ML24309A046

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RO as Given Catawba 2024
ML24309A046
Person / Time
Site: Catawba  
Issue date: 11/04/2024
From:
NRC/RGN-III/DRSS
To:
Duke Energy Corp
References
Download: ML24309A046 (1)
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Text

Question:

(1 point) 1 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following initial conditions:

Unit 1 was at 100% RTP 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 Control Rod H-8 fails to fully insert into the core 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.

Control Rod position _____(2)_____ require emergency boration.

Which ONE of the following completes the statement 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 1 of 75 ML24309A046

Question:

(1 point) 2 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following initial conditions:

Unit 1 is at 100% RTP A Pressurizer Safety Valve begins leaking by its seat AP/1/A/5500/010 (Reactor Coolant Leak) Case II (NC System Leak) is entered 1NV-294 (NV Pmps A&B Disch Flow Ctrl) is throttled to the fully open position Subsequently:

Pressurizer Level is at 53% and lowering at a rate of 0.2% per minute Letdown flow is 85 gpm and stable Pressurizer Pressure is 2215 psig and lowering slowly Per AP/10, charging flow must be maintained less than a MAXIMUM of

_____(1)_____ gpm.

Reducing letdown flow to 45 gpm _____(2)_____ establish control of PZR level.

Which ONE of the following completes the statements above?

A.

1.
2.

120 will B.

1.
2.

120 will NOT C.

1.
2.

180 will D.

1.
2.

180 will NOT Page 2 of 75

Question:

(1 point) 3 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Both units at 100% RTP A Small Break LOCA occurred on Unit 1 Unit 2 remains at power The Unit 1 crew has entered EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) 1A NI Pump failed to automatically start 2B RN Pump failed to automatically start The CRS has instructed the Unit 1 BOP to perform Enclosure 2 (Automatic S/I Actions Verification)

In accordance with E-0, Enclosure 2 the BOP:

_____(1)_____ reset 1A ECCS.

_____(2)_____ reset 1B ECCS.

Which ONE of the following completes the statements above?

A.

1. will
2. will B.
1. will
2. will NOT C.
1. will NOT
2. will D.
1. will NOT
2. will NOT Page 3 of 75

Question:

(1 point) 4 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 2 is in Mode 3 Rod control is capable of rod withdrawal NC loops 2A, 2B, and 2D are in operation The crew has entered AP/2/A/5500/008 (Malfunction of Reactor Coolant Pump) 2A NC Pump motor bearing temperature is currently 190ºF and rising at 5ºF per minute 2A NC Pump motor bearing temperature will reach trip setpoint in

_____(1)_____.

Following the trip of 2A NCP, LCO 3.4.5 (RCS Loops - MODE 3) specifies a REQUIRED ACTION to _____(2)_____.

Which ONE of the following completes the statements above?

A.

1. 7 minutes
2. deenergize all CRDMs within ONE HOUR B.
1. 7 minutes
2. IMMEDIATELY suspend operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet SDM of LCO 3.1.1 C.
1. 1 minute
2. deenergize all CRDMs within ONE HOUR D.
1. 1 minute
2. IMMEDIATELY suspend operations that would cause introduction of coolant into the RCS with boron concentration less than required to meet SDM of LCO 3.1.1 Page 4 of 75

Question:

(1 point) 5 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following initial conditions:

1A NV Pump is removed from service for PMs 1B NV Pump trips on breaker malfunction The crew has entered AP/1/A/5500/012 (Loss of Charging or Letdown)

All other systems remain in normal alignment The crew _____(1)_____ trip the reactor based on direction provided by AP/12.

The loss of both NV Pumps results in degradation of the _____(2)_____ head injection subsystem of ECCS.

Which ONE of the following completes the statements above?

A.

1.

will

2.

high B.

1.

will

2.

intermediate C.

1.

will NOT

2.

high D.

1.

will NOT

2.

intermediate Page 5 of 75

Question:

(1 point) 6 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is at 4% RTP following startup 1NC-29 (PZR Spray Ctrl Frm Loop B) fails to an intermediate position The BOP selected FAIL CLOSED on 1NC-29 PZR Spray Vlv Mode Select switch Pressurizer Pressure continues to lower slowly Per the immediate actions of AP/1/A/5500/011 (Pressurizer Pressure Anomalies)

Case I (Pressurizer Pressure Trending Down):

The BOP will secure NC Pump(s) _____(1)_____.

The crew will transition to _____(2)_____.

Which ONE of the following completes the statements above?

A.

1. 1B and check pressure, if pressure not rising then secure 1A
2. AP/1/A/5500/004 (Loss of Reactor Coolant Pump)

B.

1. 1B and check pressure, if pressure not rising then secure 1A
2. EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

C.

1. 1A AND 1B
2. AP/1/A/5500/004 (Loss of Reactor Coolant Pump)

D.

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

Page 6 of 75

Question:

(1 point) 7 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 Reactor has experienced a Safety Injection due to Low PZR Pressure The CRS has just completed reading the immediate action steps of EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

The following EMFs are in Trip 2 condition:

o 1EMF-33 (Condenser Air Ejector Exhaust) o 1EMF-71 (S/G A Leakage) o 1EMF-74 (S/G D Leakage) o 1EMF-26 (Steam Line 1A) 1A S/G NR level is 35%

1B, 1C and 1D S/G NR levels are 23%

Total CA flow is approximately 1000 gpm The RO has depressed the CA SYS VLV CTRL TRN A and CA SYS VLV CTRL TRN B reset buttons CA SYS VLV CTRL TRN A reset light is DARK CA SYS VLV CTRL TRN B reset light is LIT CA flow to 1A S/G using the flow control valve _____(1)_____ under operator control.

EP/1/A/5000/E-0 _____(2)_____ require isolation of CA flow to the 1A S/G at this time.

Which ONE of the following completes the statements above?

A.

1. is
2. does B.
1. is
2. does NOT C.
1. is NOT
2. does D.
1. is NOT
2. does NOT Page 7 of 75

Question:

(1 point) 8 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following initial conditions:

Unit 2 is in Mode 3 performing a plant cooldown NC System pressure is 1300 PSIG All S/G pressures are 800 PSIG BLOCK pushbuttons have been depressed for both trains of ECCS steam pressure and ECCS Pzr pressure Subsequently:

A steamline rupture occurs inside containment from the 2A S/G Containment pressure peaked at 1.5 PSIG All MSIV's indicate closed Based on the conditions above, the Main Steam Isolation Valves closed because SG pressure lowered _____(1)_____.

In addition to the closure of the MSIV's, the _____(2)_____.will also receive a signal to close.

Which ONE of the following completes the statements above?

A.

1.
2.

100 psig in 1 second MSIV bypass valves ONLY B.

1.
2.

100 psig in 1 second MSIV bypass valves AND the S/G PORVs C.

1.
2.

to less than or equal to 775 psig MSIV bypass valves ONLY D.

1.
2.

to less than or equal to 775 psig MSIV bypass valves AND the S/G PORVs Page 8 of 75

Question:

(1 point) 9 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 Reactor was manually tripped due to loss of feedwater The Main Turbine failed to trip Automatically and Manually Safety Injection actuated on low Pressurizer pressure due to NC cooldown caused by the Turbine trip failure MSIVs remain open The crew has entered EP/1/A/5000/FR-H.1 (Response To Loss of Secondary Heat Sink)

Feed and Bleed criteria has NOT been met All attempts to restore CA flow have failed The crew is attempting to restore feed flow via operation of 1A CFPT In accordance with FR-H.1, the CF Isolation signal _____(1)_____ required to be bypassed prior to initiating feedwater flow.

Once the 1A CFPT is placed in service, the crew _____(2)_____ limit feedwater flow to 100 gpm to each S/G.

Which ONE of the following completes the statements above?

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 9 of 75

Question:

(1 point) 10 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following initial conditions:

Both units have experienced a Loss of Offsite Power (LOOP)

No backup Diesel VI compressor is available EP/1/A/5000/ECA-0.0 (Loss of All AC Power) was implemented on Unit 1 and the crew has just transitioned to EP/1/A/5000/ECA-0.1 (Loss of All AC Power Recovery Without S/I Required)

Current conditions:

30 minutes have elapsed since the LOOP NC Thots are STABLE S/G pressures are STABLE at 735 PSIG S/G levels are 16% NR and STABLE NC Tcolds are 510°F and STABLE VI header pressure is 0 PSIG Natural Circulation flow _____(1)_____ be verified.

In accordance with ECA-0.1, the Operators will increase CA flow

_____(2)_____.

Which ONE of the following completes the statements above?

A.

1. can
2. using flow controllers in the control room B.
1. can
2. by notifying AO to throttle CA valves locally C.
1. can NOT
2. using flow controllers in the control room D.
1. can NOT
2. by notifying AO to throttle CA valves locally Page 10 of 75

Question:

(1 point) 11 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following:

A Loss of Offsite Power has occurred on Unit 1 1A and 1B D/Gs have automatically started and loaded their respective busses Subsequently (following D/G start):

The crew has entered AP/1/A/5500/007 (Loss of Normal Power)

Cooling water flow cannot be established to 1A D/G o The CRS has directed 1A D/G shutdown 1B D/G Annunciator A/4 Trip Low Press Lube Oil is in alarm o 1B D/G lube oil pressure is 33 psig and stable Per AP/07, to complete the shutdown of 1A D/G, the 1A sequencer

_____(1)_____ required to be reset or deenergized.

Based on above listed conditions, 1B D/G Annunciator A/4 _____(2)_____

direct a trip of 1B D/G.

Which ONE of the following completes the statements above?

A.

1.
2.

is does B.

1.
2.

is does NOT C.

1.
2.

is NOT does D.

1.
2.

is NOT does NOT Page 11 of 75

Question:

(1 point) 12 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is stable at 100% RTP The following Annunciators actuate:

o 1AD-11 A/8 125VDC Diesel Gen A Control Pwr Sys Trbl o 1AD-11 B/7 D/G A Panel Trouble The dispatched operator reports the following:

o 1A D/G Panel E/5 Loss of DC Control Power lit o Breaker 1DGCA-B304 has tripped open and appears to be damaged In accordance with the 1A D/G Panel E/5 Annunciator Response Procedure:

Upon a Loss of Offsite Power, the 1A D/G _____(1)_____ automatically start.

The 1A D/G _____(2)_____ be started manually.

Which ONE of the following completes the statements above?

A.

1. will
2. can B.
1. will NOT
2. can C.
1. will
2. can NOT D.
1. will NOT
2. can NOT Page 12 of 75

Question:

(1 point) 13 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Units 1 and 2 have entered AP/0/A/5500/032 (Loss of Recirculated Cooling Water) due to a loss of KR cooling E & F VI Compressor oil temperatures have reached Hi alarm (Foldout Page) of AP/32 will direct operators to align

_____(1)_____ cooling to two VI compressors.

Cooling water discharge will be aligned to the _____(2)_____ system.

Which ONE of the following completes the statements above?

A.

1. RF
2. RN B.
1. RF
2. RL C.
1. RL
2. RN D.
1. RN
2. RL Page 13 of 75

Question:

(1 point) 14 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

1VI-7 (VI Receiver A Relief) opened due to high pressure and failed to re-seat The crew entered AP/0/A/5500/022 (Loss of Instrument Air) 1VI-7 has been isolated VI pressure has been restored to normal operating pressure Isolation of 1VI-7 required __________ to be isolated from the system.

Which ONE of the following completes the statement above?

REFERENCE PROVIDED A.

D VI Compressor ONLY B.

E VI Compressor ONLY C.

D AND F VI Compressors D.

E AND F VI Compressors Page 14 of 75

Question:

(1 point) 15 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is operating at 100% power Main Generator hydrogen pressure is at 60 PSIG A grid disturbance then occurs The operator observes the following indications in the Control Room:

o Turbine Load: 1225 MWs o MegaVARS: - 500 MVARs (a negative value) o Generator Voltage: 20.8 Kilovolts o 1AD-1, C/4 GEN EXCITATION LIMITER ACTIVE is in alarm o 1AD-1, D/5 GEN VOLT REG COMMON TROUBLE is in alarm o GEN VOLT REG EMERGENCY MANUAL MODE indicating light is LIT Which ONE of the following describes how the operator will operate the Turbine Generator controls, per AP/1/A/5500/037, (Generator Voltage and Electric Grid Disturbances) to address these conditions?

REFERENCE PROVIDED A.

Maintain turbine load at 1225 MWs Manually lower excitation current to change MVARs by a value of 250 MVARs.

B.

Maintain turbine load at 1225 MWs Manually raise excitation current to change MVARs by a value of 250 MVARs.

C.

Lower turbine load to 1180 MWs Operate the VOLTAGE ADJUST AUTO setpoint to a higher value.

D.

Lower turbine load to 1180 MWs Operate the VOLTAGE ADJUST AUTO setpoint to a lower value.

Page 15 of 75

Question:

(1 point) 16 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following initial conditions:

Unit 1 has experienced a LOCA outside containment 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 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 75

Question:

(1 point) 17 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

A Unit 1 LOCA has occurred 1NI-184B and 1NI-185A (Containment Sump Isolation Valves) are closed and cannot be opened The crew has entered EP/1/A/5000/ECA-1.1 (Loss of Emergency Coolant Recirculation)

All NC Pumps are off Minimum ECCS flow to remove decay heat has been established In accordance with ECA-1.1, the crew will raise NC make-up flow if _________.

Which ONE of the following completes the statement above?

A.

Hot Leg Wide Range (WR) temperatures raise by 5° F B.

Pressurizer level is 2% and lowering C.

RVLIS Lower Range (LR) is 64% and stable D.

Core Exit Thermocouples are 650°F and rising Page 17 of 75

Question:

(1 point) 18 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 has entered EP/1/A/5000/FR-H.1 (Response to Loss of Secondary Heat Sink) due to loss of heat sink All attempts to restore CA flow have been unsuccessful Both CFPTs are unavailable. The crew will depressurize to establish feed flow from the CM system Feed and Bleed criteria has NOT been met In accordance with FR-H.1, it is preferable to depressurize _____(1)_____

S/G(s) in order to _____(2)_____.

Which ONE of the following completes the statement above?

A.

1.

1

2.

minimize NC system cooldown B.

1.

2

2. maintain maximum remaining heat sink C.
1.

2

2.

leave two S/G levels above feed and bleed criteria D.

1.

3

2.

maximize available condensate makeup flow Page 18 of 75

Question:

(1 point) 19 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following WR NIS Power trends:

TREND A TREND B Based on the trends above, _____(1)_____ indicates that a dropped rod has occurred.

For a dropped rod, the background color on the DRPI display for the affected rod group will be _____(2)_____.

Which ONE of the following completes the statements above?

A.

1. Trend A
2. orange B.
1. Trend A
2. black C.
1. Trend B
2. orange D.
1. Trend B
2. black Page 19 of 75

Question:

(1 point) 20 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

A spurious Unit 1 Turbine trip, from 100% RTP, has initiated a Reactor Trip signal The Reactor has failed to trip automatically and manually The crew has transitioned from EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) to the designated procedure o The OATC is performing appropriate actions Based on the given conditions, the crew _____(1)_____ initiate Emergency Boration.

If required to be initiated, Emergency Boration flow must be greater than a MINIMUM of _____(2)_____.

Which ONE of the following complete the statement above?

A.

1. will
2. 30 gpm B.
1. will
2. 60 gpm C.
1. will NOT
2. 30 gpm D.
1. will NOT
2. 60 gpm Page 20 of 75

Question:

(1 point) 21 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Following a Unit 1 Turbine Runback, a Pressurizer Level Control malfunction has erroneously raised the Pressurizer level setpoint The crew has placed Pressurizer Level Control master in manual and have now established control Current conditions are as follows:

o Indicated Pressurizer level is 50%

o Indicated Pressurizer temperature is 600°F Based on conditions provided above, actual Pressurizer level is __________.

Which ONE of the following completes the statement above?

REFERENCE PROVIDED A.

45%

B.

50%

C.

55%

D.

70%

Page 21 of 75

Question:

(1 point) 22 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is in Mode 3 NC pressure is stable at 1900 PSIG All shutdown banks have been withdrawn N-31 indication becomes erratic and the crew enters AP/1/A/5500/016 (Malfunction of Nuclear Instrumentation System)

The LEVEL TRIP switch for N-31 has been placed in BYPASS A loss of N-31 _____(1)_____ will result in an automatic reactor trip, and operators are required to enter _____(2)_____.

Which ONE of the following completes the statement above?

A.

1. instrument power
2. AP/1/A/5500/005 (Reactor Trip or Inadvertent S/I Below P-11)

B.

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

C.

1. control power
2. AP/1/A/5500/005 (Reactor Trip or Inadvertent S/I Below P-11)

D.

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

Page 22 of 75

Question:

(1 point) 23 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

A Unit 1 reactor startup is in progress Based on the following indications, the startup has been placed on hold:

o N-31 indicates 1.1x104 cps o

N-32 indicates 1.0x104 cps o

N-35 indicates 1.9x10-5 % power o

N-36 indicates 2.0x10-6 % power Rods are in manual with no rod motion CRS has entered AP/1/A/5500/016 (Malfunction of Nuclear Instrumentation System) Case 3 (Intermediate Range Malfunction) due to one of the intermediate range channels being inoperable The affected intermediate range channel is _____(1)_____.

The P-6 S/R BLOCK PERMISSIVE light on 1SI-18 _____(2)_____ lit.

Which ONE of the following completes the statements above?

A.

1. N-35
2. is B.
1. N-35
2. is NOT C.
1. N-36
2. is D.
1. N-36
2. is NOT Page 23 of 75

Question:

(1 point) 24 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Loaded Dry Cask movement is in progress in Unit 1 Spent Fuel Pool The Control Room receives a 1RAD-3 F/5 (Cabinet Trouble) and determines 1EMF-15 (Spent Fuel Bldg Refuel Brdg) has suffered a detector failure Which ONE of the following states the EARLIEST REQUIRED Selected Licensee Commitments (SLC) action?

A.

Provide a portable continuous monitor with the same alarm setpoint IMMEDIATELY B.

Provide a portable continuous monitor with the same alarm setpoint WITHIN 1 HOUR C.

Ensure Spent Fuel Building Ventilation (VF) is aligned to Filter Mode IMMEDIATELY D.

Suspend all fuel movement operations in the fuel handling area being monitored WITHIN 1 HOUR Page 24 of 75

Question:

(1 point) 25 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following timeline:

1000 Unit 1 is at 100% RTP 1EMF-48 (NC Sample Line Reactor Coolant) Trip 2 alarm is LIT 1EMF-18 (568 KK, 56 NC Filter 1A) count rate is rising Crew enters AP/1/A/5500/018 (High Activity in Reactor Coolant)

Letdown temperature is 128°F and stable Chemistry reports Dose Equivalent Iodine (DEI) has reached Action Level 3 per requirements of AD-NF-ALL-0806 (Nuclear Fuel Integrity) 1030 Unit 1 Large Break LOCA occurs An incomplete containment isolation results in a release At time 1000, AP/18 _____(1)_____ direct placing a mixed bed demineralizer in service.

At time 1030, the Control Room crew is being protected, from the effects of Iodine, by operation of VC system _____(2)_____.

Which ONE of the following completes the statements above?

A.

1. will
2. HEPA Filters B.
1. will
2. Carbon Adsorber C.
1. will NOT
2. HEPA Filters D.
1. will NOT
2. Carbon Adsorber Page 25 of 75

Question:

(1 point) 26 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following:

Unit 1 has experienced an event Containment pressure is 2.8 PSIG Containment radiation is indicating 37 R/Hr Containment sump level is 14 feet Entry requirements for EP/1/A/5000/FR-Z.3 (Response to High Containment Radiation Level) _____(1)_____ currently met.

TS 3.3.3 (Post-Accident Monitoring Instrumentation) requires operability of

_____(2)_____.

Which ONE of the following completes the statements above?

A.

1. are
2. Containment Radiation Instruments ONLY B.
1. are
2. Containment Radiation AND Containment Sump Water Level Instruments C.
1. are NOT
2. Containment Radiation Instruments ONLY D.
1. are NOT
2. Containment Radiation AND Containment Sump Water Level Instruments Page 26 of 75

Question:

(1 point) 27 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is at 30% RTP, holding for chemistry The 1A NC pump trips Assuming no operator action, Indicated Loop "A" Tavg will stabilize at a _____(1)_____ value than prior to the 1A NC pump trip.

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

Which ONE of the following completes the statements above?

A.

1. higher
2. is B.
1. lower
2. is C.
1. higher
2. is NOT D.
1. lower
2. is NOT Page 27 of 75

Question:

(1 point) 28 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is at 41% RTP 1D NCP (Reactor Coolant Pump) trips due to breaker failure 1D S/G level indication will initially _____(1)_____.

An automatic reactor trip _____(2)_____ occur.

Which ONE of the following completes the statements above?

A.

1. rise
2. will B.
1. rise
2. will NOT C.
1. lower
2. will D.
1. lower
2. will NOT Page 28 of 75

Question:

(1 point) 29 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is in Mode 3 1NCP5153 (PZR Level Channel 2) is removed from service for calibration A Steam Dump failure causes a cooldown o PZR level lowers to 12%

The PZR Level Master controller remains in AUTO As the PZR level lowers, NV Letdown isolation valve(s) _____(1)_____ will automatically close.

Assuming letdown remains isolated, once PZR level is restored to reference level NV charging line flow will be approximately _____(2)_____.

Which ONE of the following completes the statements above?

COMPONENT LEGEND:

1NV-1A (NC Letdn To Regen Hx Isol) 1NV-2A (NC Letdn To Regen Hx Isol)

A.

1. 1NV-2A ONLY
2. 47 gpm B.
1. 1NV-1A AND 1NV-2A
2. 47 gpm C.
1. 1NV-2A ONLY
2. 12 gpm D.
1. 1NV-1A AND 1NV-2A
2. 12 gpm Page 29 of 75

Question:

(1 point) 30 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is cooling down in Mode 4 1A1 and 1A2 KC Pumps are in service 1A ND is being aligned for RHR 1AD-9 F/7 KC Train A Two Pump Runout has alarmed Aligning cooling water flow to 1A ND Heat Exchanger increased KC system flow by a MINIMUM of _____(1)_____.

The setpoint for 1AD-9 F/7 is _____(2)_____.

Which ONE of the following completes the statements above?

A.

1. 5,000 gpm
2. 10,800 gpm B.
1. 5,000 gpm
2. 11,400 gpm C.
1. 5,600 gpm
2. 10,800 gpm D.
1. 5,600 gpm
2. 11,400 gpm Page 30 of 75

Question:

(1 point) 31 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

A Unit 1 Large Break LOCA occurred 40 minutes ago 1B ND pump is tagged out for maintenance EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation) has been completed to align 1A ND pump to the suctions of the NV and NI pumps Attempts to align an NS pump for containment spray have been unsuccessful Containment pressure is 16 PSIG and rising slowly EP/1/A/5000/FR-Z.1 (Response to High Containment Pressure) has been entered In accordance with FR-Z.1, 1A train of ND _____(1)_____ be aligned for Aux Containment Spray at this time because _____(2)_____.

Which ONE of the following completes the statement above?

A.

1. can
2. containment pressure is > 15 PSIG B.
1. can NOT
2. 1B ND pump is tagged out C.
1. can
2. ECCS is aligned in Cold Leg Recirculation D.
1. can NOT
2. the time requirement following a LOCA has not been met Page 31 of 75

Question:

(1 point) 32 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

A Unit 2 Safety Injection has occurred The BOP notices PRT level, pressure, and temperature rising slowly NO ESFAS related signals have been reset Based on the conditions above:

Venting of the PRT, to the Waste Gas System, _____(1)_____ available.

Cooling of the PRT, via RMWST makeup, _____(2)_____ available.

Which ONE of the following completes the statements above?

A.

1.

is

2.

is B.

1.

is

2.

is NOT C.

1.

is NOT

2.

is D.

1.

is NOT

2.

is NOT Page 32 of 75

Question:

(1 point) 33 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is at 100% power 1A1 KC Pump is in service Aux Safeguards testing is in progress 1KC-230A (Rx Bldg Non-Ess Hdr Isol) and 1KC-50A (Aux Bldg Non-Ess Hdr Isol) are inadvertently closed during testing Multiple Annunciators are received, including:

o 1AD-20 A/1 KC Supply Hdr Flow to NCP Brgs Low In order to restore cooling water flow, the crew will enter _____(1)_____.

The CRS will direct the BOP to _____(2)_____.

Which ONE of the following completes the statements above?

A.

1. AP/1/A/5500/021 (Loss of Component Cooling)
2. start a B train KC pump B.
1. AP/1/A/5500/021 (Loss of Component Cooling)
2. trip the reactor and NC pumps C.
1. AP/1/A/5500/008 (Malfunction of Reactor Coolant Pump)
2. start a B train KC pump D.
1. AP/1/A/5500/008 (Malfunction of Reactor Coolant Pump)
2. trip the reactor and NC pumps Page 33 of 75

Question:

(1 point) 34 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following timeline:

1000 Unit 1 is at 100% RTP 1NC-32B (PZR PORV) failed to the intermediate position NC Pressure is 2180 psig and lowering 1002 1NC-32B (PZR PORV) is in the Intermediate position 1NC-31B (PZR PORV Isol) is Closed NC Pressure is 2180 PSIG and rising slowly At time 1000, entry into _____(1)_____ is required.

At time 1002, the remaining Immediate Actions, of the appropriate procedure, include _____(2)_____.

Which ONE of the following completes the statements above?

A.

1.
2.

AP/1/A/5500/010 (Reactor Coolant Leak)

Reducing letdown B.

1.
2.

AP/1/A/5500/010 (Reactor Coolant Leak)

Verifying PZR level - Stable or Trending Up C.

1.
2.

AP/1/A/5500/011 (Pressurizer Pressure Anomalies)

Verifying all PZR Heaters are Energized D.

1.
2.

AP/1/A/5500/011 (Pressurizer Pressure Anomalies)

Verifying PZR Spray Valve(s) - Closed Page 34 of 75

Question:

(1 point) 35 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station 1NC-35B (PZR PORV Isol) receives power from __________.

Which ONE of the following completes the statements above?

A.

1EPA B.

1EDF C.

1EMXC D.

1EMXD Page 35 of 75

Question:

(1 point) 36 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following initial conditions:

Unit 1 is at 12% RTP following startup Required actions for being > 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 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 36 of 75

Question:

(1 point) 37 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station One function of the Auxiliary Building Ventilation (VA) System is to __________.

Which ONE of the following completes the statement above?

A.

maintain a negative pressure in the Annulus B.

maintain a negative pressure in the ECCS pump rooms C.

maintain proper ventilation of the Diesel Building for equipment operation D.

maintain switchgear rooms within acceptable limits for equipment operation and post-accident habitability Page 37 of 75

Question:

(1 point) 38 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following initial conditions:

2A, 2B, & 2C Lower Containment Ventilation Units (LCVUs) are operating in low speed Subsequently:

A safety injection occurs due to high containment pressure Containment pressure is 1.5 PSIG and stable One minute after the Safety Injection, with no operator actions:

The 2A, 2B, & 2C LCVUs will be operating in _____(1)_____ speed.

2RN-473 (LWR CONT VENT UNIT 2A FULL FLOW) valve is _____(2)_____.

Which ONE of the following completes the statements above?

A.

1. low
2. CLOSED B.
1. low
2. OPEN C.
1. high
2. CLOSED D.
1. high
2. OPEN Page 38 of 75

Question:

(1 point) 39 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 2 is operating at 100% RTP Aux Safeguards testing is in progress A spurious signal is inserted which causes 2VI-77B (VI Cont Isol) to close The spurious signal simulated a _____(1)_____ Containment Isolation signal.

As a result of 2VI-77B closing, lower containment temperature will

_____(2)_____.

Which ONE of the following completes the statements above?

A.

1. phase A
2. rise B.
1. phase B
2. rise C.
1. phase A
2. lower D.
1. phase B
2. lower Page 39 of 75

Question:

(1 point) 40 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Concerning operation of the Ice Condenser Air Handling Units:

Glycol cooling water supply is isolated from containment upon initiation of a

_____(1)_____ signal.

The glycol expansion tank is located in the _____(2)_____.

Which ONE of the following completes the statements above?

A.

1. Phase A
2. Auxiliary Building B.
1. Phase A
2. Containment Building C.
1. Phase B
2. Auxiliary Building D.
1. Phase B
2. Containment Building Page 40 of 75

Question:

(1 point) 41 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

A Unit 1 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(s) will be aligned when/if Containment pressure reaches a MINIMUM of _____(1)_____.

Once this pressure is reached / verified, the BOP will align RN flow through

_____(2)_____ NS Heat Exchanger(s).

Which ONE of the following completes the statements above?

A.

1.
2.

1 PSIG one B.

1.
2.

1 PSIG both C.

1.
2.

3 PSIG one D.

1.
2.

3 PSIG both Page 41 of 75

Question:

(1 point) 42 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following:

Unit 1 is at 100% RTP A loss of _____(1)_____ will result in closure of _____(2)_____ MSIVs.

Which ONE of the following completes the statements above?

A.

1. 1EPA (125 VDC Panelboard)
2. ONLY 1A and 1C B.
1. 1EPA (125 VDC Panelboard)
2. ALL Unit 1 C.
1. 1ERPA (120 VAC Panel board)
2. ONLY 1A and 1C D.
1. 1ERPA (120 VAC Panel board)
2. ALL Unit 1 Page 42 of 75

Question:

(1 point) 43 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 was at 85% RTP 1A CFPT tripped due to low vacuum Following trip of 1A CFPT, turbine load was lowered to a runback setpoint of

_____(1)_____ at a rate of _____(2)_____ per minute.

Which ONE of the following completes the statement above?

A.

1. 48%
2. 25%

B.

1. 65%
2. 25%

C.

1. 48%
2. 80%

D.

1. 65%
2. 80%

Page 43 of 75

Question:

(1 point) 44 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following initial conditions:

Unit 1 is at 100% RTP 1ETA-03 (Normal Incoming Feeder to Xfmr 1ATC) spuriously opened resulting in a Blackout of 1ETA 1A D/G failed to start due to mechanical failure Subsequently (1 Minute later):

1B S/G experiences a fault resulting in a Unit 1 Safety Injection 1A, 1C, and 1D S/G levels have lowered to 25% NR level 1B S/G level indicates 0% NR level The crew enters EP/1/A/5000/E-0 (Reactor Trip or Safety Injection)

The OATC has been directed to isolate CA flow to 1B S/G CAPT #1 _____(1)_____ receive an AUTOMATIC start signal.

1CA-58A (CA Pump A Disch To S/G 1B Isol) _____(2)_____ be used to isolate flow to 1B S/G.

Which ONE of the following completes the statements above?

A.

1. did
2. can B.
1. did
2. can NOT C.
1. did NOT
2. can D.
1. did NOT
2. can NOT Page 44 of 75

Question:

(1 point) 45 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 2 is stable at 25% RTP The power supply to 2TB from transformer 2T1B spuriously opens Due to the above conditions:

NC Pump 2B is _____(1)_____.

Once available, the power supply to 2TB is restored to normal alignment by a(n)

_____(2)_____ transfer.

Which ONE of the following completes the statements above?

A.

1. tripped
2. automatic B.
1. running
2. automatic C.
1. tripped
2. manual D.
1. running
2. manual Page 45 of 75

Question:

(1 point) 46 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is at 100% RTP Distribution Panel 1CDA has de-energized due to a malfunction of Battery 1CBA The crew has entered AP/1/A/5500/029 (Loss of Vital or Aux Control Power)

The CRS is directing steps in Enclosure 18 (Restoring Power to 1CDA) to remove Battery 1CBA from service while restoring power to 1CDA Per the direction of AP/29 to remove 1CBA from service:

Tie Breakers between 1CDA and 1CDB _____(1)_____ be closed.

1CCS (Standby Battery Charger) _____(2)_____ be aligned to 1CDA.

Which ONE of the following completes the statements above?

A.

1. will
2. will B.
1. will
2. will NOT C.
1. will NOT
2. will D.
1. will NOT
2. will NOT Page 46 of 75

Question:

(1 point) 47 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is at 100% RTP The 125 VDC/120 VAC Auxiliary Control Power System is in normal alignment The supply breaker from 1CDA to Static Inverter 1KXIA trips open Alternate power to 1KXPA will be _____(1)___ aligned.

The crew can verify 1KXPA is energized by observing that _____(2)_____.

Which ONE of the following completes the statements above?

A.

1. automatically
2. NC pump vibration monitor is IN SERVICE B.
1. manually
2. NC pump vibration monitor is IN SERVICE C.
1. automatically
2. individual P-11 Channel 1 status light on 1SI-7 is LIT D.
1. manually
2. individual P-11 Channel 1 status light on 1SI-7 is LIT Page 47 of 75

Question:

(1 point) 48 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following:

The 1B KD Standpipe level is measured using a differential pressure level detector The level instrument is calibrated at the current water temperature in the tank A leak in the 1B LD Heat Exchanger results in lube oil collecting in the 1B KD Standpipe Assuming that the temperature of the contents in the standpipe does not change, indicated Standpipe level will be _____(1)_____ than actual tank level because lube oil is _____(2)_____ than water.

Which ONE of the following completes the statement above?

A.

1. lower
2. less dense B.
1. lower
2. more dense C.
1. higher
2. less dense D.
1. higher
2. more dense Page 48 of 75

Question:

(1 point) 49 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is operating at 100% RTP RP has requested the setpoints be changed for Trip 1 and 2 on 1EMF-38 (Containment Monitor - Particulate)

Current 1EMF-38 setpoints are as follows:

o Trip 1 - 7.0E+1 cpm o Trip 2 - 1.0E+2 cpm If the BOP inputs a Trip 1 value of 1.2E+2, the EMF module _____(1)_____

accept it.

When performing a source check on an EMF, the Trip 1 and Trip 2 lights

_____(2)_____ illuminate.

Which ONE of the following completes the statements above?

A.

1. will
2. will B.
1. will
2. will NOT C.
1. will NOT
2. will D.
1. will NOT
2. will NOT Page 49 of 75

Question:

(1 point) 50 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Concerning the operation of 1EMF-46A (Component Cooling Water):

When a Trip 2 alarm is received, 1KC-122 (KC Surge Tank Vent)

_____(1)_____ automatically close.

When the associated KC train pumps are NOT running, the EMF loss of flow alarm _____(2)_____ blocked from being received in the control room.

Which ONE of the following completes the statements above?

A.

1. will
2. is B.
1. will
2. is NOT C.
1. will NOT
2. is D.
1. will NOT
2. is NOT Page 50 of 75

Question:

(1 point) 51 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following initial conditions:

Unit 1 is shutdown with cooldown in progress Unit 1 NC system temperature is 195°F and lowering Unit 2 is at 100% RTP 1B and 2A RN pumps are in service 1B1, 1B2, and 2B1 KC pumps are in service All KC Hx Outlet Throttle Valves remain in Automatic control Subsequently:

1B RN pump trips 1RN-351 (1B KC Hx Outlet Throttle) will throttle in the _____(1)_____ direction.

Tech Spec 3.7.8 (Nuclear Service Water System (NSWS)) _____(2)_____

applicable at this time for Unit 1.

Which ONE of the following completes the statements above?

A.

1.

open

2.

is B.

1.

open

2.

is NOT C.

1.

closed

2.

is D.

1.

closed

2.

is NOT Page 51 of 75

Question:

(1 point) 52 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Units 1 & 2 are at 100% RTP 1A RN pump is in service 1B and 2B KC trains are 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 The crew has entered AP/0/A/5500/020 (Loss of Nuclear Service Water), Case II (Loss of RN Pit Level)

(RN Valve Alignment for RN Swap to SNSWP) will direct the BOP to ensure _____(1)_____ is closed.

Following system stabilization, the BOP is directed to Ensure KC Hx Outlet Mode Switches - Properly Aligned. In response, the BOP _____(2)_____

required to reposition the 1A KC Hx Outlet Mode Switch.

Which ONE of the following completes the statements above?

A.

1. 1RN-47A (RN Supply X-Over Isol)
2. is B.
1. 1RN-47A (RN Supply X-Over Isol)
2. is NOT C.
1. 1RN-48B (RN Supply X-Over Isol)
2. is D.
1. 1RN-48B (RN Supply X-Over Isol)
2. is NOT Page 52 of 75

Question:

(1 point) 53 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Both units are at 100% RTP VI pressure is lowering The crew has entered AP/0/A/5500/022 (Loss of Instrument Air)

In accordance with AP/22, an operator will be dispatched to align air cylinders to operating compressors if VI pressure lowers below a MAXIMUM of

_____(1)_____ in order to _____(2)_____.

A.

1. 60 PSIG
2. provide a backup VI supply B.
1. 60 PSIG
2. prevent compressor damage C.
1. 76 PSIG
2. provide a backup VI supply D.
1. 76 PSIG
2. prevent compressor damage Page 53 of 75

Question:

(1 point) 54 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Following a LOCA, Containment Valve Injection Water (NW) will be aligned within a MINIMUM of _____(1)_____ seconds after a Phase _____(2)_____ signal is initiated.

Which ONE of the following completes the statement above?

A.

1. 10
2. A B.
1. 10
2. B C.
1. 60
2. A D.
1. 60
2. B Page 54 of 75

Question:

(1 point) 55 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is preparing for Reactor startup following refueling outage o Shutdown Banks have been withdrawn o The crew is preparing to perform PT/0/A/4150/019 (1/M Approach to Criticality)

High Flux at Shutdown alarms _____(1)_____ be blocked prior to withdrawing control banks for reactor startup.

When High Flux at Shutdown alarms are defeated, the applicable switch will be taken to BLOCK on _____(2)_____.

Which ONE of the following completes the statements above?

A.

1. will
2. Control Board 1MC-1 B.
1. will NOT
2. Control Board 1MC-1 C.
1. will
2. the Source Range Drawer D.
1. will NOT
2. the Source Range Drawer Page 55 of 75

Question:

(1 point) 56 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is at 100% RTP The OATC is performing PT/1/A/4600/002A (Mode 1 Periodic Surveillance Items) and has reached the step to compare each Power Range NI Channel to Thermal Power Best In accordance with the Mode 1 Surveillance procedure, each NI channel should agree with Thermal Power Best within _____(1)_____.

If the NI channel / Thermal Power Best comparison falls outside of the desired range, the crew will refer to _____(2)_____.

Which ONE of the following completes the statements above?

A.

1. +/- 2%
2. LCO 3.9.2 (Nuclear Instrumentation)

B.

1. +/- 2%
2. LCO 3.3.1 (Reactor Trip System Instrumentation)

C.

1. +/- 4%
2. LCO 3.9.2 (Nuclear Instrumentation)

D.

1. +/- 4%
2. LCO 3.3.1 (Reactor Trip System Instrumentation)

Page 56 of 75

Question:

(1 point) 57 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Concerning the design features of the Inadequate Core Cooling Monitor:

The calculation to determine NC System subcooling (based on Core Exit Thermocouples) is derived from an average of _____(1)_____ thermocouple temperatures.

If this calculation results in a negative value (versus positive), the display indication _____(2)_____ change.

Which ONE of the following completes the statements above?

A.

1. all valid
2. will B.
1. all valid
2. will NOT C.
1. the 5 highest
2. will D.
1. the 5 highest
2. will NOT Page 57 of 75

Question:

(1 point) 58 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 has just entered Mode 5 in preparation for refueling The missile shield has not been removed A lower containment entry is planned for the next shift The on-duty crew will perform purge of containment in preparation for the containment entry Currently, the VP system is secured with all fans off and containment purge and exhaust valves closed For this planned containment purge and in accordance with OP/1/A/6450/015 (Containment Purge System):

The NORMAL-REFUEL SELECTOR switch is placed in the _____(1)____

position.

This alignment is used in order to _____(2)_____.

Which ONE of the following completes the statements above?

A.

1. NORM
2. Prevent overpressurization of upper containment and an unmonitored release path B.
1. NORM
2. Prevent opening the ice condenser doors and to ensure air flow is routed through clean up filters C.
1. REFUEL
2. Prevent overpressurization of upper containment and an unmonitored release path D.
1. REFUEL
2. Prevent opening the ice condenser doors and to ensure air flow is routed through clean up filters Page 58 of 75

Question:

(1 point) 59 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 is at 100% power 1A KF (Spent Fuel Cooling) Pump is in service 1A VF (Spent Fuel Pool Ventilation) is operating in a normal alignment Subsequently:

A LOCA has occurred on Unit 1 Containment pressure peaked at 2.6 PSIG 1EMF-39 (Containment) is in Trip 2 1EMF-35 (Unit Vent) is in Trip 2 1EMF-42 (Fuel Building Ventilation) is in Trip 1 1EMF-15 (Spent Fuel Bldg Refueling Bridge) has experienced a loss of power As a result of the above conditions:

1A KF _____(1)_____ have cooling water aligned.

1A VF _____(2)_____ in Filter Mode.

Which ONE of the following completes the statements above?

A.

1.

does

2.

is NOT B.

1.

does

2.

is C.

1.

does NOT

2.

is NOT D.

1. does NOT
2. is Page 59 of 75

Question:

(1 point) 60 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

A 2C S/G tube rupture has occurred Total CA flow is 1200 GPM and stable Containment pressure is 0.2 PSIG and stable EP/2/A/5000/E-0 (Reactor Trip or Safety Injection) Enclosure 1 (Foldout Page) will require CA flow to be isolated to 2C S/G if level is above a MINIMUM of Which ONE of the following completes the statement above?

A.

11%

B.

15%

C.

26%

D.

62%

Page 60 of 75

Question:

(1 point) 61 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following timeline:

1000:00 Unit 1 is at 100% RTP 1C Condensate Booster Pump is removed from service for maintenance 1B Condensate Booster Pump tripped 1000:10 Applicable conditions are as follows:

o 1A CFPT Suction Pressure is 295 PSIG and stable o 1A CFPT Suction Flow is 2900 gpm and stable 1A CFPT tripped at _____(1)_____ due to low suction _____(2)_____.

Which ONE of the following completes the statement above?

A.

1. 1000:10
2. flow B.
1. 1000:10
2. pressure C.
1. 1000:30
2. flow D.
1. 1000:30
2. pressure Page 61 of 75

Question:

(1 point) 62 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Concerning the operation of 1EMF-26 (Steamline 1A):

1EMF-26 is a(n) _____(1)_____ monitor that provides indication of a S/G tube leak by monitoring _____(2)_____.

Which ONE of the following completes the statements above?

A.

1.

area

2.

N-16 decay B.

1.

process

2.

N-16 decay C.

1.

area

2.

dose rate D.

1.

process

2.

dose rate Page 62 of 75

Question:

(1 point) 63 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

The Fire Protection (RF) system heat sensitive element located at Unit 1 Main Turbine Bearing #8 has broken / actuated As a result of this actuation (ONLY):

RF discharge flow to the Main Turbine Bearing #8 _____(1)_____ initiate.

The Unit 1 Main Turbine _____(2)_____ trip.

Which ONE of the following completes the statements above?

A.

1.

will

2.

will B.

1.

will

2.

will NOT C.

1.

will NOT

2.

will D.

1.

will NOT

2.

will NOT Page 63 of 75

Question:

(1 point) 64 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

You are performing a post maintenance lineup You are verifying 4160V breaker 1ETA-9 (1A NI PUMP), RACKED IN Per AD-HU-ALL-0005 (Human Performance Tools):

Verification of the Racked In status of this breaker_____(1)_____.

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

Which ONE of the following completes the statements above?

A.

1. MUST be performed locally
2. Independent Verification (IV)

B.

1. CAN be performed using the C/R remote indicating light
2. Independent Verification (IV)

C.

1. MUST be performed locally
2. Concurrent Verification (CV)

D.

1. CAN be performed using the C/R remote indicating light
2. Concurrent Verification (CV)

Page 64 of 75

Question:

(1 point) 65 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station During core refueling, in accordance with AD-NS-ALL-1001 (Conduct of Refueling), the Control Room RO:

_____(1)_____ maintain awareness of all fuel and component handling activities in the Spent Fuel and Reactor Buildings.

_____(2)_____ approve alternate fuel assembly moves as recommended (with procedure guidance) by Reactor Engineering.

Which ONE of the following completes the statements above?

A.

1. will
2. can B.
1. will
2. can NOT C.
1. will NOT
2. can D.
1. will NOT
2. can NOT Page 65 of 75

Question:

(1 point) 66 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

During an outage, a planned maintenance activity will result in an ORANGE Defense in Depth (DID) sheet configuration o The planned activity is not included in an approved procedure In accordance with AD-WC-ALL-0420 (Shutdown Risk Management):

Defense in Depth (DID) sheets are first initiated once _____(1)_____is reached on a shutdown.

An Elevated Risk Management Plan _____(2)_____ required for an ORANGE DID condition.

Which ONE of the following completes the statements above?

A.

1. Mode 3
2. is B.
1. Mode 3
2. is NOT C.
1. Mode 4
2. is D.
1. Mode 4
2. is NOT Page 66 of 75

Question:

(1 point) 67 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following:

The "DC Power On" light for CAPT Elect Ops Status, 1SA-145 on 1MC-10 is OUT Which ONE of the following describes the process for troubleshooting this condition?

A.

Follow the guidance in 1AD-11, L/2 (B/O ALTERNATE CONT PWR LOSS) to dispatch an AO to 1TBOX0398 (SB594, U-31) to troubleshoot the condition.

B.

Replace the light bulb. If it is still not lit, this means FU1 or FU2 is blown.

Write a Work Request to have the fuse replaced.

C.

Follow the guidance in OMP 2-39, (Changing Control Indicating Lights). It provides a specific troubleshooting sequence for this particular component.

D.

Use OP/0/A/6350/014, (Operations Troubleshooting Guidelines), to determine the cause of this condition. Then write the appropriate Work Request for repair.

Page 67 of 75

Question:

(1 point) 68 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 2 is in Mode 5 with Reactor Coolant System vented 2EMF-39 has been declared Non-Functional 2EMF-36 is in service In accordance with SLC 16.11-7 (Radioactive Gaseous Effluent Monitoring Instrumentation):

An in-progress Containment Purge (VP) release _____(1)_____ continue.

A new Containment Purge (VP) release _____(2)_____ be initiated.

Which ONE of the following completes the statements above?

A.

1.
2.

may may B.

1.
2.

may NOT may C.

1.
2.

may may NOT D.

1.
2.

may NOT may NOT Page 68 of 75

Question:

(1 point) 69 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Per AD-OP-ALL-1001 (CONDUCT OF ABNORMAL OPERATION):

Regarding parallel use of EPs and APs, the _____(1)_____ determines how many procedures can be implemented at a time.

Use caution when implementing APs concurrently with EPs, APs are generally written assuming a _____(2)_____ has NOT occurred.

Which ONE of the following completes the statements above?

A.

1. Shift Manager
2. Safety Injection B.
1. Shift Manager
2. Loss of Offsite Power C.
1. CRS 2 Safety Injection D.
1. CRS
2. Loss of Offsite Power Page 69 of 75

Question:

(1 point) 70 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following:

Unit 1 Reactor tripped from 100% RTP following 100 days of continuous full power operation Xenon-135 concentration will peak approximately _____(1)_____ hours after the Reactor trip.

If a Reactor startup is performed prior to the Xenon-135 peak, _____(2)_____

reactivity will need to be added to maintain stable Reactor power.

Which ONE of the following completes the statement above?

A.

1. 10
2. positive B.
1. 24
2. positive C.
1. 10
2. negative D.
1. 24
2. negative Page 70 of 75

Question:

(1 point) 71 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following on Unit 1:

A reactor trip from 100% RTP and MOL equilibrium conditions has occurred The crew has implemented EP/1/A/5000/ES-0.2 (Natural Circulation Cooldown)

Per ES-0.2:

Shutdown Margin calculation for Cold Shutdown is required to be performed

_____(1)_____ Xenon credit.

The MINIMUM boration required prior to cooldown is cold shutdown boron plus

_____(2)_____.

Which ONE of the following completes the statement above?

A.

1. with
2. 150 ppm B.
1. with
2. 150 pcm C.
1. without
2. 150 ppm D.
1. without
2. 150 pcm Page 71 of 75

Question:

(1 point) 72 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station While withdrawing control rods during a Unit 2 reactor startup, the stable source range count rate doubled. If the same amount of reactivity that caused the first doubling is added again, the stable count rate will _____(1)_____ and the reactor will be

_____(2)_____.

Which ONE of the following completes the statement above?

A.

1. double
2. critical B.
1. double
2. subcritical C.
1. more than double
2. critical D.
1. more than double
2. subcritical Page 72 of 75

Question:

(1 point) 73 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions of Units 1 and 2 Pressurizers:

Unit 1 Pressurizer 1000 psig 550° F 25% level Unit 2 Pressurizer 1000 psig 300° F 25% level Nitrogen blanket Which pressurizer will maintain the higher pressure following a sudden 10%

liquid outsurge from each pressurizer, and why?

A.

Unit 1 Pressurizer due to vaporizing of saturated water as pressure begins to lower B.

Unit 1 Pressurizer due to the expansion characteristics of saturated steam being better than the expansion characteristics of nitrogen C.

Unit 2 Pressurizer due to the subcooled water removing a relatively small amount of energy during the outsurge D.

Unit 2 Pressurizer due to the expansion characteristics of nitrogen being better than the expansion characteristics of saturated steam Page 73 of 75

Question:

(1 point) 74 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 2 is operating at 50% RTP Pzr pressure is 2235 PSIG Pzr Relief Tank (PRT) pressure is 5 PSIG PRT temperature is 125°F A Pzr code safety valve is leaking by its seat Which ONE of the following identifies the approximate temperature that is indicated on the leaking safety valve discharge RTD?

A.

123 - 127°F B.

161 - 165°F C.

227 - 231°F D.

266 - 270°F Page 74 of 75

Question:

(1 point) 75 ILT24 CNS NRC EXAM CNS RO NRC Examination Catawba Nuclear Station Given the following conditions:

Unit 1 was initially at 85% RTP at EOL During power ascension, Control Bank D rod M4 partially fell into the core and became stuck One hour later, the following Power Range NI readings are noted:

N-43 N-42 N-44 N-41 Upper Power %

80.820 81.223 80.817 65.696 Lower Power %

81.028 81.597 81.024 75.584 Current QPTR is _____(1)_____.

QPTR is monitored / maintained in order to limit long term effects of exceeding

_____(2)_____ power distribution design limits.

Which ONE of the following completes the statements above?

A.

1. 1.053
2. axial B.
1. 1.053
2. radial C.
1. 1.037
2. axial D.
1. 1.037
2. radial Page 75 of 75

Examination KEY ILT24 CNS NRC EXAM CNS RO NRC Examination Q A Q A Q A Q A 1

D 26 B

51 B

2 C

27 B

52 D

3 B

28 D

53 B

4 C

29 B

54 C

5 C

30 A

55 C

6 D

31 D

56 B

7 C

32 D

57 C

8 B

33 A

58 A

9 B

34 D

59 B

10 A

35 D

60 B

11 B

36 D

61 C

12 D

37 B

62 C

13 B

38 B

63 D

14 B

39 D

64 C

15 B

40 B

65 B

16 D

41 C

66 C

17 D

42 B

67 C

18 C

43 D

68 C

19 A

44 B

69 C

20 A

45 D

70 A

21 A

46 B

71 C

22 C

47 A

72 C

23 C

48 A

73 A

24 A

49 B

74 C

25 B

50 C

75 B

Printed 9/5/2024 8:01:48 AM Page 1 of 1

WRITTEN EXAM REFERENCE PACKAGE CONTENTS EXAM ID: CNS ILT 24 NRC Exam (RO) 1 CN-1605-01.01 (Flow Diagram of Instrument Air System) 2 AP/1/A/5500/037 Encl 1 (Unit 1 Generator Capability Curve) 3 Unit 1 Data Book Figure 50 (Indicated (Hot Cal) vs Actual Pressurizer Level 4

Steam Tables 5

Mollier Diagram 6

NRC Form 4.3-1 GFES Equation Sheet

Facility Code :

Applicable Facilities :

Document Number :

Document Revision Number :

Document EC Number :

Change Reason :

Document Title :

Notes :

1/11/2022 Responsible Engineer Adams, Stephan G 1/11/2022 Originator Redding, Jeffrey L REV PER EC 414063 FLOW DIAGRAM OF INSTRUMENT AIR SYSTEM (VI)

EC0000414063 041 CN -1605-01.01 CN

E C

INSTRUMENT AIR 06 G

4" 4"

4" 3"

PRESSURE TEMPERATURE CLASS MATERIAL 130 PSIA G

GS VS D-13 CN-1605-2.0 STATION AIR 3"

3/4" 1/4" 3"

BACKUP SUPPLY 4"

4" LINE LISTING 02 PIPE SPEC.

04 154.1 151.4 130 PSIA G

SS DESIGN PARAMETERS NOTE 2 NOTE 2 4"

NOTE 3 4"

1" 1/2" 4"

14 10 9

8 7

6 5

4 3

2 1

L K

D B

A L

K J

I H

G F

E D

C B

A 8

7 6

5 4

3 2

1 INSTRUMENT AIR TO UNIT 2 5260 5260 5260 INSTRUMENT AIR TO UNIT 1 5250 5250 1VIPG 1VIFE 0VIPS 5240 0VIPS 0VIPS 0VIPS 0VIPS 0VIPS 5240 5241 5242 5243 5244 5245 0VIPG 0VIPT 0VIP 0VIPS 1VI118 1VI120 D

T 1VI36 02 02 E

INSTRUMENT G

1VI19 SET @

115 PSIG 1 1/2" 2"

NOTE 3 4"

4" RD 02 02 B

1VI24 4"

C CN-2605-1.5 110{F 110{F 1VI55 0VSPT I-12 5130 CN-1605-2.0 VI CN-1605-1.2 C-2 1VI1766 3l8" 1l2" 3"

0VIPS 5246 1VI1767 1VI124 T-23 I-7 VI I-1 1VI3885 1VI3888 1/2" VI K-12 CN-1605-1.0 FROM CENTRIFUGAL AIR COMPRESSOR D 17 VI D-12 CN-1605-1.0 4"

4" AIR COMPRESSOR F 4"

4" 4"

4" 4"

6" 1VI502 17 154.1 165 PSIA G

GS 1VI576 18 151.4 25 PSIA G

SS 02 4"

P P

VS 1VI598 A

02 A

VS 1VI582 AFTERFILTER A AFTERFILTER B VS 1VI586 VS 1VI585 VS 1VI584 PREFILTER B 4"

0VIPG 0VIPG 0VIPG 0VIPG 0VIPG PREFILTER A 6260 B

0VIHG 5920 VS 1VI623 1VI621 A

1VI620 4"

6100 6090 0VIPG 6110 6070 6080 1VI626 D

E E

D 3"

72 73 76 77 1

VS 1VI579 VS 1VI580 VS 1VI578 VS 1VI581 VS 1VI577 VS 1VI583 S

S 1VI648 1VI649 1VI650 1/2" 0VIPS 6330 NOTE 5 NOTE 6 04 04 1VI622 VS RD RD DRYER E 0VIPG 0VIPG 0VIPG 0VIPS 0VIPS 0VIPG 0VIPG 02 02 D

C 3"

6140 6160 6120 6130 6150 6170 6180 VS VS VS VS VS VS VS 74 78 FC VS A

A A

A A

1VI487 0VISV 4870 RD RD DRYER F 0VIPG 0VIPG 0VIPG 0VIPS 0VIPS 0VIPG 0VIPG 02 02 D

C 3"

6210 6230 6190 6200 6220 6240 6250 VS VS VS VS VS VS VS 75 79 FC VS A

A A

A A

1VI488 0VISV 4880 6"

3" 1VI619 4"

4" 1VI396 2"

1VI3886 1VI3887 LAB LAB 1VI54 1VI56 1VI50 1VI52 1VI57 1VI58 1VI59 1VI60 1VI53 1VI30 1VI51 1VI49 1VI119 1VI18 6"

4" 4"

4" 1VI397 83 82 1"

1VI398 STORAGE AREA DEPT. WORK &

PERFORMANCE AIR DRYER TO CLRT 1VI61 2VI59 VI K-1 CN-1605-1.4 E

MUFFLER EXHAUST PURGE VS 1VI592 VS 1VI591 VS 1VI589 VS 1VI645 VS 1VI588 VS 150 PSIG SET @

1VI612 INDICATOR TO MOISTURE VALVE ASS'Y INTERFACE TO DRYER E VS 1VI665 VS 1VI669 FILTER E PILOT GAS CHAMBER RIGHT CHAMBER LEFT VS 150 PSIG SET @

1VI611 VS 1VI667 VS 1VI666 VS 1VI596 VS 1VI595 VS 1VI593 VS 1VI594 VS 1VI597 METER DEWPOINT VS 1VI615 VS 1VI613 VS 1VI618 VS 1VI616 VS 1VI662 VS 1VI608 CHAMBER LEFT CHAMBER RIGHT VS 1VI604 VS 1VI607 VS 1VI606 VS 1VI661 FILTER F PILOT GAS VS 1VI660 VS 1VI664 VALVE ASS'Y INTERFACE TO DRYER F INDICATOR TO MOISTURE VS 1VI605 VS 150 PSIG SET @

1VI609 VS 1VI644 VS 1VI599 VS 1VI603 VS 150 PSIG SET @

1VI610 F

MUFFLER EXHAUST PURGE VS 1VI602 VS 1VI600 CN-1605-1.5 VI Y-04 Y-05

.CN000HX0 ERN 0VILL 4880 0VILL 4870 V

1VI663 VS V

1VI668 VS 6700 0VILL 6700 0VISV FO 1VI670 1VI671 02 02 04 04 1VI672 1VI670 TO 4"

4" 1/2" SEE NOTE 7 02 17 VI VI VI CN-1605-1.0 CN-1605-1.0 CN-1605-1.0 L-9 I-9 E-9 COMPRESSOR D CENTRIFUGAL AIR TO 0VIPT6360 BY COMPRESSOR E CENTRIFUGAL AIR TO 0VIPT5790 BY COMPRESSOR F CENTRIFUGAL AIR TO 0VIPT5960 BY 04 04 02 04 1VI699 04 02 6"

6" 1VI704 4"

4" 1/2" 1VI707 1"

4" 4"

6" NOTE 4 04 1VI706 04 1VI700 6890 PREFILTER C 1VI708 NOTE 4 4"

1/2" 1"

4" 04 04 4"

4" 4"

4" 4"

4" 4"

4" 4"

4" 04 4"

4" 4"

18 4"

04 1VI705 04 04 02 1VI701 1VI702 1VI703 0VISTY006 D

1/4" 1/2" 1VI710 1/2" 20 20 2701.4 ST 1/2" 20 0VIFLPREC 1/2" 4"

4" 04 04 02 1/2" 1VI711 1/2" 04 1"

04 20 1/2" 04 04 6701 0VILL 02 02 1VIWTT-30 1VIWTT-28 1VIWTT-29 4"

1" 1"

1" 1/2" 1VI713 1VI714 1/2" 4"

1VI712 1/2" V

V V

VS 1VI716 VS 1VI715 VS 1VI717 1/4" 1/4" 1/4" NOTE 9 4"

NOTE 9 6"

6" SEE NOTE 10 NOTE 10 SEE 1VI155 NOTE 9 6"

6" 6"

NOTE 9 NOTE 9 4"

4" 4"

6" D

T VS 1VI587 T

T D

D P

0VIPG D

130 PSIA 110{F G

REV SCALE REVISIONS NO FLOW DIAGRAM OF NO DWG REV PER EC 105082 14 13 12 10 9

DUKE ENERGY CATAWBA NUCLEAR STATION UNITS 1 & 2 CN-1605-01.01 INSTRUMENT AIR SYSTEM (VI)

N/A 11 36 37 41 20 20 ABANDONED COMPONENTS RELATED AIR RECEIVER L

38 1VI31 SET @

115 PSIG 1 1/2" 2"

J I

H G

F E

RD 02 E

G 1VI7 SET @

115 PSIG 1 1/2" 2"

NOTE 3 4"

RD 02 02 05 02 A

INSTRUMENT 04 1VI12 17 VI G-12 CN-1605-1.0 FROM CENTRIFUGAL AIR COMPRESSOR E 4"

FROM CENTRIFUGAL 1VI359 1VI360 1"

1VI6 1VI698 04 1VI697 04 02 4"

6" 4"

NOTE 9 4"

6" 6"

20 20 L

1/2" D

1/4" F

T-04 2"

2" D

C 1/2" 1VI10 1VI8 1VI739 1VI740 20 02 20 B-8 CN-1605-1.6 T

VI 1/2" 02 1/2" D

1/4" F

T-06 2"

2" D

C 1/2" 1VI34 1VI32 02 20 1VI743 1VI744 20 B-8 CN-1605-1.6 4"

1/2" RECEIVER NOTES:

C 1VI361 T

02 VI L

39 1/2" D

1/4" F

T-05 2"

2" D

C 1/2" 1VI742 1VI741 20 02 20 C-8 CN-1605-1.6 T

02 1VI20 1VI22 VI 41 REV PER EC 105082 40 SB TB-2 SB TB-2 4"

VI CN-1605-1.2 J-1 BUILDING MONITOR TANK SUPPLY TO COMPRESSOR AND FROM BACKUP 25 26 25 26 FROM INSTRUMENT AIR DRYER G 1VI750 1VI751 6"

6" 6"

6" 6"

VI CN-1605-1.26 REV PER EC 414063 6"

6" 6"

AIR DRYER G TO INSTRUMENT 6"

VI 1VI746 6"

CN-1605-1.26 AIR DRYER G TO INSTRUMENT K-1 J-1 25 26 1VI752 1VI753 1VI747 D

1" VI C-14 CN-1605-01.26 1VI488 1VI487 &

TO VI E-11 CN-1605-01.26 START UP AIR TO VI DRYER G 1/2" AIR RECEIVER 0VIPG 5460 13 12 11 1VI797 6"

NOTE 12 REV PER EC 407554 151.4 G

SS 26 154.1 GS 130 PSIA 150{F G

25 130 PSIA 150{F 125{F 110{F 02 26 02 26 25 04 REV PER EC 105082 02 04 02 04 TEMPORARY VI SKID AS DESCRIBED ON CNDS-1223.55-01-0049.

12. THIS LOCATION MAY BE USED AS THE ADDITION POINT FOR THE THE OPERATING PROCEDURE FOR NORMAL VALVE POSITION.

NORMALLY OPEN ON THE FLOW DIAGRAM. REFER TO COMPONENTS ARE NORMALLY CLOSED BUT MAY REFLECT

11. VALVES THAT DO NOT SUPPLY AIR TO DOWNSTREAM
10. ABANDONED IN PLACE PER EC 106813.

AN ENGINEERING EVALUATION. REFERENCE EC 108664.

OF PIPING IS PERMISSIBLE GIVEN THAT IT IS ACCOMPANIED BY FURTHERMORE, THE USE OF A STRONGBACK IN THIS SECTION EPOXY BONDER, FIBER RIBBON/TAPE AND BELZONA PRODUCTS.

CATASTROPHIC PIPE OR COUPLING FAILURE: DEACON 427 OF PIPING IN ORDER TO ASSIST IN PREVENTING A TO EXTERNALLY COAT THINNING AREAS OF THIS SECTION

9. THE FOLLOWING MATERIALS ARE ALLOWABLE FOR USE DRAWINGS FOR MORE DETAILS.

FIELD ROUTED CPVC (PS172). SEE THE PIPING ISOMETRIC

8. THE ONE INCH DRAIN PIPE DOWNSTREAM OF THE TRAP IS
7. EQUIPMENT ABANDONED IN PLACE PER NSM CN-50431/02.
6. DO NOT PUT PIPE DRAIN LINES BELOW WATER SURFACE IN SUMP.

CONCRETE PAD.

5. SUMP FABRICATED FROM 12 INCH SS PIPE EMBEDDED IN PREFILTERS' INLETS REQUIRE LOW POINT DRAINS.

COMPRESSORS' DISCHARGES AND DESICCANT DRYER

4. ALL LOW POINTS IN PIPING BETWEEN CENTRIFUGAL THREE INCH PIPE IS TO HAVE LINE LISTING OF 04.
3. DUKE SUPPLIED PIPE INSIDE RECEIVER TANK.

0VSFE5140.

WILL ALSO BE USED ON UNIT 2 SIDE AND FOR

2. 1VIFE5250 IS A TEMPORARY FLOW ORIFICE THAT
1. ALL GS PIPING WILL BE GALVANIZED CARBON STEEL.

REV PER EC 105082 NOTE 13 NOTE 13 NOTE 13 CONNECTION PER CNM 1213.00-0223.001.

AND INSTALLING NEEDLE VALVE ON TRAP BALANCE LINE BY CLOSING AND PLUGGING RESPECTIVE ISOLATION VALVE,

13. OPTION ALLOWED TO VENT DRAIN TRAP TO ATMOSPHERE 41 41 41 41 41 41 41 41 41 41 41

PAGE NO.

CNS GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES - Page 1 of 1 20 of 21 AP/1/A/5500/037 Revision 12 Unit 1 Generator Capability Curves

Unit 1 Data Book Source: IP/1/A/3222/061A,B, and C Rev.1, 3/27/14 Figure 50 - Indicated (Hot Cal) vs Actual Pressurizer Level Page 60 0

20 40 60 80 100 120 100 150 200 250 300 350 400 450 500 550 600 650 Actural Level (%)

Pressurizer Temperature (Deg F)

Indicated Level (%)

Indicated Level = 100%

90%

80%

70%

60%

50%

40%

30%

20%

10%

0%

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