Text

301 1A Final SRO Written Exam (2-Year Delayed Release)
	ML21015A020
Person / Time
Site:	Brunswick
Issue date:	01/15/2021
From:	; Duke Energy Progress
To:	; Division of Reactor Safety II
References
	Download: ML21015A020 (126)
	v • d • e

ML21015A020 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: Facility/Unit: Brunswick 1/2 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

1. Unit Two is in MODE 2 during a startup with 25 control rods withdrawn.

The RO has reported that the RWM is not enforcing rod blocks when control rods reach their banked positions.

Which one of the following completes the statement below IAW Tech Spec 3.3.2.1, Control Rod Block Instrumentation?

Control rod movement:

A. is NOT permitted except by a scram.

B. withdrawal ONLY is NOT permitted. Unit shutdown is required to repair RWM prior to proceeding with the startup.

C. is permitted, the RWM is not required to be operable when less than or equal to 8.75% rated thermal power.

D. is permitted provided control rod movement is independently verified to comply with banked position withdrawal sequence (BPWS) by a second licensed operator or a qualified member of the technical staff.

Page: 1

2. Which of the following completes both statements below?

Reactor Recirc Pump normal outer seal leakage flow is routed to the (1) .

Reactor Recirc Pump normal seal staging flow is routed to the (2) .

A. (1) drywell equipment drain tank (2) drywell floor drain tank B. (1) drywell equipment drain tank (2) drywell equipment drain tank C. (1) drywell floor drain tank (2) drywell floor drain tank D. (1) drywell floor drain tank (2) drywell equipment drain tank Page: 2

3. A LOCA has occurred on Unit Two with the following sequence of events:

1200 Drywell pressure rises above scram setpoint.

1204 RPV level drops below the LPCI initiation setpoint 1206 RPV pressure drops to the LPCI initiation setpoint Which one of the following identifies the response for the E11-F015, LPCI Inboard Injection Valve, and the E11-F017, LPCI Outboard Injection Valve?

The operator can close:

A. E11-F015 no sooner than 1209.

E11-F017 cannot be closed.

B. E11-F015 no sooner than 1211.

E11-F017 cannot be closed.

C. E11-F015 cannot be closed.

E11-F017 no sooner than 1209.

D. E11-F015 cannot be closed.

E11-F017 no sooner than 1211.

Page: 3

4. Which one of the following identifies the normal power supply to 1-E11-F008, RHR Shutdown Cooling Otbd Isol Vlv?

A. 480 V MCC 1XA B. 480 V MCC 1XD C. 250 VDC MCC 1XDA D. 250 VDC MCC 1XDB Page: 4

5. Which one of the following identifies the Unit One HPCI turbine speed control power supply?

A. 125 VDC Panel 3A B. 125 VDC Panel 3B C. 125 VDC Panel 4A D. 125 VDC Panel 4B Page: 5

6. Following a Group 1 Isolation and reactor scram, reactor water level is being maintained by HPCI with the flow controller in AUTO at 1500 gpm.

Which one of the following completes both statements below?

If the HPCI flow transmitter fails downscale, HPCI flow would (1) .

The operator would be required to place the HPCI flow controller in manual and (2) to control reactor water level.

A. (1) lower (2) depress the up arrow pushbutton B. (1) lower (2) move the demand lever to the right C. (1) rise (2) depress the down arrow pushbutton D. (1) rise (2) move the demand lever to the left Page: 6

7. Which one of the following completes the statement below concerning the Core Spray Line Break Detection differential pressure instrument?

The reference leg of this DP instrument senses (1) core plate pressure via the SLC/Core Differential Pressure penetration, which provides control room annunciation on the detected (2) differential pressure.

A. (1) above (2) lower (more negative)

B. (1) above (2) higher (less negative)

C. (1) below (2) lower (more negative)

D. (1) below (2) higher (less negative)

Page: 7

8. Which one of the following completes both statements below?

The highest SLC Tank level that will maintain the reactor shutdown under hot standby conditions is (1) .

The highest SLC Tank level that will maintain the reactor shutdown under ALL conditions is (2) .

A. (1) 21%

(2) 0%

B. (1) 21%

(2) 10%

C. (1) 37%

(2) 0%

D. (1) 37%

(2) 10%

Page: 8

9. Which one of the following completes both statements below?

The fuel thermal time constant is incorporated into the (1) RPS trip.

This RPS setpoint is clamped at (2) .

A. (1) Simulated thermal power (2) 115.8%

B. (1) Simulated thermal power (2) 108.0%

C. (1) Instantaneous neutron flux (2) 115.8%

D. (1) Instantaneous neutron flux (2) 108.0%

Page: 9

10. Which one of the following identifies the reactor mode switch position(s), in conjunction with placing the SDV High Level Bypass Switch in the BYPASS position, that eliminates the SDV high level RPS trip signal?

A. Refuel, ONLY.

B. Shutdown, ONLY.

C. Refuel or Shutdown, ONLY.

D. Startup, Refuel or Shutdown.

Page: 10

11. During a plant startup IAW 0GP-02, Approach to Criticality and Pressurization of the Reactor, control rod 18-35 is withdrawn to its withdraw limit of position 12.

Subsequently, the individual reed switch at position 12 fails.

Loss of the individual reed switch for control rod 18-35 will cause the Rod Worth Minimizer (RWM) to do which one of the following?

A. The RWM will use an inferred position and no further action is required to continue moving control rods.

B. The RWM will cause an insert and withdraw block until a substitute position is placed in the RWM memory.

C. The RWM will require removing the rod from the BPWS and establishing a position allowed by the RWM pattern.

D. The RWM will sense that a Bank Position Withdrawal Sequence (BPWS) incompatible pattern is selected, generate a "critical self-test failure" and generate rod blocks.

Page: 11

12. Unit Two is operating at 100% power and Reactor Engineering has just completed running TIP Traces with TIP Channel D. The TIP detector has been left at the index position to allow for sufficient decay. Switch positions for TIP Channel D are as follows:

MAN VALVE CONTROL switch CLOSED MODE switch OFF Subsequently, a loss of power occurs to PCIS.

Which one of the following identifies the response of the TIP system?

A. The TIP detector automatically retracts to the shield chamber and the ball valve will automatically isolate.

B. The TIP system will automatically fire the shear valve since the TIP detector was left in the index position.

C. The TIP detector cannot be retracted until the isolation is cleared.

D. The TIP PCIS function is disabled.

Page: 12

13. Unit Two is in MODE 2 with reactor pressure at 50 psig.

IRM F is failed downscale and bypassed.

All other IRMs are OPERABLE and on Range 8.

Subsequently, IRM C High Voltage Power Supply output fails downscale.

Which one of the following identifies the automatic protective function(s) that occur(s) due to this failure?

A half scram (1) be generated.

The rod block (2) be cleared by bypassing IRM C.

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: 13

14. Unit Two is in MODE 1 with reactor power at 15%.

The IRMs are in the process of being withdrawn.

Which one of the following completes both statements below?

A-05 (2-4) IRM Upscale (yellow bar) setpoint is (1) of the 125 scale, which (2) cause a control rod block to occur.

A. (1) 70 (2) will B. (1) 70 (2) will NOT C. (1) 117 (2) will D. (1) 117 (2) will NOT Page: 14

15. Which one of the following distribution systems provides power to the Source Range Monitor (SRM) detectors and signal processing circuitry?

A. 24/48 VDC B. 125/250 VDC C. 120 VAC Emergency Power System D. 120 VAC Uninterruptible Power Supply Page: 15

16. Which one of the following completes both statements below concerning the APRM/LPRM System?

Each APRM must have a minimum of 3 OPERABLE LPRMs per axial level to ensure that the APRM will provide an accurate representation of (1) .

An LPRM detector (2) be substituted between APRM channels.

A. (1) localized flux levels (2) can B. (1) localized flux levels (2) can NOT C. (1) core wide average power (2) can D. (1) core wide average power (2) can NOT Page: 16

17. Excluding jumper installation, which one of the following scram signals is never bypassed automatically or manually in the RPS logic circuitry?

A. Turbine control valve closure.

B. Reactor vessel low water level.

C. Turbine stop valve closure.

D. MSIV closure.

Page: 17

18. A Unit One reactor scram has occurred.

A valid RCIC initiation signal has been received.

Which one of the following completes both statements below?

RCIC turbine speed will begin to increase when (1) begins to open.

RCIC turbine speed is initially controlled by (2) .

A. (1) E51-F045 Steam supply valve (2) ramp generator output.

B. (1) E51-F045 Steam supply valve (2) flow controller/signal converter output C. (1) E51-V9 Turbine governor valve (2) ramp generator output.

D. (1) E51-V9 Turbine governor valve (2) flow controller/signal converter output Page: 18

19. Which one of the following completes both statements below concerning the Automatic Depressurization System (ADS) reactor water level inputs from the Nuclear Boiler System?

The (1) instruments provide LL3 inputs to ADS initiation logic.

The (2) range instruments provide LL1 inputs to ADS logic.

A. (1) Fuel Zone (2) Narrow B. (1) Fuel Zone (2) Shutdown C. (1) Wide range (2) Narrow D. (1) Wide range (2) Shutdown Page: 19

20. Which one of the following is affected by a loss of 125VDC Distribution Panel 3A?

A. U1 RHR Loop A Cooling/Spray Permissive Logic B. U1 RHR Loop B Cooling/Spray Permissive Logic C. U2 RHR Loop A Cooling/Spray Permissive Logic D. U2 RHR Loop B Cooling/Spray Permissive Logic Page: 20

21. Which one of the following completes the statement below concerning motor operated Primary Containment Isolation Valves (PCIVs)?

In order to provide a physical separation, Group (1) penetration PCIVs in containment require a(n) (2) power source for the inboard valve.

A. (1) A (2) AC B. (1) A (2) DC C. (1) B (2) AC D. (1) B (2) DC Page: 21

22. Unit One is at 75% power.

The 1A RPS MG set trips.

No operator actions have been taken.

Which one of the following identifies the Main Steam Line Isolation Valve (MSIV) logic lamp status on P601 panel?

Inboard MSIV Logic Outboard MSIV Logic DC AC DC AC A.

B.

C.

D.

Page: 22

23. Which one of the following completes the statement below?

(Assume all instrumentation is available)

PCCP directs spraying the (1) before (2) pressure reaches 11.5 psig.

A. (1) Torus (2) Torus B. (1) Torus (2) DW C. (1) DW (2) Torus D. (1) DW (2) DW Page: 23

24. Which one of the following identifies the 4160V power supply to RHR Pump 1B?

A. E1 B. E2 C. E3 D. E4 Page: 24

25. Annunciator A-4 (6-7), Fuel Pool Cooling Alarm, has been received on Unit One.

RB AO reports the skimmer surge tank level is low.

Which one of the following completes both statements below?

If the skimmer surge tank level reaches 36.5 inches, the fuel pool cooling pumps (1) .

Makeup to the skimmer surge tank is supplied from (2) IAW 1OP-13, Fuel Pool Cooling and Cleanup System Operating Procedure.

A. (1) must be manually tripped (2) demin water B. (1) must be manually tripped (2) condensate transfer C. (1) will automatically trip (2) demin water D. (1) will automatically trip (2) condensate transfer Page: 25

26. An ATWS has occurred on Unit Two with the following plant conditions:

Reactor power 16%

MSIVs Closed SRVs Cycling Which one of the following completes the statement below IAW the ATWS Procedure?

A minimum of (1) SRVs must be opened to reduce pressure to (2) .

A. (1) 2 (2) 950 psig B. (1) 2 (2) 1000 psig C. (1) 3 (2) 950 psig D. (1) 3 (2) 1000 psig Page: 26

27. Unit One is at 100% power when SRV E fails open.

Digital feedwater level control system remains in 3 element control.

Which one of the following completes both statements below?

The main turbine generator output will (1) .

Reactor vessel water level stabilizes (2) the original level.

A. (1) remain the same (2) above B. (1) remain the same (2) below C. (1) lower (2) above D. (1) lower (2) below Page: 27

28. Unit Two reactor pressure is 100 psig when the CST is ruptured.

Current CST Level is 2 feet.

Which one of the following completes the statement below?

The RCIC system 2-E51-F029 and 2-E51-F031, Torus Suction Valves, will (1) and the CST Suction Valve, 2-E51-F010, will (2) .

A. (1) remain closed (2) auto close B. (1) remain closed (2) remain open C. (1) auto open (2) auto close D. (1) auto open (2) remain open Page: 28

29. Unit One is performing a startup IAW 0GP-02, Approach to Criticality and Pressurization of the Reactor.

Current Conditions:

Reactor water level 187 inches Reactor pressure 150 psig Which one of the following completes the statement below?

The Digital Feedwater Control System (DFCS) is controlling (1) to control feedwater flow into the reactor vessel using (2) element control.

A. (1) reactor feed pump speed (2) three B. (1) reactor feed pump speed (2) single C. (1) startup level control valve position (2) three D. (1) startup level control valve position (2) single Page: 29

30. 1-VA-1B-BFV-RB, SGT Filter Train 1A Outlet Valve, is closed for testing.

Subsequently, both reactor feed pumps trip resulting in a Reactor Scram.

Current conditions:

Reactor water level 100 inches Reactor pressure 950 psig DW pressure 0.15 psig RB negative pressure 0.1 inches of water Which one of the following completes both statements below?

The 1A SBGT (1) running.

In order to open the SGT Filter Train 1A Outlet Valve, the use of overrides (2) required.

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: 30

31. Unit Two is in operation with the following Condensate System alignment:

Condensate pumps 2A, 2B running Condensate pump 2C in standby with Unit trip load shed enabled Condensate Booster pumps 2B & 2C running Condensate Booster pump 2A in standby with Unit trip load shed enabled A reactor scram is initiated by a turbine trip.

The main generator backup lockout relay trips.

BOP Bus 2C fails to transfer to the SAT.

Which one of the following identifies the Condensate and Condensate Booster pumps that are running?

A. Condensate pump A ONLY.

B. Condensate pump A and Condensate Booster pump B ONLY.

C. Condensate pumps A and C and Condensate Booster pump B ONLY.

D. Condensate pumps A and C and Condensate Booster pumps A and B.

Page: 31

32. UPS was in a normal lineup on Unit Two when the following alarms were received:

UA-06 (6-7), UPS Primary Power Convtr Trouble, (yellow bar)

UA-06 (6-9), UPS Transfer To Reserve, (yellow bar)

The following conditions are noted at the UPS Panel:

Primary UPS Standby UPS Load on UPS (DS10) OFF OFF Load on Inverter (DS151) OFF ON Load on Alternate (DS152) ON OFF Alt Source Failure (DS11) OFF OFF Manual Bypass Switch (S1) NORM BYP TEST Which one of the following identifies the current status of UPS system loads?

A. De-energized.

B. Energized from the primary inverter.

C. Energized from the standby inverter.

D. Energized from the alternate source.

Page: 32

33. Unit Two is operating at 100% power when a loss of DC Distribution Panel 2B has occurred.

Which one of the following completes both statements below?

The alternate control power is aligned to Bus E4 via a(n) (1) transfer.

The alternate control power is aligned to Bus E8 via a(n) (2) transfer.

A. (1) auto (2) manual B. (1) auto (2) auto C. (1) manual (2) manual D. (1) manual (2) auto Page: 33

34. Unit One has scrammed and RCIC is injecting at 300 gpm.

The following alarms occur:

A-03 (2-2), Auto Depress Control Pwr Failure A-03 (3-4), RCIC Pump Disch Flow Lo All ADS (and non-ADS SRV) Red/Green indicating lights are ON.

Which one of the following completes the statement below?

ADS Logic (1) has transferred to Panel (2) .

A. (1) A (2) 3A B. (1) A (2) 3B C. (1) B (2) 3A D. (1) B (2) 3B Page: 34

35. The operator is performing 0OP-50.1, Diesel Generator Emergency Power System Operating Procedure, Section 6.3.5, Control Room Manual Transfer of 4160V Emergency Bus Supply from Normal Feeder to Diesel Generator.

Upon closing the DG output breaker, the operator raises DG load to 900 KW and notes that KVARs are negative.

All voltage regulator indications for the DG on the RTGB are normal.

Which one of the following completes both statements below?

Operating the DG with negative KVARs will lead to (1) .

IAW 0OP-50.1 the operator will raise KVARs using the (2) Regulator Voltage control switch.

A. (1) exceeding DG heat removal capability (2) Manual B. (1) exceeding DG heat removal capability (2) Auto C. (1) loss of field generator lockout (2) Manual D. (1) loss of field generator lockout (2) Auto Page: 35

36. Which one of the following completes both statements below?

Automatic opening of AOG-HCV-102, AOG system Bypass Valve, will occur with master switch AOG-CS-3161 in (1) position.

When off gas flow first reaches (2) scfm, the AOG-HCV-102 bypass valve will automatically open.

A. (1) CENT ONLY (2) 70 B. (1) CENT ONLY (2) 150 C. (1) EITHER CENT OR LOCAL (2) 70 D. (1) EITHER CENT OR LOCAL (2) 150 Page: 36

37. Unit One was operating at 100% power when a trip of a recirc pump occurs.

Which one of the following completes both statements below?

Thermal Limits (1) required to be adjusted IAW Tech Spec 3.4.1, Recirculation Loops Operating, for continued power operation. (Assume operation greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months )

IAW Tech Specs, the MCPR Safety Limit for single recirculation loop operation is (2) .

A. (1) are (2) 1.07 B. (1) are (2) 1.09 C. (1) are not (2) 1.07 D. (1) are not (2) 1.09 Page: 37

38. 0PT-12.1B, No. 2 Diesel Generator LOOP/LOCA Loading Test, is in progress.

The Unit One loss of off-site power signal has been simulated in conjunction with the Unit One LOCA test signal.

Which one of the following completes the statement below?

The (1) pump and the (2) pump must de-energize to satisfy the PT.

A. (1) 1B RHR (2) 1D RHR B. (1) 1B RHR (2) 1B CSW C. (1) 2D RHR (2) 1D RHR D. (1) 2D RHR (2) 1B CSW Page: 38

39. A 250 VDC Battery 1B ground alarm is received and sealed in on Unit One.

An AO reports the following readings from the ground detector:

N Bus 2.15 mA P Bus 1.75 mA P/N Bus 0.9 mA Which one of the following completes both statements below?

The ground is located on the (1) Bus.

Interaction of two or more ground faults may cause failure of control devices to pick up (2) when required.

A. (1) N (2) ONLY B. (1) N (2) or dropout C. (1) P (2) ONLY D. (1) P (2) or dropout Page: 39

40. Unit Two was operating at power when a main turbine trip occurs causing a reactor scram.

Which one of the following identifies the minimum reactor power prior to the trip?

A. 18%

B. 23%

C. 26%

D. 29%

Page: 40

41.

Which one of the following identifies a Unit One Scram Immediate Action that can be performed based on the above conditions? (Assume all rods insert)

A. Trip the main turbine.

B. Trip a reactor feed pump.

C. Place the Mode Switch in Shutdown.

D. Adjust the master RPV level controller setpoint.

Page: 41

42. Unit Two is in day 4 of a refueling outage with RHR Loop B operating in Shutdown Cooling IAW 2OP-17, Residual Heat Removal System Operating Procedure.

Which one of the following completes both statements below?

The lowest reactor pressure that will cause a Group 8 isolation is (1) psig.

The Group 8 isolation pressure signal (2) cause E11-F015B, Inboard Injection Vlv, to auto close.

A. (1) ~135 (2) will B. (1) ~135 (2) will NOT C. (1) ~200 (2) will D. (1) ~200 (2) will NOT Page: 42

43. Which one of the following completes both statements below?

IAW the Immediate Operator Actions in 0AOP-23.0, Condensate/Feedwater System Failure, IF reactor vessel level approaches (1) , THEN trip one reactor feed pump.

High reactor water level can cause moisture (2) .

A. (1) 192 inches (2) carryover B. (1) 192 inches (2) carryunder C. (1) 206 inches (2) carryover D. (1) 206 inches (2) carryunder Page: 43

44. The following conditions exist on Unit Two:

Drywell pressure 2 psig Drywell temperature 180°F Reactor water level 95 inches Reactor pressure 450 psig Which one of the following completes both statements below?

The Drywell Cooler fans (1) running.

The DW Lower Vent Dampers are in the (2) position.

A. (1) are (2) MIN B. (1) are (2) MAX C. (1) are NOT (2) MIN D. (1) are NOT (2) MAX Page: 44

45. A turbine trip and reactor scram occurs on Unit One with the following indications:

APRM downscale lights Illuminated Full core display green lights 127 control rods Full core display red lights 1 control rod Which one of the following completes both statements below?

RWM Shutdown Confirmation Screen will display (1) .

The reactor (2) remain shutdown under all conditions without boron.

A. (1) SHUTDOWN: NO (2) will B. (1) SHUTDOWN: NO (2) will NOT C. (1) SHUTDOWN: YES (2) will D. (1) SHUTDOWN: YES (2) will NOT Page: 45

46. Pressure control is being established at the Unit Two Remote Shutdown Panel (RSDP)

IAW 0AOP-32.0, Plant Shutdown from Outside Control Room.

Which one of the following completes both statements below?

Local control for SRVs B, (1) and G is taken at the RSDP.

The SRV indication on the RSDP is indicative of (2) position.

A. (1) E (2) valve B. (1) E (2) switch C. (1) F (2) valve D. (1) F (2) switch Page: 46

47. Unit Two is in MODE 3 with shutdown cooling in service when a loss of 2D RHRSW Booster pump occurs.

Both RHR pumps and 2B RHRSW pump continue to operate.

The operator observes annunciator A-03 (2-9), RHR HX A/B Disch Clg Wtr Temp Hi, in alarm and the RHR HX service water outlet temperature is indicating 185°F.

Which one of the following completes both statements below?

Continued operation with this alarm in will cause (1) .

IAW the APP, the operator is required to (2) .

A. (1) overheating of the RHR Pump motors (2) raise RHRSW flow B. (1) overheating of the RHR Pump motors (2) throttle open E11-F003B, HX 2B Outlet Vlv C. (1) short term seismic qualification concerns with the RHRSW system (2) raise RHRSW flow D. (1) short term seismic qualification concerns with the RHRSW system (2) throttle open E11-F003B, HX 2B Outlet Vlv Page: 47

48. Unit One is operating at power when the following alarms and indications are observed:

UA-01 (5-4) Service Air Press-Low, (yellow bar) alarms UA-01 (4-4) Instr Air Press-Low, (red bar) alarms Instrument air header pressure indicates 100 psig Which one of the following identifies the expected status of the air isolation valves and the reason for their status?

A. Service Air isolation valves ONLY have automatically closed to ensure Instrument Air requirements take priority.

B. Interruptible Instrument Air isolation valves ONLY have automatically closed to ensure Non-Interruptible Air requirements take priority.

C. Interruptible Instrument Air and Service Air isolation valves have both automatically closed to ensure a pneumatic source to operate components essential to the safe shutdown of the plant.

D. Interruptible Instrument Air and Service Air isolation valves are open and must be manually closed to ensure a pneumatic source to operate components essential to the safe shutdown of the plant.

Page: 48

49. Unit Two has just been placed in MODE 4.

RHR Loop 2A is operating in Shutdown Cooling.

RWCU Pump 2A is under clearance.

Subsequently, a Unit Two Loss Of Off-Site Power occurs.

An over current trip occurs on 480V Bus E8.

Shutdown Cooling flowpath cannot be reestablished.

RPS has been restored and group isolations have been reset.

Which one of the following completes both statements below IAW 0AOP-15.0, Loss of Shutdown Cooling?

An allowable method for feed and bleed operation is to feed with CRD Pump 2B and to bleed with (1) .

The reason feed and bleed is performed is to (2) .

A. (1) RWCU (2) maintain reactor water level constant B. (1) RWCU (2) minimize reactor coolant temperature rise C. (1) Main Steam Line Drains (2) maintain reactor water level constant D. (1) Main Steam Line Drains (2) minimize reactor coolant temperature rise Page: 49

50. Which one of the following completes the statement below IAW 0AOP-02.0, Control Rod Malfunction/Misposition, for a loss of both CRD pumps?

If reactor pressure is (1) and CRD pressure cannot be restored to greater than or equal to 940 psig, immediately insert a manual reactor scram upon the receipt of the (2) HCU low pressure alarm.

A. (1) less than 950 psig (2) first B. (1) less than 950 psig (2) second C. (1) greater than or equal to 950 psig (2) first D. (1) greater than or equal to 950 psig (2) second Page: 50

51. Unit Two is performing refueling operations when the refueling SRO reports that a spent fuel bundle has been dropped in the cattle chute.

The following annunciators are in alarm:

UA-03 (2-3), Rx Bldg Roof Vent Rad High, (blue bar)

UA-03 (2-7), Area Rad Rx Bldg High, (blue bar)

UA-03 (3-7), Area Rad Refuel Floor High UA-03 (4-5), Process Rx Bldg Vent Rad High, (blue bar)

Which one of the following is an Immediate Operator Action IAW 0AOP-5.0, Radioactive Spills, High Radiation, and Airborne Activity?

A. Enter 0EOP-04, RRCP.

B. Isolate Reactor Building Ventilation.

C. Place Standby Gas Treatment (SBGT) trains in operation.

D. Ensure Control Room Emergency Ventilation System (CREVS) in operation.

Page: 51

52. Unit Two was operating at 50% power when drywell pressure rises to 2.1 psig.

Which one of the following completes both statements below?

RVCP (1) required to be entered.

PCCP (2) required to be entered.

A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Page: 52

53. A loss of off-site power occurs on Unit Two with the following plant conditions:

Reactor water level 200 inches HPCI In pressure control in MAN RCIC In standby Reactor pressure 1125 psig and rising If reactor pressure is allowed to continue to rise, which one of the following identifies the reason the HPCI system will trip?

A. Turbine overspeed.

B. High reactor water level.

C. Steam Line High Flow.

D. High turbine exhaust pressure.

Page: 53

54. Unit One is operating at power.

A Safety Relief Valve has failed open.

Suppression pool temperature is 96°F and rising.

Which one of the following identifies when PCCP requires a reactor scram, and the reason a scram is required?

A reactor scram is required:

A. before suppression pool temperature reaches 110°F.

This assures suppression pool temperature will remain in the safe region of the Heat Capacity Temperature Limit graph.

B. before suppression pool temperature reaches 110°F.

This assures reactor shutdown is attempted by control rod insertion before the requirement to initiate SLC is reached.

C. ONLY when suppression pool temperature reaches 110°F.

This assures suppression pool temperature will remain in the safe region of the Heat Capacity Temperature Limit graph.

D. ONLY when suppression pool temperature reaches 110°F.

This assures reactor shutdown is attempted by control rod insertion when the requirement to initiate SLC is reached.

Page: 54

55. A line break occurs in the Unit One Drywell with the following plant conditions:

Wide Range Level 180 inches steady on N026A/B Narrow Range Level 155 inches steady on N004A/B/C Shutdown Range Level 190 inches steady on N027A/B RPV pressure 50 psig Drywell ref leg temp 340°F Drywell average temp 255°F Reactor Building 50' temp 128°F

[Reference Provided]

Which one of the following identifies the valid RPV water level instrument(s)?

A. N004A/B/C ONLY B. N026A/B ONLY C. N026A/B and N004A/B/C ONLY D. N026A/B, N027A/B and N004A/B/C Page: 55

56. Which one of the following completes the statement below IAW 0EOP-01-UG, User's Guide?

The Vortex Limit is the lowest torus (1) above which (2) is not expected to occur in a RHR Pump that is taking suction from the torus.

A. (1) level (2) air entrainment B. (1) level (2) cavitation C. (1) pressure (2) air entrainment D. (1) pressure (2) cavitation Page: 56

57. Unit One is performing a cooldown with shutdown cooling in service.

Reactor coolant temperature is 190°F and lowering slowly.

Subsequently, a level transient occurs (level reaches 90 inches, then is stabilized at 150 inches).

Which one of the following identifies the parameter that must be monitored for indications of boiling IAW 0AOP-15.0, Loss of Shutdown Cooling?

A. Reactor vessel pressure.

B. Safety Relief Vlv temperature.

C. Bottom head drain temperature.

D. Recirculation loop suction temperatures.

Page: 57

58. Which one of the following identifies the reason for performing Emergency Depressurization due to exceeding Maximum Safe Operating Temperatures IAW 0EOP-01-UG, User's Guide?

A. Prevent an unmonitored release.

B. Preserve personnel access into the reactor building.

C. Ensure ODCM site boundary dose limits are not exceeded.

D. Provide continued operability of equipment required for safe shutdown.

Page: 58

59. Unit Two is being maintained in MODE 3 due to an anticipated arrival of a hurricane.

Subsequently, UA-05 (6-7), Rx Bldg Static Press Diff-Low (blue bar) is received.

VA-PI-1297, Reactor Bldg Neg Pressure, indication is downscale.

No standby fans are available.

Which one of the following completes both statements below?

The Reactor Building Ventilation (1) fan vortex dampers will throttle.

A SCCP entry condition (2) met.

A. (1) Supply (2) is B. (1) Supply (2) is NOT C. (1) Exhaust (2) is D. (1) Exhaust (2) is NOT Page: 59

60. The ATWS portion of 0OI-37.17, EOP Hard Cards, directs the U2 RO to initiate a recirc pump manual runback, if it is enabled.

Which one of the following completes both statements below?

The recirculation pumps will runback to approximately (1) speed.

This action is taken to (2) .

A. (1) 52%

(2) avoid turbine trip due to RPV pressure and level transient B. (1) 52%

(2) reduce core inlet subcooling C. (1) 54%

(2) avoid turbine trip due to RPV pressure and level transient D. (1) 54%

(2) reduce core inlet subcooling Page: 60

61. Which one of the following completes both statements below?

IAW 0AOP-5.4, Radiological Releases, RRCP is entered when the Turbine Building Vent Rad Monitor indication exceeds an (1) EAL.

IAW RRCP, before the radioactivity release rate reaches a (2) Emergency EAL, Emergency Depressurization is required.

A. (1) Unusual Event (2) Site Area B. (1) Unusual Event (2) General C. (1) Alert (2) Site Area D. (1) Alert (2) General Page: 61

62. Which one of the following completes both statements below concerning the Service Air Header Isolation Valves, SA-PV-706-1 and 706-2?

The service air header isolation valves will auto close when instrument air pressure first lowers to (1) .

If the low air pressure signal fails to auto close the valves, they (2) be closed from the RTGB.

A. (1) 100 psig (2) can B. (1) 100 psig (2) can NOT C. (1) 105 psig (2) can D. (1) 105 psig (2) can NOT Page: 62

63. Which one of the following completes the statement below?

Reducing the output pressure signal on 2-TCC-TIC-606, TBCCW HXS Outlet Temp Ctrlr, will cause 2-TCC-TV-606, TBCCW Heat Exchanger Outlet Temp Ctl Vlv, to travel in the (1) direction which will (2) TBCCW flow through the TBCCW heat exchangers.

A. (1) closed (2) raise B. (1) closed (2) lower C. (1) open (2) raise D. (1) open (2) lower Page: 63

64. Which one of the following identifies a Unit One valve normal feeder breaker that is maintained in a pre-fire rack out status IAW 0ASSD-00, User's Guide?

A. E11-F049, RHR to Radwaste Inboard Isolation Valve.

B. E41-F002, HPCI Steam Supply Inboard Isolation Valve.

C. E51-F062, RCIC Turbine Exhaust Vacuum Breaker Valve.

D. B21-F016, Main Steam Line Drain Inboard Isolation Valve.

Page: 64

65. Unit Two is operating at rated power when small oscillations due to unstable voltage regulation are observed.

Which one of the following completes both statements below IAW 2OP-27, Generator and Exciter System Operating Procedure?

The first action required is to (1) .

This action must be reported to the (2) .

A. (1) place the generator voltage regulator in Manual (2) System Load Dispatcher B. (1) place the generator voltage regulator in Manual (2) Plant Transmission Activities Coordinator (PTAC)

C. (1) disable the Power System Stabilizer (PSS)

(2) System Load Dispatcher D. (1) disable the Power System Stabilizer (PSS)

(2) Plant Transmission Activities Coordinator (PTAC)

Page: 65

66. Which one of the following completes both statements below IAW AD-OP-ALL-1001, Conduct of Abnormal Operations?

The (1) ensures Auxiliary Operators are dispatched.

During Event Procedure implementation, the tracking of the availability of resources and task status (2) required.

A. (1) RO (2) is B. (1) RO (2) is NOT C. (1) CRS (2) is D. (1) CRS (2) is NOT Page: 66

67. Which one of the following completes both statements below IAW AD-OP-ALL-1000, Conduct Of Operations?

A plant announcement will be made for the starting or stopping of (1) loads or greater from the control room.

When starting the 2A Condensate Pump, the announcement will include direction for plant personnel to stand clear of the pump (2) .

A. (1) 480V (2) ONLY B. (1) 480V (2) and its associated electrical switchgear C. (1) 4 kV (2) ONLY D. (1) 4 kV (2) and its associated electrical switchgear Page: 67

68. Which one of the following completes both statements below concerning valve operability testing?

The standard method of measuring the open stroke time is the time from when the (1) to the time the valve is fully stroked by light indication.

If the measured stroke time of a valve exceeds the acceptable range, but is within the limiting stroke time, the valve (2) allowed to be immediately retested.

A. (1) control switch is repositioned (2) is B. (1) control switch is repositioned (2) is NOT C. (1) red light illuminates (2) is D. (1) red light illuminates (2) is NOT Page: 68

69. Which one of the following completes the statement below IAW the Tech Spec MODE definitions table (Table 1.1-1)?

For Unit One to be in MODE 4, the reactor mode switch must be in (1) and (2) reactor head bolt(s) fully tensioned.

A. (1) Shutdown ONLY (2) one B. (1) Shutdown ONLY (2) all C. (1) Shutdown or Refuel (2) one D. (1) Shutdown or Refuel (2) all Page: 69

70. Which one of the following identifies the significance of the yellow flagging/coding (yellow dot), affixed to an annunciator window IAW 0OI-01.01, BNP Conduct of Operations Supplement?

The yellow dot means that the alarm:

A. is a nuisance alarm.

B. has its annunciator card removed.

C. has one or more of its inputs disabled.

D. is lit because its associated equipment is under clearance.

Page: 70

71. Which one of the following completes both statements below?

IAW AD-RP-ALL-4014, Dosimetry Management, the NRC has imposed a dose limit of (1) for the entire pregnancy for declared pregnant radworkers.

IAW TE-RP-ALL-4000, Exposure Extension and Reduction, an exposure extension (2) allowed during the declared pregnant worker time period.

A. (1) 100 mrem (2) is B. (1) 100 mrem (2) is NOT C. (1) 500 mrem (2) is D. (1) 500 mrem (2) is NOT Page: 71

72. An operator is making preparations to perform a valve manipulation in the RWCU area.

The RWP indicates that the dose rate in the area is 70 mR/hr.

Which one of the following completes both statements below?

This area is defined as a (1) IAW AD-RP-ALL-0004, Radiological Posting and Labeling.

A Self-Briefing (2) be performed for this task IAW AD-RP-ALL-2011, Radiation Protection Briefings.

A. (1) Radiation Area (2) can B. (1) Radiation Area (2) can NOT C. (1) High Radiation Area (2) can D. (1) High Radiation Area (2) can NOT Page: 72

73. The CRS has determined that 0EOP-01-SEP-01, Primary Containment Venting, is required due to hydrogen concentration levels.

Plant conditions are:

Drywell pressure 20 psig Torus level 2 feet Which one of the following completes both statements below?

IAW PCCP, venting of primary containment is performed (1) offsite radioactivity release rates.

IAW SEP-01, the (2) is vented first.

A. (1) ONLY if within ODCM (2) torus B. (1) ONLY if within ODCM (2) drywell C. (1) irrespective of the (2) torus D. (1) irrespective of the (2) drywell Page: 73

74. Which one of the following completes both statements below IAW 0OI-76, Preparation and Implementation Standard for Abnormal Operating Procedures?

Abnormal Operating Procedures (AOPs) immediate actions (1) required to be performed from memory.

AOPs are (2) based procedures.

A. (1) are (2) event B. (1) are (2) symptom C. (1) are NOT (2) event D. (1) are NOT (2) symptom Page: 74

75. Unit Two was at power when a trip and lockout of BOP Bus 2B required insertion of a manual reactor scram. Shortly after the scram, the following indications are noted:

Drywell pressure 1.4 psig, rising Average drywell temp 140°F, rising Which one of the following completes the statement below?

The crew will be required to enter (1) and isolate Recirc Pump (2) .

A. (1) 0AOP-14.0 (2) 2A B. (1) 0AOP-14.0 (2) 2B C. (1) PCCP (2) 2A D. (1) PCCP (2) 2B Page: 75

76. During a Unit Two startup, the C12-F002A, CRD Flow Control Valve, fails full open.

Which one of the following completes both statements below?

The high flow condition may cause control rod (1) .

The control operator will shift flow control valves IAW (2) .

A. (1) insertions (2) 2OP-08, Control Rod Drive Hydraulic System Operating Procedure B. (1) insertions (2) 0AOP-02, Control Rod Malfunction/Misposition C. (1) withdrawals (2) 2OP-08, Control Rod Drive Hydraulic System Operating Procedure D. (1) withdrawals (2) 0AOP-02, Control Rod Malfunction/Misposition Page: 76

77. Unit One is operating at 100% power.

The following information was obtained during the last scram timing for control rod 18-19 IAW 0PT-14.2.1, Single Rod Scram Insertion Times Test.

Control Position Time Rod Insertion Notch (Secs) 18-19 5% 46 0.438 20% 36 1.188 50% 26 2.026 90% 6 3.349

[Reference Provided]

Concerning control rod 18-19, which one of the following completes both statements below?

Control Rod 18-19 (1) be declared "slow" IAW Tech Spec 3.1.4, Control Rod Scram Times.

Satisfactory scram times protect the (2) safety limit ensuring 99.9% of the fuel rods do not experience transition boiling.

A. (1) may (2) MCPR B. (1) may (2) LHGR C. (1) may NOT (2) MCPR D. (1) may NOT (2) LHGR Page: 77

78. A LOCA has occurred on Unit One.

After emergency depressurization, the crew is implementing 0EOP-01-SEP-11, Alternate Source Term Actions.

Which one of the following completes both statements below?

IAW 0AP-064, Time Critical Actions/Time Sensitive Actions Supplement, the injection of SLC is required to be performed in (1) .

IAW SEP-11, if the SLC Pumps are NOT available, the performance of 0EOP-01-LEP-03, Alternate Boron Injection, (2) required.

A. (1) 20 minutes (2) is B. (1) 20 minutes (2) is NOT C. (1) 56 minutes (2) is D. (1) 56 minutes (2) is NOT Page: 78

79. Unit One has experienced a LOCA with the following plant conditions.

Reactor water level is 100 inches, lowering.

All available high pressure injection systems injecting at maximum.

Which one of the following completes the statement below IAW 0OI-37.4, RVCP Basis Document?

ADS is required to be inhibited (1) in order to (2) .

A. (1) prior to ADS timer initiation (2) prevent RPV level control complications B. (1) prior to ADS timer initiation (2) prevent high level trips due to SRV actuation C. (1) when reactor water level cannot be restored and maintained above TAF (2) prevent RPV level control complications D. (1) when reactor water level cannot be restored and maintained above TAF (2) prevent high level trips due to SRV actuation Page: 79

80. 125VDC Distribution Panel 11A has been lost.

Which one of the following completes both statements below?

SBGT 1A deluge valve (1) automatically open.

In order to flow water, the SBGT 1A deluge system valves are opened IAW (2) .

A. (1) will (2) 1OP-10 Standby Gas Treatment System Operation Procedure B. (1) will (2) 0OP-41 Fire Protection and Well Water System C. (1) will NOT (2) 1OP-10 Standby Gas Treatment System Operation Procedure D. (1) will NOT (2) 0OP-41 Fire Protection and Well Water System Page: 80

81. Unit One was operating at 100% power when the following sequence of events occurred:

0900 DG2 running loaded performing 0PT-12.2B, No. 2 Diesel Monthly Load Run 0905 UA-20 (2-1), DG-2 GEN DIFF OVCT TRIP alarms 0906 LOCA signal is received Post event the CRS is evaluating Tech Spec 3.8.1, AC Sources - Operating, entry criteria. DG1, DG3, DG4, and the Supp DG have been determined to be operable.

Which one of the following completes both statements below?

At 0906, DG2 (1) restart.

Tech Spec 3.8.1 (2) required to be entered.

A. (1) did (2) is B. (1) did (2) is NOT C. (1) did NOT (2) is D. (1) did NOT (2) is NOT Page: 81

82. A steam line break has occurred in the Unit Two HPCI room.

Which one of the following completes the statement below?

To prevent the sprinkler system from inadvertently flowing water, (1) will first be directed to be closed IAW (2) .

A. (1) 2-FP-V366, Reactor Building Sprinkler System Isolation Valve (2) 0OP-41, Fire Protection and Well Water System B. (1) 2-FP-V366, Reactor Building Sprinkler System Isolation Valve (2) 0AOP-05.0, Radioactive Spills, High Radiation, and Airborne Activity C. (1) 2-FP-PIV33, Unit 2 Reactor Building Sprinkler Deluge Valve Supply Valve (2) 0OP-41, Fire Protection and Well Water System D. (1) 2-FP-PIV33, Unit 2 Reactor Building Sprinkler Deluge Valve Supply Valve (2) 0AOP-05.0, Radioactive Spills, High Radiation, and Airborne Activity Page: 82

83. Unit One is at 100% power when main condenser vacuum begins to lower.

Which one of the following completes both statements below?

A main turbine trip will occur at approximately (1) .

The procedural step to start a standby CWIP is contained in (2) .

A. (1) 22.4 inches Hg (2) AOP-37.0, Low Condenser Vacuum B. (1) 22.4 inches Hg (2) UA-23 (2-1), Exhaust Hood A Vacuum Low C. (1) 24.5 inches Hg (2) AOP-37.0, Low Condenser Vacuum D. (1) 24.5 inches Hg (2) UA-23 (2-1), Exhaust Hood A Vacuum Low Page: 83

84. Unit Two is in MODE 4 with SDC in service on RHR loop B.

DG3 is under clearance.

Subsequently, a Unit Two Loss of Off-site power (LOOP) occurs with the following plant conditions:

Reactor water temperature 135°F, stable Reactor pressure 0 psig

[Reference Provided]

Which one of the following completes both statements below?

The highest classification that the SM is required to declare is an (1) .

Guidance for the restoration of RHR Loop B for SDC is found in (2) .

A. (1) Unusual Event (2) 0AOP-15, Loss of Shutdown Cooling B. (1) Unusual Event (2) 0AOP-36.1, Loss of Any 4160V Buses or 480V E-Buses C. (1) Alert (2) 0AOP-15, Loss of Shutdown Cooling D. (1) Alert (2) 0AOP-36.1, Loss of Any 4160V Buses or 480V E-Buses Page: 84

85. Unit One is performing a Startup with power at approximately 23%.

A main turbine roll is in progress.

Subsequently, UA-23 (6-1), Turbine Vibration High, (yellow bar), alarms Current plant conditions:

Main turbine tripped Main turbine speed 1550 rpm Main turbine oil temperature 285°F rising rapidly Bearing Vibrations: V1 14 mils rising V2 13 mils rising V8 30 mils rising V10 10 mils rising Which one of the following completes both statements below?

The CRS will direct a reactor scram (1) IAW 1OP-26, Turbine System Operating Procedure.

The CRS will enter (2) IAW 0OI-37.11, Transient Mitigation Guidelines .

A. (1) ONLY (2) RSP ONLY B. (1) ONLY (2) RSP and RVCP C. (1) and MSIVs closure (2) RSP ONLY D. (1) and MSIVs closure (2) RSP and RVCP Page: 85

86. With Unit Two operating at 100% power, an inadvertent actuation of one Core Spray logic system occurs and cannot be reset. The BOP operator observes the following:

SW-V103, RBCCW HXS SW INLET VLV closed SW-V106, RBCCW HXS SW INLET VLV open Which one of the following completes both statement below?

Core Spray Logic (1) inadvertently actuated.

(2) contains the guidance for restoring cooling to the RBCCW system.

A. (1) A (2) 0AOP-18, Nuclear Service Water System Failure B. (1) A (2) 0AOP-19, Conventional Service Water System Failure C. (1) B (2) 0AOP-18, Nuclear Service Water System Failure D. (1) B (2) 0AOP-19, Conventional Service Water System Failure Page: 86

87. Unit Two is operating at 100% power when a PNS leak occurs.

Drywell pneumatics have been transferred to RNA IAW 0AOP-20.0, Pneumatic (Air/Nitrogen) System Failures.

Primary containment oxygen concentration remains less than 4 volume percent.

Which one of the following completes both statements below?

RNA is supplying pneumatics to the Reactor Building to Torus Vacuum breakers (1) .

Tech Spec LCO 3.6.3.1, Primary Containment Oxygen Concentration, action statement (2) required to be entered IAW 0AOP-20.0.

A. (1) and the Suppression Pool to Drywell Vacuum Breakers (2) is B. (1) and the Suppression Pool to Drywell Vacuum Breakers (2) is NOT C. (1) ONLY (2) is D. (1) ONLY (2) is NOT Page: 87

88. An event on Unit One has resulted in the following plant conditions:

Reactor pressure 1000 psig Reactor Water Level 120 inches Control Rod position Unknown APRMs Downscale Drywell pressure 3 psig Torus pressure 2 psig Torus water temp 152°F Torus water level -42 inches

[Reference Provided]

Which one of the following identifies the required actions for reactor pressure control?

A. Exit the RC/P flowpath of ATWS, and go to 0EOP-01-EDP, Emergency Depressurization.

B. Exit the RC/P flowpath of RVCP, and go to 0EOP-01-EDP, Emergency Depressurization.

C. Remain in the RC/P flowpath of ATWS, and exceed 100°F/hr cooldown rate if necessary.

D. Remain in the RC/P flowpath of RVCP, and exceed 100°F/hr cooldown rate if necessary.

Page: 88

89. The following conditions exist on Unit One.

Reactor water level -35 inches and rising on B21-LI-R611, Reactor Water Level Uncompensated Reactor pressure 0 psig DW temperature 195°F SLC Squib lights off SLC pump red lights lit

[Reference Provided]

Which one of the following completes both statements below?

The CBEAF system (1) in the expected line up.

The CBEAF system (2) required to be aligned IAW 0EOP-01-SEP-11, Alternate Source Term Actions.

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: 89

90. Following a reactor scram on Unit Two due to a loss of off-site power, the following plant conditions exist:

UA-03 (2-7) Area Rad RX Bldg High (blue bar) In alarm UA-12 (2-4) South RHR RM Flood Level Hi, (blue bar) In alarm UA-12 (2-3) South CS RM Flood Level Hi (blue bar) In alarm Reactor Building 20' rad level Rising Reactor Building 20' temperature 125°F and rising Reactor water level 150 inches Drywell pressure 2.1 psig The CRS is evaluating the following:

Which one of the following completes both statements below?

The CRS should proceed to step (1) .

The CRS will direct the restart of RB HVAC IAW (2) .

A. (1) SCCP-4 (2) 0EOP-01-SEP-04, RB HVAC Restart Procedure B. (1) SCCP-4 (2) OP-37.1, RB Heating and Ventilation System Operating Procedure C. (1) SCCP-11 (2) 0EOP-01-SEP-04, RB HVAC Restart Procedure D. (1) SCCP-11 (2) OP-37.1, RB Heating and Ventilation System Operating Procedure Page: 90

91. Unit One is executing RVCP and SCCP due to a primary leak discharging into the Reactor Building.

The following annunciators are in alarm:

UA-12 (2-1), North CS RM Flood Level HI (blue bar)

UA-12 (1-1), North CS RM Flood Level HI-HI (red bar)

UA-12 (2-2), North RHR RM Flood Level HI (blue bar)

Which one of the following completes both statements below?

Equipment required for safe shutdown in the (1) will fail.

The CRS is (2) .

A. (1) North CS Room ONLY (2) allowed to direct 0EOP-01-SEP-15, Anticipate Emergency Depressurization B. (1) North CS Room ONLY (2) required to direct 0EOP-01-EDP, Emergency Depressurization C. (1) North CS and North RHR Rooms (2) allowed to direct 0EOP-01-SEP-15, Anticipate Emergency Depressurization D. (1) North CS and North RHR Rooms (2) required to direct 0EOP-01-EDP, Emergency Depressurization Page: 91

92. Unit One is operating at 100% power when annunciator UA-03 (1-4), TBCCW Head Tank Level Hi/Lo, (yellow bar) is received.

The level in the TBCCW head tank is reported as lowering.

All TBCCW pumps are running with header pressure at 38 psig.

Which one of the following completes both statements below?

As the TBCCW head tank continues to lower the running TBCCW pumps (1) trip on TBCCW head tank low level.

The CRS will direct closing TCC-V1, Head Tank Supply To Unit 1, IAW (2) .

A. (1) will (2) UA-03 (1-4), TBCCW Head Tank Level Hi/Lo B. (1) will (2) 0AOP-17, Turbine Building Closed Cooling Water System Failure C. (1) will NOT (2) UA-03 (1-4), TBCCW Head Tank Level Hi/Lo D. (1) will NOT (2) 0AOP-17, Turbine Building Closed Cooling Water System Failure Page: 92

93. Both Units are operating at 100% power.

12/07 @ 0700 DG3 under clearance.

12/13 @1400 the load dispatcher has reported that system conditions are currently inadequate to ensure E-bus voltage support under LOCA conditions. This condition affects both units.

[Reference Provided]

Which one of the following completes the statement below?

IAW TS 3.8.1, AC Sources - Operating, Unit Two is required to be in MODE 3 no later than:

A. 12/15 @ 0200 B. 12/14 @ 1400 C. 12/14 @ 0300 D. 12/14 @ 0200 Page: 93

94. Unit One is in an accident condition and is executing RVCP with the following conditions:

Reactor Water Level -60 inches on B21-LI-R611, Reactor Water Level Uncompensated Reactor Pressure 800 psig Reference Leg Temperature 208° F Injection sources available None

[Reference Provided]

Which one of the following completes both statements below?

The CRS shall (1) flowpath of RVCP, and (2) .

A. (1) exit RC/P (2) go to Emergency Depressurization Procedure B. (1) exit RC/P (2) proceed to Steam Cooling C. (1) remain in RC/P (2) go to Emergency Depressurization Procedure D. (1) remain in RC/P (2) proceed to Steam Cooling Page: 94

95. The following conditions exist for Unit Two:

Reactor Mode Switch Refuel Average Reactor Coolant Temp 195°F Reactor Head Closure Bolts Fully tensioned On December 14 at 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months chemistry reports the following sample results:

Conductivity 1.98 µmhos/cm @25°C Chlorides 0.53 ppm

[Reference Provided]

Which one of the following identifies the latest time that Unit Two must be in MODE 4 IAW TRM 3.13, RCS Chemistry?

A. 12/15 at 2000 B. 12/16 at 0800 C. 12/16 at 2000 D. 12/17 at 0800 Page: 95

96. TS 3.6.1.3, Primary Containment Isolation Valves (PCIVs), requires deactivation of a solenoid operated primary containment isolation valve in the closed position.

Opening the breaker for this valve will also de-energize other components.

No fuse is available to deactivate the valve.

IAW 0OI-01.01, BNP Conduct of Operations Supplement, which one of the following identifies the method that is required to be used to deactivate the valve to comply with Tech Spec 3.6.1.3?

A. Open the breaker IAW AD-OP-ALL-0200, Clearance and Tagging.

B. Remove the solenoid amphenol connector IAW 0AI-59, Jumpering and Wire Removal.

C. Maintain the control switch in the close position IAW AD-OP-ALL-0204, Plant Status Control.

D. Lift a wire between the control switch and the solenoid to de-energize the valve IAW AD-EG-ALL-1139, Temporary Configuration Changes.

Page: 96

97. Which one of the following is a condition of the Unit Two plant operating license?

A. The valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation, except for one bypass valve.

B. The licensee shall not operate the facility within the MELLLA+ operating domain with an inoperable Main Turbine Bypass System.

C. The end-of-cycle recirculation pump trip system instrumentation shall be maintained operable when thermal power is greater than or equal to 30% rated thermal power.

D. The licensee may not make changes to the Tech Spec Bases without prior NRC approval.

Page: 97

98. The BSEP Radioactive Liquid Release Permit is being approved with the following step filled out on the permit:

Which one of the following completes both statements below?

The Radioactive Liquid Release (1) .

The minimum required approval to commence any liquid release is(are) the (2) .

A. (1) is NOT allowed unless 2-G16-FIT-N057 is operable (2) Unit CRS ONLY B. (1) is NOT allowed unless 2-G16-FIT-N057 is operable (2) Unit CRS and Shift Manager C. (1) can still occur if ODCM compensatory actions are implemented (2) Unit CRS ONLY D. (1) can still occur if ODCM compensatory actions are implemented (2) Unit CRS and Shift Manager Page: 98

99. Unit Two is at 18% power.

Drywell entry is required.

Which one of the following completes both statements below?

The Drywell entry shall be approved by the (1) IAW 0E&RC-0261, Drywell Entry.

A clearance (2) required to be placed on each TIP Ball Valve IAW 0OI-01.03, Non-Routine Activities.

A. (1) RP Manager (2) is B. (1) RP Manager (2) is NOT C. (1) Plant General Manager (2) is D. (1) Plant General Manager (2) is NOT Page: 99

100. A transient has occurred on Unit One resulting in multiple Event Procedure entry conditions.

Which one of the following completes both statements below?

IAW AD-OP-ALL-1001, Conduct of Abnormal Operations, the implementation of the Event Procedures will be (1) .

IAW 0OI-076, Preparation and Implementation Standard for Abnormal Operating Procedures, associated immediate actions will be (2) .

A. (1) concurrent (2) delayed until entry of Event Procedure B. (1) concurrent (2) performed upon recognition of event C. (1) prioritized (2) delayed until entry of Event Procedure D. (1) prioritized (2) performed upon recognition of event Page: 100

SRO Written Exam Reference Index

1. 0EOP-01-UG, Users Guide, Attachments:

19 (RPV Saturation Limit) 20 (Unit 1 Narrow Ranger Level Instrument (N004A, B, C) Caution) 22 (Shutdown Range Level Instrument (N027A, B) Caution) 31 (RPV Level Caution) pages 1-2

2. 0EOP-01-UG, Users Guide, Attachments:

7 (Heat Capacity Temperature Limit) 23 (Unit 1 RPV Level at TAF) 25 (Unit 1 RPV Level at LL4) 27 (Unit 1 RPV Level at LL5)

3. Tech Spec 3.1.4, Control Rod Scram Times

4. Tech Spec 3.8.1, AC Sources - Operating

5. TRM 3.13, RCS Chemistry

6. CSD-EP-BNP-0101-02, Brunswick Nuclear Plant EALs

USER'S GUIDE 0EOP-01-UG Rev. 075 Page 92 of 168 ATTACHMENT 19 Page 1 of 1

<< RPV Saturation Limit >>

USER'S GUIDE 0EOP-01-UG Rev. 075 Page 93 of 168 ATTACHMENT 20 Page 1 of 1

<< Unit 1 Narrow Range Level Instrument (N004A, B, C) Caution >>

USER'S GUIDE 0EOP-01-UG Rev. 075 Page 95 of 168 ATTACHMENT 22 Page 1 of 1

<< Shutdown Range Level Instrument (N027A, B) Caution >>

USER'S GUIDE 0EOP-01-UG Rev. 075 Page 104 of 168 ATTACHMENT 31 Page 1 of 4

<< RPV Level Caution >>

Caution 1 A RPV level instrument may be used to determine RPV level only when the conditions for use specified below are satisfied for that instrument.

NOTE

Reference leg area drywell temperature is determined using Attachment 18, Level Instrument Reference Leg Area Drywell Temperature Calculations, ERFIS or Instructional Aid based on Attachment 18. ...............................

If the temperature near any instrument run is in the UNSAFE region of the Attachment 19, RPV Saturation Limit, the instrument may be unreliable due to boiling in the run. ...........................................................................................................

Immediate reference leg boiling is not expected to occur for short duration excursions into the unsafe region due to heating of the drywell. The thermal time constant associated with the mass of metal and water in the reference leg will prohibit immediate boiling of the reference leg. Reference leg boiling is an obvious phenomenon. Large scale oscillations of all water level instruments associated with the reference leg that is boiling will occur. This occurrence will be obvious and readily observable by the operator. Additionally, if the operator is not certain whether boiling has occurred, he can refer to plant history as provided on water level recorders or ERFIS. Reference leg boiling is indicated by level oscillations without corresponding pressure oscillations. .................................

Instrument Conditions for Use Narrow Range Level Instruments Unit 1 Only: The indicated level is in the C32-LI-R606A, B, C (N004A, B, C) SAFE region of Attachment 20.

C32-LPR-R608 (N004A, B) Unit 2 Only: The indicated level is in the Indicating Range 150-210 Inches SAFE region of Attachment 21.

Cold Reference Leg Shutdown Range Level Instruments The indicated level is in the SAFE region of B21-LI-R605A, B (N027A, B) Attachment 22.

Indicating Range 150-550 Inches Cold Reference Leg To determine RPV level at the Main Steam Line Flood Level (MSL), see Attachment 30.

Attachment 30 has two curves: The upper curve is for reference leg area drywell temperature equal to or greater than 200°F.

The lower curve is for reference leg area drywell temperature less than 200°F.

USER'S GUIDE 0EOP-01-UG Rev. 075 Page 105 of 168 ATTACHMENT 31 Page 2 of 4

<< RPV Level Caution >>

Caution 1 (Continued)

Instrument Conditions for Use Wide Range Level Instruments

Temperature on the Reactor Building B21-LI-R604A, B (N026A, B) 50' below 140°F (B21-XY-5948A C32-PR-R609 (N026B) A2-4, B21-XY-5948B A2-4, Indicating Range 0-210 Inches ERFIS Computer Point B21TA102, Cold Reference Leg OR B21TA103)

AND

IF the reference leg area drywell temperature is in the UNSAFE region of Attachment 19, RPV Saturation Limit, THEN the indicated level is greater than 20 inches OR IF the reference leg area drywell temperature is in the SAFE region of Attachment 19, RPV Saturation Limit, THEN the indicated level is greater than 10 inches.

USER'S GUIDE 0EOP-01-UG Rev. 075 Page 79 of 168 ATTACHMENT 7 Page 1 of 1

<< Heat Capacity Temperature Limit >>

Torus water temperature is determined by:

CAC-TR-4426-1A, Point Wtr Avg OR

CAC-TR-4426-2A, Point Wtr Avg OR

Computer point G050 OR

Computer point G051 OR

CAC-TY-4426-1 OR

CAC-TY-4426-2 Select graph line immediately below torus water level as the limit.

USER'S GUIDE 0EOP-01-UG Rev. 075 Page 96 of 168 ATTACHMENT 23 Page 1 of 1

<< Unit 1 RPV Level at TAF >>

When RPV pressure is less than 60 psig, use indicated level. TAF is -7.5 inches.

USER'S GUIDE 0EOP-01-UG Rev. 075 Page 98 of 168 ATTACHMENT 25 Page 1 of 1

<< Unit 1 RPV Level at LL 4 (Minimum Steam Cooling RPV Level) >>

When RPV pressure is less than 60 psig, use indicated level. LL-4 is -27.5 inches.

USER'S GUIDE 0EOP-01-UG Rev. 075 Page 100 of 168 ATTACHMENT 27 Page 1 of 1

<< Unit 1 RPV Level at LL 5 (Minimum Zero Injection RPV Level) >>

When RPV pressure is less than 60 psig, use indicated level. LL-5 is -45.0 inches.

Control Rod Scram Times 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.1.4 a. No more than 10 OPERABLE control rods shall be "slow," in accordance with Table 3.1.4-1; and

b. No more than 2 OPERABLE control rods that are "slow" shall occupy adjacent locations.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months not met.

SURVEILLANCE REQUIREMENTS

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

During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.

SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is within the limits Prior to exceeding of Table 3.1.4-1 with reactor steam dome pressure 40% RTP after 800 psig. each reactor shutdown 120 days (continued)

Brunswick Unit 1 3.1-12 Amendment No. 219

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.4.2 Verify, for a representative sample, each tested In accordance with control rod scram time is within the limits of the Surveillance Table 3.1.4-1 with reactor steam dome pressure Frequency Control 800 psig. Program SR 3.1.4.3 Verify each affected control rod scram time is within Prior to declaring the limits of Table 3.1.4-1 with any reactor steam control rod dome pressure. OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is within Prior to exceeding the limits of Table 3.1.4-1 with reactor steam dome 40% RTP after pressure 800 psig. fuel movement within the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time Brunswick Unit 1 3.1-13 Amendment No. 276

Control Rod Scram Times 3.1.4 Table 3.1.4-1 (page 1 of 1)

Control Rod Scram Times

NOTES ----------------------------------------------------------

1. OPERABLE control rods with scram times not within the limits of this Table are considered "slow."

2. Enter applicable Conditions and Required Actions of LCO 3.1.3, "Control Rod OPERABILITY," for control rods with scram times > 7 seconds to notch position 06. These control rods are inoperable, in accordance with SR 3.1.3.3, and are not considered "slow."

SCRAM TIMES WHEN REACTOR STEAM DOME NOTCH POSITION PRESSURE 800 psig(a)(b)

(seconds) 46 0.44 36 1.08 26 1.83 06 3.35 (a) Maximum scram time from fully withdrawn position, based on de-energization of scram pilot valve solenoids at time zero.

(b) When reactor steam dome pressure is < 800 psig, established scram time limits apply.

Brunswick Unit 1 3.1-14 Amendment No. 250

AC SourcesOperating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC SourcesOperating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:

a. Two Unit 2 qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System;

b. Four diesel generators (DGs); and

c. Two Unit 1 qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME A. --------------NOTE--------------- A.1 Restore Unit 1 offsite circuit 45 days Only applicable when Unit 1 to OPERABLE status.

is in MODE 4 or 5.

One Unit 1 offsite circuit inoperable.

(continued)

Brunswick Unit 2 3.8-1 Amendment No. 260

AC SourcesOperating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. -------------NOTES-------------- B.1 Declare required feature(s) Immediately from

1. Only applicable when with no power available discovery of Unit 1 is in MODE 4 inoperable when the Condition B or 5. redundant required concurrent with feature(s) are inoperable. inoperability of

2. Condition B shall not be redundant required entered in conjunction feature(s) with Condition A.

Two Unit 1 offsite circuits inoperable due to one Unit 1 balance of plant circuit path to the downstream 4.16 kV emergency bus inoperable for planned maintenance.

AND AND 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months DG associated with the affected downstream B.2 Perform SR 3.8.1.1 for AND 4.16 kV emergency bus OPERABLE offsite inoperable for planned circuit(s). Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months maintenance. thereafter AND B.3 Restore both Unit 1 offsite 7 days circuits and DG to OPERABLE status. AND 10 days from discovery of failure to meet LCO 3.8.1.a or b (continued)

Brunswick Unit 2 3.8-2 Amendment No. 235

AC SourcesOperating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One offsite circuit inoperable C.1 Perform SR 3.8.1.1 for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for reasons other than OPERABLE offsite Condition A or B. circuit(s). AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Declare required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from with no offsite power discovery of no available inoperable when offsite power to one the redundant required 4.16 kV emergency feature(s) are inoperable. bus concurrent with inoperability of redundant required feature(s)

AND C.3 Restore offsite circuit to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

AND 17 days from discovery of failure to meet LCO 3.8.1.a or b (continued)

Brunswick Unit 2 3.8-3 Amendment No. 292

AC SourcesOperating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One DG inoperable for D.1 Perform SR 3.8.1.1 for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months reasons other than OPERABLE offsite Condition B. circuit(s). AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND D.2 Evaluate availability of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months supplemental diesel generator (SUPP-DG) AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND D.3 Declare required feature 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from (s), supported by the discovery of inoperable DG, inoperable Condition D when the redundant concurrent with required feature (s) are inoperability of inoperable. redundant required feature (s)

AND D.4.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DG(s) are not inoperable due to common cause failure.

OR D.4.2 Perform SR 3.8.1.2 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DG(s).

AND (continued)

Brunswick Unit 2 3.8-4 Amendment No. 292

AC SourcesOperating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. (continued) D.5 Restore DG to OPERABLE ---------NOTE----------

status. Until DG 4 is returned to OPERABLE status, not to exceed 0745 EST on December 13, 2017, the 14 day and 17 day Completion Times are extended to 30 days and 33 days, respectively.

7 days from discovery of unavailability of SUPP-DG AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from discovery of Condition D entry 6 days concurrent with unavailability of SUPP-DG AND 14 days AND 17 days from discovery of failure to meet LCO 3.8.1.a or b (continued)

Brunswick Unit 2 3.8-5 Amendment No. 310

AC SourcesOperating 3.8.1 ACTIONS (continued)

E. Two or more offsite circuits E.1 Declare required feature(s) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from inoperable for reasons other inoperable when the discovery of than Condition B. redundant required Condition E feature(s) are inoperable. concurrent with inoperability of redundant required feature(s)

AND E.2 Restore all but one offsite 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months circuit to OPERABLE status.

(continued)

Brunswick Unit 2 3.8-5a Amendment No. 310

AC SourcesOperating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. One offsite circuit inoperable ----------------------NOTE------------------

for reasons other than Enter applicable Conditions and Condition B. Required Actions of LCO 3.8.7, "Distribution SystemsOperating,"

AND when Condition F is entered with no AC power source to any 4.16 kV One DG inoperable for emergency bus.

reasons other than -------------------------------------------------

Condition B.

F.1 Restore offsite circuit to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

OR F.2 Restore DG to OPERABLE 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months status.

G. Two or more DGs G.1 Restore all but one DG to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. OPERABLE status.

H. Required Action and H.1 -------------NOTE--------------

associated Completion Time LCO 3.0.4.a is not of Condition A, B, C, D, E, F applicable when entering or G not met. MODE 3.

Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I. One or more offsite circuits I.1 Enter LCO 3.0.3. Immediately and two or more DGs inoperable.

OR Two or more offsite circuits and one DG inoperable for reasons other than Condition B.

Brunswick Unit 2 3.8-6 Amendment No. 308

RCS Chemistry 3.13 3.13 REACTOR COOLANT SYSTEM (RCS) CHEMISTRY TRMS 3.13 The chemistry of the RCS shall be maintained within the limits of Table 3.13-1.

APPLICABILITY: According to Table 3.13-1.

COMPENSATORY MEASURES REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. Conductivity greater than A.1 Verify by administrative Immediately the limit of Table 3.13-1 but means that operation

< 10mhos/cm at 25°C in under this condition shall MODE 1, 2, or 3. not exceed 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year.

OR AND Chloride concentration greater than the limit of A.2 ---------------NOTE------------

Table 3.13-1 but < 0.5 ppm -

in MODE 1, 2, or 3. TRMS 3.0.4 is not applicable.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Restore chemistry parameter(s) to within limit(s).

B. Required Compensatory B.1 Submit a Special Report to 14 days Measure A.1 and associated the NRC outlining the Completion Time not met. cause of the non-compliance, plans for restoring the parameter to within limit, and the impact of the non-compliance on RCS integrity.

(continued)

Brunswick Unit 2 3.13-1 Revision No. 23

RCS Chemistry 3.13 COMPENSATORY MEASURES (continued)

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME C. Required Compensatory C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Measure A.2 and associated Completion Time not met. AND OR C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Conductivity 10mhos/cm

@ 25°C in MODE 1, 2, or 3.

OR Chloride concentration 0.5 ppm in MODE 1, 2, or 3.

D. Conductivity greater than D.1 Restore chemistry 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months the limit of Table 3.13-1 in parameter to within limit.

MODE 4 or 5.

OR Chloride concentration greater than the limit of Table 3.13-1 in MODE 4 or 5.

Brunswick Unit 2 3.13-2 Revision No. 23

RCS Chemistry 3.13 TEST REQUIREMENTS TEST FREQUENCY TR 3.13.1 ---------------------------------NOTE-------------------------------

Not required to be met if all continuous recording conductivity monitors are inoperable and TR 3.13.2 is satisfied.

Record RCS conductivity. Continuously TR 3.13.2 ---------------------------------NOTE-------------------------------

Not required to be met if TR 3.13.1 is satisfied.

Analyze an RCS sample for conductivity. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TR 3.13.3 Analyze an RCS sample for conductivity. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months TR 3.13.4 Analyze an RCS sample for chloride concentration. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Brunswick Unit 2 3.13-3 Revision No. 23

RCS Chemistry 3.13 Table 3.13-1 (page 1 of 1)

RCS Chemistry Limits CHEMISTRY APPLICABLE LIMIT PARAMETER MODES OR OTHER SPECIFIED CONDITION

1. Chlorides 1 < 0.5 ppm 2,3,4,5 < 0.2 ppm

2. Conductivity 1,2 < 2.0 mhos/cm @ 25°C 3,4,5 < 10.0 mhos/cm @ 25°C Brunswick Unit 2 3.13-4 Revision No. 23

ML21015A020

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