Latest revision as of 21:38, 29 October 2025

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301 Exam Report Items - SRO as Given Written Exam (1)
	ML23258A148
Person / Time
Site:	Mcguire, McGuire
Issue date:	09/15/2023
From:	; NRC/RGN-II
To:	;
References
	Download: ML23258A148 (1)
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Question:

(1 point) 1 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

A reactor trip and safety injection has occurred

Safety injection and the Sequencer have been reset Subsequently:

A Blackout occurs on Bus 2ETA 2ETA is energized by the 2A D/G Based on the conditions above:

1) The 2A NV pump ________ automatically restart.

2) The 2A ND pump ________ automatically restart.

Which ONE of the following completes the statements above?

A.

1. will NOT

2. will NOT B.

1. will NOT

2. will C.

1. will

2. will NOT D.

1. will

2. will Page 1 of 100 ML23258A148

Question:

(1 point) 2 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

A reactor trip from 100% RTP has occurred

The Unit 1TDCA pump tripped on overspeed upon starting

Bus 1ETB locked out due to a ground fault on the bus Based on the conditions above:

1) With no initial operator action, there will be 450 gpm ______.

2) If needed, the operator will be able to manually adjust feed flow to ______

S/Gs.

Which ONE of the following completes the statements above?

A.

1. to each S/G

2. 1A and 1B B.

1. total CA flow

2. 1A and 1B C.

1. to each S/G

2. 1C and 1D D.

1. total CA flow

2. 1C and 1D Page 2 of 100

Question:

(1 point) 3 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

The 1A D/G has been placed in operation to facilitate the Diesel Generator Operability Test

The 1ETA Normal Breaker and 1ETA Emergency Breaker are both CLOSED.

Based on the conditions above:

1) Depressing the "1A D/G Gov Cntrl" "Raise" pushbutton will result in raising 1A D/G ________.

2) Rotating the "1A D/G Volt Adjust" switch to "Raise" will result in raising 1A D/G ________.

Which ONE of the following completes the statements above?

A.

1. frequency

2. KVARs B.

1. load

2. KVARs C.

1. frequency

2. voltage D.

1. load

2. voltage Page 3 of 100

Question:

(1 point) 4 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following:

Both units are operating at 100% RTP

An instrument air system leak develops in the Unit 1 Turbine Building

The Diesel VI Compressors (G & H) AUTO/OFF-RESET selector switches are in AUTO The following indications are observed in the Control Room:

Based on the indications above:

1) The Diesel VI Compressors (G & H) ______ received a start signal.

2) 1VI-820 (VI to VS Supply Valve) is ______.

Which ONE of the following completes the statements above?

A.

1. have

2. OPEN B.

1. have NOT

2. OPEN C.

1. have

2. CLOSED D.

1. have NOT

2. CLOSED Page 4 of 100

Question:

(1 point) 5 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 100% RTP

All Pressurizer heaters are energized in MANUAL

The SLIM for 1NV-238 (Charging Flow Control) has been placed in MANUAL due to a malfunction of the Pressurizer Level Master Controller Subsequently:

Charging Line Flow is reduced and maintained at 18 GPM Based on the conditions above, if the 1NV-238 controller output remains constant and 5 minutes have passed:

1) Pressurizer level will be slowly ______.

2) Pressurizer heaters will be ______.

Which ONE of the following completes the statements above?

A.

1. lowering

2. OFF B.

1. rising

2. OFF C.

1. lowering

2. ON D.

1. rising

2. ON Page 5 of 100

Question:

(1 point) 6 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is operating at 100% RTP

Train B components are in service Subsequently,

An Inadvertent SI is initiated by Maintenance during testing Based on the conditions above:

1) Lower Containment Ventilation Cooling will be supplied from ______.

2) 0RN-301AC (RV Supply from LLI) and 0RN-302B (RV Supply from LLI) will be ______.

Which ONE of the following completes the statements above?

A.

1. RV pumps

2. CLOSED B.

1. RN non-essential header

2. CLOSED C.

1. RN non-essential header

2. OPEN D.

1. RV pumps

2. OPEN Page 6 of 100

Question:

(1 point) 7 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

A Large Break LOCA occurred

The crew has implemented ES-1.3 ( TRANSFER TO COLD LEG RECIRC)

Containment Pressure on 1MC-11 is as follows:

Based on the containment pressure conditions given above:

1) At Time 1, Containment Spray ________ be aligned per ES-1.3.

2) At Time 2, the CPCS interlock that automatically closes the NS Pump Discharge Valves ________ been met.

Which ONE of the following completes the statements above?

A.

1. can

2. has NOT B.

1. can

2. has C.

1. can NOT

2. has NOT D.

1. can NOT

2. has Time 1 Time 2 Page 7 of 100

Question:

(1 point) 8 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

A shutdown is in progress and the unit is currently at 7% RTP

A LOCA occurs A Reactor Trip ___ (1) ___ occur if Pzr pressure lowers to 1945 PSIG.

If a Reactor Trip occurs, and all turbine throttle valves are NOT CLOSED after manually tripping the turbine, the NEXT required action per E-0 (REACTOR TRIP OR SAFETY INJECTION), is to ___ (2) ___.

Which ONE of the following completes the statements above?

A.

1. will

2. place turbine in manual and CLOSE GVs in fast action B.

1. will

2. CLOSE all MSIVs and MSIV Bypass valves C.

1. will NOT

2. place turbine in manual and CLOSE GVs in fast action D.

1. will NOT

2. CLOSE all MSIVs and MSIV Bypass valves Page 8 of 100

Question:

(1 point) 9 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 100% RTP

The 1D Steam Line PORV and Safety Valves are as follows:

Subsequently:

An event occurs that causes steam header pressure to rise.

Valve SV-1 (SM PORV) will OPEN when steam header pressure rises above a MINIMUM of ____ (1) ____ PSIG.

If pressure continues rising to 1200 PSIG, Main Steam Safety Valve SV-4

____ (2) ____ be OPEN.

Which ONE of the following completes the statements above?

A.

1. 1125

2. will NOT B.

1. 1125

2. will C.

1. 1170

2. will NOT D.

1. 1170

2. will Page 9 of 100

Question:

(1 point) 10 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 75% RTP

1D NCP Thermal Barrier KC Outlet Flow is in alarm on the OAC When KC Thermal Barrier Outlet flow exceeds a MINIMUM of (1) gpm, 1KC-413B (1D NCP THERM BAR OTLT) will automatically CLOSE.

With 1KC-413B CLOSED, 1D NCP operational limits (2) be exceeded.

Which ONE of the following completes the statements above?

A.

1. 75

2. will B.

1. 75

2. will NOT C.

1. 60

2. will D.

1. 60

2. will NOT Page 10 of 100

Question:

(1 point) 11 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 30% RTP, holding for chemistry The 1A NC pump trips Based on the conditions above, indicated Loop "A" Tavg will stabilize at a (1) value than prior to the 1A NC pump trip.

The reason that indicated Loop "A" Tavg changes (2) due to reverse flow in Loop 1A.

Which ONE of the following completes the statements above?

A.

1. higher

2. is B.

1. higher

2. is NOT C.

1. lower

2. is D.

1. lower

2. is NOT Page 11 of 100

Question:

(1 point) 12 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following current conditions on Unit 1:

Unit is operating at 100% RTP

A malfunction of the Letdown Hx Outlet temperature controller has caused 1KC-132 (Letdown Hx Cooling Water Control) valve to slowly drift closed

Letdown Heat Exchanger Outlet temperature has increased from 106°F to 115°F Based on the conditions above, NC system temperature will ___ (1) ___.

If Letdown Hx Outlet temperature continues to rise, 1NV-127A, L/D HX OUTLET 3-WAY TEMP CNTRL, will divert to the VCT at ___ (2) ___.

Which ONE of the following completes the statements above?

A.

1. rise

2. 120°F B.

1. rise

2. 138°F C.

1. lower

2. 120°F D.

1. lower

2. 138°F Page 12 of 100

Question:

(1 point) 13 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Based on the conditions above, 1ND-1B ___ (1) ___ be opened from the pushbutton on 1MC-11.

If NC pressure rises above a MINIMUM of 440 PSIG, 1ND-1B and 1ND-2AC

___ (2) ___ AUTOMATICALLY close.

Which ONE of the following completes the statements above?

Valve Legend:

1ND-1B (1C NC Loop to ND Pumps Isol) 1ND-2AC (1C NC Loops to ND PUMPS CONT INSIDE ISOL)

A.

1. can

2. will B.

1. can

2. will NOT C.

1. can NOT

2. will D.

1. can NOT

2. will NOT Page 13 of 100

Question:

(1 point) 14 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 100% RTP

1NV-6 (LETDOWN LINE INSIDE RB RELIEF) is leaking 9.0 GPM to the PRT The crew will lower PRT level with OP/1/A/6150/004, PRESSURIZER RELIEF TANK, by draining to the ______.

Which ONE of the following completes the statement above?

A.

WEFT (Waste Evaporator Feed Tank)

B.

RHT (Recycle Holdup Tank)

C.

NCDT (Reactor Coolant Drain Tank)

D.

FDT (Floor Drain Tank)

Page 14 of 100

Question:

(1 point) 15 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Regarding operation of the Pressurizer Relief Tank (PRT),

1) Leakage through ________ will cause PRT pressure to RISE.

2) If the input continues, the PRT ________ will operate to reduce PRT pressure.

Which ONE of the following completes the statements above?

VALVE LEGEND:

1NV-93 (UNIT 1 NC PUMPS SEAL WATER RETURN HEADER RELIEF) 1NV-170 (UNIT 1 VCT RELIEF)

A.

1

1. 1NV-93

2. rupture disc B.

1

1. 1NV-170

2. rupture disc C.

1

1. 1NV-93

2. relief valve D.

1

1. 1NV-170

2. relief valve Page 15 of 100

Question:

(1 point) 16 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

A DCS failure occurs affecting Pzr pressure control

The crew is taking action per OP/2/A/6102/005 (Operator Response to Loss of DCS Controller(s)), Enclosure 4.4 (Response to Loss of Controller Drops 8 and

58)

When 2NC-32B (Pzr PORV) or 2NC-36B (Pzr PORV) fails to automatically open, OP/2/A/6102/005 directs the crew to manually OPEN the PORVs at ______ PSIG.

Which ONE of the following completes the statement above?

A.

2250 B.

2327 C.

2335 D.

2385 Page 16 of 100

Question:

(1 point) 17 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

A load increase is in progress

The Pressurizer Pressure Master Controller OUTPUT fails LOW

All Pressurizer Pressure control components are in AUTO

NO operator actions have been taken Based on the conditions above:

1) NC system pressure will initially be ________.

2) If conditions warrant, 2NC-34A (PZR PORV) _____ open as required.

Which ONE of the following completes the statements above?

A.

1. lowering

2. will B.

1. lowering

2. will NOT C.

1. rising

2. will D.

1. rising

2. will NOT Page 17 of 100

Question:

(1 point) 18 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following:

Unit 1 was operating at 100% RTP Subsequently:

A pressurizer steam space leak occurred.

Pressurizer Pressure decreased by 300 psig.

Ambient air temperature surrounding the reference leg increased by 80ºF

Actual pressurizer water level is 60 percent There are ___ (1) ___ pressurizer level channels calibrated for normal pressurizer temperature.

The increased reference leg temperature will tend to make the indicated pressurizer level read ___ (2) ___ than actual.

CONSIDER EACH QUESTION SEPERATELY Refer to the following drawing:

Which ONE of the following completes the statement above?

A.

1. three

2. higher B.

1. three

2. lower C.

1. four

2. higher D.

1. four

2. lower Page 18 of 100

Question:

(1 point) 19 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Which ONE of the following is the power supply to 1A Upper Containment Ventilation System (VU) air handling unit?

A.

1EMXD B.

1EMXC C.

1MXJ D.

1MXK Page 19 of 100

Question:

(1 point) 20 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is operating at 100% RTP

MSR System Control is in Automatic Subsequently:

A component failure causes a turbine trip Based on the conditions above:

1) The MSR RESET light on the Moisture Separator Reheater Control section of 1MC01 will be ______.

2) 1SM-15 (U1 SM To MSR 2nd Sta Tube Bundle Isol) on 1MC02 will indicate Which ONE of the following completes the statements above?

A.

1. OFF

2. OPEN B.

1. OFF

2. CLOSED C.

1. ON

2. OPEN D.

1. ON

2. CLOSED Page 20 of 100

Question:

(1 point) 21 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Regarding Feedwater Pump Speed Control:

In ___ (1) ___ mode, the CF pump will maintain speed based on a setpoint from the Low-Pressure Governor Control Station.

In order to adjust the Low-Pressure Governor Control SETPOINT, the operator will use the raise/lower controls on the ___ (2) ___ side of the SLIM.

Which ONE of the following completes the statements above?

A.

1. SPEED SET

2. right B.

1. SPEED SET

2. left C.

1. AUTO

2. right D.

1. AUTO

2. left Page 21 of 100

Question:

(1 point) 22 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Regarding cleanup of the Condensate and Feedwater System to meet chemistry requirements:

1) The ______ pressure cleanup flowpath has water circulate through the hotwell pump through the polishing demineralizers, through the system to the outlet of the A heaters.

2) Water used for cleanup is returned to the ______.

Which ONE of the following completes the statement above?

A.

1. high

2. CST B.

1. low

2. CST C.

1. high

2. UST D.

1. low

2. UST Page 22 of 100

Question:

(1 point) 23 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

1AD-11, L-2, ETB DEGRADED VOLTAGE, is in alarm.

Based on the condition above:

1) The degraded voltage relays will initiate a blackout and the 1B DG will start if the condition continues for a MINIMUM of ______ minutes.

2) When D/G speed is greater than a MINIMUM of ______ the D/G output breaker will close.

Which ONE of the following completes the statements above?

A.

1. 12

2. 95%

B.

1. 10

2. 95%

C.

1. 10

2. 97%

D.

1. 12

2. 97%

Page 23 of 100

Question:

(1 point) 24 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

A fault required battery EVCB to be removed from service

The crew is aligning charger EVCD and battery EVCD to supply distribution center EVDB per OP/0/A/6350/001A Enclosure 4.13, Removal of Battery From Service for Maintenance (EVCA-EVCD).

Subsequently:

2AD-11 F3 (BATT EVCD GROUND) alarms in the Control Room

Relay Board 2EB9 indicates a positive leg ground exists on EVCD Based on the conditions above:

1) The detector lamp on 2EB9 will be ________ to indicate a ground.

2) Per Enclosure 4.13, Limits and Precautions, the alignment of EVCD should NOT occur if a ________ leg ground exists on EVDB.

Which ONE of the following completes the statements above?

A.

1. bright

2. positive B.

1. dim

2. positive C.

1. bright

2. negative D.

1. dim

2. negative Page 24 of 100

Question:

(1 point) 25 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following conditions on Unit 1:

Unit is at 100% RTP

A leak has developed on the RC piping in the turbine building basement

The crew is performing an Urgent Release to RC discharge per OP/1/B/6400/001 D (TURBINE BUILDING SUMP OPERATION)

All TB Sump pumps are in Manual and ON, maintaining sump level stable Subsequently:

A failed power supply causes a detector failure on 1EMF-31 (TURBINE BUILDING SUMP MONITOR)

Based on the conditions above:

1) The TB Sump pumps will trip due to an 1EMF-31 ________ being generated.

2) Placing the HI RAD INHIBT/BYPASS switch to BYPASS allow restart of the TB Sump pumps.

Which ONE of the following completes the statements above?

A.

1. Trip 2

2. will NOT B.

1. Trip 1

2. will NOT C.

1. Trip 2

2. will D.

1. Trip 1

2. will Page 25 of 100

Question:

(1 point) 26 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

A failure of the RP-86A module on 1EMF-46A (COMPONENT COOLING WATER MONITOR) has occurred

The failure has resulted in a Trip 2 condition on 1EMF-46A Based on the conditions above, ______ will CLOSE.

Which ONE of the following completes the statement above?

A.

1KC-51A (TRAIN A RECIRC ISOL)

B.

1KC-122 (KC SURGE TANK VENT)

C.

1KC-50A (TRN A AUX BLDG NON ESS SUP ISOL)

D.

1KC-230A (TRN A RX BLDG NON ESS SUP ISOL)

Page 26 of 100

Question:

(1 point) 27 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Concerning Unit 0 designated RN (Nuclear Service Water) valves:

The valve motors for the Train "B" valves are NORMALLY powered from ______.

Which ONE of the following completes the statement above?

A.

1EMXH B.

2EMXH C.

1EMXB D.

2EMXB Page 27 of 100

Question:

(1 point) 28 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Regarding the Annulus Ventilation (VE) System:

The VE System starts on a Phase ___ (1) ___ Containment Isolation Signal and runs in the ___ (2) ___.

Which ONE of the following completes the statement above?

A.

1. A

2. discharge mode until annulus pressure reaches the recirculation mode setpoint B.

1. B

2. discharge mode until annulus pressure reaches the recirculation mode setpoint C.

1. A

2. recirculation mode until annulus pressure reaches the discharge mode setpoint D.

1. B

2. recirculation mode until annulus pressure reaches the discharge mode setpoint Page 28 of 100

Question:

(1 point) 29 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Unit 2 is performing a MOL plant startup with the following conditions:

Reactor Power is at 55% and stable A S/G Safety valve fails open Based on the conditions above:

Pressurizer level will ___ (1) ___ and reactor power will ___ (2) ___.

Which ONE of the following completes the statement above?

A.

1. lower

2. rise B.

1. rise

2. rise C.

1. rise

2. lower D.

1. lower

2. lower Page 29 of 100

Question:

(1 point) 30 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following:

Both Units at 100% RTP Subsequently,

EVCA Battery Charger Output breaker trips open

Attempts to align distribution center EVDA to Charger EVCS per OP/0/A/6350/001A (125 VDC/120 VAC VITAL INSTRUMENT AND CONTROL POWER SYSTEM) were NOT successful To prevent a loss of 1NCP-5161 (Pzr Pressure Channel 1), AC Panelboard 1EKVA

____(1)____ to 1KRP upon loss of power.

Battery EVCA is rated to supply loads without charger assistance for a MAXIMUM of

____(2)____ hour(s).

Which ONE of the following completes the statements above?

A.

1. will automatically transfer

2. four B.

1. will automatically transfer

2. one C.

1. must be manually transferred

2. four D.

1. must be manually transferred

2. one Page 30 of 100

Question:

(1 point) 31 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is in No MODE

Preparations are being made for moving fuel To operate the Containment Purge (VP) system in the REFUEL position, the reactor missile shields ____(1)____ required to be removed.

When VP is operating in the REFUEL position, the ratio of supply air will be

____(2)____ (Upper/Lower Containment).

Which ONE of the following completes the statements above?

A.

1. are

2. 2/1 B.

1. are NOT

2. 2/1 C.

1. are

2. 4/1 D.

1. are NOT

2. 4/1 Page 31 of 100

Question:

(1 point) 32 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following:

Unit 1 Fuel Handling is in progress

During Fuel Assembly removal, the hoist is stopped mid travel due to overload cutoff limit During fuel movement the refueling crane load cell sensed a MINIMUM of

___ (1) ___ pounds.

Based on the above conditions, bridge and trolley motion ___ (2) ___ possible.

Which ONE of the following completes the statements above?

A.

1. 2900

2. is B.

1. 2900

2. is NOT C.

1. 1000

2. is D.

1. 1000

2. is NOT Page 32 of 100

Question:

(1 point) 33 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

Unit has just entered Mode 3 preparing for cooldown to Mode 5

NC System pressure is 2235 PSIG

NC Tave is 557°F To perform the cooldown using the STEAM DUMP CTRL M/A station, the STEAM DUMP SELECT switch must be in the ____(1)____ position.

Based on the conditions above, when initiating NC system cooldown at maximum rate, ____(2)____ condenser dump valves will throttle OPEN.

Which ONE of the following completes the statements above?

A.

1. T-AVG

2. ONLY three B.

1. T-AVG

2. all C.

1. STM PRESS

2. ONLY three D.

1. STM PRESS

2. all Page 33 of 100

Question:

(1 point) 34 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

A SGTR has occurred on 1A S/G

The crew has implemented E-3 (STEAM GENERATOR TUBE RUPTURE)

The OATC is performing the initial cooldown Based on the conditions above, if NC system TAVG lowers to less than the setpoint of ___ (1) ___, steam dump valve operation will be blocked.

After steam dump operation is blocked, if TAVG rises above the P-12 setpoint, the Bypass interlock ___ (2) ___ automatically reset.

Which ONE of the following completes the statement above?

A.

1. 551°F

2. will B.

1. 553°F

2. will C.

1. 551°F

2. will NOT D.

1. 553°F

2. will NOT Page 34 of 100

Question:

(1 point) 35 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit 1 was operating at 100% RTP Subsequently:

Multiple equipment failures occur and the indications below are observed:

Based on the conditions above:

A ___ (1) ___ turbine runback will be performed to reduce ___ (2) ___.

Which ONE of the following completes the statement above?

A.

1. slow rate (3 minutes)

2. Delta T below setpoint B.

1. fast rate (200%/min)

2. RTP to 55%

C.

1. slow rate (3 minutes)

2. RTP to 55%

D.

1. fast rate (200%/min)

2. Delta T below setpoint On 1MC01:

On 1MC11:

1AD2 A8/B8:

1A CLSD: LIT 1B CLSD: LIT Page 35 of 100

Question:

(1 point) 36 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

2A S/G has developed a 200 GPD tube leak

2EMF-33 (CSAE DISCHARGE) Trip 2 light is illuminated The normal discharge flowpath for the Condenser Steam Jet Air Ejectors (CSAE) is to the ____(1)____.

A Trip 2 condition on 2EMF-33, ____(2)____ isolate the CSAE drains to the turbine building sump.

Which ONE of the following completes the statements above?

A.

1. Turbine Building roof

2. will B.

1. Unit Vent

2. will C.

1. Unit Vent

2. will NOT D.

1. Turbine Building roof

2. will NOT Page 36 of 100

Question:

(1 point) 37 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Annunciator 1RAD-2/C2 (1EMF 44 CONT VENT DRN TANK HI RAD) is in alarm

The BOP reports 1EMF-44 is in Trip 2 Based on the conditions above:

1WM-46 (0EMF49 Outlet High Rad Shutoff Isol) ___ (1) ___ receive an auto CLOSE signal.

1WP-37 (Liquid Waste to RC Cntrl) (2) receive an auto CLOSE signal.

Which ONE of the following completes the statements above?

A.

1. will

2. will B.

1. will

2. will NOT C.

1. will NOT

2. will D.

1. will NOT

2. will NOT Page 37 of 100

Question:

(1 point) 38 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

A Reactor trip and Safety Injection has occurred due to a stuck open PZR PORV

The CRS implemented E-0 (REACTOR TRIP OR SAFETY INJECTION)

The crew closed the PORV using nitrogen The crew is now evaluating S/I termination criteria with the following indications:

NC system pressure is 1200 PSIG and stable

Containment pressure peaked at 1.2 PSIG and is slowly lowering

NC subcooling is 2°F

PZR level is 10% and rising slowly

Total CA flow is 475 GPM

SG N/R levels are 10% and stable Based on the conditions above, S/I can NOT be terminated because ________

requirements are NOT met.

Which ONE of the following completes the statement above?

A.

NC Pressure B.

NC Subcooling C.

Heat sink D.

Pzr level Page 38 of 100

Question:

(1 point) 39 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

A Safety Injection due to High Containment pressure has occurred

The crew has implemented E-0 (REACTOR TRIP OR SAFETY INJECTION)

NV pump flow to the NC system Cold Legs is 390 GPM

NC system pressure is 1350 PSIG and STABLE

SG pressures are 1092 PSIG and STABLE

NC system subcooling on the ICCM is 22°F and STABLE Per E-0 Foldout Page, the crew ____(1)____ secure NC pumps.

Upon transition to E-1 (LOSS OF REACTOR OR SECONDARY COOLANT), Steam Generators ____(2)____ be required for heat removal.

Which ONE of the following completes the statements above?

A.

1. will NOT

2. will NOT B.

1. will

2. will C.

1. will

2. will NOT D.

1. will NOT

2. will Page 39 of 100

Question:

(1 point) 40 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Time 10:00:00

A Large Break LOCA has occurred

Containment pressure peaked at 3.1 PSIG

The CRS has implemented E-0 (REACTOR TRIP OR SAFETY INJECTION)

Time 10:10:00

Containment Pressure is now 0.7 PSIG Based on the conditions above:

Per E-0, the crew ___ (1) ___ required to perform Enclosure 2 (PHASE B HVAC EQUIPMENT).

At time 10:10, the Containment Air Return Fans (C.A.R.F.s) ___ (1) ___ be ON.

Which ONE of the following correctly completes the statements above?

A.

1. is

2. will NOT B.

1. is

2. will C.

1. is NOT

2. will NOT D.

1. is NOT

2. will Page 40 of 100

Question:

(1 point) 41 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 100% RTP

The BOP observes the following 1C NC Pump readings on the OAC (all readings are valid):

Time 2100 2105 2110 2115 Lower Radial Bearing Temp (°F) 170 190 200 225

1 Seal Outlet Temp (°F) 175 200 225 235 Per AP-08 (MALFUNCTION OF NC PUMP):

The EARLIEST time that the 1C NCP must be secured is ______.

Which ONE of the following completes the statement above?

A.

2100 B.

2105 C.

2110 D.

2115 Page 41 of 100

Question:

(1 point) 42 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 100% RTP

The CRS has implemented AP-12 (LOSS OF LETDOWN, CHARGING OR SEAL INJECTION) following a trip of 1A NV Pump Subsequently:

1B NV Pump has been started When initially restoring seal injection flow, the BOP will slowly throttle ____(1)____ on 1NV-241 (U1 SEAL WATER INJ FLOW CONTROL) to ____(2)____.

Which ONE of the following completes the statement above?

A.

1. CLOSED

2. limit NCP lower bearing cooldown rate to 1°F/min B.

1. OPEN

2. limit NCP lower bearing cooldown rate to 1°F/min C.

1. OPEN

2. establish 8-10 gpm seal flow per NC pump D.

1. CLOSED

2. establish 8-10 gpm seal flow per NC pump Page 42 of 100

Question:

(1 point) 43 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 100% RTP

The CRS has implemented AP-21 (LOSS OF KC OR KC SYSTEM LEAKAGE)

KC Surge Tank level is lowering with FIRST makeup source aligned Based on the conditions above:

1) The NEXT source of makeup to be aligned per AP-21 is ________.

2) A possible location of the KC system leakage is into the ________ heat exchanger.

Which ONE of the following completes the statements above?

A.

1. RN

2. Seal Water Return B.

1. YM

2. Seal Water Return C.

1. RN

2. Letdown D.

1. YM

2. Letdown Page 43 of 100

Question:

(1 point) 44 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is in MODE 3

Shutdown Banks are withdrawn

NC System is at normal operating temperature and pressure Subsequently:

1NC-32B (PZR PORV) fails open

AP-11 (PRESSURIZER PRESSURE ANOMALIES) has been implemented

The PORV isolation valve for 1NC-32B will not close

An RO is directed to trip the reactor and initiate Safety Injection

Neither reactor trip breaker will open

Pressurizer Pressure is 1840 PSIG and lowering

S/I Actuated status light is DARK Based on the conditions above:

1) The crew ______ required to initiate SI at this time.

2) The crew will subsequently transition to ______.

Which ONE of the following completes the statements above?

A.

1. is NOT

2. E-0 (REACTOR TRIP OR SAFETY INJECTION)

B.

1. is NOT

2. AP-34 (SHUTDOWN LOCA)

C.

1. is

2. AP-34 (SHUTDOWN LOCA)

D.

1. is

2. E-0 (REACTOR TRIP OR SAFETY INJECTION)

Page 44 of 100

Question:

(1 point) 45 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

A transient has occurred requiring an automatic reactor trip

While performing E-0 Immediate Actions the OATC observes the following indications:

Based on the conditions above, entry into FR-S.1 (RESPONSE TO NUCLEAR POWER GENERATION/ATWS) is required due to ___ (1) ___ path on Subcriticality.

Per FR-S.1, one Immediate Action is to ensure control rod insertion in ____(2)____.

Which ONE of the following completes the statements above?

A.

1. a RED

2. Manual ONLY B.

1. a RED

2. Manual OR Auto C.

1. an ORANGE

2. Manual ONLY D.

1. an ORANGE

2. Manual OR Auto Page 45 of 100

Question:

(1 point) 46 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

The unit is at 100% RTP

1EMF 71-74 (N16 MONITORS) are in Trip 2

1EMF-24 (STEAM LINE 1A MONITOR) is in Trip 1

1EMF-33 (CSAE) is in Trip 2

1EMF-34(L) (S/G SAMPLE - LOW RANGE) is in Trip 1

The CRS has implemented AP-10 (NC SYSTEM LEAKAGE WITHIN THE CAPACITY OF BOTH NV PUMPS) Case 1 (STEAM GENERATOR TUBE LEAKAGE)

Based on the conditions above, S/G Blowdown ____(1)____ been isolated.

Per AP-10, Case 1, RP is required to frisk all Unit 1 (2) and compare them to determine if any activity level is significantly higher.

Which ONE of the following completes the statements above?

A.

1. has NOT

2. Main Steam Lines B.

1. has

2. Main Steam Lines C.

1. has NOT

2. SG Cation Columns D.

1. has

2. SG Cation Columns Page 46 of 100

Question:

(1 point) 47 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit 1 has established feed and bleed while performing the actions of FR-H.1 (RESPONSE TO LOSS OF SECONDARY HEAT SINK)

Subsequently:

The TDCA pump has been started and is available to feed the S/Gs

CETs are STABLE

All S/G WR levels are indicating 0%

1) Based on the conditions above, the criteria for restoration of CA flow is to restore cooling to ________ at a rate not to exceed 100 GPM.

2) The basis for the restoration of flow criteria is to minimize ________.

Which ONE of the following completes the statements above?

A.

1. ALL intact S/Gs

2. additional NC cooldown causing thermal stress to the reactor vessel B.

1. ONE intact S/G

2. additional NC cooldown causing thermal stress to the reactor vessel C.

1. ALL intact S/Gs

2. the thermal stress on the S/G to prevent failure of S/G components D.

1. ONE intact S/G

2. the thermal stress on the S/G to prevent failure of S/G components Page 47 of 100

Question:

(1 point) 48 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

The CRS has just implemented ECA-0.0 (LOSS OF ALL AC POWER)

1A D/G automatically started, but then immediately tripped

1B D/G failed to automatically start

Unit 2 was unaffected by the loss of offsite power on Unit 1 Per ECA-0.0, the crew will FIRST attempt to restore power to an essential bus by Which ONE of the following completes the statement above?

A.

manually starting both diesel generators from the control room B.

initiating safety injection on both trains C.

locally starting the 1B diesel generator D.

aligning offsite power from Unit 2 Page 48 of 100

Question:

(1 point) 49 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

A small break LOCA has occurred

Safety Injection has been initiated

The sequencer has NOT been reset

S/G NR levels indicate the following:

S/G 2A 2B 2C 2D NR Level

(%)

15 19 16 18 Subsequently:

The normal incoming breaker to 2ETA OPENS Two minutes after the Blackout on 2ETA, the 2A and 2B SGs are ________.

Which ONE of the following completes the statement above?

A.

not being fed B.

being fed by the 2A MDCA pump ONLY C.

being fed by the U2 TDCA pump ONLY D.

being fed by the 2A MDCA pump AND U2 TDCA pump Page 49 of 100

Question:

(1 point) 50 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following:

A loss of 1EKVD has occurred

The CRS has implemented AP-15 (LOSS OF VITAL OR AUX CONTROL POWER)

Per AP-15:

1) When checking Vital AC panelboards ENERGIZED, the crew will check ________.

2) Annunciator 1AD-2/F-1 (SSPS TRN B GENERAL WARNING) ________

be LIT.

Which ONE of the following completes the statements above?

A.

1. bottom row of channel status lights - NORMAL

2. will NOT B.

1. switch indication on any pump powered from 1ETB - DARK

2. will NOT C.

1. bottom row of channel status lights - NORMAL

2. will D.

1. switch indication on any pump powered from 1ETB - DARK

2. will Page 50 of 100

Question:

(1 point) 51 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 100% RTP

A total loss of offsite and onsite power occurs As vital battery terminal voltage lowers, battery discharge rate will ____(1)____.

Per AP-15 (LOSS OF VITAL OR AUX CONTROL POWER), the vital batteries are required to be removed from service when voltage on the DC Vital busses lowers below a MAXIMUM of ____(2)____ volts.

Which ONE of the following completes the statements above?

A.

1. rise

2. 107.5 B.

1. lower

2. 107.5 C.

1. rise

2. 115 D.

1. lower

2. 115 Page 51 of 100

Question:

(1 point) 52 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 100% RTP

Both Trains of KC and RN are in service Subsequently,

A loss of 1A RN pump occurs

A Blackout occurs on 2ETA Based on the conditions above:

1) 1A Component Cooling (KC) heat exchanger ________ have RN cooling water flow.

2) The 1B RN suction ________ automatically swap to the Standby Nuclear Service Water Pond (SNSWP).

Which ONE of the following completes the statements above?

A.

1. does NOT

2. will B.

1. does NOT

2. will NOT C.

1. does

2. will D.

1. does

2. will NOT Page 52 of 100

Question:

(1 point) 53 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

The crew has implemented ECA-1.2 (LOCA OUTSIDE CONTAINMENT)

U2 FWST level is slowly lowering

NC system pressure is 1600 PSIG and slowly lowering Per ECA-1.2,

1) the crew will FIRST stop and isolate the ________ pumps from the FWST.

2) the overall mitigation strategy includes cooldown and depressurization of the NCS to allow the ________.

Which ONE of the following completes the statements above?

A.

1. NI

2. ND isolation valves (2NI-173A and 2NI-178B) to be closed B.

1. NI

2. Cold Leg Accumulators to inject C.

1. ND

2. ND isolation valves (2NI-173A and 2NI-178B) to be closed D.

1. ND

2. Cold Leg Accumulators to inject Page 53 of 100

Question:

(1 point) 54 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

A LOCA has occurred

The CRS has implemented ECA-1.1 (LOSS OF EMERGENCY COOLANT RECIRC) following multiple equipment failures in the ND system Subsequently:

Initial NC system cooldown and depressurization is in progress

NC system pressure is 1000 PSIG and lowering

Pzr level is 70% and rising slowly

Containment pressure peaked at 3.2 PSIG and is stable at 1.8 PSIG Per ECA-1.1:

1) The NC system cooldown is required to be performed at ________.

2) NC system depressurization ________ be secured at this time.

Which ONE of the following completes the statements above?

A.

1. maximum rate

2. can B.

1. maximum rate

2. can NOT C.

1. a rate NOT to exceed 100°F in an hour

2. can D.

1. a rate NOT to exceed 100°F in an hour

2. can NOT Page 54 of 100

Question:

(1 point) 55 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit 1 has established feed and bleed per FR-H.1 (RESPONSE TO LOSS OF SECONDARY HEAT SINK) following a feed line break inside containment Subsequently:

The TDCA pump has been started and is available to feed the S/Gs

CETs are slowly RISING

All S/G W/R levels are indicating 10% and slowly lowering

Containment Pressure rose to 2.6 PSIG and stabilized Per FR-H.1 and based on the conditions above, the criteria for restoration of CA flow is to throttle CA flow to ____(1)____ until S/G W/R level is greater than ____(2)____.

Which ONE of the following completes the statements above?

A.

1. a rate required to lower Core Exit T/Cs

2. 12%

B.

1. a rate required to lower Core Exit T/Cs

2. 17%

C.

1. less than or equal to 25 GPM

2. 12%

D.

1. less than or equal to 25 GPM

2. 17%

Page 55 of 100

Question:

(1 point) 56 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 35% RTP Control Bank D, Rod D-4 has dropped AP-14 (ROD CONTROL MALFUNCTION) has been implemented Based on the conditions above, the Digital Rod Position Indication (DRPI) CRT background for the affected rods will be ____(1)____.

Per AP-14, when performing steps to realign Rod D-4, the crew will OPEN the Control Bank D lift coil disconnect switch(es) for ____(2)____.

Which ONE of the following completes the statements above?

A.

1. orange

2. all rods except the misaligned rod B.

1. black

2. all rods except the misaligned rod C.

1. orange

2. the misaligned rod ONLY D.

1. black

2. the misaligned rod ONLY Page 56 of 100

Question:

(1 point) 57 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following conditions on Unit 1:

A runback from 100% RTP has occurred

During the runback, control rod H-8 became stuck

Rod H-8 is determined to be 16 steps misaligned Based on the conditions above, the action statement of T.S 3.1.4 (Rod/Group Alignment Limits) ___ (1) ___ required to be entered.

Per T.S 3.2.3 (Axial Flux Difference (AFD)), if AFD exceeds the COLR limits due to the stuck rod, reactor THERMAL POWER must be reduced to a value less than a MAXIMUM of ___ (2) ___.

Which ONE of the following completes the statements above?

A.

1. is 2 50%

B.

1. is NOT 2 75%

C.

1. is NOT 2 50%

D.

1. is 2 75%

Page 57 of 100

Question:

(1 point) 58 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

A reactor trip signal has been received o 3 rod bottom lights are NOT lit o Reactor trip and bypass breakers are OPEN o I/R power is going down

The crew has completed E-0, (REACTOR TRIP OR SAFETY INJECTION) and transitioned to ES-0.1 (REACTOR TRIP RESPONSE)

Subsequently:

Per ES-0.1, the BOP operator is performing AP-38 (EMERGENCY BORATION AND RESPONSE TO INADVERTENT DILUTION).

1B Boric Acid Transfer pump is RUNNING Based on the conditions above, ES-0.1 will require the crew to emergency borate a TOTAL of ____(1)____ gallons per AP-38.

Per AP-38, when INITIALLY aligning for emergency boration, the crew ____(2)____ be required to start a second Boric Acid Transfer pump.

Which ONE of the following completes the statements above?

A.

1. 8000

2. will B.

1. 8000

2. will NOT C.

1. 6000

2. will D.

1. 6000

2. will NOT Page 58 of 100

Question:

(1 point) 59 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

The crew is performing a reactor start-up per OP/1/A/6100/003 (CONTROLLING PROCEDURE FOR UNIT OPERATION)

Source Range N-32 has failed LOW

Other NI indications are as follows:

Source Range N-31 Intermediate Range N-35 and N-36 Based on the indications above, and per OP/1/A/6100/003, the required overlap between the IR channels and SR N-31 (1) met.

While removing SR N-32 from service, AP-16 (MALFUNCTION OF NUCLEAR INSTRUMENTATION) Case 1(SOURCE RANGE MALFUNCTION) (2) direct the crew to place the High Flux at Shutdown switch to Block.

Which ONE of the following completes the statements above?

A.

1. is NOT

2. does B.

1. is NOT

2. does NOT C.

1. is

2. does D.

1. is

2. does NOT Page 59 of 100

Question:

(1 point) 60 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following Unit on 1:

Unit startup is in progress

All Power Range Instruments indicate 6%

Intermediate Range Detector N35 fails low

The CRS has implemented AP-16 (MALFUNCTION OF NUCLEAR INSTRUMENTATION SYSTEM)

Based on the conditions above:

1) Reactor power indication on ____ ____ will be affected.

2) A loss of N35 Control Power ____ ____ result in a Reactor trip.

Which ONE of the following completes the statements above?

A.

1. N31(SR) AND N35

2. will NOT B.

1. N35 ONLY

2. will NOT C.

1. N31(SR) AND N35

2. will D.

1. N35 ONLY

2. will Page 60 of 100

Question:

(1 point) 61 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is conducting refueling operations in MODE 6

The containment purge (VP) system is in operation in the REFUEL mode

B train of SSPS is in TEST Subsequently:

The refueling crew dropped a fuel assembly into the refueling cavity

1RAD-1 A/2 (1EMF-39 CONTAINMENT GAS HI RAD) - LIT

1RAD-3 D/1 (1EMF-16 CONTAINMENT REFUELING BRIDGE) - LIT

The crew has implemented AP-25 (DAMAGED SPENT FUEL)

Based on the conditions above, ____(1)____ when AP-25 is entered.

Per AP-25 basis document, VP is removed from service to prevent ____(2)____.

Which ONE of the following completes the statements above?

A.

1. B Train of VP is running

2. the release of radioactive material from containment B.

1. B Train of VP is running

2. an excessive negative pressure in containment C.

1. VP is secured

2. the release of radioactive material from containment D.

1. VP is secured

2. an excessive negative pressure in containment Page 61 of 100

Question:

(1 point) 62 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

A Reactor trip and Safety Injection have occurred The crew has completed E-0 (REACTOR TRIP OR SAFETY INJECTION)

Subsequently:

The CRS has implemented ES-0.0 (REDIAGNOSIS)

The following indications are observed:

o NC System pressure is 1850 PSIG and LOWERING o NC System temperature is 525 °F and LOWERING o Containment humidity is RISING o Containment Pressure is 0.8 PSIG and RISING Based on the conditions above, a ____ (1) ____ is occurring.

When containment pressure exceeds 1.0 PSIG, a Main Steam Isolation

____ (2) ____ occur.

Which ONE of the following completes the statements above?

A.

1. small break LOCA

2. will B.

1. small break LOCA

2. will NOT C.

1. faulted steam generator

2. will D.

1. faulted steam generator

2. will NOT Page 62 of 100

Question:

(1 point) 63 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

A LOCA occurred

Containment pressure peaked at 2.8 PSIG and is currently stable at 2.5 PSIG

1EMF-51A is reading 40 R/Hr

ECCS suctions have been swapped to the Cold Leg Recirculation alignment

FWST level is 4% and slowly lowering

CLA levels indicate 0%

Reactor Vessel Lower Range level is 49% and slowly lowering

Containment Sump level is 12.6 feet and rising Based on the conditions above:

1) Containment sump levels ________ higher than expected.

2) An ORANGE path on the Containment Critical Safety Function

________ been generated.

Which ONE of the following completes the statements above?

A.

1. are

2. has B.

1. are

2. has NOT C.

1. are NOT

2. has D.

1. are NOT

2. has NOT Page 63 of 100

Question:

(1 point) 64 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following:

You are performing a post maintenance lineup

You are verifying 4160V breaker 1ETA-9 (1A NI PUMP), RACKED IN Per AD-HU-ALL-0005 (HUMAN PERFORMANCE TOOLS):

1) Verification of the Racked In status of this breaker ________.

2) ________ will be used when the consequences of an incorrect action would lead to immediate and irreversible harm to systems or personnel.

Which ONE of the following completes the statements above?

A.

1. MUST be performed locally

2. Independent Verification (IV)

B.

1. CAN be performed using the C/R remote indicating light

2. Independent Verification (IV)

C.

1. MUST be performed locally

2. Concurrent Verification (CV)

D.

1. CAN be performed using the C/R remote indicating light

2. Concurrent Verification (CV)

Page 64 of 100

Question:

(1 point) 65 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following separate scenarios:

Unit 1 has suffered a loss of Main Feed Pump runback from 100% RTP o Control rods failed to automatically insert on the runback

Unit 2 is currently raising power to 100% RTP following Control Valve Movement Testing o An ILT student is manipulating control rods under the instruction of the OATC Per AD-OP-ALL-0203 (REACTIVITY MANAGEMENT):

1) An additional Reactor Operator ________ required to peer check the Unit 1 OATC manually operating failed control rods.

2) An additional Reactor Operator ________ required to peer check control rod manipulations performed by the ILT student on Unit 2.

Which ONE of the following correctly completes the statements above?

A.

1.

is

2.

is NOT B.

1.

is

2.

is C.

1.

is NOT

2.

is NOT D.

1.

is NOT 2

is Page 65 of 100

Question:

(1 point) 66 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit shutdown and cooldown in progress

NC System Tavg is 325°F Per T.S 1.1 (Definitions), Unit 1 is in ____(1)____.

Based on the current status of Unit 1, ____(2)____ train(s) of ECCS shall be OPERABLE.

Which ONE of the following completes the statements above?

A.

1. MODE 4

2. two B.

1. MODE 4

2. one C.

1. MODE 3

2. two D.

1. MODE 3

2. one Page 66 of 100

Question:

(1 point) 67 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Per AD-OP-ALL-0200 (CLEARANCE AND TAGGING)

When Main Control Board control switches are tagged to indicate a component is only affected by a Clearance they should normally be tagged with a ______

tag.

Which ONE of the following completes the statement above?

A.

Comment B.

Danger C.

Equipment Protection (EQP)

D.

Clearance Information (CIT)

Page 67 of 100

Question:

(1 point) 68 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Regarding Liquid radioactive releases, Re-initiation of a Waste Monitor Tank release following a Trip 2 signal on 0EMF-49L (LIQUID WASTE - LOW RANGE) ____(1)____ allowed WITHOUT resampling and generating new LWR paperwork.

Re-initiation of a TB sump release to Waste Water Treatment following a Trip 2 signal on 1EMF-31 (TURBINE BLDG SUMP) ____(2)____ allowed WITHOUT resampling and generating new LWR paperwork.

Consider Each Statement Separately Which ONE of the following completes the statements above?

A.

1. is

2. is B.

1. is

2. is NOT C.

1. is NOT

2. is D.

1. is NOT

2. is NOT Page 68 of 100

Question:

(1 point) 69 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Regarding Post Accident Instrumentation:

Of the four (4) nuclear instruments listed in F-0 (CRITICAL SAFETY FUNCTION STATUS TREES) for assessing the Subcriticality safety function, which ONE is a Post-Accident Monitoring (PAM) instrument required by LCO 3.3.3, PAM (Post-Accident Monitoring) Instrumentation?

A.

Wide Range B.

Source Range C.

Intermediate Range D.

Power Range Page 69 of 100

Question:

(1 point) 70 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following:

Unit 1 was operating at 100% RTP Subsequently:

A reactor trip occurs.

Shutdown Margin 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the reactor trip will be ___ (1) ___ the shutdown margin immediately following the reactor trip.

Xenon-135 concentration 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months after the reactor trip will be ___ (2) ___ than the Xenon-135 concentration immediately following the reactor trip.

Which ONE of following completes the statement above?

A.

1. higher than

2. higher B.

1. the same as

2. higher C.

1. higher than

2. lower D.

1. the same as

2. lower Page 70 of 100

Question:

(1 point) 71 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

A reactor trip from 100% RTP and MOL equilibrium conditions has occurred

The crew has implemented ES-0.2 (NATURAL CIRCULATION COOLDOWN)

Per ES-0.2:

1) Shutdown Margin calculation for cold shutdown (Modes 5, 4 or 3) is required to be performed ________ Xenon credit.

2) The MINIMUM boration required prior to cooldown is cold shutdown boron plus Which ONE of the following completes the statement above?

A.

1. with

2. 150 ppm B.

1. with

2. 150 pcm C.

1. without

2. 150 ppm D.

1. without

2. 150 pcm Page 71 of 100

Question:

(1 point) 72 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Per OP/1/A/6100/003 (Controlling Procedure for Unit Operation):

1) An IR SUR that exceeds a MAXIMUM of ______ dpm requires a reactor trip.

2) Critical data is required to be taken ______.

Which ONE of the following completes the statements above?

A.

1. 0.5

2. after raising power to 4 x 10-3 RTP B.

1. 1.0

2. after raising power to 4 x 10-3 RTP C.

1. 0.5

2. as soon as indications are indicative of a critical reactor D.

1. 1.0

2. as soon as indications are indicative of a critical reactor Page 72 of 100

Question:

(1 point) 73 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Regarding the McGuire Moisture Separator Reheaters:

There are ___ (1) ___ MSRs connected to each low-pressure turbine to help remove entrained water.

The ratio of the mass of this water to the total mass of both water and steam defines ___ (2) ___.

Which ONE of the following completes the statements above?

A.

1. two

2. moisture content B.

1. three

2. moisture content C.

1. two

2. quality D.

1. three

2. quality Page 73 of 100

Question:

(1 point) 74 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Regarding the steam cycle:

Condensate depression (subcooling) is necessary to ______.

Which ONE of the following completes the statement above?

A.

minimize turbine blade and condenser tube erosion B.

provide net positive suction head for the condensate pumps C.

maximize overall secondary efficiency D.

provide a better condenser vacuum Page 74 of 100

Question:

(1 point) 75 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Regarding Axial Flux Difference (AFD):

A negative AFD means the ___ (1) ___ half of the core is producing more power.

AFD Target will become ___ (2) ___ negative over core life.

Which ONE of the following completes the statements above?

A.

1. bottom

2. less B.

1. bottom

2. more C.

1. top

2. less D.

1. top

2. more Page 75 of 100

Question:

(1 point) 76 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 30% RTP

The 1C NC pump trips due to mis-operation during I&E testing

Two minutes after the 1C NC pump trip, a lockout occurs on 1A Busline due to a fault

The Reactor Trip breakers remain closed Based on the conditions above, an ATWS ___ (1) ___ in progress.

A subsequent action that is required and the basis for that action is to ___ (2) ___.

Which ONE of the following completes the statement above?

PROCEDURE LEGEND:

TECHNICAL SPECIFICATION 3.4.4 (RCS LOOPS MODES 1 & 2)

A.

1. is

2. manually trip the turbine to generate a redundant reactor trip signal B.

1. is

2. manually trip the turbine to conserve SG inventory C.

1. is NOT

2. restart 1C NC pump within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to comply with TS 3.4.4 D.

1. is NOT

2. place the unit in MODE 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to comply with TS 3.4.4 Page 76 of 100

Question:

(1 point) 77 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is in MODE 6

NC system temperature is 110ºF Subsequently:

AP-19 (LOSS OF RESIDUAL HEAT REMOVAL SYSTEM) has been implemented due to lowering NC system level

The CRS has decided to makeup to the NC system using gravity feed through 1ND-35 (U1 ND TO FWST ISOL) and 1NI-173A (1A ND TO A & B COLD LEGS ISOL)

Per AP-19:

1) Flow to the NC system will be established by throttling 1ND-35 ________.

2) If refueling water level is also going down, then ______ AP-40 (LOSS OF REFUELING CAVITY LEVEL).

Which ONE of the following completes the statements above?

A.

1. locally

2. GO TO B.

1. locally

2. concurrently implement C.

1. from the Control Room

2. GO TO D.

1. from the Control Room

2. concurrently implement Page 77 of 100

Question:

(1 point) 78 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 75% RTP

An AO has reported a steam leak from the equalization header

The CRS has implemented AP-01 (STEAM LEAK)

The crew will INITIALLY reduce turbine load up to a MAXIMUM of ____ (1) ____ MWe.

Per AP-01, the CRS will direct the crew to trip Unit 1 reactor and ____ (2) ____.

Which ONE of the following completes the statements above?

A.

1. 10

2. immediately GO TO E-0 (REACTOR TRIP OR SAFETY INJECTION)

B.

1. 20

2. immediately GO TO E-0 (REACTOR TRIP OR SAFETY INJECTION)

C.

1. 10

2. CLOSE all MSIVs, CLOSE AS-12, then GO TO E-0 D.

1. 20

2. CLOSE all MSIVs, CLOSE AS-12, then GO TO E-0 Page 78 of 100

Question:

(1 point) 79 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit was at 100% RTP

A Loss of offsite power (LOOP) has occurred

Diesel Generators on Unit 1 and Unit 2 failed to start Upon entry into ECA-0.0 (LOSS OF ALL AC POWER), the FIRST action attempted to restore power to an essential bus is to ____(1)____.

An upgrade in EAL classification is required if a loss of all offsite and all onsite AC power capability to essential 4160V busses occurs for greater than or equal to a MINIMUM of ____(2)____ minutes.

Which ONE of the following completes the statements above?

A.

1. manually start BOTH D/Gs

2. 30 B.

1. manually start BOTH D/Gs

2. 15 C.

1. initiate Safety Injection on BOTH trains

2. 30 D.

1. initiate Safety Injection on BOTH trains

2. 15 Page 79 of 100

Question:

(1 point) 80 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

VI header pressure is lowering

The crew has implemented AP-22 (LOSS OF VI)

Subsequently:

Rounds AO reports that 1SM-7AB (1A MSIV) VI accumulator pressure indicates 50 PSIG Based on the conditions above, 1SM-7AB (1A MSIV) is ___ (1) ___.

AP-22 ___ (2) ___ provide direction to close the MSIVs on lowering VI header pressure once the reactor is tripped.

Consider Each Statement Separately Which ONE of the following completes the statements above?

A.

1. INOPERABLE

2. does B.

1. OPERABLE

2. does C.

1. INOPERABLE

2. does NOT D.

1. OPERABLE

2. does NOT Page 80 of 100

Question:

(1 point) 81 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following:

Unit 1 & 2 are at 100% RTP

The DEC TOP (Transmission Operations) has notified the Control Room that the "Real Time Contingency Analysis" (RTCA) indicates that switchyard voltage would not be adequate should a Unit Trip occur

AP-05, (GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES) has been implemented on BOTH units Per Unit 1 AP-05:

1) The CRS ________ be directed to enter Tech. Spec. LCO 3.0.3.

2) T.S. 3.8.1 (AC SOURCES-OPERATING) is required to be entered due to BOTH ________ being INOPERABLE.

Which ONE of the following completes the statements above?

A.

1. will

2. Emergency D/Gs B.

1. will

2. Offsite Power Sources C.

1. will NOT

2. Emergency D/Gs D.

1. will NOT

2. Offsite Power Sources Page 81 of 100

Question:

(1 point) 82 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

A batch release of the Ventilation Unit Condensate Drain Tank (VUCDT) is in progress

Thirty minutes after the release is initiated, 1WLFS7010 (1EMF44 Outlet Flow (Min Flow Device)) fails Per SLC 16.11.2 (RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION):

1) 1EMF-44 (L) (Cont Vent Unit Condensate Line) is ______.

2) The VUCDT release ______ required to be suspended.

Which ONE of the following completes the statements above?

A.

1. FUNCTIONAL

2. is NOT B.

1. FUNCTIONAL

2. is C.

1. NON-FUNCTIONAL

2. is NOT D.

1. NON-FUNCTIONAL

2. is Page 82 of 100

Question:

(1 point) 83 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

A LOCA has occurred

Due to multiple equipment failures, the CRS has implemented FR-C.1, (RESPONSE TO INADEQUATE CORE COOLING)

Low Pressure Steam Line Isolation has been BLOCKED

All S/G NR levels are at 34%

Per FR-C.1:

1) Secondary depressurization is performed ____(1)____ until all intact S/Gs are less than 190 PSIG.

2) Following secondary depressurization to 190 PSIG, if NC hot leg temperatures are greater than 388 °F and CET temperatures are greater than 1200 °F, the CRS will direct the crew to ____(2)____.

Which ONE of the following completes the statements above?

A.

1. at a rate not to exceed 100 °F/hr

2. start an NCP in an idle loop B.

1. at a rate not to exceed 100 °F/hr

2. transition to SAMG/SAG-1 (CONTROL ROOM SEVERE ACCIDENT GUIDELINE INITIAL RESPONSE)

C.

1. at maximum rate

2. start an NCP in an idle loop D.

1. at maximum rate

2. transition to SAMG/SAG-1 (CONTROL ROOM SEVERE ACCIDENT GUIDELINE INITIAL RESPONSE)

Page 83 of 100

Question:

(1 point) 84 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Chemistry has confirmed two leaking fuel rods

A Large Break LOCA has occurred

ES-1.2 (POST LOCA COOLDOWN AND DEPRESSURIZATION) has been implemented

All Red and Orange paths have been addressed

1EMF-53A (Containment Train A) = 39 R/Hr

Pressurizer level = 15% and STABLE

The CRS is currently considering implementing Yellow Path procedures Based on the conditions above, the CRS will direct the crew to.

Which ONE of the following completes the statement above?

PROCEDURE LEGEND:

FR-I.2 (RESPONSE TO LOW PRESSURIZER LEVEL)

FR-Z.3 (RESPONSE TO HIGH CONTAINMENT RADIATION LEVEL)

A.

transition from ES-1.2 to FR-Z.3 B.

remain in ES-1.2 and implement FR-Z.3 concurrently C.

transition from ES-1.2 to FR-I.2 D.

remain in ES-1.2 and implement FR-I.2 concurrently Page 84 of 100

Question:

(1 point) 85 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 2:

A steam line break has occurred

E-0 (REACTOR TRIP OR SAFETY INJECTION) has been completed

The crew is performing actions of E-2 (FAULTED S/G ISOLATION)

Subsequently:

The CRS has implemented FR-P.1 (RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION) due to an ORANGE condition on NC Integrity status tree.

A one hour soak is in progress Per FR-P.1, during the soak, the CRS ____(1)____ permitted to continue actions in other EP network procedures.

While performing the soak, if the NC Integrity status tree elevates to a RED condition, the CRS should ____(2)____

Which ONE of the following completes the statements above?

A.

1. is NOT

2. restart FR-P.1 B.

1. is NOT

2. continue and complete FR-P.1 C.

1. is

2. restart FR-P.1 D.

1. is

2. continue and complete FR-P.1 Page 85 of 100

Question:

(1 point) 86 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 10% RTP

1AD-9/ A5 (ICE COND LOWER INLET DOORS OPEN) alarm is LIT

The lower inlet door position display panel indicates that a door is OPEN

An AO has confirmed a lower inlet door is cracked OPEN and the door will not move further OPEN and cannot be CLOSED

The BOP has reported ice bed temperature is 25°F and slowly rising Based on the conditions above, actions of T.S LCO 3.6.12 (Ice Bed) ____(1)____

required.

Per TS Bases, the limiting Design Basis Accident (DBA) shows that the maximum peak containment pressure results from a ____(2)____ event.

Which ONE of the following completes the statements above?

A.

1. are NOT

2. Loss of Coolant Accident (LOCA)

B.

1. are NOT

2. Steam Line Break (SLB)

C.

1. are

2. Loss of Coolant Accident (LOCA)

D.

1. are

2. Steam Line Break (SLB)

Page 86 of 100

Question:

(1 point) 87 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 100% RTP

At 1600 on 2/5/23 the 1A NS pump was declared INOPERABLE

At 2100 on 2/5/23 I&E informs the Control Room that instrument 1NSLP 5510 (CPCS TR B-NS PUMP B) is INOPERABLE Based on the conditions above, Tech. Specs require ________.

Which ONE of the following completes the statement above?

REFERENCES PROVIDED A.

declaring 1B NS pump INOPERABLE IMMEDIATELY ONLY B.

being in MODE 3 by 0300 on 2/6/23 C.

being in MODE 3 by 0400 on 2/6/23 D.

restoring 1A NS Pump to OPERABLE by 1600 on 2/8/23 Page 87 of 100

Question:

(1 point) 88 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 100% RTP Testing of the 1B D/G Sequencer is in progress Annunciator 1AD-11 / E1 (SEQ B IN TEST) is illuminated Based on the conditions above:

1) The 1B D/G is currently ________.

2) If an automatic SI actuation occurs, SI loads on ________ will start automatically.

Which ONE of the following completes the statements above?

A.

1. OPERABLE

2. A Train ONLY B.

1. OPERABLE

2. BOTH Trains C.

1. INOPERABLE

2. A Train ONLY D.

1. INOPERABLE

2. BOTH Trains Page 88 of 100

Question:

(1 point) 89 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 100% RTP

B Train is in service Subsequently:

A transient occurred resulting in a reactor trip and safety injection

0RN-9B (TRAIN 1B & 2B SNSWP SUPPLY) failed to OPEN

While performing E-0 (REACTOR TRIP OR SAFETY INJECTION), the CRS has decided to concurrently implement AP-20 (LOSS OF RN)

Based on the conditions above:

1) RN cooling to ________ has been lost.

2) To mitigate this event, The CRS is required to implement AP-20 (LOSS OF RN), ________.

Which ONE of the following completes the statements above?

A.

1. Unit 1 NC pumps

2. Case 1 (LOSS OF OPERATING RN TRAIN)

B.

1. 1B D/G

2. Case 1 (LOSS OF OPERATING RN TRAIN)

C.

1. Unit 1 NC pumps

2. Case 2 (LOSS OF LOW LEVEL INTAKE OR RC SUPPLY CROSSOVER)

D.

1. 1B D/G

2. Case 2 (LOSS OF LOW LEVEL INTAKE OR RC SUPPLY CROSSOVER)

Page 89 of 100

Question:

(1 point) 90 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following:

VI pressure is 88 PSIG and lowering

Both units have implemented AP-22 (LOSS OF VI)

Based on the conditions above, the VI Dryer Purge Exhaust Valves ________ auto CLOSED.

Per AP-22, the CRS will direct implementation of Enclosure 5 (VI DRYER and VI TO VS ISOLATION) if VI pressure lowers to less than a MAXIMUM of ________.

Which ONE of the following completes the statements above?

A.

1. have NOT

2. 82 PSIG B.

1. have NOT

2. 70 PSIG C.

1. have

2. 82 PSIG D.

1. have

2. 70 PSIG Page 90 of 100

Question:

(1 point) 91 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is in MODE 2 with power ascension in progress

Reactor power is 4% RTP

The crew determines that Control Rod M-4 is misaligned by 14 steps Per AP-14 (ROD CONTROL MALFUNCTION) Enclosure 1 (RESPONSE TO DROPPED OR MISALIGNED ROD):

1) When checking reactor power at Step 12, the crew will use ________.

2) Based on current plant conditions, the crew will.

Which ONE of the following completes the statements above?

PROCEDURE LEGEND:

OP/1/A/6100/003 (CONTROLLING PROCEDURE FOR UNIT OPERATION)

A.

1. Thermal Power Best Estimate

2. transition to OP/1/A/6100/003 and shutdown to MODE 3 B.

1. Excore Nuclear Instruments

2. transition to OP/1/A/6100/003 and shutdown to MODE 3 C.

1. Thermal Power Best Estimate

2. remain in AP-14 and hold at current power level D.

1. Excore Nuclear Instruments

2. remain in AP-14 and hold at current power level Page 91 of 100

Question:

(1 point) 92 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following on Unit 1:

Unit is at 100% RTP

1AD-2, E10 (RPI NON-URGENT FAILURE) is in alarm

DRPI indicates Data B failure for ALL rods Based on the conditions above:

1) The DRPI system is ______.

2) The current accuracy of the DRPI system is within ______ steps of the demand counters.

Which ONE of the following completes the statements above?

A.

1. INOPERABLE

2. +/- 12 B.

1. INOPERABLE

2. +/- 4 C.

1. OPERABLE

2. +/- 12 D.

1. OPERABLE

2. +/- 4 Page 92 of 100

Question:

(1 point) 93 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Unit 1 was at 100% RTP when the following occured:

TIME DATE CONDITION 0600 1/11 1 required channel of Core Exit thermocouples was declared inoperable in quadrant 2 1130 1/14 1 required channel of Core Exit thermocouples was declared inoperable in quadrant 4 1400 1/18 1 additional required channel of Core Exit thermocouples was declared inoperable in quadrant 4 The EARLIEST time Unit 1 is required to be in Mode 3 is ___ (1) ___.

Per T.S. 3.3.3 (PAM INSTRMENTATION) Bases, Core Exit Temperatures ___ (2) ___

used to determine whether to re-initiate SI, if it has been stopped.

Which ONE of the following completes the statements above?

REFERENCE PROVIDED A.

1. 1730 on 1/21

2. are NOT B.

1. 1730 on 1/21

2. are C.

1. 2000 on 1/25

2. are NOT D.

1. 2000 on 1/25

2. are Page 93 of 100

Question:

(1 point) 94 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Per AD-NS-ALL-1001 (CONDUCT OF REFUELING):

1) Bypassing fuel handling interlocks not specified in approved procedures require the concurrence of the Shift Manager.

2) The Refueling SRO required to be present inside Containment for control rod latching.

Which ONE of the following completes the statements above?

A.

1. does NOT

2. is NOT B.

1. does NOT

2. is C.

1. does

2. is NOT D.

1. does

2. is Page 94 of 100

Question:

(1 point) 95 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Per AD-OP-ALL-0111 (OPERATIONS COMMUNICATIONS),

1) Communications packages will be distributed to the crews through

2) If a revision to a Standing Instruction is issued, then a ________ or higher is required to review and sign the revision.

Which ONE of the following completes the statements above?

A.

1. Standing Instructions

2. CRS B.

1. Standing Instructions

2. SM C.

1. an Operations Supplemental Information Package (OSIP)

2. CRS D.

1. an Operations Supplemental Information Package (OSIP)

2. SM Page 95 of 100

Question:

(1 point) 96 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Per AD-WC-ALL-0420 (SHUTDOWN RISK MANAGEMENT):

1) Defense in Depth (DID) sheets are first REQUIRED for risk management once ________ is reached during the shutdown.

2) An Elevated Risk Activity Plan ________ required for planned ORANGE DID conditions.

Which ONE of the following completes the statements above?

A.

1. MODE 3

2. is B.

1. MODE 3

2. is NOT C.

1. MODE 4

2. is D.

1. MODE 4

2. is NOT Page 96 of 100

Question:

(1 point) 97 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Per AD-OP-ALL-0204 (PLANT STATUS CONTROL):

1) A Plant Status Control Tag (PSC) ________ be hung on a component that already has another tag type placed.

2) Placement of a PSC tag can be waived by the ________ if it would result in excessive radiation exposure.

Which ONE of the following completes the statements above?

A.

1. can NOT

2. Shift Manager B.

1. can NOT

2. WCC SRO C.

1. can

2. Shift Manager D.

1. can

2. WCC SRO Page 97 of 100

Question:

(1 point) 98 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following:

A General Emergency has been declared

An AO must be dispatched from the Operations Support Center to an area with an identified radiation field of 90 R/hr in order to isolate the pathway of a large release to the environment

The operator will be in the area for 15 minutes Per AD-EP-ALL-0205 (EMERGENCY EXPOSURE CONTROLS),

1) the AO selected to perform this isolation ____(1)____ required to be a volunteer.

2) Performance of this task ____(2)____ considered a Planned Special Exposure (PSE).

Which ONE of the following completes the statements above?

A.

1. is

2. is NOT B.

1. is

2. is C.

1. is NOT

2. is NOT D.

1. is NOT

2. is Page 98 of 100

Question:

(1 point) 99 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Per SLC 16.13.4 (MINIMUM STATION STAFFING REQUIREMENTS),

1) A properly trained and equipped Fire Brigade of at least ________ personnel is required to provide response to fires that may occur on site.

2) The individual fulfilling the position of Fire Brigade Leader ________ be a RO.

Which ONE of the following completes the statements above?

A.

1. five

2. can B.

1. four

2. can C.

1. five

2. can NOT D.

1. four

2. can NOT Page 99 of 100

Question:

(1 point) 100 ILT23-1 NRC Written MNS SRO NRC Examination McGuire Nuclear Station Given the following:

An Unusual Event was declared on Unit 2

Initial Notification to the States, Counties and the NRC has been completed Subsequently:

The Emergency Coordinator has just made the decision to upgrade the classification to an Alert The NRC is required to be notified as soon as possible but no more than ____(1)____

after a change of classification.

After the initial notification of the change in classification is made to the State and Counties, follow up notifications are required to be made every ____(2)____ minutes until the emergency is terminated. (Assume no time extension has been agreed upon between the site and each agency)

Which ONE of the following completes the statements above?

A.

1. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

2. 30 B.

1. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

2. 60 C.

1. 15 minutes

2. 30 D.

1. 15 minutes

2. 60 Page 100 of 100

Examination KEY ILT23-1 NRC Written MNS SRO NRC Examination Q A Q A Q A Q A 1

C 26 B

51 A

76 B

2 B

27 B

52 B

77 B

3 B

28 B

53 C

78 C

4 C

29 A

54 C

79 D

5 B

30 D

55 A

80 A

6 D

31 C

56 A

81 B

7 A

32 B

57 A

82 C

8 C

33 D

58 B

83 C

9 A

34 B

59 C

84 B

10 B

35 D

60 C

85 D

11 C

36 C

61 C

86 A

12 D

37 B

62 D

87 C

13 D

38 D

63 A

88 B

14 C

39 D

64 C

89 B

15 A

40 B

65 D

90 C

16 C

41 D

66 B

91 A

17 D

42 A

67 D

92 C

18 A

43 A

68 B

93 D

19 B

44 D

69 A

94 B

20 C

45 D

70 A

95 D

21 B

46 C

71 C

96 C

22 C

47 D

72 B

97 C

23 B

48 B

73 A

98 C

24 C

49 D

74 B

99 A

25 C

50 C

75 A

100 B

Printed 8/21/2023 1:33:04 PM Page 1 of 1

Reference List for ILT23-1 NRC Written MNS SRO NRC Examinatio n

T.S. 3.3.3 Post Accident Monitoring (PAM) Instrumentation TS Reference Manual, section 2 (Unit 1 instrumentation)

TS-3.3.2 TS-3.6.6 Printed 8/21/2023 2:53:49 PM Page 1 of 1

ESFAS Instrumentation 3.3.2 McGuire Units 1 and 2 3.3.2-1 Amendment Nos. 184/166 3.3 INSTRUMENTATION 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.2-1.

ACTIONS

NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more Functions with one or more required channels or trains inoperable.

A.1 Enter the Condition referenced in Table 3.3.2-1 for the channel(s) or train(s).

Immediately B.

One channel or train inoperable.

B.1 Restore channel or train to OPERABLE status.

OR B.2.1 Be in MODE 3.

AND B.2.2 Be in MODE 5.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 54 hours 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months (continued)

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

McGuire Units 1 and 2 3.3.2-2 Amendment Nos. 250/230 CONDITION REQUIRED ACTION COMPLETION TIME C.

One train inoperable.

C.1

NOTE--------------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

Restore train to OPERABLE status.

OR C.2.1 Be in MODE 3.

AND C.2.2 Be in MODE 5.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 30 hours 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months D.

One channel inoperable.

D.1

NOTE--------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

Place channel in trip.

OR D.2.1 Be in MODE 3.

AND D.2.2 Be in MODE 4.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 78 hours 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months (continued)

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

McGuire Units 1 and 2 3.3.2-3 Amendment Nos. 248/228 CONDITION REQUIRED ACTION COMPLETION TIME E.

One Containment Pressure channel inoperable.

E.1

NOTE--------------

One additional channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

Place channel in bypass.

OR E.2.1 Be in MODE 3.

AND E.2.2 Be in MODE 4.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 78 hours 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months F.

One channel or train inoperable.

F.1 Restore channel or train to OPERABLE status.

OR F.2.1 Be in MODE 3.

AND F.2.2 Be in MODE 4.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 54 hours 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months G.

One Steam Line Isolation Manual Initiation - individual channel inoperable.

G.1 Restore channel to OPERABLE status.

OR G.2 Declare associated steam line isolation valve inoperable.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 48 hours (continued)

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

McGuire Units 1 and 2 3.3.2-4 Amendment Nos. 248/228 CONDITION REQUIRED ACTION COMPLETION TIME H.

One train inoperable.

H.1

NOTE--------------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

Restore train to OPERABLE status.

OR H.2.1 Be in MODE 3.

AND H.2.2 Be in MODE 4.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 30 hours 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months I.

One train inoperable.

I.1

NOTE--------------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

Restore train to OPERABLE status.

OR I.2 Be in MODE 3.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 30 hours (continued)

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

McGuire Units 1 and 2 3.3.2-5 Amendment Nos. 248/228 CONDITION REQUIRED ACTION COMPLETION TIME J.

One channel inoperable.

J.1

NOTE--------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

Place channel in trip.

OR J.2 Be in MODE 3.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 78 hours K.

One Main Feedwater Pumps trip channel inoperable.

K.1 Place channel in trip.

OR K.2 Be in MODE 3.

1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 7 hours L.

One required channel in one train of Doghouse Water Level-High High inoperable.

L.1 Restore the inoperable train to OPERABLE status.

OR L.2 Perform continuous monitoring of Doghouse water level.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 73 hours M.

Two trains of Doghouse Water Level-High High inoperable.

M.1 Perform continuous monitoring of Doghouse water level..

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (continued)

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

McGuire Units 1 and 2 3.3.2-6 Amendment Nos. 198/179 CONDITIONS REQUIRED ACTION COMPLETION TIME N.

One or more channels of Auxiliary Feedwater Suction Pressure-Low for one auxiliary feedwater pump inoperable.

N.1 Restore channel(s) to OPERABLE status.

OR N.2 Declare associated auxiliary feedwater pump inoperable.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 48 hours O.

One or more channels of Auxiliary Feedwater Suction Pressure-Low for two or more auxiliary feedwater pumps inoperable.

O.1 Declare associated auxiliary feedwater pumps inoperable.

Immediately P.

One channel inoperable.

P.1 Place channel in trip.

AND P.2 Restore channel to OPERABLE status.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 48 hours (continued)

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

McGuire Units 1 and 2 3.3.2-7 Amendment Nos. 198/179 CONDITION REQUIRED ACTION COMPLETION TIME Q.

One channel inoperable.

Q.1 Verify interlock is in required state for existing unit condition.

OR Q.2.1 Be in MODE 3.

AND Q.2.2 Be in MODE 4.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 7 hours 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months R.

One or more Containment Pressure Control System channel(s) inoperable.

R.1 Declare affected supported system inoperable.

Immediately S.

Required Action and associated Completion Time of Condition P not met.

S.1 Be in MODE 3.

AND S.2 Be in MODE 4.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours

ESFAS Instrumentation 3.3.2 McGuire Units 1 and 2 3.3.2-8 Amendment Nos. 261/241 SURVEILLANCE REQUIREMENTS

NOTE--------------------------------------------------------------

Refer to Table 3.3.2-1 to determine which SRs apply for each ESFAS Function.

SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL CHECK.

In accordance with the Surveillance Frequency Control Program SR 3.3.2.2 Perform ACTUATION LOGIC TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.2.3 Perform COT.

In accordance with the Surveillance Frequency Control Program SR 3.3.2.4 Perform MASTER RELAY TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.2.5 Perform COT.

In accordance with the Surveillance Frequency Control Program SR 3.3.2.6 Perform SLAVE RELAY TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.2.7

NOTE---------------------------------

Verification of setpoint not required for manual initiation functions.

Perform TADOT.

In accordance with the Surveillance Frequency Control Program (continued)

ESFAS Instrumentation 3.3.2 SURVEILLANCE REQUIREMENTS (continued)

McGuire Units 1 and 2 3.3.2-9 Amendment Nos. 261/241 SURVEILLANCE FREQUENCY SR 3.3.2.8

NOTE----------------------------------

This Surveillance shall include verification that the time constants are adjusted to the prescribed values.

Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program SR 3.3.2.9

NOTE----------------------------------

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after SG pressure is > 900 psig.

Verify ESFAS RESPONSE TIMES are within limit.

In accordance with the Surveillance Frequency Control Program

ESFAS Instrumentation 3.3.2 McGuire Units 1 and 2 3.3.2-10 Amendment Nos. 272/252 Table 3.3.2-1 (page 1 of 6)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

1.

Safety Injection

a.

Manual Initiation 1,2,3,4 2

B SR 3.3.2.7 NA NA

b.

Automatic Actuation Logic and Actuation Relays 1,2,3,4 2 trains C

SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA NA

c.

Containment Pressure - High 1,2,3 3

D SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.8 SR 3.3.2.9

< 1.2 psig 1.1 psig

d.

Pressurizer Pressure - Low Low 1,2,3(a) 4 D

SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.8 SR 3.3.2.9

> 1835 psig 1845 psig

2.

Not Used

3.

Containment Isolation

a.

Phase A Isolation (1) Manual Initiation 1,2,3,4 2

B SR 3.3.2.7 NA NA (2) Automatic Actuation Logic and Actuation Relays 1,2,3,4 2 trains C

SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA NA (continued)

(a)

Above the P-11 (Pressurizer Pressure) interlock.

ESFAS Instrumentation 3.3.2 McGuire Units 1 and 2 3.3.2-11 Amendment Nos. 265/245 Table 3.3.2-1 (page 2 of 6)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

3.

Containment Isolation (continued)

(3) Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

b.

Phase B Isolation (1) Manual Initiation 1,2,3,4 1 per train, 2 trains B

SR 3.3.2.7 NA NA (2) Automatic Actuation Logic and Actuation Relays 1,2,3,4 2 trains C

SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA NA (3) Containment Pressure -

High High 1,2,3 4

E SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.8

< 3.0 psig 2.9 psig

4.

Steam Line Isolation

a.

Manual Initiation (1) System (2) Individual 1,2(b),3(b) 1,2(b),3(b) 2 trains 1 per line F

G SR 3.3.2.7 SR 3.3.2.7 NA NA NA NA

b.

Automatic Actuation Logic and Actuation Relays 1,2(b),3(b) 2 trains H

SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA NA

c.

Containment Pressure - High High 1,2(b), 3(b) 4 E

SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.8 SR 3.3.2.9

< 3.0 psig 2.9 psig

d.

Steam Line Pressure (1) Low 1,2(b), 3(a)(b) 3 per steam line D

SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.8 SR 3.3.2.9

> 755 psig 775 psig (continued)

(a) Above the P-11 (Pressurizer Pressure) interlock.

(b) Except when all MSIVs are closed and de-activated.

ESFAS Instrumentation 3.3.2 McGuire Units 1 and 2 3.3.2-12 Amendment Nos. 265/245 Table 3.3.2-1 (page 3 of 6)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

4.

Steam Line Isolation (continued)

(2) Negative Rate - High 3(b)(c) 3 per steam line D

SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.8 SR 3.3.2.9

< 120(d) psi 100(d) psi

5.

Turbine Trip and Feedwater Isolation

a.

Turbine Trip (1) Automatic Actuation Logic and Actuation Relays (2) SG Water Level-High High (P-14) 1,2 1,2 2 trains 3 per SG I

J SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 SR 3.3.2.8 SR 3.3.2.9 NA

< 85.6%

NA 83.9%

(3) Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements. See item 5.a.(1) for Applicable MODES.

b.

Feedwater Isolation (1) Automatic Actuation Logic and Actuation Relays 1,2(e), 3(e) 2 trains H

SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA NA (2) SG Water Level-High High (P-14) 1,2(e), 3(e) 3 per SG D

SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 SR 3.3.2.8 SR 3.3.2.9

< 85.6 83.9%

(continued)

(b)

Except when all MSIVs are closed and de-activated.

(c)

Trip function automatically blocked above P-11 (Pressurizer Pressure) interlock and may be blocked below P-11 when Steam Line Isolation Steam Line Pressure-Low is not blocked.

(d)

Time constant utilized in the rate/lag controller is > 50 seconds.

(e)

Except when all MFIVs, MFCVs, and associated bypass valves are closed and de-activated or isolated by a closed manual valve.

ESFAS Instrumentation 3.3.2 McGuire Units 1 and 2 3.3.2-13 Amendment Nos. 265/245 Table 3.3.2-1 (page 4 of 6)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

5. Turbine Trip and Feedwater Isolation (continued)

(3) Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements. See Item 5.b.(1) for Applicable MODES.

(4) Tavg-Low 1,2(e) 1 per loop J

SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.8

> 551°F 553°F coincident with Reactor Trip, P-4 Refer to Function 8.a (Reactor Trip, P-4) for all initiation functions and requirements.

(5) Doghouse Water Level-High High 1,2(e) 2 per train per Doghouse L,M SR 3.3.2.1 SR 3.3.2.7

< 13 inches 12 inches

6.

Auxiliary Feedwater

a.

Automatic Actuation Logic and Actuation Relays 1,2,3 2 trains H

SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.6 NA NA

b.

SG Water Level -

Low Low 1,2,3 4 per SG D

SR 3.3.2.1 SR 3.3.2.5 SR 3.3.2.8 SR 3.3.2.9

> 15%

16.7%

c.

Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

d.

Station Blackout (1) Loss of voltage 1,2,3 3 per bus D

SR 3.3.2.7 SR 3.3.2.9

> 3122 V (Unit 1)

> 3108 V (Unit 2) with 8.5 +/- 0.5 sec time delay 3174 V (Unit

1) 3157 V (Unit 2) +/-

45 V with 8.5 +/- 0.5 sec time delay (2) Degraded Voltage 1,2,3 3 per bus D

SR 3.3.2.7 SR 3.3.2.9

> 3661 V (Unit 1)

> 3685.5 V (Unit 2) with < 11 sec with SI and

< 600 sec without SI time delay 3678.5 V (Unit

1) 3703 V (Unit 2) with < 11 sec with SI and < 600 sec without SI time delay (continued)

(e)

Except when all MFIVs, MFCVs, and associated bypass valves are closed and de-activated or isolated by a closed manual valve.

ESFAS Instrumentation 3.3.2 McGuire Units 1 and 2 3.3.2-14 Amendment Nos. 293/272 Table 3.3.2-1 (page 5 of 6)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

6. Auxiliary Feedwater (continued)

e.

Trip of all Main Feedwater Pumps 1,2 1 per MFW pump K

SR 3.3.2.7 SR 3.3.2.9 NA NA

f.

Auxiliary Feedwater Pump Suction Transfer on Suction Pressure - Low 1,2,3 2 per MDP, 4 per TDP N,O SR 3.3.2.7(a)(b)

SR 3.3.2.8(a)(b)

SR 3.3.2.9

> 6.5 psig

> 7.5 psig (2A MDP only) 7.0 psig 8.0 psig (2A MDP only)

7.

Automatic Switchover to Containment Sump

a.

Refueling Water Storage Tank (RWST) Level -

Low 1,2,3 3

P,S SR 3.3.2.1 SR 3.3.2.3(a)(b)

SR 3.3.2.8(a)(b)

SR 3.3.2.9

> 92.3 inches 95 inches Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

(continued)

(a) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(b) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable.

Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The methodologies used to determine the as-found and the as-left tolerances are specified in the UFSAR.

NOTE 1: The Trip Setpoint for the Containment Pressure Control System start permissive/termination (SP/T) shall be

> 0.3 psig and < 0.4 psig. The allowable value for the SP/T shall be > 0.25 psig and < 0.45 psig.

ESFAS Instrumentation 3.3.2 McGuire Units 1 and 2 3.3.2-15 Amendment Nos. 320/299 Table 3.3.2-1 (page 6 of 6)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

8.

ESFAS Interlocks

a.

Reactor Trip, P-4 1,2,3(f) 1 per train, 2 trains F

SR 3.3.2.7 NA NA

b.

Pressurizer Pressure, P-11 1,2,3 3

Q SR 3.3.2.5 SR 3.3.2.8

< 1965 psig 1955 psig

c.

Tavg - Low Low, P-12 1,2,3 1 per loop Q

SR 3.3.2.5 SR 3.3.2.8

> 551°F 553°F

9.

Containment Pressure Control System 1,2,3,4 4 per train, 2 trains R

SR 3.3.2.1 SR 3.3.2.3 SR 3.3.2.8 Refer to Note 1 on Page 3.3.2-14 Refer to Note 1 on page 3.3.2-14 (f) The functions of the Reactor Trip, P-4 interlock required to meet the LCO are:

Trip the main turbine - MODES 1 and 2 Isolate MFW with coincident low Tavg - MODES 1, 2, and 3 Prevent reactuation of SI after a manual reset of SI - MODES 1, 2, and 3 Prevent opening of MFIVs if closed on SI or SG Water Level - High High - MODES 1, 2, and 3

Containment Spray System 3.6.6 McGuire Units 1 and 2 3.6.6-1 Amendment Nos. 316/295 3.6 CONTAINMENT SYSTEMS 3.6.6 Containment Spray System LCO 3.6.6 Two containment spray trains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One containment spray train inoperable.

A.1 Restore containment spray train to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B.

Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 84 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1

NOTE--------------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each containment spray manual and power operated valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

In accordance with the Surveillance Frequency Control Program (continued)

Containment Spray System 3.6.6 McGuire Units 1 and 2 3.6.6-2 Amendment Nos. 309/288 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6.2 Verify each containment spray pump's developed head at the flow test point is greater than or equal to the required developed head.

In accordance with the INSERVICE TESTING PROGRAM SR 3.6.6.3 Not Used Not Used SR 3.6.6.4 Not Used Not Used SR 3.6.6.5 Verify that each spray pump is de-energized and prevented from starting upon receipt of a terminate signal and is allowed to manually start upon receipt of a start permissive from the Containment Pressure Control System (CPCS).

In accordance with the Surveillance Frequency Control Program SR 3.6.6.6 Verify that each spray pump discharge valve closes or is prevented from opening upon receipt of a terminate signal and is allowed to manually open upon receipt of a start permissive from the Containment Pressure Control System (CPCS).

In accordance with the Surveillance Frequency Control Program SR 3.6.6.7 Verify each spray nozzle is unobstructed.

Following activities which could result in nozzle blockage SR 3.6.6.8 Verify containment spray locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency control Program

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 7 1CALP5110 3.3.3.17 / 3.3.4.3.c CA FLOW C S/G 1CALP5111 3.3.3.17 / 3.3.4.3.c CA FLOW C S/G 1CALP5120 3.3.3.17 / 3.3.4.3.c CA FLOW D S/G 1CALP5121 3.3.3.17 / 3.3.4.3.c CA FLOW D S/G 1CALP5240 16.10.1 S/G A CA INLET TEMP 1CALP5250 16.10.1 S/G B CA INLET TEMP 1CALP5260 16.10.1 S/G C CA INLET TEMP 1CALP5270 16.10.1 S/G D CA INLET TEMP 1CALT5610 16.9.7.19 CAST LEVEL 1CALT5620 16.9.7.19 CAST LEVEL 1CAP5092 3.3.3.17 / 3.3.4.3.c CA Flow A S/G 1CAP5102 3.3.3.17 / 3.3.4.3.c CA Flow B S/G 1CAP5112 3.3.3.17 / 3.3.4.3.c CA Flow C S/G 1CAP5122 3.3.3.17 / 3.3.4.3.c CA Flow D S/G 1CAPS5002 3.3.2.6.f / 3.7.5 A CA SUCT PRESS 1CAPS5012 3.3.2.6.f / 3.7.5 B CA SUCT PRESS 1CAPS5042 3.3.2.6.f / 3.7.5 TD CA SUCT PRESS 1CAPS5350 3.3.2.6.f / 3.7.5 A CA SUCT PRESS 1CAPS5360 3.3.2.6.f / 3.7.5 B CA SUCT PRESS 1CAPS5370 3.3.2.6.f / 3.7.5 TD CA SUCT PRESS 1CAPS5381 3.3.2.6.f / 3.7.5 TD CA SUCT PRESS 1CAPS5390 3.3.2.6.f / 3.7.5 TD CA SUCT PRESS 1CFCA6960 16.7.12 U1 CF LOOP A LEFM XMTR CABINET 1 1CFCA6961 16.7.12 U1 CF LOOP A LEFM XMTR CABINET 2 1CFCA6970 16.7.12 U1 CF LOOP B LEFM XMTR CABINET 1 1CFCA6971 16.7.12 U1 CF LOOP B LEFM XMTR CABINET 2 1CFCA6980 16.7.12 U1 CF LOOP C LEFM XMTR CABINET 1 1CFCA6981 16.7.12 U1 CF LOOP C LEFM XMTR CABINET 2 1CFCA6990 16.7.12 U1 CF LOOP D LEFM XMTR CABINET 1 1CFCA6991 16.7.12 U1 CF LOOP D LEFM XMTR CABINET 2 1CFCA7000 16.7.12 U1 LEFM CPU CABINET A 1CFCA7010 16.7.12 U1 LEFM CPU CABINET B 1CFCA9000 16.7.1 AMSAC CTRL PANEL 1CFLL0172 16.7.1 D S/G FRV 1CFLL0202 16.7.1 C S/G FRV 1CFLL0232 16.7.1 B S/G FRV 1CFLL0261 16.7.1 D S/G CONT ISOL 1CFLL0281 16.7.1 C S/G CONT ISOL 1CFLL0301 16.7.1 B S/G CONT ISOL 1CFLL0322 16.7.1 A S/G FRV

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 8 1CFLL0351 16.7.1 A S/G CONT ISOL 1CFLL1040 16.7.1 A S/G BYP VLV 1CFLL1050 16.7.1 B S/G BYP VLV 1CFLL1060 16.7.1 C S/G BYP VLV 1CFLL1070 16.7.1 D S/G BYP VLV 1CFLP5490 3.3.1.13 / 3.3.2.5.a.2 / 3.3.2.5.b.2 /

3.3.2.6.b / 3.3.3.12 / 3.4.5/ 3.4.6/ 3.4.7 A S/G NR LEV CH 4 1CFLP5500 3.3.1.13 / 3.3.2.5.a.2 / 3.3.2.5.b.2 /

3.3.2.6.b / 3.3.3.12 / 3.4.5/ 3.4.6/ 3.4.7 A S/G NR LEV CH 3 1CFLP5510 3.3.1.13 / 3.3.2.5.a.2 / 3.3.2.5.b.2 /

3.3.2.6.b / 3.3.3.12 / 3.4.5/ 3.4.6/ 3.4.7 A S/G NR LEV CH 2 1CFLP5520 3.3.1.13 / 3.3.2.5.a.2 / 3.3.2.5.b.2 /

3.3.2.6.b / 3.3.3.12 / 3.4.5/ 3.4.6/ 3.4.7 B S/G NR LEV CH 4 1CFLP5530 3.3.1.13 / 3.3.2.5.a.2 / 3.3.2.5.b.2 /

3.3.2.6.b / 3.3.3.12 / 3.4.5/ 3.4.6 /3.4.7 B S/G NR LEV CH 3 1CFLP5540 3.3.1.13 / 3.3.2.5.a.2 / 3.3.2.5.b.2 /

3.3.2.6.b / 3.3.3.12 / 3.4.5/ 3.4.6/ 3.4.7 B S/G NR LEV CH 1 1CFLP5550 3.3.1.13 / 3.3.2.5.a.2 / 3.3.2.5.b.2 /

3.3.2.6.b / 3.3.3.12 / 3.4.5/ 3.4.6/ 3.4.7 C S/G NR LEV CH 4 1CFLP5560 3.3.1.13 / 3.3.2.5.a.2 / 3.3.2.5.b.2 /

3.3.2.6.b / 3.3.3.12 / 3.4.5/ 3.4.6/ 3.4.7 C S/G NR LEV CH 3 1CFLP5570 3.3.1.13 / 3.3.2.5.a.2 / 3.3.2.5.b.2 /

3.3.2.6.b / 3.3.3.12/ 3.4.5/ 3.4.6/ 3.4.7 C S/G NR LEV CH 1 1CFLP5580 3.3.1.13 / 3.3.2.5.a.2 / 3.3.2.5.b.2 /

3.3.2.6.b / 3.3.3.12 / 3.4.5/ 3.4.6/ 3.4.7 D S/G NR LEV CH 4 1CFLP5590 3.3.1.13 / 3.3.2.5.a.2 / 3.3.2.5.b.2 /

3.3.2.6.b / 3.3.3.12 / 3.4.5/ 3.4.6/ 3.4.7 D S/G NR LEV CH 3 1CFLP5600 3.3.1.13 / 3.3.2.5.a.2 / 3.3.2.5.b.2 /

3.3.2.6.b / 3.3.3.12 / 3.4.5/ 3.4.6/ 3.4.7 D S/G NR LEV CH 2 1CFLP5610 3.3.4.3.c A S/G WR LEV 1CFLP5620 3.3.4.3.c B S/G WR LEV 1CFLP5630 3.3.4.3.c C S/G WR LEV 1CFLP5640 3.3.4.3.c D S/G WR LEV 1CFLP6000 3.3.1.13 / 3.3.2.6.b / 3.3.3.12 / 3.4.5 / 3.4.6

/ 3.4.7 A S/G NR LEV CH 1 1CFLP6010 3.3.1.13 / 3.3.2.6.b / 3.3.3.12 / 3.4.5 / 3.4.6

/ 3.4.7 B S/G NR LEV CH 2 1CFLP6020 3.3.1.13 / 3.3.2.6.b / 3.3.3.12 / 3.4.5 / 3.4.6

/ 3.4.7 C S/G NR LEV CH 2 1CFLP6030 3.3.1.13 / 3.3.2.6.b / 3.3.3.12 / 3.4.5 / 3.4.6

/ 3.4.7 D S/G NR LEV CH 1 1CFLP6080 16.9.7 A S/G LEV SSF 1CFLP6090 16.9.7 B S/G LEV SSF 1CFLP6100 16.9.7 C S/G LEV SSF 1CFLP6110 16.9.7 D S/G LEV SSF 1CFLS6440 3.3.2.5.b.5 INBD DH LEV A TR

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 9 1CFLS6450 3.3.2.5.b.5 INBD DH LEV A TR 1CFLS6460 3.3.2.5.b.5 INBD DH LEV A TR 1CFLS6470 3.3.2.5.b.5 INBD DH LEV B TR 1CFLS6480 3.3.2.5.b.5 INBD DH LEV B TR 1CFLS6490 3.3.2.5.b.5 INBD DH LEV B TR 1CFLS6500 3.3.2.5.b.5 OUTBD DH LEV A TR 1CFLS6510 3.3.2.5.b.5 OUTBD DH LEV A TR 1CFLS6520 3.3.2.5.b.5 OUTBD DH LEV A TR 1CFLS6530 3.3.2.5.b.5 OUTBD DH LEV B TR 1CFLS6540 3.3.2.5.b.5 OUTBD DH LEV B TR 1CFLS6550 3.3.2.5.b.5 OUTBD DH LEV B TR 1CFPT6960 16.7.12 U1 LOOP A LEFM Pressure Transmitter 1CFPT6961 16.7.12 U1 LOOP A LEFM Pressure Transmitter 1CFPT6970 16.7.12 U1 LOOP B LEFM Pressure Transmitter 1CFPT6971 16.7.12 U1 LOOP B LEFM Pressure Transmitter 1CFPT6980 16.7.12 U1 LOOP C LEFM Pressure Transmitter 1CFPT6981 16.7.12 U1 LOOP C LEFM Pressure Transmitter 1CFPT6990 16.7.12 U1 LOOP D LEFM Pressure Transmitter 1CFPT6991 16.7.12 U1 LOOP D LEFM Pressure Transmitter 1CFVA0026 3.6.3 / 3.7.3 SG 1D CF ISOLATION 1CFVA0028 3.6.3 / 3.7.3 SG 1C CF ISOLATION 1CFVA0030 3.6.3 / 3.7.3 SG 1B CF ISOLATION 1CFVA0032 3.6.3 / 3.7.3 SG 1A CF CONTROL VALVE 1CFVA0035 3.6.3 / 3.7.3 SG 1A CF ISOLATION 1CFVA0104 3.6.3 / 3.7.3 SG 1A CF CONTROL BYPASS 1CFVA0105 3.6.3 / 3.7.3 SG 1B CF CONTROL BYPASS 1CFVA0106 3.6.3 / 3.7.3 SG 1C CF CONTROL BYPASS 1CFVA0107 3.6.3 / 3.7.3 SG 1D CF CONTROL BYPASS 1CFVA0126 3.6.3 / 3.7.3 SG 1A CF TO CA ISOLATION 1CFVA0127 3.6.3 / 3.7.3 SG 1B CF TO CA ISOLATION 1CFVA0128 3.6.3 / 3.7.3 SG 1C CF TO CA ISOLATION 1CFVA0129 3.6.3 / 3.7.3 SG 1D CF TO CA ISOLATION 1EBABKPCB11 16.8.2 PCB 11 1EBABKPCB12 16.8.2 PCB 12 1EBABKPCB8 16.8.2 PCB 8 1EBABKPCB9 16.8.2 PCB 9 1EBASXMOG11R 16.8.2 230 KV MOTOR OPERATED GANG (disconnect)

SWITCH 1EBASXMOG11Y 16.8.2 230 KV MOTOR OPERATED GANG (disconnect)

SWITCH 1EBASXMOG12R 16.8.2 230 KV MOTOR OPERATED GANG (disconnect)

SWITCH

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 10 1EBASXMOG12Y 16.8.2 230 KV MOTOR OPERATED GANG (disconnect)

SWITCH 1EBASXMOG1A 16.8.2 MOTOR OPERATED GANG (disconnect switch) 1A BUSLINE 1EBASXMOG1B 16.8.2 MOTOR OPERATED GANG (disconnect switch) 1B BUSLINE 1EBASXMOG8R 16.8.2 230 KV MOTOR OPERATED GANG (disconnect)

SWITCH 1EBASXMOG8Y 16.8.2 230 KV MOTOR OPERATED GANG (disconnect)

SWITCH 1EBASXMOG9R 16.8.2 230 KV MOTOR OPERATED GANG (disconnect)

SWITCH 1EBASXMOG9Y 16.8.2 230 KV MOTOR OPERATED GANG (disconnect)

SWITCH 1EBDRLBUS1A 16.8.2 1A BUSLINE RELAYS AND METERS 1EBDRLBUS1B 16.8.2 1B BUSLINE RELAYS AND METERS 1EBDRLTRANTRIP 16.8.2 BUSLINE 1A/1B T TRIP UNITS 1EBDRLTRANTRIP/Y 16.8.2 UNIT 1 TRANSFER TRIP CHANNEL Y 1EBDRLTRANTRIP/Z 16.8.2 UNIT 1 TRANSFER TRIP CHANNEL Z 1EDA 3.1.7 / 16.7.9 DRPI 1EEBLP9100 16.7.3.F1b UPPR WIND SPEED 1EEBLP9110 16.7.3.F1a LWR WIND SPEED 1EEBLP9120 16.7.3.F2b UPPR WIND DIR 1EEBLP9130 16.7.3.F2a LWR WIND DIR 1EEBLP9140 16.7.3.F3 AIR TEMP D/T 1EHM 3.6.9 H2 MITIGATION 1EIACA9010 3.3.1 / 3.3.2 RPS CH1 1EIACA9020 3.3.1 / 3.3.2 RPS CH2 1EIACA9030 3.3.1 / 3.3.2 RPS CH3 1EIACA9040 3.3.1 / 3.3.2 RPS CH4 1EIACR9100 3.3.3.19 PAMS REC'R-SM PRESS A,B 1EIACR9110 3.3.3.19 / 3.3.3.20 PAMS REC'R-SM PRESS C,D 1EIALP9200 3.3.2.8.c LO-LO TAVG, P-12 1EIALP9210 3.3.3.5 / 3.3.3.6 / 3.3.3.13 / 3.3.3.14 /

3.3.3.15 / 3.3.3.16 /3.3.3.18 ICCM TRAIN A 1EIALP9220 3.3.3.5 / 3.3.3.6 / 3.3.3.13 / 3.3.3.14 /

3.3.3.15 / 3.3.3.16 / 3.3.3.18 ICCM TRAIN B 1EIALP9500 3.4.11/ 3.4.12 / 3.3.3.18 PORV OVRPRESS PROT 1EKVA 3.8.9 / 3.8.10 120 VAC VITAL I&C PNLBD 1EKVB 3.8.9 / 3.8.10 120 VAC VITAL I&C PNLBD 1EKVC 3.8.9 / 3.8.10 120 VAC VITAL I&C PNLBD 1EKVD 3.8.9 / 3.8.10 120 VAC VITAL I&C PNLBD 1ELXA 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1ELXB 3.8.9 / 3.8.10 600 VAC SAFETY BUS

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 11 1ELXC 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1ELXD 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMDLP9100 16.7.4 LOOSE PARTS MON 1EMERL027A 3.3.1.11 RCP 1A Undervoltage Relay 1EMERL027B 3.3.1.11 RCP 1B Undervoltage Relay 1EMERL027C 3.3.1.11 RCP 1C Undervoltage Relay 1EMERL027D 3.3.1.11 RCP 1D Undervoltage Relay 1EMERL081A 3.3.1.12 RCP 1A Underfrequency Relay 1EMERL081B 3.3.1.12 RCP 1B Underfrequency Relay 1EMERL081C 3.3.1.12 RCP 1C Underfrequency Relay 1EMERL081D 3.3.1.12 RCP 1D Underfrequency Relay 1EMFLP0016 16.7.6.F4 Rx Bldg Handling Area Radiation 1EMFLP0017 16.7.6.F3 EMF 17 - Spent Fuel Handling Area Radiation Monitor 1EMFLP0020 16.7.6.F5 New Fuel Vault Area Radiation 1EMFLP0021 16.7.6.F5 New Fuel Vault Area Radiation 1EMFLP0031 16.11.2.F2a EMF 31 - CONVENTIONAL WASTE WATER TREATMENT LINE OR TURB. BLDG. SUMP TO RC 1EMFLP0033 16.7.6.F7, 16.11.7.F2 EMF 33 - CONDENSER EVACUATION 1EMFLP0036L 16.11.7.F1a, 3a, 5, 6, 10 EMF 36 LO - WASTE GAS HOLDUP SYSTEM 1EMFLP0038L 3.4.15.b EMF 38 LO - CONT. PARTICULATE MONITOR 1EMFLP0039L 16.7.6.F1 / 16.11.7.F4 / 16.11.7.F10 EMF 39 Lo-Cont. Gaseous Monitor 1EMFLP0042 3.7.12 / 16.11.7.F6 / 16.7.6.F2 EMF 42 - FUEL STORAGE AREA VENTILATION 1EMFLP0044L 16.11.2.F1c EMF 44 LO - CONT. VENTILATION CONDENSATE LINE 1EMFLP0051A 3.3.3.9 EMF 51A - CONT. ATMOSPHERE HIGH RANGE 1EMFLP0051B 3.3.3.9 EMF 51B - CONT. ATMOSPHERE HIGH RANGE 1EMFLP0071 16.7.6.F8 Steam Line A N-16 Leakage Monitor 1EMFLP0072 16.7.6.F8 Steam Line B N-16 Leakage Monitor 1EMFLP0073 16.7.6.F8 Steam Line C N-16 Leakage Monitor 1EMFLP0074 16.7.6.F8 Steam Line D N-16 Leakage Monitor 1EMFRT0035L 16.11.7.F3c UNIT VENT PARTICULATE SAMPLER (EMF-35) 1EMTTE5000 16.9.16.F3 ND PUMP A ROOM TEMP 1EMTTE5010 16.9.16.F3 ND PUMP B ROOM TEMP 1EMTTE5020 16.9.16.F1 NS PUMP A ROOM TEMP 1EMTTE5030 16.9.16.F1 NS PUMP B ROOM TEMP 1EMTTE5040 16.9.16.F5 KF PUMP ROOM TEMP 1EMTTE5050 16.9.16.F2c TB496 TEMP 1EMTTE5060 16.9.16.F4 D/G A ROOM TEMP 1EMTTE5061 16.9.16.F4 D/G A ROOM TEMP

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 12 1EMTTE5070 16.9.16.F4 D/G B ROOM TEMP 1EMTTE5071 16.9.16.F4 D/G B ROOM TEMP 1EMTTE5080 16.9.16.F2a TB208-209 TEMP 1EMXA 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXA-1 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXA-2 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXA-3 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXA-4 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXA-5 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXB 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXB-1 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXB-2 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXB-3 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXB-4 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXB-5 3.8.9 / 3.8.10 600 VAC SAFETYBUS 1EMXC 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXD 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXE 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXF 3.8.9 / 3.8.10 600 VAC SAFETY BUS 1EMXG 3.8.9 / 3.8.10 600 VAC A TRAIN SHARED SAFETY BUS 1EMXH 3.8.9 / 3.8.10 600 VAC A TRAIN SHARED SAFETY BUS 1EMXH-1 3.8.9 / 3.8.10 600 VAC A Train Shared Safety Bus 1ENACR9010 16.7.7 A & B INCORES 1ENACR9030 16.7.7 C & D INCORES 1ENACR9050 16.7.7 E & F INCORES 1ENALP9100 16.9.7 INCORE T/C (IC T/C) 1ENALP9110 16.9.7 IC TC/REF JUNC TEMP DEV 1ENBLP9310 3.3.1.5.a / 3.9.3 / 16.7.14 SR N-31 (Testing may affect IR) 1ENBLP9320 3.3.1.5.a / 3.9.3 / 16.7.14 SR N-32 (Testing may affect IR) 1ENBLP9350 3.3.1.4 / 3.3.1.16.a IR N-35 (Testing may affect SR) 1ENBLP9360 3.3.1.4 / 3.3.1.16.a IR N-36 (Testing may affect SR) 1ENBLP9410 3.2.4 / 3.3.1.2 / 3.3.1.3 / 3.3.1.6 / 3.3.1.16.b

/ 3.3.1.16.c / 3.3.1.16.d / 3.3.1.7 PR CH 1 N-41 1ENBLP9420 3.2.4 / 3.3.1.2 / 3.3.1.3 / 3.3.1.6 / 3.3.1.16.b

/ 3.3.1.16.c /3.3.1.16.d / 3.3.1.7 PR CH 2 N-42 1ENBLP9430 3.2.4 / 3.3.1.2 / 3.3.1.3 / 3.3.1.6 / 3.3.1.16.b

/ 3.3.1.16.c / 3.3.1.16.d / 3.3.1.7 PR CH 3 N-43 1ENBLP9440 3.2.4 / 3.3.1.2 / 3.3.1.3 / 3.3.1.6 / 3.3.1.16.b

/ 3.3.1.16.c / 3.3.1.16.d / 3.3.1.7 PR CH 4 N-44 1ENBLP9510 1ENBLP9520

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 13 1ENBP9512 3.9.3 / 16.7.14 Gamma Metrics A N-51 1ENBP9522 3.9.3 / 16.7.14 Gamma Metrics B N-52 1EPBBKTA10 SR 3.8.1.8 6.9KV SWGR 1TA ALTERNATE SUPPLY BKR.

FROM 1ATB 1EPBBKTA6 SR 3.8.1.8 6.9KV SWGR 1TA NORMAL SUPPLY BKR.

FROM 1ATA 1EPBBKTB10 SR 3.8.1.8 6.9KV SWGR 1TB NORMAL SUPPLY BKR.

FROM 1ATB 1EPBBKTB6 SR 3.8.1.8 6.9KV SWGR 1TB ALTERNATE SUPPLY BKR FROM 1ATA 1EPBBKTC10 SR 3.8.1.8 6.9 KV SWGR 1TC ALTERNATE SUPPLY BKR FROM 1ATB 1EPBBKTC6 SR 3.8.1.8 6.9 KV SWGR 1TC NORMAL SUPPLY BKR FROM 1ATA 1EPBBKTD10 SR 3.8.1.8 6.9 KV SWGR 1TD NORMAL SUPPLY BKR FROM 1ATB 1EPBBKTD6 SR 3.8.1.8 6.9 KV SWGR 1TD ALTERNATE SUPPLY BKR FROM 1ATA 1EPL 3.8.4 / 3.8.7 / 3.8.8 VITAL BATTERIES 1EQB 3.8.1 / 3.8.2 LOAD SEQUENCER 1EQBLP27A&B 3.3.2.6.d / 3.3.5 4Kv DEGRADED VOLT. RELAY 1EQCSW7720 3.8.1 / 3.8.2 DG A Speed Switch #1 1EQCSW7750 3.8.1 / 3.8.2 DG B Speed Switch #1 1ESTME1AMTU 16.8.2 1AMTU SWITCHYARD SUPERVISORY EQUIPMENT 1ESTME1ARTU 16.8.2 1ARTU SWITCHYARD SUPERVISORY EQUIPMENT 1ESTME1BMTU 16.8.2 1BMTU SWITCHYARD SUPERVISORY EQUIPMENT 1ESTME1BRTU 16.8.2 1BRTU SWITCHYARD SUPERVISORY EQUIPMENT 1ETA 3.8.9 / 3.8.10 4160 VAC SAFETY BUS 1ETB 3.8.9 / 3.8.10 4160 VAC SAFETY BUS 1EVDA 3.8.9 / 3.8.10 125 VDC VITAL I&C PNLBD 1EVDB 3.8.9 / 3.8.10 125 VDC VITAL I&C PNLBD 1EVDC 3.8.9 / 3.8.10 125 VDC VITAL I&C PNLBD 1EVDD 3.8.9 / 3.8.10 125 VDC VITAL I&C PNLBD 1FDLP5040 3.8.1 / 3.8.2 D/G A DAY TK LEV 1FDLP5050 3.8.1 / 3.8.2 D/G B DAY TK LEV 1FDLP5140 3.8.3 D/G A STOR TK LEV 1FDLP5150 3.8.3 D/G B STOR TK LEV 1FWLP5000 3.3.2.7 / 3.3.3.20 / 16.9.11 / 16.9.14 FWST LEV CH 4 1FWLP5010 3.3.2.7 / 3.3.3.20 / 16.9.11 / 16.9.14 FWST LEV CH 1 1FWLP5020 3.3.2.7 / 3.3.3.20 / 16.9.11 / 16.9.14 FWST LEV CH 2

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 14 1FWLP5340 3.5.4 / 16.9.11 / 16.9.14 FWST LEV 1FWRD5030 3.5.4 / 16.9.11 / 16.9.14 FWST TEMP 1FWRD5120 3.5.4 / 16.9.11 / 16.9.14 FWST TEMP 1FWRD5280 3.5.4 / 16.9.11 / 16.9.14 FWST TEMP 1IAE 3.6.2 PERSONNEL AIRLOCK 1IEELP9000 16.7.2 TRI-AX ACCEL 1IEEVD1000 16.7.2.F1c SEIS ACCEL - Control Room 1IEEVD1010 16.7.2.F1b SEIS ACCEL REMOTE B - CA Pump Room 1IEEVD1020 16.7.2.F1a SEIS ACCEL REMOTE A - Containment Base Slab 1IEEVD1030 16.7.2.F1d SEIS ACCEL - Cont. Bldg. Elev. 825' + 4" 1IEEVD1040 16.7.2.F1e SEIS ACCEL - Cont. Bldg. Elev. 784' & 10" 1ILELPXXX1 3.4.9 PZR Heaters 1IPECA9010 3.3.1.15 / 3.3.1.17 / 3.3.1.19 / 3.3.2 SSPS TR-A 1IPECA9020 3.3.1.15 / 3.3.1.17 / 3.3.1.19 / 3.3.2 SSPS TR B 1IREBKBYA 3.3.1.17 / 3.3.1.18 RTBYA 1IREBKBYB 3.3.1.17 / 3.3.1.18 RTBYB 1IREBKRTA 3.3.1.17 / 3.3.1.18 RTA 1IREBKRTB 3.3.1.17 / 3.3.1.18 RTB 1ITECA9080 16.7.5 TURBINE OVERSPEED 1KDTT5260 3.8.1 / 3.8.2 DG Intercooler 1A Temp. Control 1KDTT5270 3.8.1 / 3.8.2 DG Intercooler 1B Temp. Control 1KFLP5120 3.7.13 / 16.9.21 / 16.9.7 SFP LEVEL 1KFLP5350 16.7.13 SFP Flex Strategy PRIMARY Channel WR Level Indicator (Radar) 1LDLL5320 3.8.1 / 3.8.2 DG A Barring Gear Limit Switch 1LDLL5321 3.8.1 / 3.8.2 DG A Barring Gear Limit Switch 1LDLL5330 3.8.1 / 3.8.2 DG B Barring Gear Limit Switch 1LDLL5331 3.8.1 / 3.8.2 DG B Barring Gear Limit Switch 1LDPS5120 3.8.1 / 3.8.2 Lube Oil to Engine - DG A 1LDPS5123 3.8.1 / 3.8.2 Lube Oil to Engine - DG A 1LDPS5130 3.8.1 / 3.8.2 Lube Oil to Engine - DG B 1LDPS5133 3.8.1 / 3.8.2 Lube Oil to Engine - DG B 1LDPT5360 3.8.1 / 3.8.2 DG LUBE OIL FILTER HIGH DP 1LDPT5370 3.8.1 / 3.8.2 DG LUBE OIL FILTER HIGH DP 1LPPS5180 3.3.2.6.e A FWPT OIL PRESS 1LPPS5181 16.7.1 A FWPT OIL PRESS 1LPPS5182 16.7.1 A FWPT OIL PRESS 1LPPS5183 16.7.1 A FWPT OIL PRESS 1LPPS5190 3.3.2.6.e B FWPT OIL PRESS 1LPPS5191 16.7.1 B FWPT OIL PRESS

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 15 1LPPS5192 16.7.1 B FWPT OIL PRESS 1LPPS5193 16.7.1 B FWPT OIL PRESS 1LTLP5560 3.3.1.14.a ASO CH 1 1LTLP5570 3.3.1.14.a ASO CH 2 1LTLP5580 3.3.1.14.a ASO CH 3 1MIFS7280 16.11.7.F3e IODINE SAMPLER MINIMUM FLOW DEVICE 1MIFT7310 16.11.7.F3a,e,f UNIT VENT EMF-36L NOBLE GAS ACTIVITY MONITOR AND PARTICULATE / IODINE SAMPLER MINIMUM FLOW DEVICE 1MILP6850 16.7.11 HYDROGEN MONITOR A 1MILP6860 16.7.11 HYDROGEN MONITOR B 1NCCR5161 3.3.3.11 PZR LEVEL CHANNEL 3 1NCLP5000 3.3.1.10 / 3.4.1 NC LOOP A FLOW 1 1NCLP5010 3.3.1.10 / 3.4.1 NC LOOP A FLOW 2 1NCLP5020 3.3.1.10 / 3.4.1 NC LOOP A FLOW 3 1NCLP5030 3.3.1.10 / 3.4.1 NC LOOP B FLOW 1 1NCLP5040 3.3.1.10 / 3.4.1 NC LOOP B FLOW 2 1NCLP5050 3.3.1.10 / 3.4.1 NC LOOP B FLOW 3 1NCLP5060 3.3.1.10 / 3.4.1 NC LOOP C FLOW 1 1NCLP5070 3.3.1.10 / 3.4.1 NC LOOP C FLOW 2 1NCLP5080 3.3.1.10 / 3.4.1 NC LOOP C FLOW 3 1NCLP5090 3.3.1.10 / 3.4.1 NC LOOP D FLOW 1 1NCLP5100 3.3.1.10 / 3.4.1 NC LOOP D FLOW 2 1NCLP5110 3.3.1.10 / 3.4.1 NC LOOP D FLOW 3 1NCLP5120 3.3.3.4 / 3.3.3.5 / 3.3.3.6 / 3.3.3.18 / 3.4.3 /

16.10.1 NC D WR PRESS 1NCLP5121 16.9.7 NC D WR PRESS - SSS 1NCLP5122 3.4.12 / 16.10.1 NC LOOP D NR PRESS (LTOP) 1NCLP5140 3.3.3.4 / 3.3.3.5 / 3.3.3.6 / 3.3.3.18 / 3.4.3 /

16.10.1 NC C WR PRESS 1NCLP5141 16.10.1 NC C NR PRESS 1NCLP5142 3.4.12 NC LOOP C NR PRESS (LTOP) 1NCLP5151 3.3.1.9 / 3.3.3.11 / 3.3.4.4 / 3.4.9 / 16.9.7 PZR LEV - CHANNEL 2 1NCLP5370 16.5.8 PZR LIQUID TEMP 1NCLP5420 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 / 3.3.2.8.c LOOP A D/T / TAV 1NCLP5421 3.3.1.7 LOOP A OP D/T 1NCLP5422 3.3.1.6 LOOP A OT D/T 1NCLP5423 3.4.1 / 3.4.2 / 3.4.3 LOOP A TAVG INDICATION 1NCLP5460 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 / 3.3.2.8.c LOOP B D/T / TAV 1NCLP5461 3.3.1.7 LOOP B OP D/T 1NCLP5462 3.3.1.6 LOOP B OT D/T

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 16 1NCLP5463 3.4.1 / 3.4.2 / 3.4.3 LOOP B TAVG INDICATION 1NCLP5500 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 / 3.3.2.8.c LOOP C D/T / TAV 1NCLP5501 3.3.1.7 LOOP C OP D/T 1NCLP5502 3.3.1.6 LOOP C OT D/T 1NCLP5503 3.4.1 / 3.4.2 / 3.4.3 LOOP C TAVG INDICATION 1NCLP5540 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 / 3.3.2.8.c LOOP D D/T / TAV 1NCLP5541 3.3.1.7 LOOP D OP D/T 1NCLP5542 3.3.1.6 LOOP D OT D/T 1NCLP5543 3.4.1 / 3.4.2 / 3.4.3 LOOP D TAVG INDICATION 1NCLP5850 3.3.3.2 / 3.3.3.18 / 16.10.1 LOOP A TH WR TEMP 1NCLP5860 3.3.3.3 / 3.4.3 / 3.4.12 / 16.10.1 LOOP A TC WR TEMP 1NCLP5861 16.9.7 LOOP A TC WR TEMP 1NCLP5870 3.3.3.2 / 3.3.3.18 / 16.10.1 LOOP B TH WR TEMP 1NCLP5880 3.3.3.3 / 3.4.3 / 3.4.12 / 16.10.1 LOOP B TC WR TEMP 1NCLP5900 3.3.3.2 / 3.3.3.18 / 16.10.1 LOOP C TH WR TEMP 1NCLP5910 3.3.3.3 / 3.4.3 / 3.4.12 / 16.10.1 LOOP C TC WR TEMP 1NCLP5920 3.3.4.3.a / 3.3.3.2 / 3.3.3.18 / 3.4.3 / 3.4.12

/ 16.10.1 LOOP D TH WR TEMP 1NCLP5930 3.3.3.3 / 3.4.3 / 3.4.12 / 16.10.1 LOOP D TC WR TEMP 1NCLP5931 16.9.7 LOOP D TC WR TEMP 1NCLP5990 3.9.7 / 16.5.4.a NC WR LEVEL 1NCLP5991 16.5.4.a NC NR LEVEL 1NCLP8120 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP A HOT LEG NR TEMP 1NCLP8130 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP A HOT LEG NR TEMP 1NCLP8140 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP A HOT LEG NR TEMP 1NCLP8150 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP A COLD LEG NR TEMP 1NCLP8160 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP A COLD LEG NR TEMP 1NCLP8170 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP B HOT LEG NR TEMP 1NCLP8180 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP B HOT LEG NR TEMP 1NCLP8190 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP B HOT LEG NR TEMP 1NCLP8200 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP B COLD LEG NR TEMP 1NCLP8210 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP B COLD LEG NR TEMP 1NCLP8220 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP C HOT LEG NR TEMP

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 17 1NCLP8230 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP C HOT LEG NR TEMP 1NCLP8240 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP C HOT LEG NR TEMP 1NCLP8250 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP C COLDLEG NR TEMP 1NCLP8260 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP C COLD LEG NR TEMP 1NCLP8270 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP D HOT LEG NR TEMP 1NCLP8280 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP D HOT LEG NR TEMP 1NCLP8290 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP D HOT LEG NR TEMP 1NCLP8300 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP D COLD LEG NR TEMP 1NCLP8310 3.1.4 / 3.3.1.6 / 3.3.1.7 / 3.3.2.5.b.4 /

3.3.2.8.c / 3.4.1 / 3.4.2 LOOP D COLD LEG NR TEMP 1NCLP8320 3.3.3.5 / 3.3.3.6 / 16.5.4.b TEMP COMP HEAD - RVLIS 1NCLP8330 3.3.3.5 / 3.3.3.6 / 16.5.4.b TEMP COMP HEAD - RVLIS 1NCLP8350 3.3.3.5 / 3.3.3.6 / 16.5.4.b TEMP COMP HOT LEG-RVLIS 1NCLP8360 3.3.3.5 / 3.3.3.6 / 16.5.4.b TEMP COMP SEAL TBL-RVLIS 1NCLP8370 3.3.3.5 / 3.3.3.6 / 16.5.4.b TEMP COMP SEAL TBL-RVLIS 1NCLP8380 3.3.3.5 / 3.3.3.6 / 16.5.4.b TEMP COMP SEAL TBL-RVLIS 1NCLP8390 3.3.3.5 / 3.3.3.6 / 16.5.4.b TEMP COMP HEAD-RVLIS 1NCLP8400 3.3.3.5 / 3.3.3.6 / 16.5.4.b TEMP COMP HEAD-RVLIS 1NCLP8420 3.3.3.5 / 3.3.3.6 / 16.5.4.b TEMP COMP HOT LEG-RVLIS 1NCLP8430 3.3.3.5 / 3.3.3.6 / 16.5.4.b TEMP COMP SEAL TBL-RVLIS 1NCLP8440 3.3.3.5 / 3.3.3.6 / 16.5.4.b TEMP COMP SEAL TBL-RVLIS 1NCLP8450 3.3.3.5 / 3.3.3.6 / 16.5.4.b TEMP COMP SEAL TBL-RVLIS 1NCLP8460 16.5.4 NC C HL ULTRASONIC LEVEL 1NCLP8470 16.5.4 NC A HL ULTRASONIC LEVEL 1NCLT5150 3.3.1.9 / 3.3.3.11 / 3.4.9 PZR LEV 2 1NCLT5151 16.9.7 PZR LEVEL SSS 1NCLT5160 3.3.1.9 / 3.3.3.11 / 3.3.4.4 / 3.4.9 PZR LEV 1 1NCLT5170 3.3.1.9 / 3.3.3.11 / 3.4.9 PZR LEV 3 1NCLT6640 3.3.3.5 / 3.3.3.6 / 16.5.4.b TRAIN A LR RVLIS 1NCLT6650 3.3.3.5 / 3.3.3.6 / 16.5.4.b TRAIN A D/P RVLIS 1NCLT6670 3.3.3.5 / 3.3.3.6 / 16.5.4.b TRAIN B LR RVLIS 1NCLT6680 3.3.3.5 / 3.3.3.6 / 16.5.4.b TRAIN B D/P RVLIS 1NCP5150 3.4.1 / 3.3.1.8 / 3.3.4.2a PZR PRESSURE CHANNEL 2 1NCP5151 3.3.1.9 / 3.3.3.11 / 3.4.9 PZR LEVEL CHANNEL 2 1NCP5153 16.9.7 PZR LEVEL SSS

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 18 1NCP5160 3.3.1.9 / 3.3.3.11 / 3.4.9 PZR LEVEL CHANNEL 1 1NCP5161 3.4.1 / 3.3.1.8 / 3.3.4.2a PZR PRESSURE CHANNEL 1 1NCP5162 3.3.1.9 / 3.3.3.11 / 3.3.4.4 / 3.4.9 PZR LEVEL CHANNEL 1 1NCP5163 3.4.1 / 3.3.1.8 / 3.3.4.2a PZR PRESSURE CHANNEL 1 1NCP5170 3.4.1 / 3.3.1.8 PZR PRESSURE CHANNEL 3 1NCP5171 3.4.1 / 3.3.1.8 PZR PRESSURE CHANNEL 4 1NCP5172 3.3.3.11 / 3.4.9 PZR LEVEL CHANNEL 3 1NCPT5150 3.3.1.6 / 3.3.1.8.a / 3.3.1.8.b / 3.3.2.1.d /

3.3.2.3.a.3 / 3.3.2.5.a.3 / 3.3.2.5.b.3 /

3.3.2.6.c / 3.3.2.8.b / 3.4.1 / 3.4.11 PZR PRESS CH 2 1NCPT5160 3.3.1.6 / 3.3.1.8.a / 3.3.1.8.b / 3.3.2.1.d /

3.3.2.3.a.3 / 3.3.2.5.a.3 / 3.3.2.5.b.3 /

3.3.2.6.c / 3.3.2.8.b / 3.3.4.2 /3.4.1 / 3.4.11 PZR PRESS CH 1 1NCPT5170 3.3.1.6 / 3.3.1.8.a / 3.3.1.8.b / 3.3.2.1.d /

3.3.2.3.a.3 / 3.3.2.5.a.3 / 3.3.2.5.b.3 /

3.3.2.8.b / 3.3.2.6.c / 3.4.1 / 3.4.11 PZR PRESS CH 3 1NCPT5171 3.3.1.6 / 3.3.1.8.a / 3.3.1.8.b / 3.3.2.1.d /

3.3.2.3.a.3 / 3.3.2.5.a.3 / 3.3.2.5.b.3 /

3.3.2.6.c / 3.4.1 / 3.4.11 PZR PRESS CH 4 1NDCR5060 3.4.12 1A ND HX DISC TEMP CHART RECORDER 1NDCR5070 3.4.12 1B ND HX DISC TEMP CHART RECORDER 1NDLP5040 3.4.7 / 3.4.8 / 3.5.2 / 3.5.3 / 3.9.5 / 3.9.6 ND A MIN FLOW 1NDLP5050 3.4.7 / 3.4.8 / 3.5.2 / 3.5.3 / 3.9.5 / 3.9.6 ND B MIN FLOW 1NDRD5000 3.4.12 1A ND HX DISC TEMP RTD 1NDRD5120 3.4.12 1B ND HX DISC TEMP RTD 1NILP5260 3.3.3.7 CONT SUMP WR LEV A 1NILP5270 3.3.3.7 CONT SUMP WR LEV B 1NILS9450 3.3.3.7 CONT. SUMP WR LEV TRN A 1NILS9460 3.3.3.7 CONT. SUMP WR LEV TRN A 1NILS9470 3.3.3.7 CONT. SUMP WR LEV TRN B 1NILS9480 3.3.3.7 CONT. SUMP WR LEV TRN B 1NILT5040 3.5.1 A CLA LEV CH 1 1NILT5050 3.5.1 A CLA LEV CH 2 1NILT5060 3.5.1 B CLA LEV CH 1 1NILT5070 3.5.1 B CLA LEV CH 2 1NILT5080 3.5.1 C CLA LEV CH 1 1NILT5090 3.5.1 C CLA LEV CH 2 1NILT5100 3.5.1 D CLA LEV CH 1 1NILT5110 3.5.1 D CLA LEV CH 2 1NIPT5040 3.5.1 A CLA PRESS CH 1 1NIPT5050 3.5.1 A CLA PRESS CH 2 1NIPT5060 3.5.1 B CLA PRESS CH 1 1NIPT5070 3.5.1 B CLA PRESS CH 2

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 19 1NIPT5080 3.5.1 C CLA PRESS CH 1 1NIPT5090 3.5.1 C CLA PRESS CH 2 1NIPT5100 3.5.1 D CLA PRESS CH 1 1NIPT5110 3.5.1 D CLA PRESS CH 2 1NNCP5153 16.9.7 PZR LEVEL SSS 1NSLP5040 3.3.2.1.c / 3.3.2.3.a.3 / 3.3.2.3.b.3 /

3.3.2.4.c / 3.3.2.5.a.3 / 3.3.2.5.b.3 /

3.3.2.6.c CONT PRESS CH 4 1NSLP5050 3.3.2.1.c / 3.3.2.3.a.3 / 3.3.2.3.b.3 /

3.3.2.4.c / 3.3.2.5.a.3 / 3.3.2.5.b.3 /

3.3.2.6.c CONT PRESS CH 3 1NSLP5060 3.3.2.1.c / 3.3.2.3.a.3 / 3.3.2.3.b.3 /

3.3.2.4.c / 3.3.2.5.a.3 / 3.3.2.5.b.3 /

3.3.2.6.c CONT PRESS CH 2 1NSLP5070 3.3.2.3.b.3 / 3.3.2.4.c CONT PRESS CH 1 1NSLP5360 3.3.2.9 / 3.6.6 CPCS TR B - NS12B,15B 1NSLP5370 3.3.2.9 / 3.6.6 CPCS TR A - NS29A,32A 1NSLP5380 3.3.2.9 / 3.6.8 / 3.6.11 CPCS TR B - VX/H2 Skimmer FANS 1NSLP5390 3.3.2.9 / 3.6.8 / 3.6.11 CPCS TR A - VX/H2 Skimmer FANS 1NSLP5490 3.3.2.9 / 3.6.11 CPCS TR B - VX DMPR/CARF 1NSLP5500 3.3.2.9 / 3.6.11 CPCS TR A - VX DMPR/CARF 1NSLP5510 3.3.2.9 / 3.6.6 CPCS TR B - NS PUMP B 1NSLP5520 3.3.2.9 / 3.6.6 CPCS TR A - NS PUMP A 1NSLP5530 3.3.3.8 CONT PRESS TR A 1NSLP5540 3.3.3.8 CONT PRESS TR B 1NSLP5550 3.6.4 CONT PRESS NR 1NVLP5120 16.9.7.c NCP D #1 SEAL LEAKOFF FLO 1NVLP5130 16.9.7.c NCP C #1 SEAL LEAKOFF FLO 1NVLP5140 16.9.7.c NCP B #1 SEAL LEAKOFF FLO 1NVLP5150 16.9.7.c NCP A #1 SEAL LEAKOFF FLO 1NVLP5300 3.5.5 NCP D SEAL FLOW 1NVLP5310 3.5.5 NCP C SEAL FLOW 1NVLP5320 3.5.5 NCP B SEAL FLOW 1NVLP5330 3.5.5 NCP A SEAL FLOW 1NVLP5720 16.9.11 / 16.9.14 BAT TEMPERATURE 1NVLP5740 16.9.11 / 16.9.14 BAT LEVEL CH 1 1NVLP6070 16.9.11 / 16.9.14 BAT LEVEL CH 2 1NVLP6420 16.9.7 STBY MU PUMP FLOW 1NVPG6530 16.7.13 SFP FLEX STRATEGY BACK-UP CHANNEL WR LEVEL 1RCCA 3.7.9 / 3.7.10 / 3.7.12 / 3.7.13 / 3.8.2 FUEL MOVEMENT 1RNLP5000 3.7.7 1A RN PUMP STRAINER 1RNLP5010 3.7.7 1B RN PUMP STRAINER

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 20 1RNLP5220 3.3.3.21 / 3.7.7 / 3.8.1 / 3.8.2 RN/KD HX A FLOW 1RNLP5230 3.3.3.21 / 3.7.7 / 3.8.1 / 3.8.2 RN/KD HX B FLOW 1RNLP5870 3.3.3.22 / 3.6.6 / 3.7.7 RN/NS HX A FLOW 1RNLP5880 3.3.3.22 / 3.6.6 / 3.7.7 RN/NS HX B FLOW 1SCLL5440 16.7.5 RHSV A1 1SCLL5450 16.7.5 INTV A1 1SCLL5460 16.7.5 RHSV A2 1SCLL5470 16.7.5 INTV A2 1SCLL5480 16.7.5 RHSV B1 1SCLL5490 16.7.5 INTV B1 1SCLL5500 16.7.5 RHSV B2 1SCLL5510 16.7.5 INTV B2 1SCLL5520 16.7.5 RHSV C1 1SCLL5530 16.7.5 INTV C1 1SCLL5540 16.7.5 RHSV C2 1SCLL5550 16.7.5 INTV C2 1SMLL5780 3.3.1.14b / 16.7.5 TV1 1SMLL5800 3.3.1.14b / 16.7.5 TV2 1SMLL5820 3.3.1.14b / 16.7.5 TV3 1SMLL5840 3.3.1.14b / 16.7.5 TV4 1SMLP5080 3.3.2.4.d.1 / 3.3.2.4.d.2 / 3.3.4.3.b /

3.3.3.19 / 16.10.1 A STM LINE PRESS CH1 1SMLP5090 3.3.2.4.d.1 / 3.3.2.4.d.2 / 3.3.3.19 / 16.10.1 A STM LINE PRESS CH2 1SMLP5100 3.3.2.4.d.1 / 3.3.2.4.d.2 / 16.10.1 A STM LINE PRESS CH4 1SMLP5110 3.3.2.4.d.1 / 3.3.2.4.d.2 / 3.3.4.3.b /

3.3.3.19 / 16.10.1 B STM LINE PRESS CH1 1SMLP5120 3.3.2.4.d.1 / 3.3.2.4.d.2 / 3.3.3.19 / 16.10.1 B STM LINE PRESS CH2 1SMLP5130 3.3.2.4.d.1 / 3.3.2.4.d.2 / 16.10.1 B STM LINE PRESS CH3 1SMLP5140 3.3.2.4.d.1 / 3.3.2.4.d.2 / 3.3.4.3.b /

3.3.3.19 / 16.10.1 C STM LINE PRESS CH1 1SMLP5150 3.3.2.4.d.1 / 3.3.2.4.d.2 / 3.3.3.19 / 16.10.1 C STM LINE PRESS CH2 1SMLP5160 3.3.2.4.d.1 / 3.3.2.4.d.2 / 16.10.1 C STM LINE PRESS CH3 1SMLP5170 3.3.2.4.d.1 / 3.3.2.4.d.2 / 3.3.4.3.b /

3.3.3.19 / 16.10.1 D STM LINE PRESS CH1 1SMLP5180 3.3.2.4.d.1 / 3.3.2.4.d.2 / 3.3.3.19 / 16.10.1 D STM LINE PRESS CH2 1SMLP5190 3.3.2.4.d.1 / 3.3.2.4.d.2 / 16.10.1 D STM LINE PRESS CH4 1SMP5081 3.3.4.3.b A STM LINE PRESS CH 1 on MDAFWP Panel 1SMP5082 3.3.4.3.b A STM LINE PRESS CH 1 on TDAFWP Panel 1SMP5111 3.3.4.3.b B STM LINE PRESS CH 1 on MDAFWP Panel 1SMP5112 3.3.4.3.b B STM LINE PRESS CH 1 on TDAFWP Panel 1SMP5141 3.3.4.3.b C STM LINE PRESS CH 1 on MDAFWP Panel

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 21 1SMP5142 3.3.4.3.b C STM LINE PRESS CH 1 on TDAFWP Panel 1SMP5171 3.3.4.3.b D STM LINE PRESS CH 1 on MDAFWP Panel 1SMP5172 3.3.4.3.b D STM LINE PRESS CH 1 on TDAFWP Panel 1SMPS5213 16.7.1 TURB INLET PRESS CH I 1SMPS5220 16.7.1 TURB INLET PRESS CH II 1SMPT5210 3.3.1.16.b / 3.3.1.16.e TURB IMP PRESS CH I 1SMPT5220 3.3.1.16.b / 3.3.1.16.e TURB IMP PRESS CH II 1VALP5120 16.11.7.F3d UNIT VENT FLOW RATE MONIOTR 1VELP5100 3.6.10 / 3.6.16.2 ANN PRESS A 1VELP5110 3.6.10 / 3.6.16.2 ANN PRESS B 1VELP5440 3.6.10 Annulus WR Pressure Train A 1VELP5450 3.6.10 Annulus WR Pressure Train B 1VGPG5000 3.8.3.3 1A1 & 1A2 VG Pressure, Alternate 1VGPG5010 3.8.3.3 1A1 & 1A2 VG Pressure, Alternate 1VGPG5020 3.8.3.3 1B1 & 1B2 VG Pressure, Alternate 1VGPG5030 3.8.3.3 1B1 & 1B2 VG Pressure, Alternate 1VGPG5040 3.8.3.3 1A1 & 1A2 VG Pressure, Primary 1VGPG5060 3.8.3.3 1B1 & 1B2 VG Pressure, Primary 1VLRD5000 3.6.5.b VL TEMP A 1VLRD5010 3.6.5.b VL TEMP B 1VLRD5020 3.6.5.b VL TEMP C 1VLRD5030 3.6.5.b VL TEMP D 1VURD5000 3.6.5.a VU TEMP A 1VURD5010 3.6.5.a VU TEMP B 1VURD5020 3.6.5.a VU TEMP C 1VURD5030 3.6.5.a VU TEMP D 1VXLL9120 3.6.11 1RAF-D-2 Damper Position 1VXLL9121 3.6.11 1RAF-D-2 Damper Position 1VXLL9140 3.6.11 1RAF-D-4 Damper Position 1VXLL9141 3.6.11 1RAF-D-4 Damper Position 1VXPS9140 3.6.11 1A Carf Discharge Damper D/P 1VXPS9160 3.6.11 1B Carf Discharge Damper D/P 1WCLP5240 16.11.2.F2b EMF 31 Minimum Flow Device 1WLCO5900 16.11.2.F3a VUCDT Line Composite Sampler 1WLFS7010 16.11.2.F1c / 16.11.2.F1d EMF44 Minimum Flow Device 1WLLP5250 3.4.15.a F&E SUMP A LEV 1WLLP5260 3.4.15.a F&E SUMP B LEV 1WLLP5590 3.4.15.c VUCDT LEV 1WLLP5900 16.11.2.F1c / 16.11.2.F1d / 16.11.2.F4b /

16.11.2.F3a VUCDT FLOW RATE MEASUREMENT DEVICE

Equipment No.

TS/SLC No.

Description 9-Sep-21 Revision 004 Page 22 1WLLS5270 3.4.15.a Incore Instrument Sump Level Alarm Annunciator 1WLLS5660 3.4.15.a Incore Instrument Sump Level Alarm (OAC) 1WMPP 16.09.26 Unit 1 CA Pump Room Floor Drains (MC-1220-013) 1WMVA0046 16.11.2.F1 LIQUID RADWASTE AUTO ISOLATION VALVE 1WNLS5020 3.8.1 / 3.8.2 / 16.09.26 DIESEL GEN 1A RM SUMP Hi-Hi LVL 1WNLS5030 3.8.1 / 3.8.2 / 16.09.26 DIESEL GEN 1B RM SUMP Hi-Hi LVL 1WNLS5040 16.09.26 1A DG Room Sump Hi Level.

1WNLS5050 16.09.26 1B DG Room Sump Hi Level.

1WNPP 16.09.26 Unit 1 DG Room Floor Drains (MC-1231-13.00) 1WPCO0001 16.11.2.F3c Turb. Bldg. Sump to RC Composite Sampler 1WPFT5120 16.11.2.F4d / 16.11.2.F3c Contaminated Turb. Bldg. Sump Discharge Flow Totalizer 1WPLS5130 16.09.26 Unit 1 Condenser Pit Hi-Hi Level 1WPPS5022 16.09.26 Unit 1 Turb. Bldg. Sump Hi-Hi Level.

1WPVA0035 16.11.2.F1 LIQUID RADWASTE AUTO ISOLATION VALVE 1WPVA0037 16.11.2.F1 LIQUID RADWASTE AUTO ISOLATION VALVE 1WZLS5060 16.9.8.a / 16.9.8.b / 16.9.8.c / 16.9.8.d GND WATER LEVEL-RX BLDG EXTERIOR 1WZLS5070 16.9.8.e / 16.9.8.f / 16.9.8.g GND WATER LEVEL-AUX BLDG WEST WALL 1WZLP5080 16.9.8.a / 16.9.8.b / 16.9.8.c / 16.9.8.d GND WATER LEVEL MONITOR 1 1B DG BLDG INTERIOR 1WZLP5090 16.9.8.a / 16.9.8.b / 16.9.8.c / 16.9.8.d GND WATER LEVEL MONITOR 2 1A DG BLDG INTERIOR 1WZLP5100 16.9.8.e / 16.9.8.f / 16.9.8.g GND WATER LEVEL MONITOR 5 NW AUX BLDG INTERIOR 1XNAPP 16.09.26 Unit 1 Turb. Bldg. Basement Floor Drains (MC-1151-01.00)

PAM Instrumentation 3.3.3 McGuire Units 1 and 2 3.3.3-1 Amendment Nos. 221/203 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS

NOTE----------------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more Functions with one or more required channels inoperable.

A.1 Enter the Condition referenced in Table 3.3.3-1 for the channel.

Immediately B.

One or more Functions with one required channel inoperable.

B.1 Restore required channel to OPERABLE status.

30 days C.

Required Action and associated Completion Time of Condition B not met.

C.1 Initiate action in accordance with Specification 5.6.7 Immediately D.

One or more Functions with one required channel inoperable.

D.1 Restore required channel to OPERABLE status.

7 days (continued)

PAM Instrumentation 3.3.3 ACTIONS (continued)

McGuire Units 1 and 2 3.3.3-2 Amendment Nos. 227 / 209 CONDITION REQUIRED ACTION COMPLETION TIME E.

One or more Functions with two required channels inoperable.

E.1 Restore one channel to OPERABLE status.

7 days F.

Not Used F.1 Not Used Not Used G.

Required Action and associated Completion Time of Condition D or E not met.

G.1 Be in MODE 3.

AND G.2 Be in MODE 4.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours H.

Required Action and associated Completion of Condition D not met.

H.1 Initiate action in accordance with Specification 5.6.7.

Immediately

PAM Instrumentation 3.3.3 McGuire Units 1 and 2 3.3.3-3 Amendment Nos 261/241 SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------------------------------

SR 3.3.3.1 and SR 3.3.3.3 apply to each PAM instrumentation Function in Table 3.3.3-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required instrumentation channel that is normally energized.

In accordance with the Surveillance Frequency Control Program SR 3.3.3.2 Not Used Not Used SR 3.3.3.3

NOTE----------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program

PAM Instrumentation 3.3.3 McGuire Units 1 and 2 3.3.3-4 Amendment Nos. 227 / 209 Table 3.3.3-1 (page 1 of 1)

Post Accident Monitoring Instrumentation FUNCTION REQUIRED CHANNELS CONDITIONS 2

B,C,E,G 2

B,C,E,G 1

D,H Not Used Not Used 2

B,C,E,G 2 per steam generator B,C,E,G 2(a)

B,C,E,G 2(a)

B,C,E,G 2 per steam generator B,C,E,G 2

B,C,E,G 1 per DG D,G 1.

2.

Reactor Coolant System (RCS) Hot Leg Temperature 3.

RCS Cold Leg Temperature 4.

RCS Pressure (Wide Range) 5.

Reactor Vessel Water Level (Dynamic Head Range) 6.

Reactor Vessel Water Level (Lower Range) 7.

Containment Sump Water Level (Wide Range) 8.

Containment Pressure (Wide Range) 9.

Containment Atmosphere Radiation (High Range) 10.

Not Used 11.

Pressurizer Level 12.

Steam Generator Water Level (Narrow Range) 13.

Core Exit Temperature - Quadrant 1 14.

Core Exit Temperature - Quadrant 2 15.

Core Exit Temperature - Quadrant 3 16.

Core Exit Temperature - Quadrant 4 17.

Auxiliary Feedwater Flow 18.

RCS Subcooling Margin Monitor 19.

Steam Line Pressure 20.

Refueling Water Storage Tank Level 21.

DG Heat Exchanger NSWS Flow(b) 22.

Containment Spray Heat Exchanger NSWS Flow(b) 1 per train D,G (a)

A channel consists of two core exit thermocouples (CETs).

(b)

Not applicable if the associated outlet valve is set to its flow balance position with power removed or if the associated outlet valve's flow balance position is fully open.

ML23258A148: Difference between revisions

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ML23258A148: Difference between revisions

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