A

94) C

95) C

96) B

97) C

98) B

99) A 100) B 5lPage

ML21034A519

Text

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