ML16166A102

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301 as Given SRO Written Exam with References and Answer Key
ML16166A102
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 06/13/2016
From:
NRC/RGN-II
To:
Duke Energy Corp
References
Download: ML16166A102 (27)
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Text

Catawba Nuclear Station IL Ti 6 CNS SRO NRC Examination Question: 76 (1 point)

Given the following conditions on Unit 2:

  • Unit initially operating at 100% RTP
  • Containment pressure rapidly increased to 3.4 PSIG
  • 2B S/G completely depressurized
  • OATC is manually inserting control rods per EP/2/N5000/FR-S.1 (Response to Nuclear Power Generation/ATWS)

Current conditions:

  • While inserting rods, the OATC notes the following:

o DRPI indication for Control Bank D rod M4 is YELLOW with a DATA B indication above the rod o DRPI indication for rod M4 indicates 198 steps o Demand position counters for Groups 1 & 2 are blinking with position indication of 210 steps In accordance with T.S. 3.1.7 (Rod Position Indication) bases, LCO 3.1.7 (1) met.

When reactor shutdown has been verified, the NEXT required procedure transition from FR-S.1 is to GO TO (2)

Which ONE (1) of the following completes the statements above?

A. 1. is

2. E-0 (Reactor Trip or Safety Injection)

B. 1. is NOT

2. E-0 (Reactor Trip or Safety Injection)

C. 1. is

2. E-2 (Faulted Steam Generator Isolation)

D. 1. is NOT

2. E-2 (Faulted Steam Generator Isolation)

Page 76 of 100

Catawba Nuclear Station IL Ti 6 CNS SRO NRC Examination Question: 77 (1 point)

Given the following conditions on Unit 2:

  • Initial cooldown of the NC system to the target CET temperature has just been completed In accordance with the E-3 basis document, the purpose of the initial cooldown of the NC system is to establish a MINIMUM of (1) of subcooling, including allowances for subcooling uncertainties.

If the above amount of subcooling cannot be maintained after the cooldown is stopped, E-3 requires the operators to GO TO (2)

Procedure Legend:

Which ONE (1) of the following completes the statements above?

A. 1. 0°F

2. ECA-3.1 B. 1. 0°F
2. ECA-3.2 C. 1. 20°F
2. ECA-3.1 D. 1. 20°F
2. ECA-3.2 Page 77 of 100

Catawba Nuclear Station IL Ti 6 CNS SRO NRC Examination Question: 78 (1 point)

Given the following conditions on Unit 2:

  • The crew has transitioned to EP/2/N5000/FR-H.1 (Loss of Secondary Heat Sink)
  • Containment pressure is 3.2 PSIG and slowly increasing
  • NC System Bleed and Feed has been established Subsequently:
  • 2B CA pump is started
  • Total CA flow is currently 400 GPM
  • 2D S/G NIR level is 27% and slowly increasing
  • All other S/G WIR levels are 1 5% and slowly decreasing
  • CET temperatures and NC system T-hots are decreasing Based on the given conditions, the heat sink criteria to terminate NC system Bleed and Feed (1) met; AND After operators have terminated NC system Bleed and Feed, the NEXT required procedural transition from FR-H.1 is to GO TO (2)

Which ONE (1) of the following completes the statements above?

A. 1. is

2. EP/2/N5000/E-1 (Loss of Reactor or Secondary Coolant)

B. 1. is NOT

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

C. 1. is

2. EP/2/N5000/ES-1.1 (Safety Injection Termination)

D. 1. is NOT

2. EP/2/N5000/ES-1.1 (Safety Injection Termination)

Page 78 of 100

Catawba Nuclear Station ILTJ6 CNS SRO NRC Examination Question: 79 (1 point)

Given the following initial conditions on Unit 1:

  • The crew is performing EP/1/N5000/ECA-O.O (Loss of All AC Power)
  • The Standby Makeup Pump is ON
  • The crew was NOT able to start EITHER Diesel Generator
  • It is desired to align Unit 1 alternate power to 1 ETA through SATA Given the following current conditions on Unit 1:
  • The crew is at step 45 of ECA-O.O Select recovery procedure as follows:
  • NCS subcooling is 8°F
  • Pzr level is 4% and decreasing slowly
  • lNl-9A (NV Pmp C/L lnj lsol) and INI-1OB (NV Pmp C/L lnj Isol) are both CLOSED Eased on the initial conditions, ECA-O.O required that the crew REFER TO (1)

Based on the current conditions, ECA-O.O requires that the crew GO TO (2)

PROCEDURE LEGEND:

  • AP111N55001007 (Loss of Normal Power)
  • EPI1IAI5000IECA-O.1 (Loss of All AC Power Recovery Without S/I Required)
  • EPI1/N5000IECA-O.2 (Loss of All AC Power Recovery With S/I Required)

Which ONE (1) of the following completes the statements above?

A. 1. ECA-O.O Enclosure 9 (Aligning Unit 1 Alternate Power to 1 ETA (SATA))

2. ECA-O.1 B. 1. APIOO7 Enclosure 5 (Aligning Alternate Power to 1 ETA)
2. ECA-O.1 C. 1. ECA-O.O Enclosure 9 (Aligning Unit 1 Alternate Power to 1 ETA (SATA))
2. ECA-O.2 D. 1. APIOO7 Enclosure 5 (Aligning Alternate Power to 1 ETA)
2. ECA-O.2 Page 79 of 100

Catawba Nuclear Station ILTJ6 CNS SRO NRC Examination Question: 80 (1 point)

AP111N55001029 (Loss of Vital or Aux Control Power) states that vital batteries are capable of carrying their associated loads for at least (1) hours.

The basis of Tech Spec 3.8.6 (Battery Cell Parameters) states that the operability of the DC subsystems includes maintaining at least ONE (2) of DC sources OPERABLE during accident conditions.

Which ONE (1) of the following completes the statements above?

A. 1.two

2. channel B. 1.two
2. train C. 1. three
2. channel D. 1. three
2. train Page 80 of 100

Catawba Nuclear Station IL Ti 6 CNS SRO NRC Examination Question: 81 (1 point)

Given the following conditions on Unit 1:

  • The unit is at 100% RIP
  • The TCC has reported that Real Time Contingency Analysis (RTCA) indicates INADEQUATE switchyard voltage
  • The crew has entered AP/1/N5500/037 (Generator Voltage and Electric Grid Disturbances)
  • Main Generator operating conditions are as follows o Hydrogen Pressure (psig) 73 o GeneratorVAR&øl ,?7V4, 750 o Generator MW 1200 Eased on the given conditions, AP137 FIRST requires the crew to attempt to lower (1)

AP/37 states that WHEN jumpers are installed per AM/1/A/5100/008 (4Kv Essential Power (EPC) System Degraded Voltage Logic), THEN Unit 1 (2) exit LCO 3.8.1 (AC Sources) due to both trains of offsite power being inoperable.

Which ONE (1) of the following completes the statements above?

REFERENCE PROVIDED A. 1. generator voltage

2. can B. 1. generator voltage
2. can NOT C. 1. turbine load
2. can D. 1. turbine load
2. can NOT Page 81 of 100

Catawba Nuclear Station IL Ti 6 CNS SRO NRC Exainin ation Question: 82 (1 point)

Given the following initial conditions:

  • Unit 1 is at 4% RTP Subsequently:

o 1AD-2 F19 DCS ALTERNATE ACTION o 1AD-2 F/iD DCS TROUBLE o 1AD-6 A19 PZR HI LEVEL ALERT o 1AD-6 B/9 PZR HI LEVEL

  • Pressurizer Level Channels indicate as follows:

o PZR Lvl Channel I 100%

o PZR Lvl Channel II 25%

o PZR Lvl Channel III 93%

In accordance with Tech Spec 3.3.1 (Reactor Trip System (RTS) Instrumentation)

Bases, an automatic Reactor Trip (1) occurred because (2)

Which ONE (1) of the following completes the statement above?

A. 1. has

2. any liquid water release through PZR Safeties should be prevented B. 1.has
2. reactor coolant system pressure control may be challenged by repetitive cycling of PZR PORVs C. 1. has NOT
2. design analysis demonstrated that a single channel of PZR spray was sufficient to mitigate the full range of postulated accidents D. 1. has NOT
2. the operator will have sufficient time to evaluate conditions and take corrective actions Page $2 of 100

Catawba Nuclear Station IL Ti 6 CNS SRO NRC Examination Question: 83 (1 point)

Given the following indications on Unit 2:

  • Unit is operating at 100% power

Instrumentation) for the Containment Area Radiation (High Range) Function (1) met.

Tech Spec 3.3.3 bases states that diversity and backup information for this function is provided by (2) or by sampling and analysis.

EMF Legend:

  • 2EMF-39 (Containment Gas Low Range)

Which ONE (1) of the following completes the statements above?

A. 1. are NOT

2. portable instrumentation B. 1. are
2. portable instrumentation C. 1. are NOT
2. 2EMF-38 and 2EMF-39 D. 1. are
2. 2EMF-38 and 2EMF-39 Page 83 of 100

Catawba Nuclear Station IL Ti 6 CNS $RO NRC Examination Question: 84 (1 point)

Given the following conditions on Unit 1:

  • Containment pressure peaked at 2.6 PSIG
  • Subcooling based on CETs is -5°F on the 10CM monitor
  • Crew has transitioned to EP/1/N5000/ES-1.2 (Post LOCA Cooldown &

Depressurization)

  • The CRS has reached step 28, which requires the operators to depressurize the NC system Per ES-i .2 and its background document:

In accordance with ES-i .2 and based on the given conditions, the method used for depressurization will be (1)

In accordance with the ES-i .2 background document, the purpose of this depressurization step is to (2)

Which ONE (1) of the following completes the statements above?

A. 1. Normal Spray

2. increase NV S/I flow B. 1. aPressurizerPORV
2. increase NV S/I flow C. 1. Normal Spray
2. minimize break flow D. 1. a Pressurizer PORV
2. minimize break flow Page 84 of 100

Catawba Nuclear Station ILTJ6 CNS SRO NRC Examination Question: 85 (1 point)

Given the following conditions on Unit 1:

  • A loss of offsite power has occurred
  • Crew is performing EP/1IAI5000IES-O.2 (Natural Circulation Cooldown)
  • The TSC has notified the crew that plant conditions require a cooldown at 75°F/hour Based on the given conditions, the CRS (1) required to transition to EP/1/N5000/ES-O.3 (Natural Circulation Cooldown with Steam Void in Vessel).

Per the ES-O.3 background document, the basis for maintaining reactor vessel upper range level > 68% is to ensure (2)

Which ONE (1) of the following complete the statements above?

A. 1. is NOT

2. optimal conditions are maintained for reflux boiling mode of heat transfer B. 1. is NOT
2. natural circulation is not disrupted C. 1. is
2. optimal conditions are maintained for reflux boiling mode of heat transfer D. 1. is
2. natural circulation is not disrupted Page 85 of 100

Catawba Nuclear Station IL Ti 6 CN$ SRO NRC Examination Question: 86 (1 point)

Given the following conditions on Unit 2:

  • Unit is at 100% RTP
  • Containment Pressure Channel Two has failed low
  • All required Tech Spec actions have been completed Subsequently:
  • A faulty Containment Pressure bistable has initiated an automatic Reactor Trip and automatic Safety Injection The faulty bistable initiating this event was associated with Containment Pressure Channel (1)

Based on the given conditions, the procedural steps to terminate SI and establish normal charging are located in procedure (2)

Which ONE (1) of the following completes the statements above?

A. 1. One

2. EP/2/N5000/E-0 (Reactor Trip or Safety Injection)

B. 1. One

2. EP/2/N5000/ES-1.1 (Safety Injection Termination)

C. 1. Four

2. EP/2/N5000/E-0 (Reactor Trip or Safety Injection)

D. 1. Four

2. EP/2/N5000/ES-1 .1 (Safety Injection Termination)

Page 86 of 100

Catawba Nuclear Station ILTJ6 (WS SRO NRC Examination Question: 87 (1 point)

Given the following conditions on Unit 1:

  • 1 D S/G PORV (iSV-i) begins to fail OPEN
  • Attempts to close 1 SV-1 have failed
  • Nlpowerisl0l%
  • 1 SV-25B (S/G 1 D PORV Isol) is closed to isolate the failed S/G PORV
  • ISV-i indicates full OPEN When NI power was at 101% due to the throttled open S/G PORV, main turbine load (1) less than 1220 MW.

Based on the above conditions, 1 D S/G PORV line (2) OPERABLE in accordance with Tech Spec 3.7.4 (Steam Generator Power Operated Relief Valves (S/G PORV5)).

Which ONE (1) of the following completes the statements above?

A. 1. was

2. is B. 1. was
2. is NOT C. 1. was NOT
2. is D. 1. was NOT
2. is NOT Page 87 of 100

Catawba Nuclear Station ILTJ6 CNS SRO NRC Examination Question: 88 (1 point)

Given the following conditions on Unit 1:

  • Unit was at 100% RTP with no equipment out of service Subsequently:
  • An electrical fault causes bus 1 EDE to de-energize Given the following:

Per the applicable Tech Spec bases:

The ACTIONS of LCO 3.8.1 Condition F (1) required to be performed.

The ACTIONS of LCD 3.8.9 Condition D (2) required to be performed.

Which ONE (1) of the following completes the statements above regarding the MINIMUM required conditions and actions?

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 8$ of 100

Catawba Nuclear Station ILTJ6 CNS SRO NRC Examination Question: 89 (1 point)

Given the following conditions on Unit 1:

  • UnitisatlOO%RTP
  • 1 ECS is in standby with power aligned from 1 EMXA Subsequently:
  • 1 ECB DC output breaker has opened
  • In accordance with AP/1/A/5500/029 (Loss of Vital or Aux Control Power), the CRS is directing alignment of 1 ECS to 1 EDB AP/29 (1) require swapping the power supply to 1 ECS prior to aligning it to 1EDB.

Once 1 ECS is aligned to 1 EDB, LCO 3.8.4 (DC sources Operating) (2) met.

Which ONE (1) of the following completes the statements above?

A. 1. does NOT

2. is B. 1. does
2. is C. 1. does NOT
2. is NOT D. 1. does
2. is NOT Page 89 of 100

Catawba Nuclear Station ILTJ6 CNS SRO NRC Examination Question: 90 (1 point)

Given the following conditions on Unit 2:

  • Unit is at 50% power following a refueling outage
  • An AD on rounds contacts the WCC and reports that the lower containment annulus door is open and braced in such a way that it cannot be closed without maintenance support LCO3.0.3 (1) requiredtobeentered.

The requirements of LCD 3.6.16 (Reactor Building) (2) required to be met in Mode 4.

Which ONE (1) of the following completes the statements above?

A. 1. is NOT

2. are NOT B. 1. is
2. are NOT C. 1. is NOT
2. are D. 1. is
2. are Page 90 of 100

Catawba Nuclear Station IL TI 6 CNS SRO NRC Examination Question: 91 (1 point)

Given the following conditions on Unit 1:

  • Unit operating at 100% RTP
  • Maintenance has just completed sunieillance testing of A train Hydrogen Igniters
  • Maintenance reports 2 of the 35 A train Hydrogen Igniters failed the su rye i I lance Based on the given conditions, the A train Hydrogen Igniters are (1)

The Hydrogen Ignition System (2) required to be operable in Mode 3.

Which ONE (1) of the following completes the statements above?

A. 1. INOPERABLE

2. is B. 1. INOPERABLE
2. is NOT C. 1. OPERABLE
2. is D. 1. OPERABLE
2. is NOT Page 91 of 100

Catawba Nuclear Station IL Ti 6 CNS SRO NRC Examination Question: 92 (1 point)

Given the following conditions on Unit 1:

  • Crew is performing a Reactor Startup per PT101N41501019 (1IM Approach to Criticality)
  • Power history is 100 EFPD
  • 6 minutes have elapsed since the last rod pull
  • The following indications are observed during the startup:

o InitialS/Rcountrate- 13CPS o Current S/R count rate - 950 CPS and increasing o S/R SUR - 0.2 DPM and stable o Calculated ECP - 100 Steps withdrawn on Control Bank D o ECP Lower Limit - 90 Steps withdrawn on Control Bank C o Current rod position - 30 Steps withdrawn on Control Bank C Based on the above conditions and in accordance with Tech Spec 3.1.6 (Control Bank Insertion Limits) Bases, required Shutdown Margin (SDM) (1) exist.

In accordance with PT/0/N41 50/01 9, operators are required to insert (2)

Which ONE (1) of the following completes the statements above?

REFERENCE PRO VIDED A. 1. does

2. Control Banks ONLY B. 1. does NOT
2. Control Banks ONLY C. 1. does
2. ALL Control and Shutdown Banks D. 1. does NOT
2. ALL Control and Shutdown Banks Page 92 of 100

Catawba Nuclear Station ILTJ6 CNS SRO NRC Examination Question: 93 (1 point)

Given the following conditions on Unit 1:

  • A runback has occurred from 100% RTP due to 1A CFPT tripping
  • OATC notes the following control room indications after the plant is stable:

o Control Bank D step demand counters read 146 steps o Control Bank D rod M4 DRPI indicates GREEN at 156 steps o All other Control Bank D rods DRPI indicate GREEN at 144 steps o DRPI background color is ORANGE

  • Maintenance has determined that rod M4 is IMMOVABLE due to a control malfunction, but is TRIPPABLE In accordance with Tech Spec 3.1.4 (Rod Group Alignment Limits) Bases:

The MINIMUM rod deviation assumed in the safety analysis is (1)

Based on the given conditions, rod M4 is (2)

Which ONE (1) of the following completes the statements above?

A. 1. 7.5 inches

2. OPERABLE B. 1. 15.0 inches
2. OPERABLE C. 1. 7.5 inches
2. INOPERABLE D. 1. 15.0 inches
2. INOPERABLE Page 93 of 100

Catawba Nuclear Station ILT16 CNS SRO NRC Examination Question: 94 (1 point)

Given the following conditions on Unit 2:

  • Refueling is in progress
  • NC W/R Level is 98% and stable
  • No water additions are being made to the system
  • 2A ND train is OPERABLE and has been in continuous operation for the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
  • Fuel Handling SRO desires stopping the 2A ND Pump to aid in inserting a fuel assembly
  • Fuel Handling SRO expects to restart the 2A ND pump in approximately 15 minutes, after the fuel assembly is verified inserted Based on the given conditions, and in accordance with the appropriate Tech Spec:

When the 2A ND pump is stopped, the crew (1) required to enter one or more Tech Spec CONDITIONs/REQUIRED ACTIONs.

Tech Spec bases states that only one RHR loop is required to be OPERABLE, because (2) provides adequate backup decay heat removal capablity.

Which ONE (1) of the following completes the statements above?

A. 1. is NOT

2. the volume of water above the reactor vessel flange B. 1. is
2. the volume of water above the reactor vessel flange C. 1. is NOT
2. the Spent Fuel Cooling system D. 1. is
2. the Spent Fuel Cooling system Page 94 of 100

Catawba Nuclear Station ILTJ6 CNS SRO NRC Examination Question: 95 (1 point)

During an outage:

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) require d by Technical Specifications (TS) or Selected License Commitments (SLC).

Which ONE (1) of the following 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. Mode4
2. are Page 95 of 100

Catawba Nuclear Station ILTJ6 CNS SRO NRC Exantinatio;t Question: 96 (1 point)

Given the following conditions on Unit 1:

  • UnitisatlOO%RTP
  • 1EMF-33 (CSAE EXHAUST HI RAD) is in Trip 2 alarm
  • 1EMF-71 (S/G A LEAKAGE HI RAD) is in Trip 2 alarm
  • Pressurizer level has been stabilized using AP/11N5500/O1 0 (Reactor Coolant Leak)
  • Letdown flow is 45 GPM
  • Charging flow is 78 GPM The MAXIMUM time that AP/1 0 allows for the unit to teach MODE 3 for the conditions specified is (1)

In accordance with SLC 16.7-9 (Standby Shutdown System (SSS)) Condition B (Total accumulative LEAKAGE), the Standby Makeup Pump is (2)

Which ONE (1) of the following completes the statements above?

A. 1. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />

2. NON-FUNCTIONAL B. 1. 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
2. FUNCTIONAL C. 1. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
2. NON-FUNCTIONAL D. 1. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
2. FUNCTIONAL Page 96 of 100

Catawba Nuclear Station IL Ti 6 CNS SRO NRC Examination Question: 97 (1 point)

Given the following conditions:

  • A General Emergency has been declared
  • An AO must be dispatched from the Operations Support Center to an area with an identified radiation field of 110 R/hr in order to isolate the pathway for a large release to the environment
  • The operator will be in the area for 15 minutes In accordance with RPIOIAI5000/018 (Emergency Worker Dose Extension), the AC selected to perform this isolation (1) required to be a volunteer.

Per AD-RP-ALL-4012 (Planned Special Exposure), this job (2) considered a Planned Special Exposure (PSE).

Which ONE (1) of the following 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 97 of 100

Catawba Nuclear Station IL Ti 6 CNS SRO NRC Examination Question: 98 (1 point)

Given the following conditions on Unit 2:

  • Unit 2 is responding to a large LOCA with 10% failed fuel
  • The SM has determined that manual alignment of 2N1-184B is required to protect valuable property
  • RP projects that expected dose rate in the area of the valve is 120 RJhr The MAXIMUM time limit allowed per RP/0/N5000/018 (Emergency Worker Dose Extension) to meet the allowed Total Effective Dose Equivalent (TEDE) dose, with necessary extensions applied, for manually opening 2Nl-184B is (1) minutes.

to (Disregard any dose received in transit and from 2N1-184B)

In accordance with RP/018 and considering all other administrative requirements are met, the Emergency Coordinator or (2) is authorized to approve the Emergency Exposure.

Which ONE (1) of the following completes the statements above?

A. 1. 12.5

2. EOF Director B. 1. 12.5
2. RP Manager C. 1. 5.0
2. EOF Director D. 1. 5.0
2. RP Manager Page 98 of 100

Catawba Nuclear Station ILTJ6 (NS SRO NRC Examination Question: 99 (1 point)

Given the following conditions on Unit 1:

  • A Large Break LOCA has occurred
  • Containment pressure is 16 PSIG
  • EP/1/N5000/FR-Z.1 (Response To Containment High Pressure) has been entered
  • Both trains of ECCS are aligned for Cold Leg Recirculation

One train of ND may be aligned for Aux Containment Spray provided that the time since the LOCA began is greater than a MINIMUM of (1) minutes.

The basis for allowing one train of ND to be used for Aux Containment Spray is that, after the above time limit, adequate ECCS flow via Cold Leg Recirc is provided by a single train of (2)

Which ONE (1) of the following completes the statements above?

A. 1.50

2. NVORNI B. 1.90
2. NVORNI C. 1.50
2. NVANDNI D. 1.90
2. NVANDNI Page 99 of 100

Catawba Nuclear Station ILT16 (NS SRO NRC Examination Question: 100 (1 point)

Given the following conditions on Unit 1:

  • Initially operating at 100% RTP when a LOCA occurs
  • Pressurizer level is 0% and stable
  • Containment pressure is 1 .3 PSIG and increasing
  • Lower containment humidity is 70% and increasing
  • Subcooling is (-) 10°F and decreasing
  • The BOP notes indications shown on Attachments 1 & 2 The initial classification per RP/0/N5000/001 (Classification of Emergency) is (1)

Emergency Notification Form Line 6 release Is Occurring block (2) required to be checked.

Which ONE (1) of the following completes the statements above?

REFERENCE PROVIDED A. 1. 4.1.A.1

2. is NOT B. 1. 4.1.5.3
2. is NOT C. 1. 4.1.A.1
2. is D. 1. 4.1.S.3
2. is Page 100 of 100

References Provided on Catawba 2O16-O1 $RO-Only Written Exam:

1. Full copy of procedure RP/o/A/5000/ool, Classification of Emergency, revision 036 (all pages).
2. Copy of Figure 3, Control Bank Insertion Limits Versus Percent Rated Thermal Power, of the Catawba 1 Cycle 23 Core Operating Limits Report (CNEI-o4000-292) revision 001, page 12 of 31.
3. Redacted copy of Figure 43, Generator Capability Curves, from the [Catawba) Unit 1 Data Book.

ILT 2076 NRC SRO Written Exam Answer Key A

1 0 26 D 51 B 76 B 77 C 2 D 27 C 52 3 C 28 A 53 A 78 C 54 D 79 C 4 D 29 A A 80 B 5 A 30 B 55 B

6 A 31 0 56 C 81 7 D 32 B 57 D 82 D 8 B 33 C 58 C 83 B 9 B 34 D 59 C 84 D 10 A 35 C 60 B 85 D B 86 C 11 A 36 A 61 12 A 37 B 62 A 87 B 13 D 38 A 63 A 88 C 14 D 39 A 64 C 89 B A 90 D 15 B 40 D 65 B 91 B 16 C 41 B 66 17 A 42 0 67 B 92 B 18 B 43 C 68 D 93 B A

19 A 44 A 69 C 94 20 C 45 B 70 C 95 C 21 C 46 C 71 B 96 A C

22 C 47 A 72 D 97 23 C 48 D 73 C 98 C C

24 A 49 A 74 B 99 D 75 0 100 0 25 D 50

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