Text

1A Final SRO Exam, Answer Key, References
	ML21286A525
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Site:	Catawba
Issue date:	10/13/2021
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ML21286A525 ES-401 Site Specific SRO Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: September 30, 2021 Facility/Unit Catawba Nuclear Station Region: I II III IV Reactor Type: W CE BW GE Start Time: Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80 percent overall, with 70 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80 percent to pass.

You have 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months to complete the combined examination and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months if you are only taking the SRO-only portion.

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

Applicants Signature Results RO/SRO-Only/Total Examination Values __75__ / __25__ / __100__ Points Applicants Score ______ / ______ / ______ Points Applicants Grade ______ / ______ / ______ Percent

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 1 (1 point)

Given the following Unit 1 initial conditions:

Unit 1 was at 100% RTP

Core age has reached 325 EFPD

DRPI Data B power supply failure is being investigated by IAE

A Turbine runback has occurred due to a trip of 1A CFPT on lowering vacuum Subsequently:

Unit 1 Reactor is manually tripped following the loss of 1B CFPT

NC Temperature is 490 °F

The CRS has transitioned to EP/1/A/5000/ES-0.1 (Reactor Trip Response) and reached step 8:

In accordance with ES-0.1:

DRPI indication _____(1)_____ require emergency boration.

NC Temperature _____(2)_____ require emergency boration.

Which ONE of the following correctly completes the statement above?

REFERENCE PROVIDED 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 1 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 2 (1 point)

Given the following Unit 2 conditions:

The unit is in Mode 3

Pzr pressure is 1785 PSIG

Pzr Relief Tank (PRT) pressure is 10 PSIG

PRT temperature is 125°F

A Pzr code safety valve is leaking by its seat Which ONE of the following correctly identifies the approximate temperature that is indicated on the leaking safety valve discharge RTD?

REFERENCE PROVIDED A. 121 - 129°F B. 210 - 218°F C. 236 - 244°F D. 282 - 290°F Page 2 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 3 (1 point)

Given the following Unit 1 initial conditions:

A small break LOCA has occurred

EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant) has been entered

Neither train of ICCM is available Subsequently:

The crew has transitioned to EP/1/A/5000/ES-1.2 (Post LOCA Cooldown and Depressurization)

S/G PORVs are being used for cooldown

Current NC pressure is 665 psig

Core exit thermocouple temperatures are 490°F

T-Colds are 487.7°F In accordance with E-1, the value of subcooling is _____(1)_____ .

Based on current conditions, steam header pressure is _____(2)_____ .

Which ONE of the following correctly completes the statements above?

REFERENCE PROVIDED A. 1. - 10° F

2. 608 psig B. 1. - 10° F

2. 593 psig C. 1. + 10° F

2. 608 psig D. 1. + 10° F

2. 593 psig Page 3 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 4 (1 point)

Given the following Unit 1 conditions:

The crew has entered EP/1/A/5000/FR-P.1 (Response to Imminent Pressurized Thermal Shock) due to a RED path condition on the Reactor Coolant Integrity CSF Status Tree.

FR-P.1 utilizes the parameters of NC pressure and __________ to determine if a large break LOCA has occurred.

Which ONE of the following correctly completes the statement above?

A. RVLIS level B. S/G pressure C. NC T-cold temperatures D. ND flow rate to cold legs Page 4 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 5 (1 point)

Given the following Unit 1 conditions:

Unit is in Mode 3

Rod control is capable of rod withdrawal

NC loops 1A, 1B, and 1D are in operation

The crew has entered AP/1/A/5500/008 (Malfunction of Reactor Coolant Pump)

1A NC Pump Lower Bearing temperature is currently 190ºF and rising 5ºF per minute 1A NC Pump Lower Bearing temperature will reach trip setpoint in

_____(1)_____ .

Following the trip of 1A NCP, entry into the action statement of TS 3.4.5 (RCS Loops - MODE 3) _____(2)_____ required.

Which ONE of the following correctly completes the statements above?

A. 1. 7 minutes

2. is B. 1. 7 minutes

2. is NOT C. 1. 1 minute

2. is D. 1. 1 minute

2. is NOT Page 5 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 6 (1 point)

Given the following conditions on Unit 1:

The unit is at 100% RTP

1A NV pump has tripped

Unit 1 letdown has isolated

The crew has entered AP/1/A/5500/012 (Loss of Charging or Letdown)

Based on these conditions, all cooling to NC pump lower bearings

_____(1)_____ been lost.

Per AP/12, prior to initiating letdown flow, 1NV-148 (Letdn Press Control) will be throttled to _____(2)_____ demand.

Which ONE of the following correctly completes the statements above?

A. 1. has

2. 45%

B. 1. has

2. 60%

C. 1. has NOT

2. 45%

D. 1. has NOT

2. 60%

Page 6 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 7 (1 point)

Given the following Unit 1 initial conditions:

Refueling was in progress when a loss of ND occurred

CRS has implemented AP/1/A/5500/019 (Loss of Residual Heat Removal System) Case III (Loss of ND With Large Vent Path Established)

Subsequently:

The reason for the loss of ND has been corrected

Crew is performing Enclosure 8 (Restoring an ND Train To Operation) to place 1A ND train in service In accordance with Enclosure 8:

The MINIMUM KC flow established to the ND heat exchanger is _____(1)_____

GPM.

Prior to starting the 1A ND pump, 1ND-27 (ND Hx 1A Bypass Ctrl) is placed in the _____(2)_____ position.

Which ONE of the following correctly completes the statements above?

A. 1. 5000

2. CLOSED B. 1. 5000

2. OPEN C. 1. 3000

2. CLOSED D. 1. 3000

2. OPEN Page 7 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 8 (1 point)

Given the following Unit 1 timeline:

1200

The Unit is at 100% RTP

1B2 KC Pump is in service

1B KC flow is 5000 gpm and stable

1B KF is in service 1203

1KC-15 (1B2 KC Pump Disch) is inadvertently closed 1205

1KC-15 is reopened

No additional KC pumps have been started Following closure of 1KC-15, 1KC-156 (KF HX 1B Cool Wtr Otlt) _____(1)_____

automatically change position.

Assuming no operator action, once 1KC-15 is reopened 1AD-9 F/6 KC Train B Single Pump Runout _____(2)_____ alarm.

Which ONE of the following correctly completes the statements above?

A. 1. will

2. will B. 1. will NOT

2. will C. 1. will

2. will NOT D. 1. will NOT

2. will NOT Page 8 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 9 (1 point)

Given the following Unit 1 initial conditions:

Unit is at 100% RTP with surveillance testing in progress

Reactor Trip Breaker A (RTA) and Bypass Breaker B (BYB) are racked-in and closed Subsequently:

A complete loss of feedwater occurred

All efforts to trip the reactor from the control room were unsuccessful

Annunciator 1AD-1 A/5 (P-14, S/I OR RX TRIP CAUSES TURBINE TRIP) is LIT

Operators entered EP/1/A/5000/FR-S.1 (Response to Nuclear Power Generation/ATWS)

An AO was dispatched to locally trip the Reactor Based on the given conditions, the Reactor Trip Breaker A (RTA)

_____(1)_____ failed to operate as designed.

If successful in opening all Reactor Trip and Bypass breakers, then per FR-S.1, the AO _____(2)_____ required to open the MG set breakers locally.

Which ONE of the following correctly completes the statements above?

A. 1. shunt trip coil ONLY

2. is NOT B. 1. shunt trip AND undervoltage coils

2. is NOT C. 1. shunt trip coil ONLY

2. is D. 1. shunt trip AND undervoltage coils

2. is Page 9 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 10 (1 point)

Given the following Unit 2 conditions:

The Unit is at 45% RTP

The crew has entered AP/2/A/5500/028 (Secondary Steam Leak) due to a leak from the 2nd stage reheat steam tube bundle inside 2A MSR (location A)

The steam leak at location A, will cause Main Turbine Megawatts to _____(1)_____ .

In order to isolate the leak, AP/28 will direct the crew to _____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. rise

2. trip the Main Turbine B. 1. rise

2. trip the Reactor and close MSIVs C. 1. lower

2. trip the Main Turbine D. 1. lower

2. trip the Reactor and close MSIVs Page 10 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 11 (1 point)

Given the following Unit 2 conditions:

A seismic event has resulted in the following:

o 2A S/G has experienced a complete shear of the Main Steam line at the S/G outlet o 2D S/G has experienced a complete shear of the Main Feed line at the S/G inlet Steam Generator _____(1)_____ will lower to 0% WR level FIRST.

Procedural guidance to isolate 2D S/G is contained in _____(2)_____.

Which ONE of the following correctly completes the statements above?

A. 1. 2A

2. EP/2/A/5000/E-1 (Loss of Reactor or Secondary Coolant)

B. 1. 2A

2. EP/2/A/5000/E-2 (Faulted Steam Generator Isolation)

C. 1. 2D

2. EP/2/A/5000/E-1 (Loss of Reactor or Secondary Coolant)

D. 1. 2D

2. EP/2/A/5000/E-2 (Faulted Steam Generator Isolation)

Page 11 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 12 (1 point)

Given the following Unit 2 conditions:

A Loss of All Offsite Power has occurred

Both Unit 2 D/Gs started and loaded their associated bus

While monitoring D/G operating parameters, the local operator notes that D/G 2B VOLTS indicates 3925 V In order to adjust 2B D/G Voltage, local controls will be operated on the 2B Diesel _____(1)_____ Control Panel .

Following this adjustment, 2B D/G AMPS will be _____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. Engine

2. lower B. 1. Generator

2. lower C. 1. Engine

2. higher D. 1. Generator

2. higher Page 12 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 13 (1 point)

Given the following initial conditions:

1B RN Pump in service

1B1 KC Pump in service

2A1 KC Pump in service Subsequently:

Both units enter AP/0/A/5500/030 (Plant Flooding), Enclosure 8 (Flooding From RN) following discovery of a large RN leak on the 1A Essential Header

Per AP/30 guidance, the crew has isolated the 1A RN Essential Header (ONLY)

Based on current conditions:

Cooling water supply _____(1)_____ available to the 1A KD Heat Exchanger.

Mini-Flow protection _____(2)_____ available for the 1B RN Pump.

Which ONE of the following correctly 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 13 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 14 (1 point)

Given the following Unit 1 initial conditions:

The crew has entered AP/0/A/5500/022 (Loss of Instrument Air) following a complete loss of VI

Both Reactors have been tripped Subsequently:

Unit 1 has entered EP/1/A/5000/FR-H.1 (Loss of Heat Sink)

Feed and Bleed criteria has been met In order to establish Feed and Bleed, motive force will be available to

_____(1)_____ Pressurizer PORVs supplied by _____(2)_____ .

Which ONE of the following correctly completes the statement above?

A. 1. two

2. cold leg accumulators B. 1. two

2. individual air accumulators C. 1. three

2. cold leg accumulators D. 1. three

2. individual air accumulators Page 14 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 15 (1 point)

Given the following Unit 1 initial conditions:

The unit is at 100% RTP with Main Generator power factor at 0.99 lagging

Unit 1 Voltage Regulator is in "Manual" per Engineering's request

The READY status light for the Voltage Regulator Manual/Auto switch is DARK Subsequently:

Generator Voltage and MVARs begin fluctuating

The CRS enters AP/1/A/5500/037 (Generator Voltage and Electric Grid Disturbances), Case I (Abnormal Generator or Grid Voltage) o The CRS has directed the OATC to operate the Voltage Regulator to maintain Generator MVARS within the Generator Capability Curve With the Voltage Regulator in "Manual", operation of the Voltage Adjust RAISE/LOWER pushbutton _____(1)_____ adjust Reactive Power.

Placing the Voltage Regulator Manual/Auto switch in Auto (with the READY status light dark) _____(2)_____ transfer the Voltage Regulator to automatic control.

Which ONE of the following correctly 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 15 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 16 (1 point)

Given the following initial conditions on Unit 1:

A LOCA outside containment has occurred

The crew suspects the leak is located in the 1B ND header

EP/1/A/5000/ECA-1.2 (LOCA Outside Containment) has been entered Subsequently:

1B ND header has been isolated. 30 seconds following header isolation, indications are as follows:

o Unit 1 PZR level is 0%

o Subcooling is -5°F and stable o NC Pressure is 1050 psig and slowly lowering o RVLIS level is 61.3% and slowly rising In accordance with ECA-1.2:

The crew _____(1)_____ permitted to isolate 1B ND header prior to 1A ND header.

With given indications, _____(2)_____ will provide the best diagnostic of leak isolation.

Which ONE of the following correctly completes the statements above?

A. 1. is

2. NC pressure B. 1. is NOT

2. NC pressure C. 1. is

2. RVLIS level D. 1. is NOT

2. RVLIS level Page 16 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 17 (1 point)

Given the following Unit 1 conditions:

A Safety Injection due to Hi Containment Pressure has occurred

Containment pressure peaked at 2.7 psig and is now slowly lowering

The crew has implemented EP/1/A/5000/FR-H.1 (Response to Loss of Secondary Heat Sink)

All attempts to restore CA flow have been unsuccessful In accordance with FR-H.1:

The NEXT source of feed water attempted for restoration of flow to the S/Gs is through the CM/CF system using _____(1)_____.

The crew will be required to establish bleed and feed when W/R level in at least 3 S/Gs is less than a MAXIMUM level of _____(2)_____.

Which ONE of the following correctly completes the statements above?

A. 1. either Main Feed Water pump

2. 24%

B. 1. either Main Feed Water pump

2. 36%

C. 1. Hotwell and Booster pumps

2. 24%

D. 1. Hotwell and Booster pumps

2. 36%

Page 17 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 18 (1 point)

Given the following Unit 1 conditions:

EP/1/A/5000/ECA-1.1 (Loss of Emergency Coolant Recirculation) is in progress

NC Pressure is 1700 psig

FWST level is trending down

_____(1)_____ are currently providing injection flow into the NC System.

Per ECA-1.1, as the FWST level lowers less than _____(2)_____ the operator will secure these pumps.

Which ONE of the following correctly completes the statements above?

A. 1. NV AND NI Pumps

2. 20%

B. 1. NV AND NI Pumps

2. 5%

C. 1. ONLY NV Pumps

2. 20%

D. 1. ONLY NV Pumps

2. 5%

Page 18 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 19 (1 point)

Given the following Unit 1 initial conditions:

Unit is in Mode 6 performing core loading

Unit 1 TRN A SMM BORON DILUTION INTLKS switch is in the Enable position

Unit 1 TRN B SMM BORON DILUTION INTLKS switch is in the Defeat position

The VCT Outlet Valve Interlock Keyswitch is in the Normal position Subsequently:

The OATC has just reset Shutdown Margin Monitor setpoints on 1A and 1B trains

An error has resulted in mispositioning of several fuel assemblies o This mispositioning has resulted in a critical array and rising count rate 1AD-2 E(F)/2 Train A(B) Shutdown Margin Alarm will actuate once count rate rises by a MINIMUM factor of _____(1)_____ .

Following alarm actuation, 1A and 1B NV Pump suction will be aligned to the

_____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. two

2. VCT B. 1. two

2. FWST C. 1. three

2. VCT D. 1. three

2. FWST Page 19 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 20 (1 point)

Given the following Unit 1 initial conditions:

Unit is at 100% RTP

Letdown flow is 85 gpm aligned through the 1NV-10A (Letdn Orif 1B Otlt Cont Isol)

Subsequently:

1A S/G develops a tube leak

The crew has entered AP/1/A/5500/010 (Reactor Coolant Leak), Case I (Steam Generator Tube Leak)

1NV-294 (NV Pmps A&B Disch Flow Ctrl) has been fully opened o Pressurizer level continues to lower at 0.1% / minute

The CRS desires letdown flow reduction to 45 gpm Prior to this event, 1NV-849 (Letdn Flow Var Orif Ctrl) SLIM station was in

_____(1)_____ .

Per AP/10, letdown flow reduction will be accomplished via the

_____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. manual

2. 45 gpm orifice B. 1. manual

2. variable orifice C. 1. automatic

2. 45 gpm orifice D. 1. automatic

2. variable orifice Page 20 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 21 (1 point)

Given the following conditions on Unit 1:

Reactor power is currently 7%

The crew has entered AP/1/A/5500/023 (Loss of Condenser Vacuum)

In service CFPT vacuum, and Main Condenser vacuum, is currently 17 Hg and lowering In accordance with AP/23, a reactor trip _____(1)_____ required.

Main Condenser steam dumps _____(2)_____ currently available.

Which ONE of the following correctly completes the statements above?

A. 1. is

2. are B. 1. is

2. are NOT C. 1. is NOT

2. are D. 1. is NOT

2. are NOT Page 21 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 22 (1 point)

Given the following conditions:

A planned Liquid Waste Release of Waste Monitor Tank (WMT) A was initiated at 1110 The following timeline of events then occurs:

1120 1RAD-1, C/5 (EMF-49 LIQUID WASTE DISCH HI RAD) alarms 1130 The release is manually re-initiated without re-sampling 1145 1RAD-1, C/5 (EMF-49 LIQUID WASTE DISCH HI RAD) alarms 1155 The release is manually re-initiated without re-sampling 1215 1RAD-1, C/5 (EMF-49 LIQUID WASTE DISCH HI RAD) alarms The release _____(1)_____ be manually re-initiated, without re-sampling, per OP/0/B/6500/113 (Operations Liquid Waste Release).

The release was automatically isolated by closure of _____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. can

2. 1WL-X28 B. 1. can

2. 1WL-124 C. 1. can NOT

2. 1WL-X28 D. 1. can NOT

2. 1WL-124 Page 22 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 23 (1 point)

Given the following Unit 1 initial condition:

The crew has entered EP/1/A/5000/FR-Z.1 (Response to High Containment Pressure) due to a valid red path In accordance with FR-Z.1, Enclosure 3 (Containment Isolation VX System Verification), the crew will verify Containment Air Return Fans are operating if the elapsed time since Phase B actuation is greater than _____(1)_____ and secured if containment pressure lowers below _____(2)_____ .

Which ONE of the following correctly completes the statement above?

A. 1. 9 minutes

2. 0.9 PSIG B. 1. 9 minutes

2. 0.3 PSIG C. 1. 10 seconds

2. 0.9 PSIG D. 1. 10 seconds

2. 0.3 PSIG Page 23 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 24 (1 point)

Given the following Unit 1 initial conditions:

A Loss of Off-Site Power (LOOP) has occurred

Due to multiple equipment failures, the crew has implemented EP/1/A/5000/FR-C.1 (Response To Inadequate Core Cooling)

Containment pressure has risen to 2.6 psig and stabilized

ECCS steam pressure has been blocked in preparation for cooldown Subsequently:

Main steam pressure has lowered to 750 psig

Operators are preparing to depressurize intact steam generators to 140 PSIG Based on the conditions above:

Operation of S/G PORVs _____(1)_____ require depressing the SM PORV TRAIN A(B) RESET pushbutton.

In order to establish required cooldown rate, the OATC _____(2)_____ rotate all S/G PORV controllers to the full open position.

Which ONE of the following correctly 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 24 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 25 (1 point)

Given the following Unit 1 conditions:

A medium break LOCA has occurred

EP/1/A/5000/E-1 (Loss of Reactor Coolant or Secondary Coolant) has been implemented and the crew is evaluating Safety Injection termination criteria

The BOP reports the following data:

o NC pressure is 1200 PSIG and STABLE o Containment pressure is 3.3 PSIG and trending down o NC subcooling is 2°F o Pressurizer level is 17% and STABLE Based on S/I termination criteria of E-1:

NC Pressure requirement _____(1)_____ met.

Pressurizer level requirement _____(2)_____ met.

Which ONE of the following correctly completes the statement above?

A. 1. is

2. is B. 1. is NOT

2. is C. 1. is

2. is NOT D. 1. is NOT

2. is NOT Page 25 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 26 (1 point)

Given the following Unit 1 initial conditions:

The Unit is at 100% RTP Subsequently:

1100 A LOCA occurs 1215 Containment sump level is 13 feet and slowly rising If containment sump level is rising at a constant rate of 0.25 feet per minute, EP/1/A/5000/FR-Z.2 (Response to Containment Flooding) entry will be REQUIRED at _____(1)_____ .

Valves, inside containment, NOT qualified for submergence will be isolated by an _____(2)_____ signal.

Which ONE of the following correctly completes the statements above?

A. 1. 1225

2. ST B. 1. 1245

2. ST C. 1. 1225

2. SP D. 1. 1245

2. SP Page 26 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 27 (1 point)

Given the following Unit 1 conditions:

A LOCA has occurred

Containment pressure peaked at 2.8 PSIG, and is now 2.2 PSIG and slowly lowering

Crew has entered EP/1/A/5000/ES-1.2 (Post LOCA Cooldown and Depressurization) and is performing the initial cooldown In accordance with ES-1.2:

The INITIAL cooldown will be started using the _____(1)_____.

With rates established, per the graphic above, the cooldown _____(2)_____

continue at this time.

Which ONE of the following correctly completes the statements above?

A. 1. S/G PORVs

2. can NOT B. 1. S/G PORVs

2. can C. 1. Condenser Steam Dumps

2. can NOT D. 1. Condenser Steam Dumps

2. can Page 27 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 28 (1 point)

Given the following Unit 1 conditions:

The Unit is at 100% RTP

Total charging flow is currently 90 gpm

1NV-294 (NV Pmps A&B Disch Flow Ctrl) is in MANUAL

1NV-309 (Seal Water Injection Flow) is in AUTO Assuming stable plant conditions, as 1NV-294 is throttled CLOSED, 1NV-309 will throttle in the _____(1)_____ direction in order to maintain _____(2)_____

seal injection flow.

Which ONE of the following correctly completes the statements above?

A. 1. OPEN

2. 32 gpm B. 1. CLOSED

2. 32 gpm C. 1. OPEN

2. 40 gpm D. 1. CLOSED

2. 40 gpm Page 28 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 29 (1 point)

Concerning operation of the Unit 1 Volume Control Tank (VCT):

A loss of power to 1LT-5761 (VCT Level CH 1) _____(1)_____ result in a DCS Alternate Action.

A loss of 1ERPA will result in a loss of _____(2)_____ makeup capability to the VCT.

Consider each statement separately Which ONE of the following correctly completes the statements above?

A. 1. will

2. auto ONLY B. 1. will

2. auto AND manual C. 1. will NOT

2. auto ONLY D. 1. will NOT

2. auto AND manual Page 29 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 30 (1 point)

Given the following Unit 2 initial conditions:

Unit is in Mode 4

2A ND train in service in RHR Mode

2B ND train remains in Injection Mode Subsequently:

Instrument Air is lost to 2ND-26 (ND Hx 2A Outlet Ctrl)

Assuming no operator acton:

ND system flow _____(1)_____ automatically adjust to compensate for the change caused by this malfunction.

2A ND Heat Exchanger outlet temperature will _____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. will

2. rise B. 1. will NOT

2. rise C. 1. will

2. lower D. 1. will NOT

2. lower Page 30 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 31 (1 point)

Given the following Unit 2 conditions:

Unit is at 75% RTP

Several banks of FWST heaters have failed "ON"

Current FWST temperature is 91°F

FWST temperature is rising at a rate of 0.5°F/min Based on the conditions above, FWST temperature will reach the T.S. 3.5.4 (Refueling Water Storage Tank (RWST)) limit in a MINIMUM of _____(1)_____

minutes.

Normally, Group 1 FWST heaters cycle automatically to maintain FWST temperature greater than T.S. 3.5.4 MINIMUM of _____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. 10

2. 65°F B. 1. 10

2. 70°F C. 1. 18

2. 65°F D. 1. 18

2. 70°F Page 31 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 32 (1 point)

Given the following Unit 1 timeline:

1000

A load rejection resulted in a reactor trip from 100% RTP

Following the trip, a Pressurizer Safety valve opens, and will NOT reseat

The PRT rupture disks function as designed

Containment pressure is 0.1 psig and rising at 0.03 psig every 5 minutes

Lower Containment temperature is 110°F and rising at 2°F every 5 minutes Assuming these conditions remain constant, and concerning only the application of LCOs 3.6.4 and 3.6.5 Plant conditions will FIRST require entry into LCO _____(1)_____ .

At 1030, conditions for entry into _____(2)_____ will be met.

Which ONE of the following correctly completes the statements above?

LEGEND:

LCO 3.6.4 (Containment Pressure)

LCO 3.6.5 (Containment Air Temperature)

A. 1. 3.6.4

2. 3.6.4 ONLY B. 1. 3.6.4

2. 3.6.4 AND 3.6.5 C. 1. 3.6.5

2. 3.6.5 ONLY D. 1. 3.6.5

2. 3.6.4 AND 3.6.5 Page 32 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 33 (1 point)

A LOCA has occurred on Unit 1 at Time = 0 minutes. Given the following containment pressure trend:

At Time = 3 minutes, the PRT _____(1)_____ be cooled using the NCDT Heat Exchanger.

At Time = 3 minutes, the PRT _____(2)_____ be cooled using spray flow from the RMWST.

Which ONE of the following correctly completes the statements above?

A. 1. can

2. can B. 1. can

2. can NOT C. 1. can NOT

2. can D. 1. can NOT

2. can NOT Page 33 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 34 (1 point)

Unit 1 is in Mode 3 when the following alarm is received:

1AD-6, E/1 (NCP A Thermal Barrier KC Outlet Hi/Lo Flow)

The flow trend is given below:

(1) At what time on the above graph did 1KC-394A (NC Pump 1A Therm Bar Otlt) automatically close?

(2) If the NCP 1A thermal barrier cannot be isolated from the KC System by any means, how is over pressurization of the KC surge tanks prevented?

A. 1. 100 seconds

2. The KC surge tanks vent line is large enough to prevent over pressurization.

B. 1. 130 seconds

2. The KC surge tanks vent line is large enough to prevent over pressurization.

C. 1. 100 seconds

2. The KC surge tanks relief valve to the KC drain sump is large enough to prevent over pressurization.

D. 1. 130 seconds

2. The KC surge tanks relief valve to the KC drain sump is large enough to prevent over pressurization.

Page 34 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 35 (1 point)

Given the following Unit 1 conditions:

The crew has entered AP/1/A/5500/017 (Loss of Control Room) due to a Security Event

Transfer to the SSF has been completed Based on the conditions above, NC System Pressure control will be accomplished via use of PZR Heater Group _____(1)_____ which will be powered from _____(2)_____.

Which ONE of the following correctly completes the statement above?

A. 1. A

2. 1LXH B. 1. A

2. SMXG C. 1. D

2. 1LXH D. 1. D

2. SMXG Page 35 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 36 (1 point)

Given the following Unit 1 conditions:

Unit is at 100% RTP

A slight cooldown of the NC system causes the "C" PZR heaters to be full "on"

A malfunction of two PZR pressure transmitters causes an Alternate Action to occur on the Pressurizer Pressure Control System Assuming NO operator actions:

The PZR Pressure Master will be in _____(1)_____ control AND C Heaters

_____(2)_____ be energized.

Which ONE of the following correctly completes the statement above?

A. 1. Manual

2. will B. 1. Manual

2. will NOT C. 1. Automatic

2. will D. 1. Automatic

2. will NOT Page 36 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 37 (1 point)

Given the following Unit 1 conditions:

Reactor startup is in progress

The permissive P-6 status light on 1SI-18 has just LIT

Reactor power is rising In accordance with PT/0/A/4150/019 (1/M Approach to Criticality), the operator will manually block the _____(1)_____ high flux reactor trip. Following this, the reactor trip setpoint for high flux is _____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. Source Range

2. 10%

B. 1. Source Range

2. 25%

C. 1. Intermediate Range

2. 10%

D. 1. Intermediate Range

2. 25%

Page 37 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 38 (1 point)

Given the following initial conditions:

Both units are at 100% RTP Subsequently:

An inadvertent 1A Train Safety Injection occurs As a result of this event and assuming no operator actions:

The 1B Aux Building Unfiltered Exhaust Fan (ABUFXF) _____(1)_____

secured.

The 2A Aux Building Unfiltered Exhaust Fan (ABUFXF) _____(2)_____

secured.

Which ONE of the following correctly 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 38 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 39 (1 point)

Concerning operation of the Containment Ventilation Units:

Under normal conditions, Containment Ventilation Units are cooled by the

_____(1)_____ system.

Containment Ventilation cooling water supply is isolated by a _____(2)_____

signal.

Which ONE of the following correctly completes the statements above?

A. 1. YV

2. Phase A B. 1. YV

2. Phase B C. 1. RN

2. Phase A D. 1. RN

2. Phase B Page 39 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 40 (1 point)

Given the following Unit 1 conditions:

Operators are performing Aux Safeguards testing

A spurious automatic signal caused 1NF-233B (Containment Return Isolation) to inadvertently close during the testing 1NF-233B was closed by an inadvertent _____(1)_____ signal.

The glycol expansion tank _____(2)_____ overflow inside containment.

Which ONE of the following correctly completes the statements above?

A. 1. ST

2. will NOT B. 1. SP

2. will NOT C. 1. ST

2. will D. 1. SP

2. will Page 40 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 41 (1 point)

Given the following Unit 1 conditions:

Unit is in Mode 4

It has been determined that eight Ice Condenser Intermediate Deck doors will not open due to excessive ice buildup Based on the conditions listed above, peak pressure following a LOCA will be reached _____(1)_____ than normal.

Tech Spec 3.6.13 (Ice Condenser Doors) _____(2)_____ applicable.

Which ONE of the following correctly completes the statements above?

A. 1. sooner

2. is B. 1. later

2. is C. 1. sooner

2. is NOT D. 1. later

2. is NOT Page 41 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 42 (1 point)

Given the following Unit 1 conditions:

The crew is performing EP/1/A/5000/ES-1.3 (Transfer To Cold Leg Recirculation)

Containment Spray (NS) has been aligned for recirculation

Containment pressure is 3.2 PSIG and rising slowly ES-1.3 will require starting _____(1)_____ NS pump(s).

Based on the conditions above, if a loss of NS flow occurs, a Containment ORANGE path _____(2)_____ occur.

Which ONE of the following correctly completes the statements above?

A. 1. both

2. will B. 1. ONLY one

2. will C. 1. both

2. will NOT D. 1. ONLY one

2. will NOT Page 42 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 43 (1 point)

Given the following Unit 1 timeline:

0800 Reactor trip and Safety Injection initiated due to large break LOCA 0845 Crew enters EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation)

Containment pressure is currently 3.0 psig and rising at 0.8 psig / min

Crew is unable to align either Containment Spray pump for recirculation per Enclosure 2 (Aligning NS for Recirculation)

In accordance with EP/1/A/5000/FR-Z.1 (Response to High Containment Pressure), the earliest time that the crew will align ND Spray is __________ .

Which ONE of the following correctly completes the statement above?

A. 0845 B. 0850 C. 0900 D. 0930 Page 43 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 44 (1 point)

Given the following Unit 1 initial conditions:

The Unit is at 63% RTP following a refueling outage

AP/1/A/5500/028 (Secondary Steam Leak) has been entered following the discovery of a leak on the Unit 1 Main Turbine Crossover line Subsequently:

The Unit 1 Main Turbine is tripped to isolate the leak At this time, _____(1)_____ steam dumps will operate to control main steam pressure at approximately _____(2)_____ psig.

Which ONE of the following correctly completes the statement above?

A. 1. ONLY condenser

2. 1085 B. 1. ONLY condenser

2. 1115 C. 1. condenser AND atmospheric

2. 1085 D. 1. condenser AND atmospheric

2. 1115 Page 44 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 45 (1 point)

Given the following Unit 1 conditions:

Following a refueling outage, the operating crew began a power escalation

Due to chemistry concerns, the unit has been placed in hold at 65%

A tube leak has developed in 1A S/G In accordance with CSD-CP-CNS-0020 (CNS Primary to Secondary Leak Rate Monitoring Program), leak rate monitoring will be based on readings obtained from __________ .

Which ONE of the following correctly completes the statement above?

COMPONENT LEGEND:

1EMF-29 (Steam Line 1A) 1EMF-33 (Condenser Air Ejector Exhaust) 1EMF-71 (S/G A Leakage)

A. 1EMF-29 ONLY B. 1EMF-71 ONLY C. 1EMF-33 AND 1EMF-29 D. 1EMF-33 AND 1EMF-71 Page 45 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 46 (1 point)

Given the following Unit 1 conditions:

The Unit is at 12% RTP and rising DCS will maintain S/G Level Control for each S/G in the LO Power mode until a MAXIMUM Selected CF Flow of _____(1)_____ is reached on each S/G.

With DCS in the LO Power mode, the CF Control Valves will start to OPEN when the CF Control Bypass Valves demand signal reaches a MINIMUM of

_____(2)_____.

Which ONE of the following correctly completes the statements above?

A. 1. 17%

2. 55%

B. 1. 17%

2. 65%

C. 1. 20%

2. 55%

D. 1. 20%

2. 65%

Page 46 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 47 (1 point)

Given the following Unit 1 conditions:

The unit was at 100% RTP when a reactor trip occurred

Reactor Trip Breaker 1B failed to open

All S/G Narrow Range levels are OFF-Scale LOW In order to meet secondary heat sink requirements CA flow must be greater than a MINIMUM value of _____(1)_____ GPM With regard to core age, more decay heat will be generated following a reactor trip at the _____(2)_____ of core life.

Which ONE of the following correctly completes the statements above?

A. 1. 1000

2. beginning B. 1. 1000

2. end C. 1. 450

2. beginning D. 1. 450

2. end Page 47 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 48 (1 point)

Given the following Unit 1 conditions:

Unit is at 100% RTP

1B Transformer Loss of Cooler Power results in a Zone B Lockout The 1B NCP supply breaker is located on the _____(1)_____ side of 1TB Switchgear.

Following the Zone B Lockout, the 1B NCP _____(2)_____ continue to operate.

Which ONE of the following correctly completes the statements above?

A. 1. long

2. will B. 1. long

2. will NOT C. 1. short

2. will D. 1. short

2. will NOT Page 48 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 49 (1 point)

Given the following Unit 1 conditions:

1KXIB has experienced a complete loss of DC input voltage

Stable power is restored two (2) minutes later Based on the conditions above, An indication used to determine that the backup power supply has been aligned is the

_____(1)_____ light LIT.

When 1KXIB loss of voltage condition clears, the normal power supply

_____(2)_____ be automatically realigned.

Which ONE of the following correctly completes the statements above?

A. 1. 1KXMB In Sync

2. will NOT B. 1. 1KXMB In Sync

2. will C. 1. 1KXAB Alternate AC Source Supplying Load

2. will NOT D. 1. 1KXAB Alternate AC Source Supplying Load

2. will Page 49 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 50 (1 point)

Concerning operation of the Emergency Diesel Generators:

In accordance with OP/1/A/6350/002 (Diesel Generator Operation), an inspection for water accumulation in the 1A D/G is performed by opening

_____(1)_____ . This inspection is performed _____(2)_____ D/G operational testing.

Which ONE of the following correctly completes the statements above?

A. 1. Cylinder indicator cocks 1L - 8L and 1R - 8R

2. prior to B. 1. Cylinder indicator cocks 1L - 8L and 1R - 8R

2. following C. 1. 1ZD-1 (1A D/G Eng Crankcase Vent Drip Leg Drain)

2. prior to D. 1. 1ZD-1 (1A D/G Eng Crankcase Vent Drip Leg Drain)

2. following Page 50 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 51 (1 point)

Given the following Unit 2 initial conditions:

Unit was operating at 100% RTP

A containment air release (VQ) was in progress Subsequently:

A LOCA occurs

B Train safety injection failed to actuate and was performed manually when it was recognized by the crew

The following indications are noted for:

o Containment pressure o 2EMF-36 (Unit Vent Gas Monitor) o 2EMF-39 (Containment Gas Monitor) o E/S Load Sequencers status lights Time 0200 0201 0202 0203 Containment pressure (psig) 0.5 1.1 1.4 1.8 2EMF-36 Trip 2 Light LIT LIT LIT LIT 2EMF-39 Trip 2 Light DARK LIT LIT LIT E/S LOAD SEQ ACTUATED DARK DARK LIT LIT TRAIN A status light E/S LOAD SEQ ACTUATED DARK DARK DARK LIT TRAIN B status light Based on the above indications and conditions, what is the earliest time that an operator can be assured that 2VQ-3B (VQ Fan Suct From Cont Isol) has received a close signal?

A. 0200 B. 0201 C. 0202 D. 0203 Page 51 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 52 (1 point)

Given the following Unit 1 conditions:

A Large Break LOCA has occurred

The crew is performing EP/1/A/5000/ES-1.3 (Transfer To Cold Leg Recirculation)

The BOP is instructed to align NS for recirc per Enclosure 2 (Aligning NS for Recirculation)

RN flow through the NS Heat Exchanger will be aligned when/if Containment pressure reaches a MINIMUM of _____(1)_____ .

Once aligned, a CAUTION in ES-1.3 states that RN flow shall not exceed a MAXIMUM of _____(2)_____ to prevent damage to the NS Heat Exchanger tubes.

Which ONE of the following correctly completes the statements above?

A. 1. 1 psig

2. 5700 GPM B. 1. 1 psig

2. 4650 GPM C. 1. 3 psig

2. 5700 GPM D. 1. 3 psig

2. 4650 GPM Page 52 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 53 (1 point)

Given the following conditions:

Unit 1 is in Mode 5

Unit 2 is at 100% RTP

1A train of ND is in service

Both units enter AP/0/A/5500/022 (Loss of Instrument Air) following a VI pipe rupture Per AP/22:

Once positioned per procedure, 1NI-173A (ND Hdr 1A To Cold Legs C&D) will be throttled _____(1)_____ if NC temperature begins to rise.

Unit 2 Reactor Trip will be required at a MAXIMUM lowering VI pressure of

_____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. OPEN

2. 55 psig B. 1. CLOSED

2. 55 psig C. 1. OPEN

2. 76 psig D. 1. CLOSED

2. 76 psig Page 53 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 54 (1 point)

Given the following Unit 1 conditions:

Unit is at 100% RTP

A steam break occurred on the Main Steam Equalization Header

Train 1B Safety Injection failed to automatically actuate Assuming no operator action:

Phase A (St) isolation has been initiated on train _____(1)_____.

Phase B (Sp) isolation _____(2)_____ been initiated.

Which one of the following correctly completes the statements above?

A. 1. 1A ONLY

2. has B. 1. 1A ONLY

2. has NOT C. 1. 1A AND 1B

2. has D. 1. 1A AND 1B

2. has NOT Page 54 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 55 (1 point)

Given the following Unit 1 conditions:

A rapid downpower is in progress due to a secondary steam leak inside Containment

1A, 1B, and 1D Lower Containment Vent Units (LCVU) are in operation

Current Unit 1 Containment pressure is 0.58 psig and rising slowly Assuming no operator action, 1RN-473 (LCVU A Full Flow Valve) _____(1)_____ currently open.

1A LCVU _____(2)_____ operating in Hi Speed.

Which ONE of the following correctly 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 55 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 56 (1 point)

Concerning Reactor Trip Breaker 1B:

The Undervoltage coil receives power auctioneered from _____(1)_____ and 1ERPD and is _____(2)_____ to actuate.

Which ONE of the following correctly completes the statement above?

A. 1. 1ERPB

2. energized B. 1. 1ERPB

2. de-energized C. 1. 1ERPC

2. energized D. 1. 1ERPC

2. de-energized Page 56 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 57 (1 point)

Concerning the Pressurizer Cold Cal Channel:

The Pressurizer level Cold Calibrated Channel is calibrated for

_____(1)_____. This channel _____(2)_____ a required safety related indication.

Which ONE of the following correctly completes the statements above?

A. 1. 100°F

2. is B. 1. 100°F

2. is NOT C. 1. 120°F

2. is D. 1. 120°F

2. is NOT Page 57 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 58 (1 point)

Given the following Unit 1 initial conditions:

Unit is at 12% RTP following startup

Required actions for being greater than P-10 have been taken Subsequently:

1ERPA de-energizes As a result of this failure:

Power Range detector N-41 will lose _____(1)_____.

The crew will FIRST enter _____(2)_____.

Which ONE of the following correctly completes the statements above?

A. 1. control power ONLY

2. EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

B. 1. control power ONLY

2. AP/1/A/5500/016 (Malfunction of Nuclear Instrumentation)

C. 1. control and instrument power

2. EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

D. 1. control and instrument power

2. AP/1/A/5500/016 (Malfunction of Nuclear Instrumentation)

Page 58 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 59 (1 point)

Given the following Unit 1 conditions:

A Shift Maintenance Technician performing Reactor Building rounds reports that the Ice Condenser Inlet Door Positioning Monitor System panel has no indicating lights lit Which one of the following is the minimum action required to maintain compliance with SLC 16.6-3 Inlet Door Position Monitoring System?

A. Immediately verify the ice bed temperature is less than or equal to 27 °F B. Immediately verify the Ice Bed Temperature Monitoring System is Functional C. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months verify the ice bed temperature is less than or equal to 27 °F D. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months verify the Ice Bed Temperature Monitoring System is Functional Page 59 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 60 (1 point)

Given the following Unit 1 conditions:

A Design Basis Large Break LOCA has occurred combined with a loss of core cooling event

Reactor Engineering calculates cladding temperature to be approximately 2400 °F Based on given conditions, the largest contributor to hydrogen buildup in containment is _____(1)_____ .

Per OP/1/A/6450/010 (Containment Hydrogen Control Systems) Technical Support Center (TSC) approval will be required, to place Hydrogen Recombiners in service, if Hydrogen concentration exceeds a MINIMUM of

_____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. Zirc-Water reaction in core region

2. 4%

B. 1. Zirc-Water reaction in core region

2. 6%

C. 1. Dissolved hydrogen in the NC System

2. 4%

D. 1. Dissolved hydrogen in the NC System

2. 6%

Page 60 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 61 (1 point)

Given the following Unit 1 timeline:

1000

The Unit has experienced a runback, from 100% power, following a trip of 1A CFPT 1003

Main Turbine target load has been reached

1AD-2 A/9 (Control Rod Bank Lo Limit) illuminates 1005

1AD-2 B/9 (Control Rod Bank Lo-Lo Limit) illuminates

Steam Dumps have closed

Temperature Error meter indicates (+) 1.8° F Entry into the Action Statement of Tech Spec 3.1.6 (Control Bank Insertion Limits) is FIRST required at _____(1)_____ .

In accordance with the conditions provided at 1005, OMP 1-7 (Emergency /

Abnormal Procedure Implementation Guidelines) _____(2)_____ state that control rods should be placed in MANUAL.

Which ONE of the following correctly completes the statements above?

A. 1. 1003

2. does B. 1. 1003

2. does NOT C. 1. 1005

2. does D. 1. 1005

2. does NOT Page 61 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 62 (1 point)

Given the following Unit 1 conditions:

The Unit 1 is at 100% RTP

Main Condenser Vacuum is lowering due to CSAE malfunction

The crew has entered AP/1/A/5500/023 (Loss of Condenser Vacuum)

In accordance with AP/23:

A turbine load reduction _____(1)_____ be effective.

As vacuum lowers, the OATC will trip the reactor once it is imminent that vacuum, in any main condenser, will reach a MAXIMUM value of

_____(2)_____.

Which ONE of the following correctly completes the statements above?

A. 1. will

2. 24.3 in Hg B. 1. will

2. 22 in Hg C. 1. will NOT

2. 24.3 in Hg D. 1. will NOT

2. 22 in Hg Page 62 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 63 (1 point)

Concerning area monitors 1EMF-18 and 1EMF-19 (Reactor Coolant Filter A and B):

1EMF-18 and 1EMF-19_____(1)_____ required by Tech Specs, and

_____(2)_____ listed as symptoms for entry into AP/1/A/5500/018 (High Activity in Reactor Coolant).

Which ONE of the following correctly completes the statement above?

A. 1. are

2. are B. 1. are

2. are NOT C. 1. are NOT

2. are D. 1. are NOT

2. are NOT Page 63 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 64 (1 point)

Given the following initial conditions:

Units 1 & 2 are at 100% RTP

1A RN pump is in service Subsequently:

The following Unit 1 annunciators are lit o 1AD-12 B/2 RN PIT A Screen Hi D/P o 1AD-12 B/1 RN Pump Intake Pit A Level - LO o 1AD-12 E/2 RN Pit A Swap to SNSWP Based on this event:

_____(1)_____ will automatically close.

1B RN Pump _____(2)_____ automatically start.

Which ONE of the following correctly completes the statements above?

A. 1. 1RN-47A (RN Supply X-Over Isol)

2. will B. 1. 1RN-47A (RN Supply X-Over Isol)

2. will NOT C. 1. 1RN-48B (RN Supply X-Over Isol)

2. will D. 1. 1RN-48B (RN Supply X-Over Isol)

2. will NOT Page 64 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 65 (1 point)

Given the following Unit 1 conditions:

The Fire Protection (RF) system heat sensitive element located at Unit 1 Main Turbine Bearing #8 has failed open As a result of this malfunction, RF discharge flow to the Main Turbine Bearing

8 _____(1)_____ initiate.

The purpose of the Main Turbine portion of the Fire Protection system is to engulf turbine bearings with a large quantity of _____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. will

2. water B. 1. will

2. foam extinguishing agent C. 1. will NOT

2. water D. 1. will NOT

2. foam extinguishing agent Page 65 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 66 (1 point)

Given the following conditions:

A clarification related to EAL classification needs to be communicated to all licensed SROs via Standing Instruction and has been prepared by a member of the Emergency Planning group In accordance with AD-OP-ALL-0111 (Operations Communications):

This Standing Instruction _____(1)_____ be approved by another member of the Emergency Planning group..

Non-impacted operators (i.e. AOs) _____(2)_____ be exempted from documented review of this Standing Instruction Which ONE of the following correctly completes the statements above?

A. 1. can

2. can B. 1. can NOT

2. can C. 1. can

2. can NOT D. 1. can NOT

2. can NOT Page 66 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 67 (1 point)

Given the following conditions:

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 In accordance with AD-OP-ALL-0203 (Reactivity Management):

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

An additional Reactor Operator _____(2)_____ required to peer check control rod manipulations performed by the ILT student.

Which ONE of the following correctly 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 67 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 68 (1 point)

Given the following Unit 1 conditions:

A Unit startup is in progress in accordance with OP/1/A/6100/001 (Controlling Procedure for Unit Startup)

Auxiliary Steam (AS) from Unit 2 is being used for turbine warming

NC system pressure is 2235 psig

Steam dumps are controlling NC Tavg at 557ºF

The crew is preparing to restore AS to a normal alignment by closing 1AS-4, (Main Steam to AS HDR CTRL Bypass)

Operation of 1AS-4 is performed _____(1)_____ the Control Room.

In accordance with AD-OP-ALL-0203, (Reactivity Management), the Unit startup will require a dedicated _____(2)_____ with no concurrent duties.

Which ONE of the following correctly completes the statements above?

A. 1. outside

2. RO AND SRO B. 1. inside

2. RO AND SRO C. 1. outside

2. RO ONLY D. 1. inside

2. RO ONLY Page 68 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 69 (1 point)

Concerning Tech Spec 2.1.1 (Reactor Core SLs):

The peak centerline fuel temperature shall be maintained less than

_____(1)_____ .

This limit _____(2)_____ change over core life.

Which ONE of the following correctly completes the statements above?

A. 1. 2200°F

2. does B. 1. 2200°F

2. does NOT C. 1. 5080°F

2. does D. 1. 5080°F

2. does NOT Page 69 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 70 (1 point)

Given the following Unit 2 conditions:

Maintenance is performing a calibration of Pressurizer Pressure Channel 1

A technician has requested the Unit 2 BOP delete an OAC alarm per the associated IP procedure In accordance with AD-OP-ALL-1000 (Conduct of Operations):

The deleted OAC alarm _____(1)_____ required to be logged in eSOMS.

An audit of deleted computer alarms is required ____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. is

2. weekly B. 1. is

2. monthly C. 1. is NOT

2. weekly D. 1. is NOT

2. monthly Page 70 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 71 (1 point)

Given the following:

A General Emergency has been declared

A mission to protect valuable property is required In accordance with AD-EP-ALL-0205 (Emergency Exposure Controls):

The limit associated with this emergency exposure is _____(1)_____ and the worker _____(2)_____ required to be a volunteer.

Which ONE of the following correctly completes the statement above?

A. 1. 5 Rem

2. is B. 1. 5 Rem

2. is NOT C. 1. 10 Rem 2 is D. 1 10 Rem 2 is NOT Page 71 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 72 (1 point)

Given the following Unit 1 conditions:

An Operator is performing a valve lineup in the Unit 1 Auxiliary Building

While working in the area, the Operator receives a Dose Rate alarm on his Electronic Dosimeter (ED)

After a few seconds, the Dose Rate alarm automatically clears

The possibility of a Dose Rate alarm was NOT discussed during the RP brief In accordance with PD-RP-ALL-0001 (Radiation Worker Responsibilities):

the Operator _____(1)_____ .

if the Operator receives a Dose alarm, the alarm _____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. must stop work, exit the area, and notify RP immediately

2. will not clear until the ED is reset B. 1. must stop work, exit the area, and notify RP immediately

2. will automatically clear after 10 seconds C. 1. may continue to work unless two additional dose rate alarms are received

2. will not clear until the ED is reset D. 1. may continue to work unless two additional dose rate alarms are received

2. will automatically clear after 10 seconds Page 72 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 73 (1 point)

During an emergency event:

The MINIMUM level of emergency classification that ALWAYS requires activation of the OSC, TSC, and EOF is a _____(1)_____.

The MINIMUM level of emergency classification that ALWAYS requires an evacuation of all non-essential personnel from the site is a _____(2)_____.

Which ONE of the following correctly completes the statements above?

A. 1. Alert

2. Site Area Emergency B. 1. Alert

2. General Emergency C. 1. Unusual Event

2. Site Area Emergency D. 1. Unusual Event

2. General Emergency Page 73 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 74 (1 point)

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. Source Range B. Intermediate Range C. Power Range D. Wide Range Page 74 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 75 (1 point)

Given the following Unit 1 initial conditions:

Unit is cooling down for a refueling outage

NC Thots are at 365ºF

NC pressure is 400 psig

All CLAs have been isolated Subsequently:

NC pressure and PZR level are steadily lowering

Containment pressure is rising

The crew enters AP/1/A/5500/027, (Shutdown LOCA) and maximizes charging and isolates letdown

Pressurizer level and pressure continue to lower In accordance with AP/27, the cooldown rate is required to be LESS THAN

_____(1)_____ in one hour.

In accordance with OP/1/A/6200/004, (Residual Heat Removal System), ND can be placed in RHR Mode once NC Thots are less than a MAXIMUM temperature of_____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. 100ºF

2. 350ºF B. 1. 80ºF

2. 350ºF C. 1. 100ºF

2. 300ºF D. 1. 80ºF

2. 300ºF Page 75 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 76 (1 point)

Given the following Unit 2 conditions:

Unit is at 100% RTP

A DCS malfunction causes the Selected Pressurizer Pressure 1 input to the Pressurizer Master Controller to fail HIGH

In accordance with AP/2/A/5500/011 (Pressurizer Pressure Anomalies) the BOP has manually closed 2NC-34A (PZR PORV) and 2NC-27 / 2NC-29 (Pressurizer Spray Valves)

The Pressurizer Pressure Master Controller is in MANUAL In accordance with Tech Spec 3.4.11 (Pressurizer Power Operated Relief Valves):

2NC-34A is required to operable in MODES _____(1)_____

2NC-34A _____(2)_____ currently OPERABLE.

Which ONE of the following correctly completes the statements above?

A. 1. 1-3

2. is B. 1. 1-3

2. is NOT C. 1. 1-4

2. is D. 1. 1-4

2. is NOT Page 76 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 77 (1 point)

Given the following Unit 2 initial conditions:

A SGTR has occurred on 2C S/G

Prior to initiating NC system cooldown, all NC pumps were stopped due to loss of subcooling Subsequently:

NC system cooldown and depressurization is COMPLETE

NC subcooling is 25°F

The crew has reached the step in EP/2/A/5000/E-3 (Steam Generator Tube Rupture) to check NCP status In accordance with the EOP background document for E-3, the principal reason for restarting an NC pump at this point in E-3 is to _____(1)_____ during the subsequent recovery.

In accordance with E-3, Enclosure 3 (NC Pump Start), the reason for checking Reactor Vessel Upper Range level prior to the NC pump start is to ensure sufficient inventory to _____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. reduce S/G tube thermal stress

2. accommodate void collapse B. 1. provide normal Pressurizer spray flow

2. accommodate void collapse C. 1. reduce S/G tube thermal stress

2. provide adequate NC pump NPSH D. 1. provide normal Pressurizer spray flow

2. provide adequate NC pump NPSH Page 77 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 78 (1 point)

Given the following Unit 1 conditions:

The crew has entered EP/1/A/5000/ECA-0.0 (Loss of All AC Power) following a loss of offsite power

Neither Diesel Generator started manually

1B D/G started upon Safety Injection initiation Following the start of 1B D/G, the CRS will transition to _____(1)_____.

AP/07 Enclosure 5 (Aligning Alternate Power to 1ETA) _____(2)_____ be used for 1ETA alternate power alignment.

Which ONE of the following correctly completes the statements above?

A. 1. EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

2. will NOT B. 1. EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

2. will C. 1. EP/1/A/5000/ES-1.1 (Safety Injection Termination)

2. will NOT D. 1. EP/1/A/5000/ES-1.1 (Safety Injection Termination)

2. will Page 78 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 79 (1 point)

Given the following Unit 1 conditions:

Unit is at 100% RTP

1ERPA has de-energized due to an inverter failure

The crew is preparing to re-energize 1ERPA via 1VRD per AP/1/A/5500/029 (Loss of Vital or Aux Control Power)

The power supply transfer required to re-align 1ERPA to 1VRD will be performed via a(n) _____(1)_____ .

Once 1ERPA is aligned to 1VRD, the crew _____(2)_____ exit the action statement of Tech Spec 3.8.7 (Inverters - Operating).

Which ONE of the following correctly completes the statements above?

A. 1. manual bypass switch

2. will B. 1. manual bypass switch

2. will NOT C. 1. automatic transfer switch

2. will D. 1. automatic transfer switch

2. will NOT Page 79 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 80 (1 point)

Given the following timeline:

1000

Unit 1 is at 100% RTP

Unit 2 is currently at 40% RTP and rising following refueling outage o 2ETA and 2ETB remain aligned to Unit 1

Unit 1 suffers a Loss of Offsite Power (LOOP)

1A D/G is the ONLY D/G in operation 1230

Crew disconnects Unit 2 Vital Batteries (per applicable procedure) due to decay of DC Bus voltage As a result of these events:

At time 1015, the correct EAL classification will be _____(1)_____.

At time 1245, the correct EAL classification will be _____(2)_____.

Which ONE of the following correctly completes the statements above?

REFERENCE PROVIDED A. 1. ALERT

2. SITE AREA EMERGENCY B. 1. ALERT

2. GENERAL EMERGENCY C. 1. SITE AREA EMERGENCY

2. SITE AREA EMERGENCY D. 1. SITE AREA EMERGENCY

2. GENERAL EMERGENCY Page 80 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 81 (1 point)

Given the following Unit 1 conditions:

The crew entered EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation) following a Large Break LOCA

While performing ES-1.3, the crew transitioned to EP/1/A/5000/ECA-1.1 (Loss of Emergency Coolant Recirc)

Containment pressure is currently 3.2 PSIG In accordance with ECA-1.1, while attempting to establish recirculation flow the crew will cool the core by _____(1)_____.

While performing ECA-1.1, if a RED Path occurs on Core Cooling the crew

_____(2)_____ transition to FR-C.1 (Response To Inadequate Core Cooling).

Which ONE of the following correctly completes the statements above?

A. 1. aligning the NC system for Bleed and Feed

2. will B. 1. aligning the NC system for Bleed and Feed

2. will NOT C. 1. dumping steam from intact Steam Generators

2. will D. 1. dumping steam from intact Steam Generators

2. will NOT Page 81 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 82 (1 point)

Unit 1 is operating at 98% power. PT/1/A/4600/001 (RCCA Movement Test) is in progress. As Control Bank D was being moved from 215 SWD to 205 SWD, one control rod in Control Bank D slipped to 120 SWD and stopped.

Below is an incore thermocouple map one minute later.

R P N M L K J H G F E D C B A 1 576 572 576 605 546 599 611 603 2

3 605 624 BAD 569 4 597 602 609 617 5 602 625 616 614 6 563 611 611 626 623 568 7 602 606 617 620 8 561 612 634 572 626 9 619 611 613 614 10 548 610 606 613 574 11 627 BAD 610 614 12 612 599 608 622 13 620 619 576 626 562 14 540 628 613 608 614 15 BAD 622 580 Rod _____(1)_____ is misaligned.

In order to continue Mode 1 operation, Tech. Spec. 3.1.4 (Rod Group Alignment Limits) will require a power reduction, SDM verification, and completion of _____(2)_____.

Which ONE of the following correctly completes the statements above?

A. 1. D-12

2. FNH(X,Y) surveillance ONLY B. 1. M-4

2. FNH(X,Y) surveillance ONLY C. 1. D-12

2. FNH(X,Y) AND FQ(X,Y,Z) surveillances D. 1. M-4

2. FNH(X,Y) AND FQ(X,Y,Z) surveillances Page 82 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 83 (1 point)

Given the following Unit 1 conditions:

Unit is at 50% RTP

An NC system leak has developed and is determined to be in the Pressurizer compartment

Per leak hunt guidelines, Engineering has requested the crew evaluate Pressurizer level instrumentation per PT/1/A/4600/002A (Mode 1 Periodic Surveillance Items) o Selected Tavg is 574°F o Pressurizer Level Channels indicate as follows:

Channel 1 - 44.8%

Channel 2 - 42.9%

Channel 3 - 40.8%

The crew will report Pressurizer Level Channel _____(1)_____ is inoperable, in accordance with PT/1/A/4600/002A.

In accordance with Tech Spec 3.3.1 Bases, three channels of pressurizer level (vs. four) are required because _____(2)_____ .

Which ONE of the following correctly completes the statements above?

REFERENCE PROVIDED A. 1. ONE

2. of the slow rate of charging that is available B. 1. ONE

2. pressurizer level does NOT provide a backup signal to any other reactor trips C. 1. THREE

2. of the slow rate of charging that is available D. 1. THREE

2. pressurizer level does NOT provide a backup signal to any other reactor trips Page 83 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 84 (1 point)

Given the following Unit 1 initial conditions:

The crew has begun a Reactor startup

Intermediate Range Channel N-35 begins to operate erratically

Reactor Power is stabilized at 10-6 % RTP

AP/1/A/5500/016 (Malfunction of Nuclear Instrumentation System) Case III (Intermediate Range Malfunction) is entered Subsequently:

Power remains stable at 10-6 % RTP

AP/16 actions are complete The 1/N-35A I/R CHANNEL 1 TRIP BYPASS status light on 1SI-19

_____(1)_____ LIT.

Per Tech Spec 3.3.1, (RTS Instrumentation), the startup to MODE 1

_____(2)_____ continue.

Which ONE of the following correctly completes the statements above?

A. 1. is

2. may B. 1. is

2. may NOT C. 1. is NOT

2. may D. 1. is NOT

2. may NOT Page 84 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 85 (1 point)

Given the following Unit 2 conditions:

An Auxiliary Operator has reported a hole in the wall represented by the X in the drawing below In accordance with SLC 16.9-5 (Fire Rated Assemblies):

A High Safety Significant (HSS) Fire Area _____(1)_____ impacted.

A Fire Watch will be established per Condition _____(2)_____ .

Which ONE of the following correctly completes the statements above?

REFERENCE PROVIDED A. 1. is

2. A B. 1. is

2. C C. 1. is NOT

2. A D. 1. is NOT

2. C Page 85 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 86 (1 point)

Given the following Unit 1 conditions:

The Unit is stable at 100% RTP

Operators are performing PT/1/A/4150/001 A (NC Pump Seal Injection Flow Verification)

1NV-294 is fully open

Seal Injection flow is 42 gpm and stable Based on the conditions above, the Action Statement of Tech Spec 3.5.5 (Seal Injection Flow) _____(1)_____ required to be entered.

In accordance with the Bases of Tech Spec 3.5.5, the Seal Injection Flow Limit

_____(2)_____ based on the safety analysis assumptions for minimum ECCS Injection flow.

Which ONE of the following correctly completes the statements above?

A. 1. is

2. is B. 1. is NOT

2. is C. 1. is

2. is NOT D. 1. is NOT

2. is NOT Page 86 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 87 (1 point)

Given the following Unit 2 conditions:

The Unit is at 100% RTP

A loss of 2ERPD has occurred

The crew has entered AP/2/A/5500/029 (Loss of Vital or Aux Control Power)

NO Tech Spec actions have been addressed The current Containment Pressure channel logic for the remaining Containment Pressure channels which will cause a Phase B actuation is _____(1)_____ .

In accordance with Tech Spec 3.3.2 (ESFAS Instrumentation), when the failed channel is removed from service, I&E will place the Containment Pressure Hi-Hi Bistable in _____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. 2/3

2. Trip B. 1. 2/3

2. Bypass C. 1. 1/3

2. Trip D. 1. 1/3

2. Bypass Page 87 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 88 (1 point)

Given the following Unit 1 conditions:

Unit is at 50% RTP

A failure of the IFE System (Steam Generator Water Level and Feedwater Pump Speed Control System) results in SG narrow range levels rising to 87%

In order to mitigate the above condition, the CRS will enter _____(1)_____ .

In accordance with T.S. 3.3.2 (ESFAS Instrumentation) Bases, feedwater isolation coincident with low Tavg is a function of the _____(2)_____ interlock.

Consider each statement separately Which ONE of the following correctly completes the statements above?

A. 1. EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

2. P-14 B. 1. AP/1/A/5500/002 (Turbine Generator Trip)

2. P-14 C. 1. EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

2. P-4 D. 1. AP/1/A/5500/002 (Turbine Generator Trip)

2. P-4 Page 88 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 89 (1 point)

Given the following Unit 2 conditions:

A loss of all offsite power (LOOP) occurred 20 minutes ago

2A D/G failed to start and remains shutdown

2B CA Pump will not start

#2 CAPT has tripped and cannot be restarted

All Unit 2 S/G levels are 13% and slowly lowering Based on the conditions above, this Shift Manager will classify this event as a/an _____(1)_____ .

Per AD-EP-ALL-0111 (Control Room Activation of the ERO), initial NRC notification will be performed via transmittal of _____(2)_____ .

Which ONE of the following correctly completes the statements above?

REFERENCE PROVIDED A. 1. Alert

2. Emergency Notification Form (ENF)

B. 1. Alert

2. NRC Form 361 (Reactor Plant Event Notification Worksheet)

C. 1. Site Area Emergency

2. Emergency Notification Form (ENF)

D. 1. Site Area Emergency

2. NRC Form 361 (Reactor Plant Event Notification Worksheet)

Page 89 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 90 (1 point)

Concerning operation of the Emergency Diesel Generator:

In accordance with OP/1/A/6350/002 (Diesel Generator Operation), the reason for not operating a D/G unloaded for a long period of time _____(1)_____ to prevent sludge buildup in the engine.

In accordance with TS 3.8.1 (AC Sources - Operating) Bases, the maximum loading limit for each D/G is _____(2)_____ KW for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

Which ONE of the following correctly completes the statements above?

A. 1. is

2. 7700 B. 1. is

2. 8750 C. 1. is NOT

2. 7700 D. 1. is NOT

2. 8750 Page 90 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 91 (1 point)

Given the following Unit 1 initial conditions:

Unit was at 100% RTP

The #1 CAPT is out-of-service for maintenance Subsequently:

The unit is manually tripped when both CF pumps trip

1A and 1B CA pumps fail to automatically start and cannot be started manually

The crew has implemented EP/1/A/5000/FR-H.1 (Response to Loss of Secondary Heat Sink)

SG WR level is 40% in all SGs In accordance with FR-H.1:

NC system Feed and Bleed must be initiated within a MAXIMUM of

_____(1)_____ minutes after reaching Feed and Bleed initiation criteria.

After Feed and Bleed is initiated, efforts to restore feedwater flow to the S/Gs

_____(2)_____ be terminated.

Which ONE of the following correctly completes the statements above?

A. 1. 8

2. MAY B. 1. 4

2. MAY C. 1. 8

2. MAY NOT D. 1. 4

2. MAY NOT Page 91 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 92 (1 point)

Given the following Unit 1 conditions:

The crew is performing PT/0/A/4150/019 (1/M Approach to Criticality)

All shutdown banks are fully withdrawn

Control Bank A rods are fully withdrawn

Control Bank B rods are being withdrawn Subsequently:

Control Bank B rod K14 drops

DRPI indication for rod K14:

o Rod position indication is 0 with RB indication below the rod

Demand position counter for Bank B Groups 1 & 2 indicates 114 steps In accordance with T.S. 3.1.7 (Rod Position Indication) Bases, LCO 3.1.7

_____(1)_____ met.

In accordance with PT/0/A/4150/019, the CRS will direct insertion of

_____(2)____.

Which ONE of the following correctly completes the statements above?

A. 1. is

2. all control banks ONLY B. 1. is NOT

2. all control banks ONLY C. 1. is

2. all control banks AND shutdown banks D. 1. is NOT

2. all control banks AND shutdown banks Page 92 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 93 (1 point)

Given the following Unit 1 initial conditions:

Unit is at 100% RTP

At 0900 a Large Break LOCA occurs

At 0910 the Shift Manager declares an Alert

Efforts to establish adequate Safety Injection flow to the core are unsuccessful

The crew has secured NCPs due to loss of subcooling Subsequently:

Core Exit Thermocouples and RVLIS level indications are as follows for the times listed Time CETC RVLIS 0930 650° - Rising 50% - lowering 0945 720° - Rising 46% - lowering 1000 770° - Rising 41% - lowering 1015 790° - Rising 38% - lowering The Shift Manager re-evaluated EALs at 0945 and is evaluating again at 1010.

At time 0945, EAL upgrade criteria _____(1)_____ met.

At time 1015, the Shift Manager _____(2)_____ declare a General Emergency.

Which ONE of the following correctly completes the statements above?

REFERENCE PROVIDED A. 1. is

2. will B. 1. is

2. will NOT C. 1. is NOT

2. will D. 1. is NOT

2. will NOT Page 93 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 94 (1 point)

In accordance with AD-OP-ALL-1001, (Conduct of Abnormal Operations), regarding 10 CFR 50.54 (x) Deviations:

the SRO approving the Deviation _____(1)_____ required to obtain concurrence from a second SRO prior to taking the action.

the NRC Operations Center must be notified within a maximum time of

_____(2)_____ after taking the action.

Which ONE of the following correctly completes the statements above?

A. 1. is

2. 1 HOUR B. 1. is

2. 15 minutes C. 1. is NOT

2. 1 HOUR D. 1. is NOT

2. 15 minutes Page 94 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 95 (1 point)

Given the following unit 2 conditions:

The unit is at 100% RTP

It is determined that some S/G Safety Valve test results were incorrectly recorded during the previous refueling outage

The following indicates the correct S/G Safety Valve lift setpoints:

Lift Press Lift Press Lift Press Lift Press Safety Safety Safety Safety (psig) (psig) (psig) (psig) 2SV-20 1185 2SV-14 1178 2SV-8 1165 2SV-2 1213 2SV-21 1228 2SV-15 1201 2SV-9 1183 2SV-3 1190 2SV-22 1245 2SV-16 1212 2SV-10 1244 2SV-4 1208 2SV-23 1222 2SV-17 1260 2SV-11 1225 2SV-5 1222 2SV-24 1241 2SV-18 1233 2SV-12 1238 2SV-6 1273 Based on the conditions above, Rated Thermal Power is limited to a MAXIMUM of _____(1)_____ .

Per 3.7.1 (Main Steam Safety Valves) bases, the most limiting Anticipated Operational Occurrence (AOO) is a _____(2)_____ .

Which ONE of the following correctly completes the statements above?

REFERENCE PROVIDED A. 1. 24%

2. full power turbine trip without steam dump operation B. 1. 24%

2. steam generator tube rupture C. 1. 41%

2. full power turbine trip without steam dump operation D. 1. 41%

2. steam generator tube rupture Page 95 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 96 (1 point)

In accordance with AD-OP-ALL-200 (Clearance and Tagging):

a previously licensed SRO _____(1)_____ sign as clearance APPROVER.

if a clearance is designated as an Exceptional Clearance, Shift Manager permission _____(2)_____ required for approval.

Which ONE of the following correctly completes the statements above?

A. 1. can

2. is B. 1. can

2. is NOT C. 1. can NOT

2. is D. 1. can NOT

2. is NOT Page 96 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 97 (1 point)

In accordance with AD-WC-ALL-0420 (Shutdown Risk Management) and AD-WC-ALL-0340 (Outage Schedule Development and Revision Process):

defense in Depth (DID) sheets are first REQUIRED for risk management once

_____(1)_____ is reached during the shutdown.

the Plant Condition Mode Change (PCMC) reports _____(2)_____ intended to track operability of structures, systems, or components (SSC) required by Technical Specifications (TS) or Selected License Commitments (SLC).

Which ONE of the following correctly completes the statements above?

A. 1. Mode 3

2. are NOT B. 1. Mode 3

2. are C. 1. Mode 4

2. are NOT D. 1. Mode 4

2. are Page 97 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 98 (1 point)

Given the following conditions:

A release, of AMT A, is being prepared from the Monitor Tank Building utilizing 0EMF-57 as the monitor OP/0/B/6500/060 (Discharge of an AMT to the Environment) _____(1)_____

require alignment of RN to the RL header.

Per SLC 16.11-4 (Liquid Radwaste Treatment System), the Liquid Radwaste Treatment System shall be demonstrated Functional by meeting

_____(2)_____ .

Which ONE of the following correctly completes the statements above?

A. 1. does

2. SLC 16.11-1 (Liquid Effluents) AND 16.11-3 (Dose)

B. 1. does NOT

2. SLC 16.11-1 (Liquid Effluents) AND 16.11-3 (Dose)

C. 1. does

2. SLC 16.11-1 (Liquid Effluents) ONLY D. 1. does NOT

2. SLC 16.11-1 (Liquid Effluents) ONLY Page 98 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 99 (1 point)

Given the following Unit 1 conditions:

Unit is in Mode 3 following a refueling outage

The status of the Personnel Air Locks (PAL) is as follows:

o Upper Airlock Inner Door Operable o Upper Airlock Outer Door Operable o Lower Airlock Inner Door Inoperable o Lower Airlock Outer Door Operable

Repairs required are on the barrel (airlock side of the inner door)

The guidance for Containment entry, to repair the Lower Airlock Door, is contained in _____(1)_____ .

The Lower Airlock Outer Door _____(2)_____ be opened to make the repair.

Which ONE of the following correctly completes the statements above?

A. 1. Tech. Spec. 3.6.2, (Containment Air Locks)

2. may B. 1. Tech. Spec. 3.6.2, (Containment Air Locks)

2. may NOT C. 1. Site Directive 3.1.2, (Access to Reactor Building and Areas Having High Pressure Steam Relief Devices)

2. may D. 1. Site Directive 3.1.2, (Access to Reactor Building and Areas Having High Pressure Steam Relief Devices)

2. may NOT Page 99 of 100

Catawba Nuclear Station ILT 21 CNS SRO NRC Examination Question: 100 (1 point)

Given the following Unit 1 conditions:

Unit is responding to a main steam line break inside containment

The operators completed E-0 (Reactor Trip and Safety Injection) and transitioned to EP/1/A/5000/E-2 (Faulted Steam Generator Isolation)

A RED PATH on Containment Integrity occurred and the operators transitioned to EP/1/A/5000/FR-Z.1 (Response to High Containment Pressure) at Step 8 of E-2

A RED PATH on NC Integrity occurred and the operators transitioned to EP/1/A/5000/FR-P.1 (Response to Imminent Pressurized Thermal Shock Condition) from Step 4 of FR-Z.1 Following a completion of FR-P.1 and a report from the STA that all CSFs are now GREEN, what is the correct procedure transition?

A. Return to E-2 Step 1 and continue.

B. Return to E-2 step 8 and continue.

C. Return to FR-Z.1 Step 4 and complete the procedure, then return to E-2 step 8.

D. Enter EP/1/A/5000/ES-0.0 (Rediagnosis) and use guidance for procedure entry.

Page 100 of 100

WRITTEN EXAM REFERENCE PACKAGE CONTENTS EXAM ID: CNS ILT 21 NRC Exam (SRO) 1 CNS ROD Book Section 2.6 2 CNS Unit 1 Data Book Figure 57 (Reactor Coolant Saturation Curve, Wide Range) 3 PT/1/A/4600/002A, Rev. 234, Encl. 13.1, Page 11 of 37 4 SLC 16.9-5 (Fire Rated Assemblies) 5 Tech Spec. 3.7.1 Table 3.7.1-1 & 3.7.1-2 6 CSD-EP-CNS-0101-02 (EAL Wall Charts) 7 Steam Tables 8 Mollier Diagram

UNIT ONE Source: CNEI-0400-361 Prepared by: MW Hawes REACTOR OPERATING DATA Revision Number: 870 SECTION 2.6 Date: 5/25/20 MINIMUM NC TEMPERATURE FOR 1.3% SHUTDOWN MARGIN FOLLOWING REACTOR TRIP

Unit 1 Data Book Source: OAC Reactor Coolant Saturation Calculations 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 NC System Pressure (psig) 1500 Subcooled Region 1400 1300 1200 1100 1000 900 800 700 600 500 Superheated Region 400 300 200 100 0

200 250 300 350 400 450 500 550 600 650 700 NC System Temperature (Deg F)

Rev. 2, 4/5/2002 Figure 57 - Reactor Coolant Saturation Curve, Wide Range Page 61

Enclosure 13.1 PT/1/A/4600/002 A Periodic Surveillance Items Data Page 11 of 37 SURVEILLANCE ITEM QUALIFYING COMPUTER POINT/ DAY SHIFT NIGHT SHIFT

ACCEPTANCE CRITERIA (Tech Spec Reference) CONDITIONS GAUGE ID INITIALS INITIALS 21 PZR Water Level Monitor Level differential between highest C1A0707 Channel Check and lowest channels < 3.5%. C1A0867 (SR 3.3.1.1, Table 3.3.1-1 Calculate below: C1A0873 Item 9)

High Channel __________ %

Low Channel __________ %

Differential __________ %

22 PZR Total Water Volume PZR Level: < 92% C1A0707 (SR 3.4.9.1) C1A0867 C1A0873 23 PZR Pressure Monitor Press. differential between highest C1A0713 Channel Check and lowest channels < 28 psig. C1A0868 (SR 3.3.1.1, Table 3.3.1-1 Calculate below: C1A0874 Item 8a & 8b) & C1A0880 (SR 3.3.2.1, Table 3.3.2-1 High Channel _________ psig Item 1d)) Low Channel _________ psig Differential _________ psig

Fire Rated Assemblies 16.9-5 16.9 AUXILIARY SYSTEMS 16.9-5 Fire Rated Assemblies COMMITMENT All required Fire Rated Assemblies (walls, floors/ceilings, cable enclosures and other fire barriers) and all sealing devices in fire rated assembly penetrations (fire doors, fire dampers, and penetration seals) as shown on the CN-1105 drawing series shall be FUNCTIONAL.

APPLICABILITY: At all times.

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

Non-functional or breached fire barrier features (walls, floors, ceilings, doors, dampers, and penetration seals) in the diesel generator rooms and the auxiliary feedwater pump rooms may affect CO2 System FUNCTIONALITY. See SLC 16.9-3, CO2 Systems.

REMEDIAL ACTIONS IF the required Fire Rated Assembly sealing device is a Fire Door, see Table 16.9-5-1 IF the required Fire Rated Assembly sealing device is a Fire Damper see Table 16.9-5-2 IF required Fire Rated Assembly is a Fire Barrier or Penetration Seal:

1. Identify the location of the impaired fire protection feature by elevation, column, and building

2. Verify the wall, floor/ceiling is a committed boundary on the CN-1105 drawing series (if not a committed boundary, SLC 16.9-5 does not apply)

3. Refer to CN-1209-10 series drawings to identify the Fire Area on both sides of the impaired feature

4. IF either of the Fire Areas is identified as High Safety Significant (HSS) (see Table 16.9-5-3) then implement the REQUIRED ACTION CONDITION A

5. IF the Fire Areas are not HSS, then identify the associated shutdown trains/methods of the Fire Areas on each side of the barrier using Table 16.9-5-4 and implement the REQUIRED ACTION as identified in the following Chart:

Shutdown Train (Side 1 & Side A B SSS A or B A and B 2)

CONDITION CONDITION CONDITION CONDITION CONDITION A C B B C B CONDITION CONDITION CONDITION CONDITION CONDITION B B C B C B CONDITION CONDITION CONDITION CONDITION CONDITION SSS B B C B B CONDITION CONDITION CONDITION CONDITION CONDITION A or B C C B C B CONDITION CONDITION CONDITION CONDITION CONDITION A and B B B B B C Catawba Units 1 and 2 16.9-5-1 Revision 11

Fire Rated Assemblies 16.9-5 REMEDIAL ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more HSS* A.1 Establish a continuous fire 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months required Fire Rated watch on at least one side Assemblies is non- of the assembly.

functional.

OR A.2.1 Verify at least one side of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the assembly has FUNCTIONAL fire detection instrumentation.

AND A.2.2 Establish an hourly fire 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months watch patrol on at least one side of the assembly.

OR A.3 Complete an evaluation as Prior to terminating permitted by NRC RIS Required Action A.1 2005-07 to institute or A.2 required action(s).

(continued)

Catawba Units 1 and 2 16.9-5-2 Revision 11

Fire Rated Assemblies 16.9-5 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more LSS** B.1 Establish an hourly fire 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months required Fire Rated watch on at least one side Assemblies is non- of the assembly.

functional.

OR B.2.1 Verify at least one side of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the assembly has FUNCTIONAL fire detection instrumentation.

AND B.2.2 Establish a once per shift 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months fire watch patrol on at least one side of the assembly.

OR B.3 Complete an evaluation as Prior to terminating permitted by NRC RIS Required Action B.1 2005-07 to institute or B.2 required action(s).

(continued)

Catawba Units 1 and 2 16.9-5-3 Revision 11

Fire Rated Assemblies 16.9-5 REMEDIAL ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more DID*** C.1 Establish a once per shift 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months required Fire Rated fire watch on at least one Assemblies is non- side of the assembly.

functional.

OR C.2 Verify at least one side of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the assembly has FUNCTIONAL fire detection instrumentation.

OR C.3 Complete an evaluation as Prior to terminating permitted by NRC RIS Required Action C.1 2005-07 to institute required action(s).

High Safety Significant (HSS) Fire Areas containing required Fire Rated Assemblies are defined in Table 16.9-5-3.

- Low Safety Significant (LSS) Fire Areas containing required Fire Rated Assemblies are defined as those areas with a boundary between redundant shutdown trains.

- - Defense-in-Depth (DID) Fire Areas containing required Fire Rated Assemblies are defined as analysis compartment boundaries or PRA compartment boundaries that do not meet the HSS or LSS definitions.

Catawba Units 1 and 2 16.9-5-4 Revision 11

Fire Rated Assemblies 16.9-5 TESTING REQUIREMENTS TEST FREQUENCY TR 16.9-5-1 Verify each HSS and LSS interior unlocked fire door is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed.

TR 16.9-5-2 Verify each HSS and LSS locked closed fire door is 7 days closed.

TR 16.9-5-3 Perform an inspection and functional test of the release 6 months and closing mechanism and latches for each swinging fire door shown in Table 16.9-5-1.

TR 16.9-5-4 Perform a visual inspection of the exposed surfaces of 18 months each required Fire Rated Assembly.

TR 16.9-5-5 ---------------------------------NOTE---------------------------------

Any abnormal changes or degradation shall be identified and resolved via the corrective action program. Based on the investigation results, additional dampers may be selected for inspection. Samples will be grouped by unit, system, and train and shall be selected such that each damper is inspected every 15 years.

Perform a visual inspection of fire dampers in each 18 months, in required Fire Rated Assembly, shown in Table 16.9-5-2. accordance with the predefined inspection schedule (continued)

Catawba Units 1 and 2 16.9-5-5 Revision 11

Fire Rated Assemblies 16.9-5 TESTING REQUIREMENTS (continued)

TEST FREQUENCY TR 16.9-5-6 ---------------------------------NOTE---------------------------------

Any abnormal changes or degradation shall be identified and resolved via the corrective action program. Based on the investigation results, additional Fire Rated Assemblies may be selected for inspection. Samples shall be selected such that each Fire Rated Assembly is inspected every 15 years.

Perform a visual inspection of penetration seals in each 18 months, in HSS AND LSS required Fire Rated Assembly. accordance with the predefined inspection schedule TR 16.9-5-7 Perform an inspection and functional test of the 18 Months automatic hold open, release and closing mechanism for each rolling fire door shown in Table 16.9-5-1.

Catawba Units 1 and 2 16.9-5-6 Revision 11

Fire Rated Assemblies 16.9-5 Table 16.9-5-1 Required Fire Doors DOOR BLDG LOCATION ELEVATION FIRE AREA RISK REMEDIAL NUMBER INTERFACE CRITERIA ACTION CONDITION AX500F AUX 56, FF 522+0 1/4 DID C AX214A AUX 54-55, FF-GG 543+0 1/4 DID C AX214B AUX 58-59, FF-GG 543+0 1/4 DID C AX217D AUX 52-53, BB 543+0 3/34 LSS B AX217F(1) AUX 51, AA-BB 543+0 3/40 LSS B AX217G AUX 52-53, BB 543+0 3/32 LSS B AX227D AUX 54-55, MM-NN 543+0 4/22 DID C AX227E AUX 59-60, MM-NN 543+0 4/22 DID C AX228A AUX 56-57, EE 543+0 4/9 DID C AX228B AUX 57-58, EE 543+0 4/10 DID C AX248 AUX 57-58, QQ 543+0 4/ASB LSS B AX260B AUX 61-62, BB-CC 543+0 2/36 LSS B AX260F(1) AUX 62, AA-BB 543+0 2/39 LSS B AX260G AUX 61-62, BB-CC 543+0 2/31 LSS B AX260H AUX 61-62, BB-CC 543+0 2/33 LSS B T527#1 AUX 52-53, BB-CC 543+0 3/37 LSS B AX202 AUX 51, NN 543+0 4/STAIR DID C AX253A AUX 63, NN 543+0 4/STAIR DID C AX227A AUX 59, FF-GG 543+0 4/STAIR DID C AX260E AUX 52, CC 543+0 3/STAIR DID C AX516M AUX 62, CC 543+0 2/STAIR DID C AX354A AUX 55, DD-EE 554+0 22/45 LSS B AX354B AUX 59, DD-EE 554+0 22/46 LSS B AX418 AUX 57, BB 554+0 9/10 DID C AX419 AUX 57, DD-EE 554+0 9/10 DID C AX420A AUX 59, DD-EE 554+0 9/46 LSS B AX421A AUX 55, DD-EE 554+0 10/45 LSS B S102A AUX 53-54, AA 554+0 10/SRV LSS B AX302 AUX 41, CC-DD 556+0 25/41 DID C AX304 AUX 41, AA-BB 556+0 26/42 DID C AX306 AUX 73, DD-EE 556+0 27/43 DID C AX308 AUX 73, BB-CC 556+0 28/44 DID C AX348B AUX 54-55, MM-NN 560+0 11/22 DID C AX348C AUX 53-54, HH 560+0 4/11 DID C AX348D AUX 59-60, MM-NN 560+0 11/22 DID C AX348E AUX 60-61, HH 560+0 4/11 DID C AX352B AUX 53, CC-DD 560+0 6/STAIR HSS A AX352C AUX 53, CC-DD 560+0 10/STAIR DID C AX352D AUX 46-47, BB-CC 560+0 6/RB1 HSS A AX353 AUX 45, BB 560+0 6/8 HSS A AX353B AUX 45, AA-BB 560+0 8/41 LSS B AX353C AUX 45, AA-BB 560+0 8/42 DID C (continued)

Catawba Units 1 and 2 16.9-5-7 Revision 11

Fire Rated Assemblies 16.9-5 Table 16.9-5-1 Required Fire Doors DOOR BLDG LOCATION ELEVATION FIRE AREA RISK REMEDIAL NUMBER INTERFACE CRITERIA ACTION CONDITION AX393B AUX 61, CC-DD 560+0 9/STAIR DID C AX393C AUX 61, CC-DD 560+0 5/STAIR DID C AX393D AUX 67-68, BB-CC 560+0 5/RB2 LSS B AX394 AUX 69, BB 560+0 5/7 DID C AX394B AUX 69, AA-BB 560+0 7/43 LSS B AX394C AUX 69, AA-BB 560+0 7/44 DID C AX395 AUX 61, AA-BB 560+0 7/9 LSS B AX396 AUX 53, AA-BB 560+0 8/10 LSS B AX415 AUX 45-46, CC-DD 560+0 6/RB1 HSS A AX416 AUX 68-69, CC-DD 560+0 5/RB2 LSS B AX417 AUX 57, QQ 560+0 11/ASB LSS B AX313D AUX 51, NN 560+0 11/STAIR DID C AX388B AUX 63, NN 560+0 11/STAIR DID C AX348 AUX 59, FF-GG 560+0 11/STAIR DID C AX355A AUX 53-54, FF 568+0 4/11 DID C AX355D AUX 60, FF 568+0 4/11 DID C AX355E AUX 60, FF 568+0 11/STAIR DID C AX515 AUX 54, BB 574+0 17/45 HSS A AX516 AUX 56-57, DD 574+0 14/45 HSS A AX516A AUX 57-58, DD 574+0 16/46 HSS A AX516K AUX 57, AA-BB 574+0 16/17 HSS A AX517A AUX 53-54, DD-EE 574+0 22/45 LSS B AX517B AUX 60-61, DD-EE 574+0 22/46 LSS B AX517C AUX 57, DD-EE 574+0 45/46 DID C AX517D AUX 57, DD-EE 574+0 9/46 LSS B AX517E AUX 56-57, DD-EE 574+0 10/46 LSS B AX518 AUX 60, BB 574+0 16/46 HSS A S303 SRV 36-37, 1N 574+0 45/SRV DID C S303C SRV 36-37, V 574+0 45/SRV DID C S304A AUX 60, AA 574+0 46/SRV DID C AX500H AUX 54-55, MM-NN 577+0 18/22 DID C AX500K AUX 53-54, HH-GG 577+0 4/18 DID C AX500L AUX 59-60, MM-NN 577+0 18/22 DID C AX500N AUX 60-61, HH-GG 577+0 4/18 DID C AX513B AUX 53, CC-DD 577+0 13/STAIR HSS A AX514 AUX 45, BB 577+0 13/15 HSS A AX514B AUX 45-46, AA-BB 577+0 6/13 HSS A AX517 AUX 57, EE 577+0 9/18 DID C AX525 AUX 55-56, QQ 577+0 18/ASB LSS B AX525B AUX 56, QQ 577+0 18/ASB LSS B AX526D AUX 58, QQ 577+0 18/ASB LSS B A314#3 AUX 61, CC-DD 577+0 12/STAIR HSS A AX533C AUX 61, CC-DD 577+0 46/STAIR DID C AX534 AUX 69, BB 577+0 12/14 HSS A (continued)

Catawba Units 1 and 2 16.9-5-8 Revision 11

Fire Rated Assemblies 16.9-5 Table 16.9-5-1 Required Fire Doors DOOR BLDG LOCATION ELEVATION FIRE AREA RISK REMEDIAL NUMBER INTERFACE CRITERIA ACTION CONDITION AX534B AUX 68-69, AA-BB 577+0 7/14 HSS A AX535A AUX 61, AA-BB 577+0 14/46 HSS A AX536 AUX 53, AA-BB 577+0 15/45 HSS A AX656 AUX 53, CC-DD 577+0 45/STAIR DID C AX500P AUX 51, NN 577+0 18/STAIR DID C AX500S AUX 63, NN 577+0 18/STAIR DID C AX338A AUX 60, FF-GG 577+0 18/STAIR DID C AX602 AUX 52, UU-VV 594+0 24/ASB DID C AX627 AUX 62, UU-VV 594+0 23/ASB DID C AX630 AUX 58, QQ 594+0 22/ASB LSS B AX632 AUX 57, QQ 594+0 22/ASB LSS B AX635 AUX 60-61, QQ 594+0 22/ASB LSS B AX635E AUX 53-54, QQ 594+0 22/ASB LSS B AX635F AUX 53-54, QQ 594+0 22/ASB LSS B AX655 AUX 62-63, DD 594+0 19/48 LSS B AX656C AUX 61, CC-DD 594+0 19/22 LSS B AX657 AUX 60-61, CC 594+0 19/22 LSS B AX657A(2) AUX 54, BB 594+0 21/35 HSS A AX657B AUX 52-53, CC-DD 594+0 20/22 LSS B AX657E(2) AUX 53, BB 594+0 21/35 HSS A AX657F AUX 60, DD-EE 594+0 21/22 HSS A AX657G AUX 57-58, DD-EE 594+0 21/22 HSS A AX657H AUX 54, DD-EE 594+0 21/22 HSS A AX657J AUX 53, BB-CC 594+0 20/21 HSS A AX658B AUX 51-52, DD 594+0 20/49 LSS B S400 AUX 55-56, AA 594+0 21/SRV HSS A S406 AUX 58-59, AA 594+0 21/SRV HSS A AX635G AUX 51, NN 594+0 22/STAIR DID C AX635H AUX 63, NN 594+0 22/STAIR DID C AX654A AUX 60, FF 594+0 22/STAIR DID C AX654B AUX 61, CC-DD 594+0 19/STAIR DID C AX665B AUX 53, CC-DD 594+0 22/STAIR DID C AX700B AUX 50-51, JJ-KK 605+10 24/RB1 LSS B AX700D AUX 63-64, KK 605+10 22/23 LSS B AX701 AUX 50-51, JJ-KK 605+10 22/RB1 LSS B AX714B AUX 63-64, JJ-KK 605+10 23/RB2 LSS B AX720 AUX 50-51, HH-JJ 605+10 22/RB1 LSS B AX721 AUX 63-64, HH-JJ 605+10 22/RB2 LSS B AX714C AUX 50-51, KK 605+10 22/24 LSS B AX715A AUX 63-64, JJ-KK 605+10 22/RB2 LSS B S211(2) TB1 17, V 568+0 SRV/TB1 DID C S212 TB1 19, V 568+0 SRV/TB1 DID C S210 TB1 21,V 568+0 SRV/TB1 DID C (continued)

Catawba Units 1 and 2 16.9-5-9 Revision 11

Fire Rated Assemblies 16.9-5 Table 16.9-5-1 Required Fire Doors DOOR BLDG LOCATION ELEVATION FIRE AREA RISK REMEDIAL NUMBER INTERFACE CRITERIA ACTION CONDITION S206 TB1 22, V 568+0 SRV/TB1 DID C S201 TB1 33, V 568+0 SRV/TB1 DID C SR3(3) TB1 30-31, V 568+0 SRV/TB1 DID C S201A TB1 27, V 568+0 SRV/TB1 DID C T101 TB1 31, 1K 568+0 TB1/U1 OTT DID C S424 TB1 24-25, V 594+0 SRV/TB1 DID C S425 TB1 23, V 594+0 SRV/TB1 DID C S426 TB1 22, V 594+0 SRV/TB1 DID C SR21(3) TB1 24, V 594+0 SRV/TB1 DID C S472 TB1 27, V 594+0 SRV/TB1 DID C S423 TB1 29, V 594+0 SRV/TB1 DID C S422 TB1 29, V 594+0 SRV/TB1 DID C SR7(3) TB1 29-30, V 594+0 SRV/TB1 DID C S416 TB1 32, V 594+0 SRV/TB1 DID C S444 TB1 15, V 594+0 SRV/TB1 DID C TR4(3) TB1 15-16, V 594+0 SRV/TB1 DID C T200A TB1 32, 1J-1K 594+0 TB1/U1 MTOT DID C S701 TB1 22, 1L 619+6 SRV/TB1 DID C S704 TB1 33, 1L 619+6 SRV/TB1 DID C S209 TB2 20, P 568+0 SRV/TB2 DID C S208 TB2 22, P 568+0 SRV/TB2 DID C SR2(3) TB2 32-33, P 568+0 SRV/TB2 DID C S462 TB2 32, P 568+0 SRV/TB2 DID C SR4(3) TB2 30-31, P 568+0 SRV/TB2 DID C S1102 TB2 27, P 568+0 SRV/TB2 DID C T151 TB2 31, 2K 568+0 TB2/U2 OTT DID C S423E TB2 26, P-Q 594+0 SRV/TB2 DID C S416A TB2 32, P 594+0 SRV/TB2 DID C SR8(3) TB2 29-30, P 594+0 SRV/TB2 DID C S422A TB2 29, P 594+0 SRV/TB2 DID C S423A TB2 29, P 594+0 SRV/TB2 DID C S435 TB2 24-25, P 594+0 SRV/TB2 DID C S436 TB2 23, P 594+0 SRV/TB2 DID C S437 TB2 22, P 594+0 SRV/TB2 DID C SR22(3) TB2 24, P 594+0 SRV/TB2 DID C S444A TB2 15, P 594+0 SRV/TB2 DID C SR16(3) TB2 15-16, P 594+0 SRV/TB2 DID C S472A TB2 27, P 594+0 SRV/TB2 DID C T250A TB2 32, 2J-2K 594+0 TB2/U2 MTOT DID C S701A TB2 22, 2L 619+6 SRV/TB2 DID C S704A TB2 33, 2L 619+6 SRV/TB2 DID C AX662A NSWPS ---- 600+0 29/30 LSS B (1) These doors are not equipped with closing mechanisms or latches and are therefore exempt from TESTING REQUIREMENT 16.9-5-3.

(2) These doors are held open with a fusible link.

(3) Rolling Door.

Catawba Units 1 and 2 16.9-5-10 Revision 11

Fire Rated Assemblies 16.9-5 Table 16.9-5-2 Required Fire Dampers DAMPER BLDG LOCATION ELEVATION FIRE AREA RISK REMEDIAL NUMBER INTERFACE CRITERIA ACTION CONDITION 1VA-FD001 AUX 53/GG-FF 522+0 1/4 DID C 1VA-FD002 AUX 53/GG-HH 522+0 1/4 DID C 1VA-FD003 AUX 55-56/GG-HH 522+0 1/4 DID C 1VA-FD004 AUX 55-56/GG-HH 522+0 1/4 DID C 1VA-FD005 AUX 54-55/GG-HH 522+0 1/4 DID C 1VA-FD006 AUX 54-55/GG-HH 522+0 1/4 DID C 1VA-FD007 AUX 53/GG-FF 522+0 1/4 DID C 1VA-FD008 AUX 53/GG-FF 522+0 1/4 DID C 1/1 (ND 1VA-FD009 AUX 53-54/FF-GG 522+0 DID C PUMPS) 1VA-FD010 AUX 56-57/ GG-HH, 522+0 1/4 DID C 1VA-FD011 AUX 56-57/FF 522+0 1/4 DID C 1VA-FD012 AUX 51/NN-PP 543+0 11/STAIR DID C 1VA-FD013 AUX 54/MM 543+0 4/22 DID C 1VA-FD014 AUX 54/MM 543+0 4/22 DID C 1VA-FD015 AUX 54-55/MM-NN 543+0 4/22 DID C 1VA-FD016 AUX 54-55/MM-NN 543+0 4/22 DID C 1VA-FD017 AUX 54-55/MM-NN 543+0 4/22 DID C 4/4 (NV 1VA-FD020 AUX 55/JJ-KK 543+0 DID C PUMPS) 1VA-FD033 AUX 51-52/AA-BB 543+0 3/40 LSS B 1VA-FD034 AUX 51-52/AA-BB 543+0 3/40 LSS B 1VA-FD035 AUX 52/AA-BB 543+0 3/32 LSS B 1VA-FD036 AUX 52-53/BB 543+0 3/32 LSS B 1VA-FD038 AUX 52-53/BB 543+0 3/34 LSS B 1VA-FD039 AUX 52-53/BB 543+0 3/34 LSS B 1VA-FD040 AUX 52-53/BB 543+0 3/32 LSS B 1VA-FD041 AUX 52-53/BB 543+0 3/32 LSS B 1VA-FD042 AUX 53/CC 543+0 3/STAIR DID C 1VA-FD043 AUX 53/CC-DD 543+0 3/STAIR DID C 1VA-FD045 AUX 52-53/DD 560+0 3/6 HSS A 1VA-FD046 AUX 52-53/CC-DD 577+0 6/13 HSS A 1VA-FD047 AUX 52-53/CC-DD 577+0 6/13 HSS A 1VA-FD048 AUX 54/MM-NN 560+0 11/22 DID C 1VA-FD049 AUX 54/MM 560+0 11/22 DID C 1VA-FD050 AUX 54-55/MM 560+0 4/22 DID C 1VA-FD051 AUX 54-55/MM 560+0 4/22 DID C 1VA-FD052 AUX 55/MM-NN 560+0 11/22 DID C 1VA-FD053 AUX 55/MM 560+0 11/22 DID C 1VA-FD054 AUX 53/GG-HH 560+0 4/11 DID C 1VA-FD055 AUX 53/GG-HH 560+0 4/11 DID C 1VA-FD056 AUX 53/KK 560+0 4/11 DID C 1VA-FD057 AUX 53/GG-HH 560+0 4/11 DID C (continued)

Catawba Units 1 and 2 16.9-5-11 Revision 11

Fire Rated Assemblies 16.9-5 Table 16.9-5-2 REQUIRED FIRE DAMPERS DAMPER BLDG LOCATION ELEVATION FIRE AREA RISK REMEDIAL NUMBER INTERFACE CRITERIA ACTION CONDITION 1VA-FD058 AUX 53-54/HH 560+0 4/11 DID C 1VA-FD059 AUX 54/GG-HH 560+0 4/11 DID C 1VA-FD060 AUX 54/HH 560+0 4/11 DID C 1VA-FD061 AUX 56-57/QQ 577+0 18/ASB LSS B 1VA-FD062 AUX 55-56/QQ 577+0 18/ASB LSS B 1VA-FD063 AUX 55/MM-NN 577+0 18/22 DID C 1VA-FD064 AUX 55/MM 577+0 18/22 DID C 1VA-FD065 AUX 54/MM 577+0 18/22 DID C 1VA-FD066 AUX 54/MM 577+0 18/22 DID C 1VA-FD067 AUX 54/HH 577+0 4/18 DID C 1VA-FD068 AUX 53-54/HH 577+0 4/18 DID C 1VA-FD069 AUX 54/GG-HH 577+0 4/18 DID C 1VA-FD070 AUX 53-54/HH 577+0 4/18 DID C 1VA-FD071 AUX 53-54/HH 577+0 4/18 DID C 1VA-FD072 AUX 53/HH 577+0 4/18 DID C 1VA-FD073 AUX 53/HH 577+0 4/18 DID C 1VA-FD074 AUX 53/GG-HH 577+0 4/18 DID C 1VA-FD075 AUX 53-54/KK-LL 594+0 18/22 DID C 1VA-FD076 AUX 53-54/KK-LL 594+0 18/22 DID C 1VA-FD078 AUX 57/NN 594+0 22/STAIR DID C 1VA-FD087 AUX 55-56/QQ 594+0 22/ASB LSS B 1VA-FD088 AUX 53-54/QQ 594+0 22/ASB LSS B 1VA-FD133 AUX 53/CC-DD 594+0 22/STAIR DID C 1VA-FD139 AUX 51-52/DD 543+0 3/4 DID C 1VA-FD140 AUX 53-54/FF-GG 560+0 4/11 DID C 1VA-FD141 AUX 53-54/FF-GG 560+0 4/11 DID C 1VA-FD142 AUX 53/GG 560+0 4/11 DID C 1VA-FD143 AUX 53/JJ-HH 560+0 4/11 DID C 1VA-FD144 AUX 53/KK 560+0 4/11 DID C 1VA-FD145 AUX 51/KK 560+0 11/18 DID C 1VA-FD146 AUX 51/KK 560+0 11/18 DID C 1VA-FD147 AUX 52/MM 560+0 11/18 DID C 1VA-FD148 AUX 52/MM-NN 560+0 4/11 DID C 1VA-FD149 AUX 52-53/DD 560+0 3/6 HSS A 1VA-FD150 AUX 52-53/DD 560+0 3/6 HSS A 1VA-FD152 AUX 52-53/BB-CC 543+0 3/37 LSS B 1VA-FD153 AUX 52-53/CC 543+0 3/37 LSS B 1VA-FD154 AUX 53-54/GG-HH 594+0 4/22 DID C 1VA-FD155 AUX 53-54/GG-HH 594+0 4/22 DID C 1VA-FD159 AUX 49-50/AA-BB 543+0 CO2 HSS A 1VA-FD160 AUX 50-51/AA-BB 543+0 CO2 HSS A 1VA-FD163 AUX 56/EE 543+0 10/45 LSS B 1VA-FD164 AUX 56-57/EE 543+0 4/10 DID C 2VA-FD001 AUX 61/GG-FF 522+0 1/4 DID C 2VA-FD002 AUX 61/GG-FF 522+0 1/4 DID C (continued)

Catawba Units 1 and 2 16.9-5-12 Revision 11

Fire Rated Assemblies 16.9-5 Table 16.9-5-2 REQUIRED FIRE DAMPERS DAMPER BLDG LOCATION ELEVATION FIRE AREA RISK REMEDIAL NUMBER INTERFACE CRITERIA ACTION CONDITION 1/1 (ND 2VA-FD003 AUX 60-61/FF-GG 522+0 DID C PUMPS) 2VA-FD004 AUX 61/GG-FF 522+0 1/4 DID C 2VA-FD005 AUX 60-61/GG-HH 522+0 1/4 DID C 2VA-FD006 AUX 59-60/GG-HH 522+0 1/4 DID C 2VA-FD007 AUX 59-60/GG-HH 522+0 1/4 DID C 2VA-FD008 AUX 58-59/GG-HH 522+0 1/4 DID C 2VA-FD009 AUX 58-59/GG-HH 522+0 1/4 DID C 2VA-FD010 AUX 57-58/GG-HH 522+0 1/4 DID C 2VA-FD011 AUX 57-58/FF 522+0 1/4 DID C 2VA-FD012 AUX 59-60/MM-NN 543+0 4/22 DID C 2VA-FD013 AUX 59/MM 543+0 4/22 DID C 2VA-FD014 AUX 59/MM 543+0 4/22 DID C 2VA-FD015 AUX 59-60/MM-NN 543+0 4/22 DID C 2VA-FD020 AUX 63/NN 534+0 4/STAIR DID C 4/4 (NV 2VA-FD023 AUX 59/JJ-KK 543+0 DID C PUMPS) 2VA-FD036 AUX 61-62/DD 560+0 2/5 LSS B 2VA-FD037 AUX 61-62/CC-DD 577+0 5/12 HSS A 2VA-FD038 AUX 61-62/CC-DD 577+0 5/12 HSS A 2VA-FD040 AUX 62-63/AA-BB 543+0 2/39 LSS B 2VA-FD041 AUX 62-63/AA-BB 543+0 2/39 LSS B 2VA-FD042 AUX 62/AA-BB 543+0 2/31 LSS B 2VA-FD043 AUX 61-62/BB 543+0 2/31 LSS B 2VA-FD045 AUX 61/CC 543+0 2/STAIR DID C 2VA-FD046 AUX 61/CC-DD 543+0 2/STAIR DID C 2VA-FD048 AUX 61-62/BB 543+0 2/33 LSS B 2VA-FD049 AUX 61-62/BB 543+0 2/33 LSS B 2VA-FD050 AUX 61-62/BB 543+0 2/31 LSS B 2VA-FD051 AUX 61-62/BB 543+0 2/31 LSS B 2VA-FD053 AUX 60/MM 560+0 11/22 DID C 2VA-FD054 AUX 59/MM-NN 560+0 11/22 DID C 2VA-FD056 AUX 60/MM-NN 560+0 11/22 DID C 2VA-FD057 AUX 59-60/MM 560+0 11/22 DID C 2VA-FD058 AUX 59-60/MM 560+0 4/22 DID C 2VA-FD059 AUX 60-61/HH 560+0 4/11 DID C 2VA-FD060 AUX 61/HH-JJ 560+0 4/11 DID C 2VA-FD061 AUX 60-61/GG-HH 560+0 4/11 DID C 2VA-FD062 AUX 61/GG-HH 560+0 4/11 DID C 2VA-FD063 AUX 61/GG-HH 560+0 4/11 DID C 2VA-FD064 AUX 60-61/GG-HH 560+0 4/11 DID C 2VA-FD065 AUX 61/HH 560+0 4/11 DID C 2VA-FD069 AUX 58-59/QQ 577+0 18/ASB LSS B 2VA-FD070* AUX 59-60/QQ 577+0 18/ASB LSS B 2VA-FD071 AUX 59-60/MM-NN 577+0 18/22 DID C 2VA-FD072 AUX 59-60/MM 577+0 18/22 DID C (continued)

Catawba Units 1 and 2 16.9-5-13 Revision 11

Fire Rated Assemblies 16.9-5 Table 16.9-5-2 REQUIRED FIRE DAMPERS DAMPER BLDG LOCATION ELEVATION FIRE AREA RISK REMEDIAL NUMBER INTERFACE CRITERIA ACTION CONDITION 2VA-FD073 AUX 60/MM 577+0 18/22 DID C 2VA-FD074 AUX 60/MM 577+0 18/22 DID C 2VA-FD075 AUX 60/HH 577+0 4/22 DID C 2VA-FD076 AUX 60/HH 577+0 4/22 DID C 2VA-FD077 AUX 60-61/HH 577+0 4/22 DID C 2VA-FD078 AUX 60-61/HH 577+0 4/22 DID C 2VA-FD079 AUX 61/HH 577+0 4/22 DID C 2VA-FD080 AUX 61/GG-HH 577+0 4/22 DID C 2VA-FD081 AUX 61/HH 577+0 4/22 DID C 2VA-FD083 AUX 63/NN 594+0 22/STAIR DID C 2VA-FD086 AUX 60/FF 594+0 22/STAIR DID C 2VA-FD087 AUX 59-60/QQ 594+0 22/ASB LSS B 2VA-FD088 AUX 60-61/QQ 594+0 22/ASB LSS B 2VA-FD093 AUX 58-59/QQ 594+0 22/ASB LSS B 2VA-FD097 AUX 61/CC-DD 594+0 22/STAIR DID C 2VA-FD108A AUX 57-59/QQ 611+0 22/ASB LSS B 2VA-FD108B AUX 57-59/QQ 611+0 22/ASB LSS B 2VA-FD114 AUX 59-60/KK-LL 594+0 18/22 DID C 2VA-FD115 AUX 59-60/KK-LL 594+0 18/22 DID C 2VA-FD137 AUX 60-61/FF-GG 560+0 4/18 DID C 2VA-FD138 AUX 60-61/FF-GG 560+0 4/18 DID C 2VA-FD139 AUX 61/GG 560+0 4/11 DID C 2VA-FD141 AUX 62-63/DD 543+0 2/4 DID C 2VA-FD142 AUX 60-61/KK 560+0 4/11 DID C 2VA-FD143 AUX 62-63/KK 560+0 4/18 DID C 2VA-FD144 AUX 63/KK 560+0 4/18 DID C 2VA-FD145 AUX 61-62/MM-NN 560+0 4/11 DID C 2VA-FD146 AUX 61-62/DD 560+0 2/5 LSS B 2VA-FD147 AUX 61-62/DD 560+0 2/5 LSS B 2VA-FD151 AUX 61-62/BB-CC 543+0 2/36 LSS B 2VA-FD152 AUX 61-62/CC 543+0 2/36 LSS B 2VA-FD153 AUX 60-61/GG-HH 594+0 4/22 DID C 2VA-FD154 AUX 60-61/GG-HH 594+0 4/22 DID C 2VA-FD157 AUX 63-64/AA-BB 543+0 CO2 HSS A 2VA-FD158 AUX 64-65/AA-BB 543+0 CO2 HSS A 2VA-FD160 AUX 57-58/QQ 543+0 4/ASB LSS B 2VA-FD161 AUX 57-58/QQ 543+0 4/ASB LSS B 2VA-FD163 AUX 58/EE 543+0 9/46 LSS B 2VA-FD164 AUX 57-58/EE 543+0 4/9 DID C 0BRS-FD001 AUX 54-55/DD-EE 554+0 10/22 DID C 0BRS-FD010 AUX 57/DD-EE 554+0 9/10 DID C 0BRS-FD019 AUX 59/DD-EE 554+0 9/22 DID C 0BRX-AUX 54-55/DD-EE 554+0 10/22 DID C FD001A 0BRX-AUX 54-55/DD-EE 554+0 10/22 DID C FD001B (continued)

Catawba Units 1 and 2 16.9-5-14 Revision 11

Fire Rated Assemblies 16.9-5 Table 16.9-5-2 REQUIRED FIRE DAMPERS DAMPER BLDG LOCATION ELEVATION FIRE AREA RISK REMEDIAL NUMBER INTERFACE CRITERIA ACTION CONDITION 0BRX-AUX 54-55/DD-EE 554+0 10/22 DID C FD001C 0BRX-AUX 54-55/DD-EE 554+0 10/22 DID C FD001D 0BRX-AUX 54-55/DD-EE 554+0 10/22 DID C FD001E 0BRX-AUX 54-55/DD-EE 554+0 10/22 DID C FD001F 0BRX-AUX 54-55/DD-EE 554+0 10/22 DID C FD001G 0BRX-AUX 54-55/DD-EE 554+0 10/22 DID C FD001H 0BRX-FD002 AUX 54-55/DD-EE 554+0 10/22 DID C 0BRX-FD009 AUX 57/AA-BB 554+0 9/10 DID C 0BRX-FD010 AUX 57/AA-BB 554+0 9/10 DID C 0BRX-FD011 AUX 57/BB-CC 554+0 9/10 DID C 0BRX-FD012 AUX 57/CC-DD 554+0 9/10 DID C 0BRX-FD013 AUX 57/CC-DD 554+0 9/10 DID C 0BRX-FD014 AUX 57/DD-EE 554+0 9/10 DID C 0BRX-FD021 AUX 60/DD-EE 554+0 9/22 DID C 0BRX-AUX 60/DD-EE 554+0 9/22 DID C FD022A 0BRX-AUX 60/DD-EE 554+0 9/22 DID C FD022B 0BRX-AUX 60/DD-EE 554+0 9/22 DID C FD022C 0BRX-AUX 60/DD-EE 554+0 9/22 DID C FD022D 0BRX-AUX 60/DD-EE 554+0 9/22 DID C FD022E 0BRX-AUX 60/DD-EE 554+0 9/22 DID C FD022F 0BRX-AUX 60/DD-EE 554+0 9/22 DID C FD022G 0BRX-AUX 60/DD-EE 554+0 9/22 DID C FD022H 0BRX-FD023 AUX 57/BB-CC 554+0 9/10 DID C 1CRA-AUX 54-55/DD-EE 594+0 21/22 HSS A FD005A 1CRA-AUX 54-55/DD-EE 594+0 21/22 HSS A FD005B 1CRA-FD008 AUX 54/AA 594+0 21/35 HSS A 1CRA-FD009 AUX 53-54/CC-DD 594+0 22/STAIR DID C 1CRA-FD010 AUX 53-54/CC 594+0 21/STAIR HSS A 1CRA-FD011 AUX 53/AA-BB 594+0 20/35 DID C 1CRA-FD012 AUX 53/BB-CC 594+0 20/21 HSS A (continued)

Catawba Units 1 and 2 16.9-5-15 Revision 11

Fire Rated Assemblies 16.9-5 Table 16.9-5-2 REQUIRED FIRE DAMPERS DAMPER BLDG LOCATION ELEVATION FIRE AREA RISK REMEDIAL NUMBER INTERFACE CRITERIA ACTION CONDITION 1CRA-FD013 AUX 52/CC-DD 594+0 20/22 LSS B 1CRA-FD016 AUX 54-55/DD-EE 574+0 22/45 LSS B 1CRA-FD017 AUX 54-55/DD 574+0 17/45 HSS A 1CRA-FD018 AUX 54-55/DD 574+0 17/45 HSS A 1CRA-FD019 AUX 54/AA-BB 574+0 17/45 HSS A 1CRA-FD020 AUX 57/CC-DD 574+0 16/17 HSS A 1CRA-FD021 AUX 53-54/DD-EE 574+0 22/45 LSS B 1CRA-FD022 AUX 55-56/DD 574+0 17/45 HSS A 1CRA-FD023 AUX 56-57/DD 574+0 17/45 HSS A 1CRA-AUX 57/DD-EE 574+0 45/46 DID C FD024A 1CRA-AUX 57/DD-EE 574+0 45/46 DID C FD024B 1CRA-AUX 54-55/DD-EE 574+0 22/45 LSS B FD025A 1CRA-AUX 54-55/DD-EE 574+0 22/45 LSS B FD025B 1CRA-FD026 AUX 54-55/EE 577+0 18/22 DID C 1CRA-FD028 AUX 53-54/EE 577+0 18/22 DID C 1CRA-FD029 AUX 54-55/EE 568+0 11/22 DID C 1CRA-FD030 AUX 54-55/EE 568+0 11/22 DID C 18/18 (KC 1CRA-FD039 AUX 57/EE-FF 577+0 DID C PUMPS) 1CR-FD001 AUX 55-56/DD-EE 594+0 21/22 HSS A 1CR-FD002 AUX 55-56/DD-EE 594+0 21/22 HSS A 1CR-FD003 AUX 54/AA-BB 594+0 21/35 HSS A 1CR-FD004 AUX 53-54/BB 594+0 21/35 HSS A 1CR-FD005 AUX 53-54/BB 594+0 21/35 HSS A 1CR-FD007 AUX 51/CC-DD 594+0 13/20 HSS A 2CRA-AUX 59-60/DD-EE 594+0 21/22 HSS A FD005A 2CRA-AUX 59-60/DD-EE 594+0 21/22 HSS A FD005B 2CRA-FD008 AUX 60/AA-BB 594+0 19/21 HSS A 2CRA-FD009 AUX 60-61/CC 594+0 19/22 LSS B 2CRA-FD012 AUX 61/CC-DD 594+0 19/22 LSS B 2CRA-FD015 AUX 59-60/DD-EE 574+0 22/46 LSS B 2CRA-FD016 AUX 59-60/DD 574+0 16/46 HSS A 2CRA-FD017 AUX 59-60/DD 574+0 16/46 HSS A 2CRA-FD018 AUX 60/AA-BB 574+0 16/46 HSS A 2CRA-FD019 AUX 58-59/DD 574+0 16/46 HSS A 2CRA-FD020 AUX 57-58/DD 574+0 16/46 HSS A 2CRA-FD021 AUX 60-61/DD-EE 574+0 22/46 LSS B 2CRA-AUX 59-60/DD-EE 574+0 22/46 LSS B FD022A (continued)

Catawba Units 1 and 2 16.9-5-16 Revision 11

Fire Rated Assemblies 16.9-5 Table 16.9-5-2 REQUIRED FIRE DAMPERS DAMPER BLDG LOCATION ELEVATION FIRE AREA RISK REMEDIAL NUMBER INTERFACE CRITERIA ACTION CONDITION 2CRA-AUX 59-60/DD-EE 574+0 22/46 LSS B FD022B 2CRA-FD023 AUX 59-60/EE 577+0 18/22 DID C 2CRA-FD025 AUX 60-61/EE 577+0 18/22 DID C 2CRA-FD026 AUX 59-60/EE 568+0 11/22 DID C 2CRA-FD027 AUX 59-60/EE 568+0 11/22 DID C 2CR-FD001 AUX 58-59/DD-EE 594+0 21/22 HSS A 2CR-FD002 AUX 58-59/DD 594+0 21/22 HSS A 2CR-FD003 AUX 63-64/CC 594+0 12/19 HSS A 1VF-FD001A AUX 51, NN-PP 605+10 22/24 LSS B 1VF-FD001B AUX 51, NN-PP 605+10 22/24 LSS B 1VF-FD002A AUX 50-51/NN-PP 631+6 24/38 DID C 1VF-FD002B AUX 50-51/NN-PP 631+6 24/38 DID C 1VF-FD004 AUX 49/PP-QQ 631+6 24/38 DID C 1VF-FD005 AUX 49-50/PP-QQ 631+6 24/38 DID C 1VF-FD006 AUX 50-51 631+6 24/38 DID C 1VF-FD007 AUX 50-51/KK-LL 605+10 22/24 LSS B 1VF-FD010 AUX 50-51/KK 605+10 22/24 LSS B 1VF-FD011 AUX 50-51/JJ-KK 631+6 22/38 LSS B 1VF-FD013 AUX 50-51/JJ-KK 616+10 22/24 LSS B 1VF-FD014 AUX 50-51/JJ-KK 616+10 22/24 LSS B 2VF-FD001A AUX 63, NN-PP 605+10 22/23 LSS B 2VF-FD001B AUX 63, NN-PP 605+10 22/23 LSS B 2VF-FD002A AUX 63-64/NN-PP 631+6 23/47 DID C 2VF-FD002B AUX 63-64/NN-PP 631+6 23/47 DID C 2VF-FD004 AUX 65/PP-QQ 631+6 23/47 DID C 2VF-FD005 AUX 64-65/PP-QQ 631+6 23/47 DID C 2VF-FD006 AUX 63-64/PP-QQ 631+6 23/47 DID C 2VF-FD007 AUX 63-64/KK-LL 605+10 22/23 LSS B 2VF-FD010 AUX 63-64/KK 605+10 22/23 LSS B 2VF-FD011 AUX 64-64/JJ-KK 631+6 22/47 LSS B 2VF-FD013 AUX 63-64/JJ-KK 616+10 22/23 LSS B 2VF-FD014 AUX 63-64/JJ-KK 616+10 22/23 LSS B 1TB-FD001 TB1 18-19/V 594+0 TB1/SRV DID C 1TB-FD002 TB1 18-19/V 594+0 TB1/SRV DID C 1TB-FD003 TB1 18-19/V 594+0 TB1/SRV DID C 1TB-FD004 TB1 18-19/V 594+0 TB1/SRV DID C 1TB-FD005 TB1 18-19/V 594+0 TB1/SRV DID C 1TB-FD006 TB1 18-19/V 594+0 TB1/SRV DID C 1TB-FD007 TB1 21-22/V 594+0 TB1/SRV DID C 1TB-FD008 TB1 21-22/V 594+0 TB1/SRV DID C 1TB-FD009 TB1 21-22/V 594+0 TB1/SRV DID C 1TB-FD010 TB1 21-22/V 594+0 TB1/SRV DID C 1TB-FD011 TB1 21-22/V 594+0 TB1/SRV DID C 1TB-FD012 TB1 21-22/V 594+0 TB1/SRV DID C 1TB-FD032 TB1 18-19/V 594+0 TB1/SRV DID C (continued)

Catawba Units 1 and 2 16.9-5-17 Revision 11

Fire Rated Assemblies 16.9-5 Table 16.9-5-2 REQUIRED FIRE DAMPERS DAMPER BLDG LOCATION ELEVATION FIRE AREA RISK REMEDIAL NUMBER INTERFACE CRITERIA ACTION CONDITION 1TB-FD038 TB1 16-17/V 594+0 TB1/SRV DID C 1TB-FD039 TB1 16-17/V 594+0 TB1/SRV DID C 1TB-FD040 TB1 16/V 594+0 TB1/SRV DID C 1TB-FD043 TB1 30-31/1J-1K 568+0 TB1/OTT DID C 1TB-FD044 TB1 32/1J-1K 594+0 TB1/MTOT DID C 1TB-FD045 TB1 30/1J-1K 594+0 TB1/MTOT DID C 1TB-FD046 TB1 32/1K-1L 568+0 TB1/OTT DID C 2TB-FD013 TB2 21-22/P 594+0 TB2/SRV DID C 2TB-FD014 TB2 21-22/P 594+0 TB2/SRV DID C 2TB-FD015 TB2 21-22/P 594+0 TB2/SRV DID C 2TB-FD016 TB2 21-22/P 594+0 TB2/SRV DID C 2TB-FD017 TB2 21-22/P 594+0 TB2/SRV DID C 2TB-FD018 TB2 21-22/P 594+0 TB2/SRV DID C 2TB-FD019 TB2 18-19/P 594+0 TB2/SRV DID C 2TB-FD020 TB2 18-19/P 594+0 TB2/SRV DID C 2TB-FD021 TB2 18-19/P 594+0 TB2/SRV DID C 2TB-FD022 TB2 18-19/P 594+0 TB2/SRV DID C 2TB-FD023 TB2 18-19/P 594+0 TB2/SRV DID C 2TB-FD024 TB2 18-19/P 594+0 TB2/SRV DID C 2TB-FD031 TB2 32/2K-2L 568+0 TB2/OTT DID C 2TB-FD032 TB2 18/P 594+0 TB2/SRV DID C 2TB-FD036 TB2 16-17/P 594+0 TB2/SRV DID C 2TB-FD038 TB2 17-18/P 594+0 TB2/SRV DID C 2TB-FD039 TB2 32/2J-2K 594+0 TB2/MTOT DID C 2TB-FD040 TB2 30/2J-2K 594+0 TB2/MTOT DID C 2TB-FD041 TB2 30-31/2J/2K 568+0 TB2/OTT DID C

2VA-FD070 is exempt from inspection requirements (SLC TR 16.9-5-5) for ALARA reasons Table 16.9-5-3 HIGH SAFETY SIGNIFICANT (HSS) FIRE AREAS*

FIRE AREA BLDG ELEVATION DESCRIPTION 6 AUX 560+0 Unit 1 Electrical Pen Room El 560 12 AUX 577+0 Unit 2 Electrical Pen Room El 577 13 AUX 577+0 Unit 1 Electrical Pen Room El 577 14 AUX 577+0 Unit 2 4160V Essential Swgr Room (2ETA) 15 AUX 577+0 Unit 1 4160V Essential Swgr Room (1ETA) 16 AUX 574+0 Unit 2 Cable Room El 574 17 AUX 574+0 Unit 1 Cable Room El 574 21 AUX 594+0 Main Control Room El 594

High Safety Significant (HSS) Fire Areas are defined as the areas with HSS fire barrier features in accordance with the Catawba NFPA 805 Monitoring Program.

Catawba Units 1 and 2 16.9-5-18 Revision 11

Fire Rated Assemblies 16.9-5 Table 16.9-5-4 FIRE AREAS AND SHUTDOWN TRAIN / METHOD ASSURED FIRE SHUTDOWN AREA FIRE AREA DESCRIPTIONS TRAIN / METHOD 1 ND & NS Pump Room El 522 (Common) SSS 2 Unit 2 CA Pump Room El 543 SSS 3 Unit 1 CA Pump Room El 543 SSS 4 Aux Bldg. Gen Area & NV Pump Room El 543 (Common) SSS 5 Unit 2 Electrical Pen Room El 560 A 6 Unit 1 Electrical Pen Room El 560 A 7 Unit 2 4160V Essential SWGR Room El 560 A 8 Unit 1 4160V Essential SWGR Room El 560 A 9 Unit 2 Battery Room El 554 SSS 10 Unit 1 Battery Room El 554 SSS 11 Aux Bldg. Gen Area & U1 KC Pump Room El 560 (Common) SSS 12 Unit 2 Electrical Pen Room El 577 B 13 Unit 1 Electrical Pen Room El 577 B 14 Unit 2 4160V Essential SWGR Room El 577 B 15 Unit 1 4160V Essential SWGR Room El 577 B 16 Unit 2 Cable Room El 574 SSS 17 Unit 1 Cable Room El 574 SSS 18 Aux Bldg. Gen Area & U2 KC Pump Room El 577 (Common) SSS 19 Unit 2 Electrical Pen Room El 594 A 20 Unit 1 Electrical Pen Room El 594 A 21 Control Room El 594 (Common) SSS 22 Aux Bldg. Gen Area El 594 (Common) SSS 23 Unit 2 Fuel Storage Area El 605 A 24 Unit 1 Fuel Storage Area El 605 A 25 Diesel Generator Bldg. 1A El 556 B 25A Diesel Generator Bldg. 1A Stairwell B 26 Diesel Generator Bldg. 1B El 556 A 26B Diesel Generator Bldg. 1B Stairwell A 27 Diesel Generator Bldg. 2A El 556 B 27A Diesel Generator Bldg. 2A Stairwell B 28 Diesel Generator Bldg. 2B El 556 A 28B Diesel Generator Bldg. 2B Stairwell A 29 Train A RN Pump Structure El 600 (Common) B 30 Train B RN Pump Structure El 600 (Common) A 31 Unit 2 Train A Aux Shutdown Panel El 543 B 32 Unit 1 Train A Aux Shutdown Panel El 543 B 33 Unit 2 Train B Aux Shutdown Panel El 543 A 34 Unit 1 Train B Aux Shutdown Panel El 543 A 35 Control Room Tagout Area El 594 A or B 36 Unit 2 Turbine Driven CA Pump Control Panel Room El 543 B 37 Unit 1 Turbine Driven CA Pump Control Panel Room El 543 B 38 Unit 1 Fuel Storage Area HVAC Room El 631 A or B (continued)

Catawba Units 1 and 2 16.9-5-19 Revision 11

Fire Rated Assemblies 16.9-5 Table 16.9-5-4 FIRE AREAS AND SHUTDOWN TRAIN / METHOD ASSURED FIRE SHUTDOWN AREA FIRE AREA DESCRIPTIONS TRAIN / METHOD 39 Unit 2 Turbine Driven CA Pump Pit El 543 B 40 Unit 1 Turbine Driven CA Pump Pit El 543 B 41 DG1A Sequencer Tunnel El 556 B 42 DG1B Sequencer Tunnel El 556 A 43 DG2A Sequencer Tunnel El 556 B 44 DG2B Sequencer Tunnel El 556 A 45 Unit 1 Cable Room Corridor El 574 B 46 Unit 2 Cable Room Corridor El 574 B 47 Unit 2 Fuel Storage Area HVAC Room El 631 A or B 48 Unit 2 Interior Doghouse A and B 49 Unit 1 Interior Doghouse A and B 50 Unit 2 Exterior Doghouse A and B 51 Unit 1 Exterior Doghouse A and B ASB Auxiliary Service Building A or B RB1 Unit 1 Reactor Building A and B RB2 Unit 2 Reactor Building A and B SRV Service Building B SSF Standby Shutdown Facility A or B STAIR* Stairway See Note TB1 Unit 1 Turbine Building A or B TB2 Unit 2 Turbine Building A or B YRD** Yard Area A or B

IF the barrier in a stairway is adjacent to a HSS Fire Area (see Table 16.9-5-3), enter CONDITION A; otherwise enter CONDITION C.

- Exterior walls that interface with the YRD do not require entry into a CONDITION statement and therefore do not have a REQUIRED ACTION.

A = A TRAIN B = B TRAIN SSS = STANDBY SHUTDOWN SYSTEM Catawba Units 1 and 2 16.9-5-20 Revision 11

Fire Rated Assemblies 16.9-5 BASES The functional integrity of the Fire Rated Assemblies and associated sealing devices ensures that fires will be confined or adequately retarded so as not to spread between fire areas/compartments.

The fire barriers and associated penetration seals are passive elements in the facility fire protection program and are subject to periodic inspections.

Risk-informed insights from the Fire PRA process can apply to compensatory actions. The safety significance of the fire area can provide relief for required compensatory actions. In addition, the presence of functional fire detection can reduce the required compensatory actions. Functional fire detection in the area provides early warning of a fire for fire brigade response. Fire detection can provide a compensatory action equivalent to or better than fire watch.

Fire barrier penetration seals, including cable/pipe penetration seals and fire dampers, are considered FUNCTIONAL when the visually observed condition indicates no abnormal change or abnormal degradation. An evaluation is performed to determine the cause of any identified fire barrier penetration seal abnormal change in appearance or abnormal degradation and the effect of this change on the ability of the fire barrier penetration seal to perform its function. Based on this evaluation additional inspections may be performed.

Access to Fire Damper 2VA-FD070 is in a locked Hi-Rad area. Due to ALARA reasons, this damper is exempt from inspection requirements (SLC TR 16.9-5-5). The technical justification for excluding this damper from inspection is in calculation CNC-1435.00-00-0035.

During periods of time when a barrier is not FUNCTIONAL, either:

(1) Perform the recommended fire watch in accordance with the criteria in the remedial actions, or (2) a licensee may choose to implement a different required action or a combination of actions (e.g., additional administrative controls, operator briefings, temporary procedures, interim shutdown strategies, operator manual actions, temporary fire barriers, temporary detection or suppression systems). Such a change must be made to the approved Fire Protection Plan (FPP). However, the licensee must complete a documented evaluation of the impact of the proposed required action to the FPP. The evaluation must demonstrate that the required actions would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire. Any change to the FPP must maintain compliance with the General Design Criteria and 10 CFR 50.48(a).

The evaluation of the required action should incorporate risk insights regarding the location, quantity, and type of combustible material in the fire area; the presence of ignition sources and their likelihood of occurrence; the automatic fire suppression and the fire detection Catawba Units 1 and 2 16.9-5-21 Revision 11

Fire Rated Assemblies 16.9-5 capability in the fire area; the manual fire suppression capability in the fire area; and the human error probability where applicable.

BASES (continued)

The expectation is to promptly complete the corrective action at the first available opportunity and eliminate the reliance on the required action.

This SLC is part of the Catawba Fire Protection Program and therefore subject to the provisions of Section 2.C.(5) of the Catawba Renewed Facility Operating Licenses.

REFERENCES 1. Catawba UFSAR, Section 9.5.1.

2. Catawba Nuclear Station 10 CFR 50.48(c) Fire Protection Safety Evaluation (SE).

3. Catawba Plant Design Basis Specification for Fire Protection, CNS-1465.00-00-0006, as revised.

4. Catawba UFSAR, Section 18.2.8.

5. Catawba License Renewal Commitments, CNS-1274.00 0016, Section 4.12.2.

6. NRC Regulatory Issue Summary 2005-07, Compensatory Measures to Satisfy the Fire Protection Program Requirements, April 19, 2005.

7. Catawba Renewed Facility Operating License Conditions 2.C.(5).

8. CNC-1435.00-00-0084, Catawba NFPA 805 Monitoring Program.

9. CNC-1435.00-00-0044, Fire Protection Nuclear Safety Capability Assessment.

10. CNC-1435.00-00-0035, Penetration Seal Data Base and 86-10 Evaluations.

11. CN-1209.10 series drawings.

12. CN-1105 series drawings.

Catawba Units 1 and 2 16.9-5-22 Revision 11

MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)

OPERABLE Main Steam Safety Valves versus Maximum Allowable Power Range Neutron Flux High Setpoints in Percent of RATED THERMAL POWER MINIMUM NUMBER OF MAXIMUM ALLOWABLE POWER MSSVs PER STEAM RANGE NEUTRON FLUX HIGH GENERATOR REQUIRED SETPOINTS (% RTP)

OPERABLE Unit 1 Unit 2 4 < 57 < 58 3 < 40 < 41 2 < 24 < 24 Table 3.7.1-2 (page 1 of 1)

Main Steam Safety Valve Lift Settings VALVE NUMBER LIFT SETTING (psig +/- 3%)

STEAM GENERATOR A B C D SV-20 SV-14 SV-8 SV-2 1175 SV-21 SV-15 SV-9 SV-3 1190 SV-22 SV-16 SV-10 SV-4 1205 SV-23 SV-17 SV-11 SV-5 1220 SV-24 SV-18 SV-12 SV-6 1230 Catawba Units 1 and 2 3.7.1-3 Amendment Nos. 281/277

Examination KEY ILT 21 CNS SRO NRC Examination Q A Q A Q A Q A 1 D 26 A 51 B 76 A 2 C 27 D 52 D 77 B 3 B 28 B 53 A 78 B 4 D 29 B 54 B 79 B 5 A 30 C 55 B 80 D 6 C 31 D 56 D 81 C 7 A 32 C 57 B 82 D 8 B 33 D 58 D 83 C 9 D 34 B 59 B 84 B 10 A 35 D 60 B 85 D 11 D 36 A 61 C 86 A 12 B 37 B 62 D 87 B 13 A 38 C 63 C 88 C 14 A 39 B 64 C 89 C 15 A 40 C 65 C 90 A 16 D 41 A 66 B 91 D 17 A 42 B 67 C 92 B 18 D 43 C 68 A 93 A 19 B 44 D 69 C 94 C 20 B 45 D 70 C 95 C 21 A 46 C 71 D 96 C 22 D 47 D 72 A 97 C 23 B 48 C 73 A 98 B 24 C 49 D 74 D 99 A 25 C 50 A 75 A 100 C Printed 9/29/2021 1:58:09 PM Page 1 of 1

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