ML14188C246

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301 SRO As-Given Written Exam
ML14188C246
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 07/07/2014
From:
NRC/RGN-II
To:
Virginia Electric & Power Co (VEPCO)
References
50-338/14-301, 50-339/14-301 50-338/OL-14, 50-339/OL-14
Download: ML14188C246 (101)
v • d • e


Text

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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: 06/25/14 Facility/Unit: North Anna Power Station Region: I [1 Il [] III fl IV LI Reactor Type: W CE LI BW [J3E [1 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 80.00 percent overall, with 70.00 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 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.

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

Applicants Signature Results RO/S RD-Only/Total Examination Values / I Points Applicants Scores I I Points Applicants Grade / I Percent ES-401, Page 31 of 33

1. Given the following:
  • Unit 2 was operating at 100% power for 220 days
  • A reactor trip without SI occurred 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ago
  • The unit is stable in MODE 3 at NO LOAD Tave
  • No dilutions or borations have occurred Which ONE of the choices below completes the following statement regarding Shutdown Margin (SDM) after the reactor trip occurred?

SDM is (1) than at the time of the reactor trip, and SDM is currently (2)

A. (1) higher (2) lowering B. (1) higher (2) rising C. (1) lower (2) lowering D. (1) lower (2) rising

2. Given the following:
  • Unit 1 was stable at 100% power when a LOCA occurred
  • Current Conditions:
  • The crew is currently in 1 -E-1, Loss of Reactor or Secondary Coolant, and are at step 12 to CHECK IF LOW-HEAD SI PUMPS SHOULD BE STOPPED Which ONE of the choices below completes the following statement?

The CAUTION statement before step 12 states that the Low-Head SI Pumps should be manually restarted to supply water to the RCS IF A. RCS pressure decreases in an uncontrolled manner to less than 225 psig.

B. RWST level decreases to less than 23%.

C. High-Head Cold Leg SI flow is NOT indicated.

D. RCS subcooling based on Core Exit TCs is less than 25°F.

3. Given the following:
  • Unit 1 was operating at full power
  • B Train ICCM had failed and was removed from service for repairs
  • Subcooling indication on A train ICCM is suspected to be inaccurate Current Conditions:
  • Average 5 highest CETCs: 253°F
  • Wide Range RCS Pressure: 26 psig
  • RCS Cold Leg Temperature: 221°F
  • RCS Hot Leg Temperature: 247° F
  • Containment Pressure: 24 psia The crew is directed to manually calculate Subcooling.

Based on the information above, which ONE of the following is the correct value that the A train ICCM should be displaying? (Reference Provided)

A -15°F B -11°F C 15°F D. 21°F

4. Given the following:
  • Unit 1 is stable at 7% power preparing to roll the main turbine
  • A loss of the Unit 1 J Emergency bus occurs
  • The 1J EDG did not automatically start Which ONE of the choices below is correct concerning Reactor Coolant Pump operation?

A. Component Cooling water flow has been lost to the RCP motors ONLY.

B. Component Cooling water flow has been lost to the RCP motors AND thermal barriers.

C. Component Cooling water flow has been lost to the RCP thermal barriers ONLY.

D. Component Cooling water flow has NOT been lost to the RCP motors OR thermal barriers.

5. Given the following:
  • Unit 1 is at 100% power and stable Current Conditions:
  • 1-AR-C-C5, CH PP To Regen HX Hi-Lo Flow, is LIT
  • 1-AR-C-B3, Regen Hx Letdwn Line Hi Temp, is LIT
  • VCT level is 49% and rising
  • Pressurizer level is 59% and lowering
  • Letdown flow is fluctuating
  • Letdown pressure is fluctuating Which ONE of the choices below identifies the failure that has resulted in the above indications?

A. 1-CH-FT-1 122, Charging Flow transmitter, has failed high B. 1-CH-PCV-1145, Letdown Pressure control valve, has failed closed C. 1-CH-TV-1204A, Letdown Isolation valve, has failed closed D. 1-CH-FCV-1122, Charging Flow control valve, instrument air has been lost

6. Given the following:
  • Unit 1 is in MODE 5
  • The RCS is solid
  • All letdown orifice isolations are closed
  • 1-CH-HCV-1 142, RHR to Letdown, is full open
  • 1-CH-PCV-1 145, Letdown Pressure Control Valve, is in auto
  • RCS Temperature is 185°F
  • RCS Pressure is 330 psig
  • 1-RH-P-lA (A RHR Pump) is in service Which ONE of the choices below will INITIALLY occur if 1-RH-P-lA trips on overcurrent? (Assume no operator actions)

A. RCS Pressure would rise B. 1-CH-PCV-1145 would throttle open C. Charging flow would rise D. VCT level would rise

7. Given the following:
  • Unit 1 is at 100% power
  • All control systems are in their normal alignment, with the exception of the Pressurizer Master Pressure Controller, 1-RC-PCV-1444J, which is in MANUAL
  • The Pressurizer Master Pressure Controller output fails LOW Assuming no action has been taken by the crew, which ONE of the choices below describes the effect on the Pressurizer heaters and the resulting effect on Pressurizer PORVs and Spray valves?

A. Pressurizer heaters energize; Pressure rise is controlled by 1-RC-PCV-1455C, Pressurizer PORV operation B. Pressurizer heaters energize; Pressure rise is controlled by 1-RC-PCV-1456, Pressurizer PORV operation C. Pressurizer heaters de-energize; Pressurizer spray valves AND 1-RC-PCV-1456, Pressurizer PORV opens.

D. Pressurizer heaters de-energize; Pressurizer spray valves AND 1-RC-PCV-1455C, Pressurizer PORV opens.

8. Given the following:
  • The reactor failed to trip automatically
  • Operator actions to manually trip the reactor failed
  • 1-FR-S.1, Response to Nuclear Power Generation/ATWS, has been entered
  • The crew had attempted to initiate emergency boration of the RCS
  • Emergency boration flow indicates 0 gpm In accordance with 1-FR-S.1, which ONE of the following actions is directed and why?

A. Open normal charging line isolation valves; Maximize core cooling flow B. Close normal charging line isolation valves; Verify all dilution flow paths are isolated C. Close normal charging line isolation valves; Maximize negative reactivity addition through the BIT D. Open normal charging line isolation valves; Allow operators to continue attempts to emergency borate

9. Given the following:
  • The cooldown to the desired core exit temperature has NOT been initiated.
  • Current Conditions
  • RCS subcooling is 20°F
  • Pressurizer level is off scale low
  • B SG pressure is 300 psig and slowly lowering
  • Q Charging Pumps are running Which ONE of the choices below completes the following statements?

In accordance with 1-E-3 continuous action page, based on the above information, the crew (1)_ trip all RCPs, because (2).

A. (1) will not (2) no charging pumps are running B. (1) will (2) RCP seal injection flow has been lost C. (1) will (2) RCS subcooling is below minimum value D. (1)will not (2) operators will restore RCS subcooling during the cooldown

10. Given the following:
  • Unit 2 has tripped from 100% power
  • 10 minutes after the unit trip, a large fault occurs on the B main steam line upstream of the steam flow venturi Which ONE of the signals below will cause the main steam trip valves to close during this event?

A. High steam flow coincident with b-b Tavg B. High steam flow coincident with low steam line pressure C. High steam line differential pressure D. Intermediate hi-hi containment pressure

11. Given the following:
  • A tornado resulted in a complete loss of all offsite power
  • The 1J EDG automatically started, then immediately tripped on engine overspeed
  • The 1J EDG Overspeed Reset Lever has been locally reset The crew is performing 1-ECA-O.0, Loss of All AC Power, Attachment 5 in an attempt to restore power to the 1J Emergency Bus using the 1J EDG.

The IJ EDG Mode Selector switch is in MANUAL-LOCAL. The RO depresses then releases the Alarm & Shutdown Reset pushbutton.

Which ONE of the choices below completes the following statement?

In accordance with 1-ECA-0.O, the 1J EDG (1) require a 60 second time delay prior to starting and the Mode Selector switch must be in the (2) position to allow for an automatic start.

A. (1) will (2) MANUAL-REMOTE B. (1) will (2) MANUAL-LOCAL C. (1) will not (2) MANUAL-REMOTE D. (1)will not (2) MANUAL-LOCAL

12. Given the following:
  • Unit 1 is at 75% Power
  • Channel III is selected as the controlling channel for Steam Flow, Feed Flow and 1st Stage Turbine Impulse Pressure
  • Vital AC Bus 1-Ill is lost due to a bus fault With no operator action, which ONE of the choices below describes the plant response to the loss of Vital AC Bus 1-Ill?

The Main FW Regulating Valves will INITIALLY modulate in the _(1) direction.

If the plant were to trip with the conditions above, then decay heat removal would be from the (2).

A. (1) open (2) steam dumps B. (1) open (2) steam generator PORVs C. (1) close (2) steam dumps D. (1) close (2) steam generator PORVs

13. Given the following:
  • Unit 1 is in MODE 1
  • 1-PT-86B, Quarterly DC Distribution System Test for Battery 1-Il, has just been completed with the following results:

Station Battery 1-li battery terminal voltage is 118 VDC Which ONE of the choices below completes the following statement?

In accordance with Technical Specification LCO 3.8.4, DC Sources - Operating, Station Battery 1-Il (1) within limits for required battery terminal voltage.

and The required battery limits ensure the battery has adequate storage capacity to carry the required load continuously for at least (2)

A. (1)is (2) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> B. (1)is (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C. (1) is not (2) 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D. (1) is not (2) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

14. Given the following:
  • Unit 1 is at 75% power
  • Unit 1 A Control Room Chiller is running
  • The 1 H Emergency Bus is lost due to a fault In accordance with O-AP-12, Loss of Service Water, and O-AP-55, Loss of Control Room/Emergency Switchgear Room Air Conditioning, which ONE of the choices below identifies the Service Water Pump and Control Room Chiller that are required to be started?

A. Unit 2 A Service Water Pump Unit 1 B Control Room Chiller B. Unit 2 A Service Water Pump Unit 1 C Control Room Chiller C. Unit 2 B Service Water Pump Unit 1 B Control Room Chiller D. Unit 2 B Service Water Pump Unit 1 C Control Room Chiller

15. Given the following:
  • Unit 1 is in MODE 1
  • 1-IA-C-i is in automatic and not running
  • Operators note IA and SA headers pressures at the following times:

1310 1315 1320 IA Header Pressure 89 psig 75 psig 69 psig SA Header Pressure 88 psig 77 psig 71 psig Which ONE of the choices below completes the following statement?

In accordance with 1-AP-28, Loss of Instrument Air, actions are required to start i-IA-C-i, Instrument Air compressor because of the failure to automatically start at the setpoint of(1)_ psig.

and In accordance with 1-AP-28, the earliest time a Reactor trip is required due to the conditions above is (2)_.

A. (1)98 (2) 1320 B. (1)98 (2) 1315 C. (1)90 (2) 1320 D. (1)90 (2) 1315

16. Given the following:
  • Unit 1 Generator Hydrogen Bleed and Feed is in progress
  • Generator Gas pressure is 60 psig
  • Generator Megawatts: 1000 MWe
  • A problem occurred with the Voltage Regulator in Auto In accordance with the Generator Capability Curve, 1-SC-4.3, which ONE of the choices below is the MAXIMUM value for MVARs OUT that remains within the acceptable region for current Generator Gas pressure? (Reference Provided)

A. 330 MVARs B. 390 MVARs C. 475 MVARs D. 560 MVARs

17. Given the following:
  • Unit 1 was in MODE 1
  • 1-ECA-1.2, LOCA Outside Containment, was entered following verification of outside containment inventory loss In accordance with 1-ECA-1.2, which ONE of the choices below states:

(1) Which component is first directed to be isolated and (2) Which parameter will be used to evaluate if the break has been isolated?

A. (1) Low Head Safety Injection Pump (2) RVLIS Level B. (1) Low Head Safety Injection Pump (2) RCS Pressure C. (1) High Head Safety Injection Pump (2) RVLIS Level D. (1) High Head Safety Injection Pump (2) RCS Pressure

18. Given the following:
  • 1-ECA-1.1, Loss of Emergency Coolant Recirculation, is in progress
  • RWST Level is 19% and lowering In accordance with 1-ECA-1.1, which ONE of the choices below completes the following?

The HHSI pumps are required to be stopped when RWST level reaches _(1).

and The Quench Spray Pumps are required to be stopped when RWST level reaches A. (1)8%

(2)3%

B. (1)8%

(2)8%

C. (1)3%

(2)3%

D. (1)3%

(2) 8%

19. Given the following:
  • Reactor Power is stable at 60% power EOL
  • The Unit 1 RO reports the following parameter trends:
  • Reactor Power Rising
  • RCS Tave Rising
  • Pressurizer Level Rising
  • Pressurizer Pressure Rising Axial Flux Rising Which ONE of the choices below answers the following?

Power Range Channel N-44 has failed _(1)_.

and In accordance with 1-AP-4.3, Malfunction of Nuclear Instrumentation, manual control of

_(2) is required.

A. (1) High (2) Pressurizer Level B. (1) High (2) Main Feed Reg Bypass Valves C. (1)Low (2) Pressurizer Level D. (1)Low (2) Main Feed Reg Bypass Valves

20. Given the following:
  • Unit 2 is stable at 50% power
  • Tave and Tref are matched
  • Pressurizer Level is stable at program level
  • All control systems are in their normal configuration
  • The Pressurizer Level Controller 2-RC-LC-2459G fails to maximum output Assuming no operator action, which ONE of the choices below describes the expected plant response.

A. Pressurizer level will lower and result in a letdown isolation B. Pressurizer level will lower and then stabilize at minimum program level C. Pressurizer level will rise and then stabilize at maximum program level D. Pressurizer level will rise and result in an automatic reactor trip

21. Given the foNowing:

Unit 1 is at 100% power steady state N-16 Radiation Monitor readings are as follows:

0000 0100 0200 A 2 GPD 2 GPD 3GPD B 60 GPD 75 GPD 115 GPD C 3 GPD 3 GPD 4GPD Header 75 GPD 97 GPD 160 GPD Assuming the N-16 Radiation Monitor readings stabilize at these current values (no additional increase)

Which ONE of the choices below completes the following?

In accordance with 1-AP-24, Steam Generator Tube Leak, (1) is the earliest procedurally required time that Steam Generator Tube Leakage exceeded the limit which requires the Unit to be placed in MODE 3.

and The requirement to shutdown is due to leakage from _(2).

A. (1) 02:00 (2) Steam Generator B only B. (1) 02:00 (2) all Steam Generators C. (1) 01:00 (2) Steam Generator B only D. (1) 01:00 (2) all Steam Generators

22. Given the following:

Current Conditions

  • Unit 1 is at 20% power
  • The balance of plant operator identifies condenser pressure is 4 Hg absolute and degrading Based on current conditions, which ONE of the choices below completes the following statements?

An automatic turbine trip (1) have occurred.

and In accordance with 1-AP-14, Low Condenser Vacuum, a manual Reactor Trip (2) required.

A. (1) should (2) is not B. (1) should not (2) is not C. (1) should (2) is D. (1) should not V (2) is

23. Given the following:
  • Both Units are at 100%
  • The A Waste Gas Decay Tank (WGDT) is currently being released in accordance with 0-OP-23.2, WASTE GAS DECAY TANKS AND WASTE GAS DIAPHRAGM COMPRESSORS
  • 1-GW-FCV-101, WGDTto Process Vents, is controlling in automatic
  • 2B-A5 - PROCESS VENT VNT STACK A&B LOW RAD MON ALERT/RAD
  • 2B-B5 - PROCESS VENT VNT STACK A&B HI HI RADIATION
  • The operator notes on the MGPI radiation monitor recorder that the process vent radiation release rate had risen rapidly and has subsequently lowered back to previous levels.

Which ONE of the choices below completes the following statements?

Based on these indications, the release was terminated when (1) radiation monitor exceeded alarm limits and 1-GW-FCV-101 (2) be opened without resetting the radiation monitors.

A. (1) 1-GW-RM-178-1, Process Vent RM Noble Gas Normal (2) can B. (1) 1-GW-RM-178-1, Process Vent RM Noble Gas Normal (2) cannot C. (1) 1-GW-RM-178-2, Process Vent RM Noble Gas Accident (2) can D. (1) 1-GW-RM-178-2, Process Vent RM Noble Gas Accident (2) cannot

24. Given the following:
  • Unit 1 has experienced a Steam Generator tube leak with high RCS activity from a fuel failure
  • The Aux Building has rising radiation indications
  • HP reports NO high airborne activity in the Aux Bldg and Turbine Bldg
  • The Control Room Radiation Monitor, 1-RMS-RM-157, alarm was received
  • O-AP-5.1, Common Unit Radiation Monitoring System, is entered
  • The Control Room is determined to be habitable
  • The crew has reached the step to perform Main Control Room and Relay Room Emergency Ventilation Operation Which ONE of the choices below completes the following statement?

In accordance with O-AP-5.1, the crew is required to place the Control Room Emergency Ventilation System fans in service in the (1) because (2)

A. (1) Recirculation Mode (2) this isolates the Charcoal filter bypass and aligns all airflow through the Charcoal filter to reduce radioactivity in the control room.

B. (1) Recirculation Mode (2) this provides filtered air to the Control Room envelope to maintain an acceptable environment for operating personnel.

C. (1) Pressurization Mode (Turbine Building Supply)

(2) this isolates the Charcoal filter bypass and aligns all airflow through the Charcoal filter to reduce radioactivity in the control room.

D. (1) Pressurization Mode (Turbine Building Supply)

(2) this provides filtered air to the Control Room envelope to maintain an acceptable environment for operating personnel.

25. Given the following:
  • Unit 1 is at 100% power
  • Annunciator D-C8, SMOKE DET SYS SMOKE INDICATION TROUBLE, alarms
  • The Fire Protection Panel (1-El-CB-97) has a red FIRE light lit for the control room Which ONE of the choices below completes the following statements?

The detectors for the control room halon system are located in the control room (1) area and Valid indications of a Control Room fire (2) actuation of the control room halon system.

A. (1) overhead (2) require manual B. (1) overhead (2) result in automatic C. (1) under floor (2) require manual D. (1) under floor (2) result in automatic

26. Given the following:
  • Unit 1 is in MODE 1
  • 1-AR-K-D2, Rad Monitor System Hi Rad Level, is in alarm
  • Reactor Coolant Letdown Radiation, 1-CH-RI-128 is in high alarm Which ONE of the choices below completes the following statement?

The main purpose of the Reactor Coolant Letdown Radiation Monitor, 1-CH-Rl-128, is to detect (1)_.

and Auto actuations _(2)_ occur if 1-CH-RI-128 reaches the HI-HI setpoint.

A. (1)fuelfailure (2) will not B. (1)fuelfailure (2) will C. (1) a crud burst (2) will not D. (1) a crud burst (2) will

27. Given the following:
  • 1-ES-0.4, Natural Circulation Cooldown with Steam Void in Vessel (WITHOUT RVLIS), is in progress.
  • Charging and Seal injection flow are equal to Letdown and Seal Leakoff flow
  • During RCS depressurization to 800 psig, 1-AR-B-F6, PRZ HI LEVEL CH I-Il-Ill annunciates
  • Pressurizer level is 93%

Which ONE of the choices below states the required action per 1-ES-0.4 in response to these conditions and what is the basis for that action?

A. Energize pressurizer heaters; To prevent water relief out of the safety valves B. Open Reactor Vessel Head Vents; To prevent water relief out of the safety valves C. Energize pressurizer heaters; To promote reactor head cooling and collapse any existing void D. Open Reactor Vessel Head Vents; To promote reactor head cooling and collapse any existing void

28. Given the following:
  • Unit I isat 100% power

In accordance with 1-OP-5.2, Reactor Coolant Pump Startup and Shutdown, which ONE of the choices below completes the following statements?

The trip criteria for B RCP is met when RCP motor bearing temperature exceeds (1)_ °F or PROXIMITY vibrations exceed _(2)_ mils.

A. (1)225 (2) 20 B. (1)225 (2) 5 C. (1)195 (2)20 D. (1) 195 (2) 5

29. Given the following:
  • Unit 1 is in MODE 4, cooling down for a refueling outage
  • RCS Temperature is 315°F
  • RCS Pressure is 390 psig
  • All RCPs are running
  • The Crew is performing 1-OP-5.2, Reactor Coolant Pump Startup and Shutdown, to shutdown the B RCP.
  • Immediately following the shutdown of the B RCP, the following indications are present
  • Seal Water Outlet Temperature - 157°F and stable
  • Pump Radial Bearing Temp - 124°F and stable
  • Thermal Barrier Outlet Temperature - 84°F and stable
  • C-G2, RCP lB Standpipe Hi Level, is LIT
  • C-G8, RCP lA-B-C Seal Leakoff Lo Flow, is LIT
  • B RCP Seal Leakoff rate is 0.4 gpm In accordance with 1-AP-33.1, Reactor Coolant Pump Seal Failure, which ONE of the choices below completes the following?

A (1) has occurred on the B RCP and The B RCP Standpipe Hi Level alarm (2)_ be cleared by opening a drain valve in the control room.

A. (1) No. 1 Seal Failure (2) can B. (1) No. 1 Seal Failure (2) can not C. (1) No. 2 Seal Failure (2) can D. (1) No. 2 Seal Failure (2) can not

30. Given the following:
  • Unit 1 is operating at full power
  • Letdown is in service
  • 1-CH-HCV-1200B, B Letdown Orifice valve is open with normal indicated flow
  • 1C-C6, Demin Inlet Divert Hi Temp, is in alarm With no operator action, which ONE of the choices below completes the following?

Based on the indications above, 1-CH-TE-1144, non-regenerative heat exhanger outlet temperature, has failed (1) and 1-CH-TCV-1143, Low Pressure Letdown Line Divert Valve, is expected to bypass the ion exchange demineralizers when 1-CH-TE-1 143 reaches (2)_.

A. low 137°F B. low 115°F C. high 137°F D. high 115°F

31. Given the following:

Initial Conditions

  • RHR is in service
  • RHR total flow is 3,300 gpm
  • 1-RH-HCV-1758, RHR H/X Outlet, is approximately 50% open and flowing 1,500 gpm
  • i-RH-FCV-1605, RHR H/X Bypass, is in AUTOMATIC Current Conditions
  • RHR flow transmitter 1-RH-FT-i 605 fails LOW.

Which ONE of the choices below completes the following statements?

As a result of this failure, total RHR flow will _(1) and flow through the RHR HIX will (2).

A. (1) Lower (2) Rise B. (i) Lower (2) Lower C. (1) Rise (2) Rise D. (1) Rise (2) Lower

32. Given the following:

Initial Indications

  • Unit 2 is in MODE 5
  • RCS temperature is 120°F and stable
  • Pressurizer level is stable at 30% on VCT float
  • 2-RH-P-i B is running with both RHR heat exchangers in service
  • 2-RH-FCV-2605, RHR Heat Exchanger Bypass Valve, is controlling RHR flow at 3500 GPM in automatic
  • 2-RH-HCV-2758, RHR Heat Exchanger Outlet, controller is set to 20%
  • CC Flow to the RHR Heat Exchanger is 1200 gpm Current Indications
  • A total loss of instrument air pressure occurs outside and inside containment Which ONE of the choices below completes the following statements?

RCS temperature will ultimately (1)_

and Flow from the RHR system to letdown will (2)

A. (1) Lower (2) Rise B. (1) Lower (2) Lower C. (1) Rise (2) Rise D. (1) Rise (2) Lower

33. Given the following:
  • A Large Break LOCA has occurred on Unit 1
  • Safety Injection has actuated
  • The motor for 1-CH-MOV-1115D, High Head Safety Injection (HHSI) suction from the RWST, has torqued out and the valve has remained fully closed Which ONE of the choices below completes the following statements?

HHSI pump suction will be from (1) and HHSI pump suction (2)

A. (1) both the VCT and the RWST (2) will be affected when the VCT empties.

B. (1) the RWST0nIy (2) will not be affected.

C. (1)theVCTonly (2) will be affected when the VCT empties.

D. (1) both the VCT and the RWST (2) will not be affected.

34. Given the following:
  • Unit 1 is at 100% power
  • The Unit 1 RO notes the following Pressurizer Relief Tank (PRT) indication
  • PRT pressure: 10.5 psig and rising
  • PRT level: 70.5% and rising
  • PRT temp: 90°F and rising Which ONE of the choices below completes the following?

(1) is a possible cause for the indications above and following a high temperature condition, the PRT is drained to the (2).

A. (1) Packing leakage from 1-RC-PCV-1455C, Przr PORV (2) PDTT B. (1) Spurious Phase A containment isolation (2) PDTT C. (1) Packing leakage from 1-RC-PCV-1455C, Przr PORV (2) Gas Stripper D. (1) Spurious Phase A containment isolation (2) Gas Stripper

35. Given the following:

Initial Conditions:

  • Unit 1 is in MODE 1
  • 1-CC-P-lB is in operation
  • 1-CC-P-lA is in standby
  • Unit2 is in MODE 5
  • 2-CC-P-i B is tagged out for maintenance
  • 2-CC-P-lA is in operation Current Conditions:
  • 2-CC-P-lA trips Which ONE of the choices below completes the following statement?

Entry into an action statement for T.S. LCO 3.7.19, Component Cooling Water System,

_(1) required for Unit 1 and Considering ONLY T.S. LCO 3.7.19, entry into an action statement (2) required for Unit 2.

A. (1)is (2) is not B. (1)is (2) is C. (1) is not (2) is not D. (1) is not (2) is

36. Given the following:
  • Unit 1 is in MODE 1
  • 1-CC-P-lA, Component Cooling Pump A is running
  • i-CC-P-i B, Component Cooling Pump B is in standby
  • An undervoltage occurs on 1H 4160 V Emergency Bus Which ONE of the choices below answers the following question?

With NO operator action, 1 minute after the undervoltage occurred on the 1 H 4160 V Emergency Bus, which Unit 1 CC Pumps will have received an auto start signal?

A. Both B. A only C. B only D. Neither

37. Given the following:
  • Unit 1 is at 100% Power
  • The Master Pressurizer Pressure Controller is in automatic
  • Pressurizer Pressure Control Transmitter 1-RC-PT-1444 has failed due to a leak in the bellows Which ONE of the choices below completes the following statements?

Assuming no operator action is taken, ACTUAL Pressurizer Pressure will INITIALLY (1) and a Reactor Trip (2) occur.

A. (1) rise (2) will B. (1) rise (2) will not C. (1) lower (2) will D. (1) lower (2) will not C 6 / ((

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38. Given the following:
  • Unit 1 is in MODE 1
  • Reactor power is 40%
  • 1-RC-PCV-1 456, Pressurizer Power Operated Relief Valve fails open
  • Operator action to close or isolate the Pressurizer PORV flowpath has been unsuccessful With no further operator action, which ONE of the choices below states which Reactor Protection System Trip Setpoint will be exceeded FIRST and the basis for the setpoint?

A. Overtemperature T Protects against violating the DNBR limit B. Overtemperature AT Ensures less than 1% clad strain C. Pressurizer Pressure Low Protects against violating the DNBR limit D. Pressurizer Pressure Low Ensures less than 1% clad strain

39. Given the following:
  • Unit 1 is at a hold point following a refueling outage
  • 1-OP-2.1, Unit Startup from MODE 2 to MODE 1, is in progress and all steps are completed for current conditions
  • Power Range Nis indicate as follows:

N-41 32%

N-42 31%

N-43 28%

N-44 31%

  • Power Range N-44 then fails low.

Which ONE of the choices below completes the following statements?

The current status of Reactor Trip System Interlock P-8 Permissive, PR<30% 1 Loop Fail Trips Blkd, Annunciator P-Fl is(l)_.

and The Reactor Protection System function currently protecting the core against a positive reactivity excursion is (2).

A. (1) NOT LIT (2) Intermediate Range Neutron Flux B. (1) NOT LIT (2) Power Range Neutron Flux - High C. (l)LIT (2) Intermediate Range Neutron Flux D. (l)LIT (2) Power Range Neutron Flux - High

40. Given the following:

Initial Conditions Unit 2 is at 100% power Containment Pressure Protection Instrument channel 2-LM-PT-200B (Ch. II) failed and was declared inoperable

  • The crew entered 2-AP-3, Loss of Vital Instrumentation
  • Bistables for 2-LM-PT-200B have been placed in their required position lAW 2-MOP-55.75 The Safety Injection bistable has been placed in TRIP The Containment Depressurization bistable has been placed in BYPASS Current Conditions
  • Vital bus I has just lost power.

Which ONE of the choices below describes the current status of Safety Injection and Containment Depressurization?

Automatic Safety Injection actuation (1) occurred and Automatic Containment Depressurization actuation _(2)_ occurred.

A. (1)has (2) has B. (1)has (2) has not C. (1) has not (2) has D. (1) has not (2) has not

41. Given the following:
  • Unit 1 is in MODE 3 A loss of the 1 H emergency bus occurs Which ONE of the choices below describes starting the Containment Air Recirculation Fans (CARF) after the 1 H emergency bus is restored?

A. The A and C CARFs can be started immediately.

B. The A CARF cannot be started until after 30 seconds.

The C CARE can be started immediately.

C. The A CARF can be started immediately.

The C CARF cannot be started until after 30 seconds.

D. The A and C CAREs cannot be started until after 30 seconds.

42. Given the following:
  • Unit 1 was at 75% power when a large break LOCA occurred
  • 1-QS-LT-100A (RWST level ch. Ill) and 1-QS-LT-100C (RWST level ch. I) are not responding to RWST level change due to being frozen during extreme cold weather Which ONE of the choices below completes the following statements?

Due to this failure, Recirc Spray pumps (1) auto start and The automatic swapover to containment suction (2) occur when the appropriate RWST level setpoint is reached.

A. (1) will (2) will B. (1) will (2) will not C. (1)will not (2) will D. (1) will not (2) will not

43. Given the following:
  • Unit 1 was at 100% power when a Reactor Trip/Turbine Trip occurred
  • 1-AR-B-A8, Loop lA-B-C Tavg Deviation, is LIT
  • Current RCS Loop Tavg indications:

Loop A Loop B Loop C 563°F 552°F 561°F Which ONE of the choices below describes the expected indicated position of the condenser steam dump valves?

A. Banks 1, 2, 3, and 4 valves indicate full open B. Banks 1, 2, and 3 valves indicate full open; bank 4 valves indicate midposition C. Banks 1 and 2 valves indicate full open; banks 3 and 4 valves are closed D. Bank 1 valves indicate full open; bank 2 valves indicate midposition; banks 3 and 4 valves are closed

44. Given the following Initial Conditions:
  • Unit 1 is operating at 20% power
  • Feedwater Pump A is in service Current Conditions:
  • 50 seconds ago, A high-high level occurred in the 5A Feedwater Heater due to a tube rupture
  • RCS Tave is 551° F and lowering Which ONE of the choices below completes the following statement?

Assuming no operator action, in response to the above conditions, Main Feedwater Pump A is (1) and the Feed Reg Bypass Valves (2) receive an automatic closure signal.

A. (1) running (2) will B. (1) running (2) will not C. (1) tripped (2) will D. (1) tripped (2) will not

45. Given the following:
  • Unit 2 is at 100% power
  • A loss of offsite power occurs
  • No Safety Injection signal is present Which ONE of the choices below completes the following statement?

The motor-driven Auxiliary Feed Water (AFW) pumps will automatically start seconds after the associated emergency bus voltage is restored?

A.0 B. 15 C.20 D.25

46. Given the following:
  • Battery Charger 1-I has failed due to an overcurrent fault
  • 1-AR-H-B1, Battery Chgr 1-I Trouble is LIT
  • 1-AR-H-Al, Vital Bus 1-I Invert Trouble, is NOT LIT
  • In accordance with the Annuciator Response Procedure an operator has been dispatched At 1-VB-INV-O1, Vital Bus Distribution Panel 1-I Inverter, LowAC Output Voltage is NOT LIT Which ONE of the choices below completes the following statement?

Vital AC Bus 1-I is currently being supplied from (1) and the vital bus indications will be verified normal by checking_(2).

A. (1) Voltage Regulating Transformer 1-I (2) Amps in the Main Control Room B. (1) Voltage Regulating Transformer 1-I (2) Amps at the Inverter Panel, 1-VB-INV-O1 C. (1) Station Battery 1-I (2) Amps at the Inverter Panel, 1-VB-INV-O1 D. (1) Station Battery 1-I (2) Amps in the Main Control Room

47. Given the following:
  • Unit I is in MODE 4 following a refueling outage
  • Circulating Water Pumps 1-CW-P-1A and 1-OW-P-lB are in service
  • The associated C CW pump discharge MOV failed to open fully and pump amps are indicating high
  • The local operator has been directed to trip the C CW pump at the breaker in accordance with l-OP-48.2 attachment 2, Manual Operation of Circulating Water Pump Breakers
  • The Control Switch for 1-CW-P-1C has been placed in the Pull-To-Lock position in the control room Which ONE of the choices below completes the following statement?

The pump cannot be stopped from the control room due to a _(1) minute time delay interlock after closing the breaker and The operator in the control room (2)_ be able to monitor the breaker operation using the green (open) breaker position light.

A. (1)4 (2) will B. (1)4 (2) will not C. (1)5 (2) will D. (1)5 (2) will not

48. Given the following:
  • Unit 1 is at 100% power steady state
  • Alarm 1-AR-H-B 1, Battery Chgr 1-I Trouble, annunciates
  • An operator is dispatched to battery charger 1-I
  • The operator discovers the negative ground light is NOT LIT on the 1-I DC Bus Panel.

Which ONE of the choices below completes the following statement?

A blown ground indicating bulb on the DC Bus panel (1)_ cause the Battery Charger 1-I trouble alarm.

If a ground exists, the cause can be determined by swapping loads to DC Bus (2) one at a time until the grounded load is identified.

A. (1) can not (2) 1Il B. (1)can (2) 1Il C. (1) can not (2) 1Ill D. (1)can (2) 1Ill

49. Given the following:
  • The Shift Manager has directed entry into 1-AP-20, Operation from the Auxiliary Shutdown Panel
  • Step 5 of 1-AP-20 is in progress with both Emergency Busses energized by offsite power
  • Step 5 continues:

Place CRE switch for any Emergency Bus energized by offsite power to EMERGENCY while continuing with this procedure Which ONE of the choices below completes the following statement?

The Contol Room Emergency (CRE) switch is located (1) and Regarding manual operation, with the CRE switch in EMERGENCY, the associated EDG can (2).

A. (1) at the Auxiliary Shutdown Panel (2) be started from the Main Control Room and the EDG Room B. (1) at the Auxiliary Shutdown Panel (2) only be started in the EDG Room C. (1) in the EDG Room (2) only be started in the EDG Room D. (1) in the EDG Room (2) be started from the Main Control Room and the EDG Room

50. Given the following:
  • Unit 1 is in MODE 1 at 100% power
  • 1H EDG is in auto
  • 1 H-EG-A1, Starting Air Pressure Low local alarm is lit
  • 1 -EG-TK-1 HA, Air Receiver Air pressure is 175 psig
  • 1-EG-C-1 HA, 1 H EDG Air Compressor AC motor failed to start Which ONE of the choices below states the expected diesel air system response?

The 1 H EDG Air System Lister Diesel will (1).

and When the Lister Diesel air compressor discharge pressure rises to 250 psig _(2)

A. (1) start automatically due to low air receiver pressure (2) the associated pressure switch opens signaling the compressor to stop B. (1) start automatically due to low air receiver pressure (2) the unloader valves open causing the compressor to discharge to atmosphere C. (1) not start automatically and requires manual alignment (2) the associated pressure switch opens signaling the compressor to stop D. (1) not start automatically and requires manual alignment (2) the unloader valves open causing the compressor to discharge to atmosphere

51. Given the following:
  • 1-AR-K-D2, Rad Monitor System Hi Rad Level is in alarm
  • 1-AR-K-D4, Rad Monitor Syst Hi-Hi Rad Level is in alarm
  • 1-AP-5, Unit 1 Radiation Monitoring System, is initiated for process radiation monitor 1-SS-RM-124, C SG Blowdown Rad Monitor Which ONE of the choices below states what caused this condition and in accordance with 1-AP-5, what actions are taken to reset the radiation monitor?

A. Radiation Monitor Loss of Power Notify the Instrument Dept to reset the trip relays B. Radiation Monitor Loss of Power Remove then reinstall the Radiation Monitor fuses C. Radiation Detector Failure Notify the Instrument Dept to reset the trip relays D. Radiation Detector Failure Remove then reinstall the Radiation Monitor fuses

52.

Which ONE of the choices below states what Service Water (SW) equipment actuations occur DIRECTLY as a result of a Unit-i Containment Depressurization Actuation (CDA) signal?

1. Unit-i SW to Cont. Air Recirc. Coolers Valves close
2. Unit-2 SW Spray Array Bypass MOVs close
3. A SW Header supply MOVs to the CCHXs close
4. B SW Header supply MOVs to the CCHXs close
5. Unit-i SW to Recirc. Spray HX5 MOVs open
6. Unit-i SW Spray Array MOV5 open A. i;3;5 B. 2; 3; 6 C. i;4;5 D. 2; 4; 6
53. Given the following:
  • Instrument Air compressors are being swapped in accordance with 1(2)-OP-46.1, Operation of 1(2)-IA-C-i, Instrument Air Compressor
  • 1-IA-C-i Instrument Air Compressor is running in HAND
  • Instrument Air header pressure is 110 psig
  • 2-IA-C-i Instrument Air Compressor was just transferred from HAND to AUTO control Which ONE of the choices below describes the Instrument Air system 12 minutes later?

Instrument air pressure will A. be higher and both compressors will be running B. be higher and only one compressor will be running C. remain unchanged and both compressors will be running D. remain unchanged and only one compressor will be running

54. Given the following:
  • Unit 1 is in MODE 3 and cooling down using Aux. Feedwater
  • RCS Tavg is 495° F
  • AFW flow is throttled to 100 gpm to each SG
  • An instrument air line break occurs in the motor driven AFW pump house Which ONE of the choices below completes the following statement?

When all IA in the AFW pump house is depressurized, including the seismic air flasks, AFW flow to the B SG will (1) and AFW flow to the C SG will (2).

A. (1) rise (2) rise B. (1) rise (2) remain the same C. (1) remain the same (2) rise D. (1) remain the same (2) remain the same

55. Given the following:
  • Unit 1 is at 30% power
  • Chilled water is supplying cooling to containment
  • 2-CD-MR-i, Mechanical Chiller, trips due to a short in the motor
  • At time 1600, Containment air temperature is 95°F and rising at 5°F/hour Which ONE of the choices below completes the following statements?

Due to the loss of containment cooling, INDICATED containment partial air pressure will _(1).

and If cooling to containment cannot be restored, the limit of T.S. LCO 3.6.5, Containment Air Temperature, will be reached at time _(2)_. (Assume a constant temperature rise)

A. (1) Rise (2) 1800 B. (1) Rise (2) 2000 C. (1) Lower (2) 1800 D. (1) Lower (2) 2000

56.

Which ONE of the choices below completes the following statement?

Low Temperature Overpressure protection requires pressure relief and limiting coolant input capability to a maximum of _(1) charging pump(s).

and Over the life of the reactor vessel, the effect of neutron exposure accumulation will result in the reactor vessel Reference Temperature Nil Ductility Temperature (RTNDT)

(2).

A. (1)one (2) rising B. (1)one (2) lowering C. (1)two (2) rising D. (1)two (2) lowering

57. Given the following:

Initial Conditions

  • Unit 1 reactor startup is in progress
  • Control bank B demand position is 28 steps
  • All B control bank IRPIs read 28 steps +/- 3 steps Current Conditions
  • An IRPI for B control bank, rod D6, is noted to be slowly lowering on the control board and PCS Which ONE of the choices below completes the following statement?

Alarm A-Fl, CMPTR ALARM ROD DEV/SEQ, will FIRST alarm when the IRPI indication for control rod D6 reaches (1 )_ steps and Alarm A-G2, RPI ROD BOT ROD DROP, (2) alarm when the IRPI indication for rod D6 lowers below 20 steps.

A. (1)17 (2) will not B. (1) 17 (2) will C. (1)3 (2) will not D. (1)3 (2) will

58. Given the following:
  • Unit 1 is operating at 100% power steady state
  • A Core Exit Thermocouple in Quadrant 1, B05, is currently failed and reading 1300°F Which ONE of the choices below completes the following statement?

The minimum required number of operable CETCs is (1)_ per quadrant.

and If an accident occurs, entry into 1-FR-C.1, Response to Inadequate Core Cooling, is based on _(2) reading greater than 1200°F.

A. (1)4 (2) any valid CETC B. (1)4 (2) the average of the 5 highest CETCs C. (1)5 (2) any valid CETC D. (1)5 (2) the average of the 5 highest CETCs

59.

Which ONE of the choices below describes (1) how NAOH solution is added to the Containment Building during a design bases accident and (2) why?

A. (1) Gravity-fed to the suction of the Outside Recirculation Spray pumps.

(2) To aid in the prevention of hydrogen formation.

B. (1) Gravity-fed to the suction of the Outside Recirculation Spray pumps.

(2) To aid in the removal of radioactive iodine.

C. (1) Gravity-fed to the suction of the Quench Spray pumps.

(2) To aid in the prevention of hydrogen formation.

D. (1) Gravity-fed to the suction of the Quench Spray pumps.

(2) To aid in the removal of radioactive iodine.

60. Given the following:
  • Unit 1 is in MODE 5 for a mid cycle outage to repair the C RCP seal
  • Unit 2 is in a refueling outage with fuel offload operations in progress
  • Containment purge supply and exhaust are in service on both units Which ONE of the choices below states the effects of a Unit 2 manipulator crane radiation monitor Hi-Hi alarm on containment purge supply and exhaust?

A. All purge supply and exhaust fans shut down.

The Unit 2 purge supply and exhaust isolation valves shut. The purge supply and exhaust fans will NOT re-start until the radiation monitor alarm is reset.

B. All purge supply and exhaust fans shut down.

The Unit 2 purge supply and exhaust isolation valves shut. The purge supply and exhaust fans will re-start.

C. All purge supply and exhaust fans shut down.

Unit 1 and Unit 2 purge supply and exhaust isolation valves shut.

D. The purge supply and exhaust fans remain running.

Unit 2 purge supply and exhaust isolation valves shut.

61. Given the following:

Initial Conditions Both Units are operating at 100% power

  • Fuel Building Radiation Automatic Interlock Key switch is in ENABLE Current Conditions:
  • A rupture occurs on the Spent Fuel Pool Heat Exchanger
  • Fuel Pool Bridge Radiation Monitor, 1-RM-RMS-153, indication is rising
  • Spent Fuel Pool level is lowering slowly
  • All fuel movement in the Spent Fuel Pool has been stopped Which ONE of the choices below completes the following statement?

1-RM-RMS-153 radiation increase to the HI-HI setpoint will cause automatic actuations to occur _(1)_.

and The Spent Fuel Pool Cooling System is designed to prevent Spent Fuel Pool level from lowering below a minimum of (2) feet above the fuel.

A. (1) immediately (2) 10 B. (1) immediately (2)23 C. (1) after a 2 minute time delay (2) 10 D. (1) after a 2 minute time delay (2)23

62.

Which ONE of the choices below describes the function and purpose of the pictured Fuel Handling tool? (Reference Provided)

A. This tool is used to transfer new fuel assemblies for inspection or movement between shipping containers, new fuel racks or the new fuel elevator.

B. This tool is used to transfer new or spent fuel assemblies within the spent fuel pool for spent fuel pool shuffling or video inspection.

C. This tool is used to transfer spent fuel between the the transfer system upender, the spent fuel storage racks and the new fuel elevator in the full down position.

D. This tool is used to transfer a Rod Control Cluster from one fuel assembly to another fuel assembly in the spent fuel pool.

63. Given the following:
  • Unit 1 is at 20% power
  • The Main Feed Reg Valves (MFRVs) are in AUTO
  • All 3 SG water levels have lowered
  • All 3 MFRV outputs have risen Which ONE of the choices below identifies the cause of these indications?

A. The 4A feedwater heater high level divert valve failed open B. The running main condensate pump suction strainer clogged C. The 3A feedwater heater normal level control valve failed closed D. The selected Turbine First Stage Pressure transmitter failed low

64. Given the following:

Initial Conditions

  • Both Units are in MODE 1
  • A low level liquid waste tank is being discharged into the Clarifier Current Conditions:
  • The following alarms are received:
  • K-D4, Rad Monitor Syst Hi-Hi Rad Level
  • K-D2, Rad Monitor System Hi Rad Level
  • X-G4, Holdup Tank Influent Valve Closed, alarms at the Liquid Waste Panel Which ONE of the choices below identifies:

(1) the radiation monitor that caused I -LW-FCV-1 00, Clarifier Holdup Tank Influent Valve, to close and (2) the expected response from this valve automatically closing?

A. (1) 1-RM-LW-1 10, Clarifier Inlet Radiation Monitor; (2) Steam Generator Low Capacity Blowdown Pump will receive a trip signal B. (1) 1-RM-LW-110, Clarifier Inlet Radiation Monitor; (2) Clarifier Discharge Pump will receive a trip signal C. (1) 1 -RM-LW-1 11, Clarifier Outlet Radiation Monitor; (2) Steam Generator Low Capacity Blowdown Pump will receive a trip signal D. (1) 1 -RM-LW-1 11, Clarifier Outlet Radiation Monitor; (2) Clarifier Discharge Pump will receive a trip signal

65. Given the following:
  • Unit I is at 100% power
  • While taking logs, the reactor operator observes the following instrument air (IA) indications:
  • IA pressure outside containment is 106 psig and slowly cycling +/- 3 psig
  • IA pressure inside containment is 90 psig and cycling +/- 5 psig
  • No operator actions have been taken Which ONE of the choices below completes the following statement?

The failure is _(1)_.

and If instrument air pressure is lost inside containment it (2)_ result in a loss of Reactor Coolant Pump Seal Injection.

A. (1) an Instrument Air line leak inside containment (2) will not B. (1) an Instrument Air line leak inside containment (2) will C. (1) 1-IA-TV-i 02B, containment IA isolation valve, failed closed (2) will not D. (1) 1-IA-TV-i 02B, containment IA isolation valve, failed closed (2) will

66. Given the following:

It is currently 06:30 on July 10

  • A Reactor Operator is the on-coming watchstander and is preparing to assume his duties
  • He has been offsite since July 2 Which ONE of the choices below completes the following statement?

In accordance with OP-AA-1 00, Conduct of Operations, to complete his turnover the on-coming RO is required to review applicable logs and temporary orders since at least A. July 2 B. July 3 C. July 7 D. July 9

67. Given the following:
  • Unit 1 is at 100% power steady state conditions Which ONE of the choices below completes the following statement?

In accordance with the Technical Requirements Manual for Reactor Coolant Chemisty, TR 3.4.1, the Dissolved Oxygen limit is less than or equal to _(1)_ and at current conditions _(2)_ is used to maintain dissolved oxygen within limits.

A. (1) 0.10 ppm (2) Hydrazine B. (1)0.l0ppm (2) Hydrogen C. (1)1.5ppm (2) Hydrazine D. (1)1.5ppm (2) Hydrogen

68. Initial Conditions:
  • Unit 1 and Unit 2 are operating at 100% power steady state
  • 34.5 kV Bus 4 in the switchyard is out of service Current Conditions:
  • Both Units trip coincident with a loss of 34.5 kV bus 5 Which ONE of the choices below describes the Unit 1 and Unit 2 Reactor Coolant Pump (RCP) status?

A. All RCPs are running except Unit 2 A and B B. Only Unit 1 C and Unit 2 C RCPs are running C. All RCPs are running except Unit 1 C and Unit 2 C D. Only Unit 1 A and Unit 2 A RCPs are running

69. Given the following:

Unit 1 is in MODE 1 A SI Accumulator:

  • Water Volume 7590 gallons
  • Boron Concentration 2450 ppm B SI Accumululator:
  • Water Volume 7550 gallons
  • Boron Concentration 2500 ppm C SI Accumulator:
  • Water Volume 7750 gallons
  • Boron Concentration 2775 ppm In accordance with Technical Specification LCO 3.5.1, Accumulators, which ONE of the choices below states SI accumulator parameters that individually would require entry into a 1 HOUR Required Action statement for restoration based on the parameters above? (Disregard entry into LCO 3.0.3)

A. A SI Accumulator boron concentration C SI Accumulator nitrogen pressure B. B SI Accumulator water volume C SI Accumulator nitrogen pressure C. B SI Accumulator water volume C SI Accumulator boron concentration D. A SI Accumulator boron concentration C SI Accumulator boron concentration

70. Given the following:
  • Fuel failure has resulted in elevated radiation in the Auxiliary Building
  • An Operator has been dispatched to an area where radiation levels are 178 mrem/hr at 30 cm.
  • The operator is reviewing the RWP for entry into the area.

Which ONE of the choices below completes the following statement?

The posting for this area will indicate (1).

and In accordance with Technical Specification Chapter 5, Administrative Controls, this area requires the entryway_(2)_.

A. (1) Radiation Area (2) to be barricaded and conspicuously posted B. (1) High Radiation Area (2) to be provided with a locked or continuously guarded door or gate C. (1) High Radiation Area (2) to be barricaded and conspicuously posted D. (1) Radiation Area (2) to be provided with a locked or continuously guarded door or gate

71. Initial Conditions:
  • Unit 1 is in a refueling outage
  • Fuel off-load is in progress Current Conditions:
  • A report is received that a spent fuel assembly being removed from the core was significantly damaged during transit and has been placed in a safe location in containment
  • Large Bubbles were seen escaping from the damaged fuel assembly
  • NO radiation alarms have been received from the radiation monitors associated with the manipulator crane or the refueling area Based on the current conditions, which ONE of the choices below describes the actions required by O-AP-30, Fuel Failure During Handling?

A. Manual Control Room Bottle Air Dump and Isolation are required; Containment evacuation is required B. Manual Control Room Bottle Air Dump and Isolation are required.

Containment evacuation is NOT required C. Manual Control Room Bottle Air Dump and Isolation are NOT required.

Containment evacuation is required D. Manual Control Room Bottle Air Dump and Isolation are NOT required.

Containment evacuation is NOT required

72. Given the following:
  • A radioactive leak has occured in the CVCS system
  • Radiation Protection has determined area conditions are 10 mRem/hour
  • A North Anna operator is assigned to isolate the leak in the area
  • This operator currently has a TEDE of 1.95 Rem for the calender year
  • Leak isolation will require 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of time Which ONE of the choices below completes the following statement?

This operator (1) exceed the Dominion Administrative Dose Limit.

and In accordance with EPIP-4.04, Emergency Personnel Radiation Exposure, the dose limit during an emergency for life-saving activities is (2)_ TEDE.

A. (1) will not (2) 25 Rem B. (1)will not (2) 10 Rem C. (1) will (2) 25 Rem D. (1) will (2) 10 Rem

73. Given the following:
  • An event has occurred on Unit 2
  • RCS Pressure is 400 psig and lowering rapidly
  • Pressurizer Level is offscale low
  • Containment Pressure is 27 psia and rising
  • Containment Radiation is rising rapidly
  • Main Steamline Pressure is 605 psig lowering slowly
  • 2-E-0, Reactor Trip or Safety Injection, has just been entered
  • The STA had previously left the Control Room and is not present Which ONE of the choices below completes the following statement?

In accordance with OP-AP-104, Emergency and Abnormal Operating Procedures, the U-2 SRO will direct the _(l) to monitor the Critical Safety Function Status Trees and Monitoring and implementation of CSF Status Trees is required to be initiated

_(2).

A. (1) Backboards Operator (Step 7 Qualified NLO)

(2) during the performance of 2-E-0 B. (1) Backboards Operator (Step 7 Qualified NLO)

(2) upon transition out of 2-E-0 C. (1) U-i Reactor Operator (RO-B)

(2) during the performance of 2-E-0 D. (1) U-i Reactor Operator (RO-B)

(2) upon transition out of 2-E-0

74. Given the following:

Refueling Water Storage Tank level is currently 80% and a large break loss of coolant accident is in progress. Assume the following pumps are running at the specified flow rates.

  • A and B low head safety injection pumps (2500 gpm each)
  • B and C high head safety injection pumps (200 gpm each)
  • A and B quench spray pumps (1900 gpm each)

Which ONE of the choices below completes the following statement?

Disregarding the volume of the chemical addition tank, automatic swapover to cold leg recirculation will occur in minutes. (Reference Provided)

A.29 B. 34 C.38 D.41

75. Given the following:
  • The crew is at step 4 to Monitor Ruptured SG Level Which ONE of the choices below completes the following statement?

In accordance with 1-E-3, AFW flow is required until ruptured Steam Generator narrow range level is greater than (1) because (2).

A. (1)18%

(2) this ensures the steam generator steam bubble is not in contact with the steam generator U-tubes B. (1)18%

(2) the narrow range instrumentation is required to be on scale to accurately monitor the primary leak rate C. (1)11%

(2) this ensures the steam generator steam bubble is not in contact with the steam generator U-tubes D. (1)11%

(2) the narrow range instrumentation is required to be on scale to accurately monitor the primary leak rate

76. Given the following:
  • Unit 1 was at 100% when a LOCA occurred
  • The operating crew is currently in 1-FR-C.1, Response to Inadequate Core Cooling due to RED path conditions.
  • Core Exit Thermocouples currently read 1205°F and are slowly rising
  • Containment pressure is 18 psia and stable
  • Containment Rad Levels have remained <10 R/hr
  • All SGs are intact with the following narrow range levels:

5% 15% 24%

  • RCP Seal Injection and Component Cooling are unavailable
  • The crew is currently depressurizing the intact SGs to amospheric pressure In accordance with 1-FR-C.1, which ONE of the choices below completes the following?

Based on the conditions above, the C RCP (1) be started.

and If a RCP is started in one loop and RCS temperature remains above 1200°F a second RCP (2) required to be started.

A. (1) can not (2) is not B. (1)can (2) is not C. (1) can not (2) is D. (1)can (2) is

77. Given the following:

Initial Conditions:

  • 1-CH-P-1A is running
  • 1-CH-P-IB is in auto after-stop
  • 1-CH-P-1C (normal) is in standby (after stop)

Current Conditions:

  • 1-CH-P-1A trips on overcurrent Which ONE of the choices below completes the following?

Based on the above conditons, _(1) is(are) expected to automatically start.

and In accordance with LCO 3.5.2, ECCS -Operating bases, based on the above conditions, currently two trains of ECCS (2) OPERABLE.

A. (1)1-CH-P-1B (2) are not B. (1)1-CH-P-1B (2) are C. (1) both 1-CH-P-1B and 1-CH-P-1C (2) are not D. (1) both 1-CH-P-1B and 1-CH-P-C (2) are

78. Given the following:
  • 1-FR-S.1, Response to Nuclear Power Generation/ATWS was entered
  • Upon entry into 1-FR-S.1, Unit 1 B Bearing Cooling Pump tripped
  • Operators are currently performing the immediate actions of 1-FR-Si Which ONE of the choices below answers the following regarding when and how the abnormal operating procedure, 1-AP-19, Loss of Bearing Cooling Water, is used in parallel with 1-FR-S.1?

In accordance with OP-AP-104, Emergency and Abnormal Operating Procedures, during the immediate actions of 1-FR-S.1 parallel procedure usage _(1)_ allowed and In accordance with OP-AP-1 04, if an AP is used in parallel with an EOP then all steps in the AP (2) required to be performed.

A. (1)is (2) are not B. (1)is (2) are C. (1) is not (2) are not D. (1) is not (2) are

79. Given the following:
  • Unit2wasinMODEl
  • RCPs were secured in E-O due to RCP Trip Criteria being met
  • C SG has been identified as Ruptured and was isolated
  • RCS cooldown to target temperature is complete
  • RCS depressurization is complete
  • Normal charging and letdown are in service
  • Pressurizer Level is 52%
  • RVLIS upper range level is 89%
  • RCS Subcooling is 55°F
  • RCP cooling and seal flows are normal
  • Ruptured S/G level is 56% NR and stable In accordance with 2-E-3, Steam Generator Tube Rupture, which ONE of the choices below states the required action and procedure path regarding RCP restart and why?

A. Do NOT start an RCP The required RCP restart conditions for Subcooling are not met. In accordance with 2-E-3, initiate Attachment 2, Natural Circulation Verification.

B. Start 2-RC-P-1A The A RCP is preferred because the rupture is located on the C SG. Use 2-E-3 to start the A RCP, prerequisites and limitations outside of 2-E-3 do not apply.

C. Do NOT start an RCP RVLIS level indicates a steam bubble in the upper head region which may condense during the RCP start. Raise pressurizer level and continue on in 2-E-3.

D. Start 2-RC-P-1 C Normal pressurizer spray is desired. Use 2-OP-5.2, Reactor Coolant Pump Startup and Shutdown, and observe all precautions, prerequisites and limitations.

80. Given the following:
  • Both Units are at 100% power
  • The I H Diesel Generator is tagged out for planned maintenance The following alarms and indications occur:
  • Operators have verified the alarm is valid
  • 500 KV switchyard voltage is 498 KV and stable Based on these plant conditions, which ONE of the choices below identifies ALL of the Unit 1 ONLY applicable conditions of Technical Specification LCO 3.8.1? (Reference Provided)

A. Conditions A, B, D, E, F, and H B. Conditions A, B, C, E, F, and H C. Conditions A, B, C, G, H, and M D. Conditions A, B, D, G, H, and M

81. Given the following:
  • 1-ECA-1.1, Loss of Emergency Coolant Recirculation, is in progress
  • SG pressures are approximately 450 psig
  • The crew is currently depressurizing all intact SGs Which ONE of the choices below completes the following?

In accordance with 1-ECA-1 .1, SC depressurization is required to be stopped when SG pressure first reaches less than _(1) psig and The bases for this action is to _(2).

A. (1) 120 (2) prevent significant nitrogen injection into the RCS B. (1) 120 (2) allow RHR to be placed in service for continued RCS cooldown C. (1) 190 (2) prevent significant nitrogen injection into the RCS D. (1)190 (2) allow RHR to be placed in service for continued RCS cooldown

82. Given the following:
  • Unit 1 is at 100% power
  • Surveillance 1-PT-17.1, Control Rod Operability, is in progress
  • Control Bank D Control Rod B8 failed to move as required during the surveillance and is currently at 225 steps withdrawn
  • All other rods in Control Bank Dare at 218 steps
  • l&C troubleshooting has determined Rod Control is functioning properly electrically In accordance with the Technical Specification Required Actions and the COLR which ONE of the choices below describes the minimum Shutdown Margin value that is required to be verified and the Bases for the LCO requirement that is currently not met?

A. 1.77% Ak/k Ensure that upon reactor trip, the assumed reactivity will be available and will be inserted.

B. 1.00% Ak/k Ensure that the RCCAs and banks maintain the correct power distribution and rod alignment.

C. 1.77% Ak/k Ensure that the RCCAs and banks maintain the correct power distribution and rod alignment.

D. 1.00% Ak/k Ensure that upon reactor trip, the assumed reactivity will be available and will be inserted.

83. Given the following:
  • 1-ES-0.1, Reactor Trip Response, is in progress The crew is establishing emergency boration due to multiple control rods indicating greater than 10 steps Which ONE of the choices below completes the following statement?

Based on current plant conditions, in accordance with TRM 3.1.1, Boration Flow Paths - Operating, the minimum required BAST borated water volume is (1).

and In accordance with the TRM basis for Boration Flow Paths, This expected boration capability requirement occurs at (2) from full power equilibrium xenon conditions.

A. (1) 1378 gallons (2) end of life B. (1) 1378 gallons (2) beginning of life C. (1) 6000 gallons (2) beginning of life D. (1) 6000 gallons (2) end of life

84. Given the following:
  • A Reactor Startup is in progress per i-OP-i .5, Unit Startup from MODE 3 to MODE 2
  • No change in boron concentration or control rod movement is in progress and all nuclear instrumentation readings have been stable for the last five minutes.
  • Operators are preparing to deenergize the source range detectors
  • Nuclear Instruments read as follows:

SR Channel I (N-31) i.OxiO 4 cps SR Channel II (N-32) i.3xiO cps 4

  • IR Channel I (N-35) 1.ix10 8 amps

A. IR Channel I (N-35) indicates higher than expected Place affected channel in trip and initiate action to place the unit in MODE 3 B. IR Channel I (N-35) indicates higher than expected Initiate actions to increase thermal power to greater than P-i 0, Power Range Neutron Flux C. IR Channel II (N-36) indicates lower than expected Place affected channel in trip and initiate action to place the unit in MODE 3 D. IR Channel II (N-36) indicates lower than expected Initiate actions to increase thermal power to greater than P-i 0, Power Range Neutron Flux

85. Given the following:
  • A LOCA with fuel failure occurred
  • Containment pressure peaked at 18 psia and is slowly lowering
  • Containment radiation peaked at 75% on the High Range Recorder and is currently indicating 60%
  • 1 -E-1, Loss of Reactor or Secondary Coolant is in progress
  • The SRO is at the step to CHECK IF SI CAN BE TERMINATED
  • Current Indications
  • RCS subcooling is 48°F
  • SG Narrow Range levels are greater than 30% in all SG5
  • RCS pressure is stable at 390 psig
  • Pressurizer level is 30% and stable Which ONE of the choices below completes the following?

In accordance with 1 -E-1, the use of Adverse Containment Criteria setpoints (1) required.

and In accordance with 1-E-1, the SRO is required to direct the crew to (2).

A. (1)is (2) transition to 1-ES-1.1, SI Termination B. (1) is not (2) transition to 1-ES-1.1, SI Termination C. (1)is (2) continue on in 1-E-1, Loss of Reactor or Secondary Coolant D. (1) is not (2) continue on in 1-E-1, Loss of Reactor or Secondary Coolant

86. Given the following:
  • Unit 1 is at 100% power steady state
  • Letdown divert valve, 1 -CH-LCV-1 11 5A is full open
  • Actual VCT level is 20% and lowering
  • VCT Auto Make-up has NOT occurred Which ONE of the choices below completes the following?

The cause of the conditions above is VCT Level Instrument, (1) failed high.

and An entry into the required actions of (2)_ is required.

A. (1)1-CH-LT-1112 (2) TR 3.3.9, Reg Guide 1.97 Instrumentation B. (1) 1-CH-LT-1112 (2) [CO 3.3.2, ESFAS Instrumentation C. (1)1-CH-LT-1115 (2) TR 3.3.9, Reg Guide 1.97 Instrumentation D. (1) 1-CH-LT-1115 (2) LCO 3.3.2, ESFAS Instrumentation

87. Given the following:

Initial Conditions:

  • Unit 1 is shutdown for a refueling outage
  • RCS cooldown and depressurization have commenced in accordance with 1-OP-3.7, Unit Shutdown From MODE 1 To MODE 5 For Refueling
  • RCS Temperature - 535°F
  • RCS Pressure - 1890 psig
  • All actions for current plant conditions have been completed Multiple failures have just occurred resulting in rapid depressurization of all SGs inside containment Which ONE of the choices below completes the following statements?

An automatic safety injection _(1) occur.

and In accordance with 1-ECA-2.1, Uncontrolled Depressurization Of All Steam Generators, the Aux Feedwater flow to the SGs will be maintained at a minimum of j2)_.

A. (1) will (2)100 GPM to each SG to prevent dry out B. (1) will (2) 340 GPM total to all SGs to maintain heat sink C. (1)will not (2)100 GPM to each SG to prevent dry out D. (1) will not (2) 340 GPM total to all SGs to maintain heat sink

88.

Which ONE of the choices below describes the basis for the Emergency Condensate Storage Tank minimum volume required by T.S. LCO 3.7.6 - Emergency Condensate Storage Tank (ECST)?

A. Remove decay heat for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in MODE 3 followed by a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> cooldown.

B. Remove decay heat for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in MODE 3 followed by a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> cooldown.

C. Remove decay heat and maintain the unit in MODE 3 for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D. Remove decay heat and maintain the unit in MODE 3 for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

89. Given the following:
  • Both Units are at 100% power
  • 1-SW-P-lA trips due to a fault
  • The crew responds as required to start another SW pump and restore SW flow
  • Current SW pump discharge pressure is 50 psig
  • All SW spray valves are open and SW spray bypass valves are closed The SRO is reviewing 0-OP-49.6, SW System Throttling Alignment, to evaluate if T.S.

LCO 3.7.8, Service Water System, is OPERABLE.

Which ONE of the choices below completes the following statement?

In accordance with T.S. LCO 3.7.8, the affected A Service Water System loop

_(1) OPERABLE and the basis for throttling is to (2)

A. (1)isnot (2) ensure adequate flow to the RS heat exchangers following an accident B. (1)isnot (2) prevent SW pump run out following an accident C. (1)is (2) ensure adequate flow to the RS heat exchangers following an accident D. (1)is (2) prevent SW pump run out following an accident

90. Given the following:
  • The unit was operating at 100% power when a Reactor Trip and Safety Injection occurred
  • The crew transitioned from l-E-l, Loss of Reactor or Secondary Coolant, to 1-ES-i .3, Transfer to Containment Sump Recirculation
  • Upon entry into 1-ES-i .3, the STA reports:
  • The only running Quench Spray pump tripped
  • Containment pressure is 29 psia and rising
  • i-F-0, CSF Status Trees, indicates an orange path for Containment Which ONE of the choices below describes the required procedural flowpath?

A. Continue in i-ES-1.3. If a CSF Status Tree red path is reached perform i-FR-Z.1 in parallel.

B. Continue in i-ES-i .3. After completion of Cold Leg Recirc Alignment, transition to i-FR-Z.i.

C. Transition to 1-FR-Z.i. When one Quench Spray pump is restored, return to 1-ES-i .3.

D. Transition to i-FR-Z.i. When containment pressure is less than 28 psia, return to i-ES-i .3.

91. Given the following:
  • Unit 1 is at 25% power following a reactor start up
  • Pressurizer Level transmitter 1-RC-.LT-1461 output has failed In accordance with T.S. LCO 3.3.1, Reactor Trip System Instrumentation, which ONE of the choices below completes the following?

As power is raised during Unit Startup, Pressurizer Water Level - High instrumentation is FIRST required when power is above the Reactor Trip System Interlock (1)_.

and The SRO (2)_ required to direct the failed channel to be placed in trip.

A. (1)P-7 (2) is B. (1)P-7 (2) is not C. (1)P-8 (2) is D. (1) P-8 (2) is not

92. Given the following:
  • Both Units are at 100% Power
  • 1-AR-E-C6, Spent Fuel Pit Lo Level is LIT
  • A Non-licensed Operator in the field reports Spent Fuel Pool (SFP) Level is 7 and lowering
  • 0-AP-27, Malfunction of Spent Fuel Pit System, is entered
  • Spent Fuel Pool level continues to lower
  • Attempts to makeup to the SEP from either Units blender are unsuccessful Which ONE of the choices below completes the following statement?

In accordance with 0-AP-27, make up to the SEP from the Service Water System requires permission from the (1).

and The Tech Spec basis for minimum SEP water level following a fuel handling accident is to (2).

A. (1) Shift Manager (2) reduce gamma exposure B. (1) Shift Manager (2) limit iodine release C. (1) Manager Nuclear Operations (2) limit iodine release D. (1) Manager Nuclear Operations (2) reduce gamma exposure

93. Given the following:
  • Unit 1 Reactor power is 96%, steady state following turbine valve freedom testing
  • All systems are in automatic control
  • Turbine control is in IMP IN
  • The Valve Position Limiter is set at 100%
  • One Main Steam Dump valve, 1-MS-TCV-1408B, fails 100% open due to a valve positioner failure and is unable to be closed.

Which ONE of the choices below completes the following statement?

In response to this failure, Turbine governor valves will (1) and In accordance with 1-AP-38, Excessive Load Increase, the SRO will direct the crew to ramp the turbine as necessary down to a maximum of(2)

A. (1) open (2) 100%

B. (1) open (2) 96%

C. (1) not change position (2) 100%

D. (1) not change position (2) 96%

94. Given the following:
  • Unit 1 is in MODE 6
  • Core Alterations are in progress
  • Several fuel assemblies have severe bowing which requires use of the manipulator crane to operate with a safety interlock in bypass Which ONE of the choices below completes the following statement?

In accordance with OP-AA-100, Conduct of Operations, the controls the bypass key for the refueling interlocks and authorizes its use.

A. Operations Manager B. Supervisor of Operations Support C. Refueling SRO D. Shift Manager

95. Given the following:
  • Unit 1 is at 100% Rated Thermal Power (RTP)
  • The PCS calorimetric program is not functional
  • The Feedwater UFM remains functional Which ONE of the choices below completes the following statements?

In accordance with TR 3.3.10, Feedwater Ultrasonic Flow Meter Calorimetric, and associated basis, the alternate indications specified to verify thermal power are

_(l).

Performance of the next required surveillance hand calorimetric heat balance (2)_.

(Reference Provided)

A. (1) Delta T and Power Range NIs (2) allows continued operation > 2893 MWt B. (1) Delta T and Power Range Nis (2) requires power to be reduced <2893 MWt C. (1) Power Range NIs and Turbine First Stage Pressure (2) allows continued operation > 2893 MWt D. (1) Power Range Nis and Turbine First Stage Pressure (2) requires power to be reduced <2893 MWt

96. Given the following:
  • Upon completion of maintenance, a post maintenance test was performed but acceptance criteria was not met.

Which ONE of the choices below completes the following statement?

In accordance with OP-AA-102, Operability Determination, the is responsible for approving prompt Operability Determinations (ODs).

A. Shift Manager B. Operations Manager C. Engineering Manager D. Plant Manager

97. Given the following:
  • Unit 2 is in MODE 1
  • Unit 1 is in MODE 5 following completion of a refueling outage
  • 1-QS-P-1A, A QS Pump, is out of service for additional maintenance required for an oil leak that was identified last shift
  • A risk evaluation has not been performed
  • Operations is preparing for a MODE change to MODE 4 Which ONE of the choices below completes the following statement?

In accordance with Technical Specification LCO 3.0.4, a MODE change to MODE 4...

A. is allowable now provided that all applicable LCO actions are entered at the time of entry into MODE 4 for inoperable equipment.

B. requires only the Unit 1 A QS Pump be returned to service and declared OPERABLE.

C. requires only the Unit 1 A SI Accumulator be returned to service and declared OPERABLE.

D. requires both the Unit 1 A QS pump and the Unit 1 A SI Accumulator are declared OPERABLE before entry into MODE 4 is allowed.

98. Given the following:
  • 0-OP-23.2, Waste Gas Decay Tank and Waste Gas Diaphragm Compressors, has been initiated in preparation for a waste gas release
  • Operations is reviewing the release permit with HP
  • In accordance with the Precautions and Limitations of 0-OP-23.2, regarding the impending release...

Which ONE of the choices below completes the following statement?

During normal conditions of plant operations, radioactive gases should be provided with a minimum hold up of (1) days except for low radioactive gaseous wastes resulting from purge and fill operations associated with Refueling and Reactor Startup.

Regarding 1-GW-FCV-101, Char Filt In Fm Decay Tks Cont, IF manual control is required, THEN it is to only be done with _(2)_ permission.

A. (1) 30 days (2) SRO B. (1) 30 days (2) Operations Manager C. (1) 60 days (2) SRO D. (1) 60 days (2) Operations Manager

99. Given the following:
  • Unit 1 is stable in MODE 2 following a reactor startup
  • Unit 2-AR-F-H6, UNIT #1 ANN SYS Power Supply Failure, alarms
  • PCS is unavailable Which ONE of the following identifies the required Emergency Action Level (EAL) to be classified for the conditions above, if any? (Reference Provided)

A. EAL classification is not required B. 5U4.1 C. SA4.1 D. SS4.1

100. Given the following:

  • An event has occurred in the station and the emergency plan has been entered
  • The Station Emergency Manager (SEM) has relieved the Shift Manager of SEM duties and has activated the TSC
  • The Recovery Manager (RM) has reported to the LEOF and LEOF activation is in progress
  • Responsibility for State and Local communications has not been transferred to the LEOF
  • Conditions in the plant have degraded to the point of requiring entry into a General Emergency Which ONE of the choices below completes the following statement?

In accordance with EPIP-1 .05 Response To General Emergency, the initial notification to the State of the applicable PAR is required to be made within 15 minutes of _(1).

AND At this time, the _(2)_ is responsible for determining the recommendation for offsite protective actions.

A. (1) declaring the General Emergency (2) Recovery Manager B. (1) General Emergency conditions being met (2) Station Emergency Manager C. (1) General Emergency conditions being met (2) Recovery Manager D. (1) declaring the General Emergency (2) Station Emergency Manager

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