Text

301 SRO Final Exam with Key
	ML14219A748
Person / Time
Site:	Surry
Issue date:	08/07/2014
From:	; NRC/RGN-II/DRS/OLB
To:	; Virginia Electric & Power Co (VEPCO)
References
	50-280/14-301, 50-281/14-301
	Download: ML14219A748 (95)
	v • d • e

Question 1 Current Unit Conditions:

Units 1 and 2 are operating at 100% power.

CVCS is in a NORMAL configuration.

Valve number 1-CH-83, Unit 1 Boric Acid Filter Outlet Valve, is found to be plugged with boron.

The Maintenance Department has estimated a repair time of eight (8) hours to cut out and replace 1-CH-83. Tagout has been hung and verified.

Which ONE of the following is correct concerning:

1) The operability of the Boron inject flowpaths as a result of the tagout.

2) The actions required to exit the applicable LCO.

(Reference Provided)

A. 1) One inoperable.

2) Bypass the Boric Acid Filter.

B. 1) Two inoperable.

2) Bypass the Boric Acid Filter.

C. 1) One inoperable.

2) Ensure two flowpaths are operable within the required time, or place the unit in HSD within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

D. 1) Two inoperable.

2) Ensure two flowpaths are operable within the required time, or place the unit in HSD within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Question 2 Initial Unit 1 Conditions:

A small break LOCA has occurred.

RCS Pressure is 770 psig and stable.

Wide Range T-Cold indication is 446°F and slowly lowering.

Average 5 high CETC temperatures indication is 452°F and slowly lowering.

Containment Pressure is 21.4 psia and slowly rising.

Containment Radiation level by CHRRMS (1-RM-RMS-127/128) indicate 1R/Hr, and are unchanged from time of event initiation.

In accordance with the above conditions, which one of the following states:

1) The status of RCP Trip criteria.

2) The required procedural flow path is E-0 (Reactor Trip or SI), E-1 (Loss of Reactor or Secondary Coolant), and ________.

A. 1) RCP Trip criteria is met.

2) ES-1.1, SI Termination.

B. 1) RCP Trip criteria is NOT met.

2) ES-1.2, Post LOCA Cooldown and Depressurization.

C. 1) RCP Trip criteria is met.

2) ES-1.2, Post LOCA Cooldown and Depressurization.

D. 1) RCP Trip criteria is NOT met.

2) ES-1.1, SI Termination.

Question 3 Unit 1 was operating at 100% power when the following events occur:

Seismic activity 10 miles northwest of Richmond causes multiple Power Station trips, grid instability and loss of offsite power.

Both Units automatically trip, and #3 EDG starts and trips on differential current.

Unit 1 experiences a LBLOCA.

When Containment pressure exceeds 23 psia, Hi-Hi CLS alarms are received. 1-CS-P-1A fails to start due to mechanical damage.

The Team has just reached E-0, Reactor Trip or Safety Injection, Step 11, Check RCS intact inside Containment.

Based on the above conditions:

1) Which ONE of the following states the correct procedural implementation?

2) Classify the event using the Emergency Plan.

(Reference Provided)

A. 1) Immediately Transition to FR-Z.1, Response to Containment High Pressure.

2) Alert FA1.1.

B. 1) Transition to FR-Z.1 on Transition to 1-E-1, Loss of Reactor or Secondary Coolant.

2) SAE FS1.1.

C. 1) Immediately Transition FR-Z.1, Response to Containment High Pressure.

2) SAE FS1.1.

D. 1) Transition to FR-Z.1 on Transition to 1-E-1, Loss of Reactor or Secondary Coolant.

2) Alert FA1.1.

Question 4 Given the following:

Unit 1 is currently at 371 °F and is heating up to HSD following a refueling outage.

Annunciator 1D-B5, ICCM Failure is received.

Team implements ARP 1D-B5.

The following is the current Quadrant II CETC indications for Train A and Train B:

CETCs Train A CETC Train B B10 2300°F, stable A09 40°F, stable C08 40°F, stable C12 40°F, stable E11 40°F, stable D10 368°F, rising slowly F09 370°F, rising slowly F11 783°F, rising 1°/30 seconds F13 40°F, stable G09 815°F, rising 1°F/15 seconds H11 369°F, rising slowly G14 2300°F, Stable Which ONE of the following identifies

1) The number of FAILED CETCs in Train A and Train B. AND

2) The Tech Spec clock in effect.

(Reference Provided)

A. 1) Train A: 4; Train B: 5.

2) 7 day clock.

B. 1) Train A: 3; Train B 2.

2) 7 day clock.

C. 1) Train A: 4; Train B: 5.

2) 30 day clock.

D. 1) Train A: 3; Train B 2.

2) 30 day clock.

Question 5 Unit 1 is operating at 100% when the following alarms and/or indications are noted:

Pressurizer level is 53% and lowering slowly.

Annunciator 1D-E5, CHG PP TO REGEN HX HI-LO FLOW is LIT.

Annunciator 1D-F3, REGEN HX LETDOWN LINE HI TEMP is LIT.

1-RM-RR-131A, Vent Stack #2 RM, is in Alert.

CHG Line Flow, 1-CH-FI-1122, indicates 110 gpm and rising.

REGEN HX CHG Outlet Temp, 1-CH-TI-1123, indicates 458 °F and rising.

Letdown Line Flow, 1-CH-FI-1150, oscillating between 90 and 110 gpm.

Seal Injection flow to A, B, and C RCPs indicate 7.5 gpm and slowly lowering.

Containment Sump Level indicates 23% and stable.

Answer the following questions:

1) Where is the location of the leak in the Chemical and Volume Control System?

2) Make an immediate determination of operability of the High Head Safety Injection system in accordance with OP-AA-102, Operability Determination.

A. 1) Downstream of 1-CH-FCV-1122, Charging flow control valve.

2) Operable.

B. 1) Downstream of 1-CH-HCV-1186, Seal Injection flow control valve.

2) Operable.

C. 1) Downstream of 1-CH-FCV-1122, Charging flow control valve.

2) Inoperable.

D. 1) Downstream 1-CH-HCV-1186, Seal injection flow control valve.

2) Inoperable.

Question 6 Initial Conditions for Unit 1:

Unit 1 at 100% power.

Delta Flux is at -2.4% with a target of -1%.

Spurious Turbine Runback occurs causing Tave to increase rapidly.

Current Conditions:

Reactor Power is 91% and stable.

Delta Flux is at -16%.

Tave is 571.5 oF, Tref is 571.0 oF.

Annunciator 1E-E3, Delta Flux Deviation is lit.

Annunciator 1G-H8, Rod Bank D Extra Lo Limit.

The SRO directs Emergency Boration to be performed per 1-AP-3.00, Emergency Boration. When the RO attempted to open 1-CH-MOV-1350, Emergency Borate MOV; the MOV immediately thermalled.

Based on the current conditions, which ONE of the following states:

1) The next actions to be taken to start Emergency Boration in accordance with 1-AP-3.00.

2) The most restrictive LCO, and basis for this CONDITION?

A. 1) Manually open 1-CH-FCV-1113A, and locally open 1-CH-228.

2) Insertion limits to ensure adequate shutdown margin on reactor trip.

B. 1) Manually align Charging pump suction to the RWST.

2) Insertion limits to ensure adequate shutdown margin on reactor trip.

C. 1) Manually open 1-CH-FCV-1113A, and locally open 1-CH-228.

2) Delta flux to minimize the effects of Xenon redistribution during load-follow maneuvers.

D. 1) Manually align Charging pump suction to the RWST.

2) Delta flux to minimize the effects of Xenon redistribution during load-follow maneuvers.

Question 7 Unit 1 is operating at 100% Power and Normal Operating Pressure.

C and D pressurizer heater banks control switches are in ON; A, B, and E pressurizer heater control switches are in AUTO with the Green breaker open indicating light LIT.

The Master Pressure Controller malfunctions, causing a step change in the setpoint to 2310 psig.

The response of the A, B, and E pressurizer heater to this event is to ____(1)___. During power operation, at least 125 KW of heaters must be supplied electrical power from an emergency bus in order to provide assurance that these heaters will remain energized _____(2)_____.

A. 1) energize

2) to ensure the Reactor Coolant System will not be solid when critical B. 1) energize

2) during a loss of offsite power to maintain natural circulation at HOT SHUTDOWN C. 1) remain deenergized

2) during a loss of offsite power to maintain natural circulation at HOT SHUTDOWN D. 1) remain deenergized

2) to ensure the Reactor Coolant System will not be solid when critical

Question 8 Given the following:

Reactor power is currently stable at 1 x 10-8 amps to take critical data during reactor startup.

The RO notes that N36, Intermediate Range Channel 2 Indication has dropped to 1 x 10-11 amps, and Trip Status Light D2, NIS INT RGE P-6 CH-2, is no longer LIT.

The SRO enters 1-AP-4.00 Nuclear Instrument Malfunction.

Which ONE of the following identifies the actions required in accordance with 1-AP-4.00 to address the following:

1) The CONTROL power fuses for N36 _____(1)_____ (would, would not) have to be removed.

2) Reactor operational limits are to____(2)____.

A. 1) would

2) Restore N36 to Operable within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or return to HSD B. 1) would not

2) Reduce power to < P-6 or raise power above 11% within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. 1) would.

2) Reduce power to < P-6 or raise power above 11% within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months D. 1) would not.

2) Restore N36 to Operable within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or return to HSD

Question 9 Unit 1 was tripped due to the loss of the A MFP at 100% power.

The Team has completed E-0, Reactor Trip or Safety Injection; and ES-0.1, Reactor Trip Response.

The Team has withdrawn the Shutdown Banks IAW 1-OP-RX-005, Rod Control System Withdrawal of the Shutdown Banks.

The Team is preparing to withdraw Control Banks in accordance with 1-OP-RX-006, Withdrawal of the Control Banks to Critical Conditions, when the RO notes that D Bank Group Step Counters Indicate 14 on Group 1, and 0 on Group 2.

The Team has entered 0-AP-1.00, Rod Control Malfunction, for the D Bank Group Step Counter.

Which ONE of the following identifies:

1) The maximum deviation between the Group Step Counters in accordance with Tech Specs.

2) The basis for Rod Position Indication.

A. 1) +/- 2 Steps.

2) Core peaking factors.

B. 1) +/- 12 Steps.

2) Core power distribution and Shutdown Margin.

C. 1) +/- 2 Steps.

2) Core power distribution and Shutdown Margin.

D. 1) +/- 12 Steps.

2) Core peaking factors.

Question 10 Initial Conditions (0700):

Unit 1 is operating at 100% power.

UPS 1A1 Regulating Line Conditioner (RLC) is tagged out for maintenance and is scheduled to be returned to service at 1900.

Current Conditions (0720):

Fault occurs during maintenance on UPS 1A1 inverter resulting in the following indications:

o Annunciator 1K-A7, BATT SYSTEM 1A TROUBLE is lit.

o Annunciator 1K-B8, UPS SYSTEM 1A TROUBLE is lit.

o Annunciator 1K-G7, 480V BUS MCC BKR TRIP is lit.

o Vital Bus I volts indicate 0.0 volts.

o Operator reports that UPS 1A1 Inverter Output breaker has tripped.

Operator reports that Breaker 14H13, MCC 1H1-2 Supply breaker has tripped open and has an overcurrent flag.

Operator reports that Alternate Source Supplying load light is lit on the Static Switch Section for UPS 1A2.

Crew has entered 1-AP-10.01, Loss of Vital Bus I.

Based on the conditions given, answer the following questions.

1) With the conditions given Vital Bus III is powered from the UPS 1A2 ___________?

2) What is the latest time Vital bus I must be re-energized, in order to comply with 1-AP-10.01?

A. 1) Battery Charger.

2) 1320.

B. 1) Battery Charger.

2) 0920.

C. 1) RLC.

2) 1320.

D. 1) RLC.

2) 0920.

Question 11 Unit 1 is currently at 61% power following a ramp down from 100% power so that 1-FW-P-1B, B Main Feed Pump can be secured for maintenance.

Per 1-OP-FW-004, Main Feedwater System Operation; 1-FW-MOV-150B, 1-FW-P-1B Discharge MOV, has just been closed.

Which ONE of the following identifies:

1) The Tech Spec LCO Action required when 1-FW-MOV-150B is closed.

2) The reason for the Tech Spec. clock.

(Reference Provided)

A. 1) Table 3.7-2, Action 22, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to restore.

2) The TD AFW pump will not auto start if 1-FW-P-1A tripped under this condition.

B. 1) Table 3.7-2, Action 24, 48 Hours to restore.

2) The TD AFW pump will not auto start if 1-FW-P-1A tripped under this condition.

C. 1) Table 3.7-2, Action 22, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to restore.

2) The MD AFW pumps will not auto start if 1-FW-P-1A tripped under this condition.

D. 1) Table 3.7-2, Action 24, 48 Hours to restore.

2) The MD AFW pumps will not auto start if 1-FW-P-1A tripped under this condition.

Question 12 Initial Conditions:

Unit 1 was at 100% when a Seismic event occurred.

Security reports a large volume of steam coming from U1 Safeguards louvers.

A Loss of offsite Power has occurred, with a failure of EDG-3 to start.

Crew has been unable to isolate steam flow from the Steam Generators.

Efforts are in progress to close Main Steam Trip Valve/Non-Return isolation valve.

Current Conditions (10 minutes later):

RCS Pressure 1200 psig and lowering.

RCS Tave 510 °F and lowering in all 3 loops.

SG Pressure: S/GA - 480 psig/ lowering, S/GB - 541 psig/ rising, S/GC - 490 psig/ lowering.

AFW Flow: S/GA - 170 gpm, S/GB - 120 gpm, S/GC - 160 gpm.

SG Levels are: S/G A - 44% WR/lowering, S/GB - 38% WR/rising, S/GC - 43%

WR/lowering.

Containment Pressure is 10.5 psia and steady.

Crew is just starting step 2 in ECA 2.1, Uncontrolled Depressurization of all S/Gs; Control FF to minimize RCS cooldown.

Given the above information determine:

1) The correct procedural sequence. AND

2) Feed Flow directions the SRO is required to give.

A. 1) Continue in ECA-2.1, transition to FR-H.1 (Loss of Sec Heat Sink), then back to ECA-2.1.

2) Maintain a minimum of 60 gpm to each S/G.

B. 1) Continue in ECA-2.1, transition to FR-H.1 (Loss of Sec Heat Sink), then back to ECA-2.1.

2) Isolate FW to S/G A and S/G C, maintain minimum of 350 gpm to S/G B.

C. 1) Go to E-2 (Faulted S/G Isolation), then transition to E-1 (Loss of Rx. or Sec. Coolant), and then to ES-1.1 (Si Term.).

2) Maintain a minimum of 60 gpm to each S/G.

D. 1) Go to E-2 (Faulted S/G Isolation), then transition to E-1 (Loss of Rx. or Sec. Coolant), and then to ES-1.1 (Si Term.).

2) Isolate FW to S/G A and S/G C, maintain minimum of 350 gpm to S/G B.

Question 13 Initial Conditions:

Unit 1 and 2 are operating at 100% power.

A Loss of Offsite Power causes an Automatic Reactor Trip on Both Units.

3 EDG fails to start.

Current Conditions:

Intake Canal Level is 25 feet and lowering slowly.

Crew is performing immediate actions of E-0, Reactor Trip and SI.

Which ONE of the following identifies

1) The appropriate procedure flowpath to regain control of Intake Canal level.

2) The minimum intake canal level required per TS 3.14 (Circulating and SW) Bases to provide adequate design flow through RS SW heat exchangers.

A. 1) E-0, 1(2)-AP-10.07, Loss of Unit 1(2) Power, 0-AP-12.01, Loss of Intake Canal Level.

2) 17.2 feet.

B. 1) E-0, 0-AP-12.01, Loss of Intake Canal Level, 1(2)-AP-10.07, Loss of Unit 1(2) Power.

2) 23.5 feet.

C. 1) E-0, 1(2)-AP-10.07, Loss of Unit 1(2) Power. 0-AP-12.01, Loss of Intake Canal Level.

2) 23.5 feet.

D. 1) E-0, 0-AP-12.01, Loss of Intake Canal Level, 1(2)-AP-10.07, Loss of Unit 1(2) Power.

2) 17.2 feet.

Question 14 Initial Conditions (Time 0200):

Unit 1 is at cold Shutdown, with RCS temperature at 195 °F.

RCS is in solid plant pressure control.

The A RHR pump and A RHR Heat Exchanger are in service.

1-RC-P-1C, is running.

Time 0205:

Annunciator 1B-G5, INST AIR DRYER TRBL is received.

Station Instrument Air pressure is 75 psig and lowering rapidly.

TIME 0210:

Local report of both Instrument Air dryer towers blowing down.

RCS temperature is 205 °F and rising.

Which ONE of the following identifies:

1) The impact of the loss of Instrument Air to the RHR system, and the 0-AP-40.00, Non-Recoverable Loss of Instrument Air, actions taken in response.

2) The EAL used to classify this event.

(REFERENCE PROVIDED)

A. 1) 1-RH-HCV-1758, RHR HXS Flow Fails Close; use an air bottle to locally block 1-RH-HCV-1758 Open.

2) NOUE CU3.1.

B. 1) 1-RH-HCV-1758, RHR HXS Flow Fails Close; use an air bottle to locally block 1-RH-HCV-1758 Open.

2) Alert CA3.1.

C. 1) 1-CC-TV-109A/B, RHR H/X Trip Valves Fail Close; use an air bottle to locally block open 1-CC-TV-109A/B.

2) NOUE CU3.1.

D. 1) 1-CC-TV-109A/B, RHR H/X Trip Valves Fail Close; use an air bottle to locally block open 1-CC-TV-109A/B.

2) Alert CA3.1.

Question 15 Initial Conditions:

Unit 1 is at Cold Shutdown.

1-OPT-SI-014, Cold Shutdown Test of SI Check Valves to RCS Cold Legs, is currently in progress.

Previous Leak Rate data has been provided by Engineering.

Current Leak Rate data has just been determined.

SI Check Valve leakage results are as follows:

Mark Number Previous Test Current Results A

1-SI-79 3.50 gpm 4.30 gpm B

1-SI-82 0.5 gpm 0.9 gpm C

1-SI-85 1.25 gpm 3.0 gpm D

1-SI-241 4.8 gpm 5.2 gpm E

1-SI-242 0.9 gpm 0.8 gpm F

1-SI-243 0.5 gpm 2.8 gpm Which one of the following lists ALL the Check Valves that are Inoperable in accordance with Technical Specifications section 3.1.C.5.a, Primary Coolant System Pressure Isolation Valves?

A. 1-SI-241.

B. 1-SI-79, 1-SI-243.

C. 1-SI-79, 1-SI-241, 1-SI-243.

D. 1-SI-79, 1-SI-85, 1-SI-241, 1-SI-243.

Question 16 Unit 1 is operating at 100% power.

Control Rod E-11, Shutdown Bank B, Group 1, has dropped and indicates zero (0) Steps.

Indications and alarms received confirm that E-11 has dropped.

The Team initiates 0-AP-1.00, Rod Control System Malfunction.

The STA completes 0-AP-1.00 Attachment 6, Calculation of Excore Quadrant Power Tilt Ratios, and reports that the Upper channel tilt is 16%, and the Lower channel tilt is 13.5%.

The team commences a ramp to < 68% per AP-23.00, Rapid Load Reduction to comply with Tech Specs.

Which ONE of the following states:

1) The maximum time the crew has to reduce power to < 68%.

2) The basis for the power level requirement.

A. 1) one (1) hour.

2) To maintain the minimum DNBR greater than design limits.

B. 1) one (1) hour.

2) To prevent core power distribution from exceeding design limits.

C. 1) thirty (30) minutes.

2) To maintain the minimum DNBR greater than design limits.

D. 1) thirty (30) minutes.

2) To prevent core power distribution from exceeding design limits.

Question 17 Which ONE of the following examples represents an INVALID waiver of Tag removal verification by Shift Supervision?

A. Tags for 1-SI-MOV-1890A, 1-SI-MOV-1890B (LHSI to Hot Legs) and 1-SI-MOV-1890C (LHSI to Cold Legs) during Team response to a LOCA outside of Containment in accordance with 1-ECA-1.2, LOCA outside Containment.

B. Tags for 1-SI-MOV-1869A and 1-SI-MOV-1869B (HHSI to Hot Legs) when cold leg SI flow cannot be established during a SBLOCA with a loss of subcooling on Unit 1.

C. Tags in an area with a Dose Rate of 1 R/hr.

D. Tags from a Transformer disconnect being worked by substation personnel during Switchyard restoration following a tornado.

Question 18 Unit 1 is in Cold Shutdown and in the process of starting up the plant following a Refueling outage with the following conditions:

The RCS is solid Pressurizer pressure is being maintained 85-125 psig RCS temperature band is 90-98 oF You have just been notified that Post Maintenance Tests (PMTs) 1-IPT-FT-RC-P-403/458, Reactor Coolant System Pressure Functional Test, have not been completed for Pressurizer PORVs; 1-RC-PCV-1455C, and 1-RC-PCV-1456. The PMTs should have been completed 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months earlier.

What is the Operability status of the Pressurizer PORVs?

A. PORV Operability is not required for the present plant conditions given.

B. Declare both PORVs inoperable from the time the PMT should have been completed.

C. Declare both PORVs inoperable from the time of discovery.

D. Delay declaring both PORVs inoperable for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to allow the PMTs to be completed.

Question 19 Initial Conditions:

A WGDT is in service (lined up).

B WGDT release is in progress in accordance with OP-23.2.4, Release of Waste Gas Decay Tank 1B.

Annunciator 0-RMA-C6, Process Vent Part Alert /Hi is received.

The BOP has verified 1-GW-RM-130A, Rad Monitor Process Vent Particulate is valid and is reading greater than the HI alarm setpoint.

Which ONE of the following completes the statement:

1) __________ will automatically isolate to STOP the WGDT release flow path. AND

2) The dose to an individual standing _________________.

A. 1) 1-GW-FCV-101, Process Vnt WGDT Effluent Flow Controller.

2) at the exclusion area boundary will not exceed 0.5 rem TEDE over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period.

B. 1) 1-GW-FCV-160, Ctmt Vac Pump Disch Hdr Isol.

2) in an unrestricted area will not exceed 0.002 rem in any one hour.

C. 1) 1-GW-FCV-160, Ctmt Vac Pump Disch Hdr Isol.

2) at the exclusion area boundary will not exceed 0.5 rem TEDE over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period.

D. 1) 1-GW-FCV-101, Process Vnt WGDT Effluent Flow Controller.

2) in an unrestricted area will not exceed 0.002 rem in any one hour.

Question 20 Unit 2 is currently in a Refueling Shutdown with Reactor Head Lift in progress when the following occurs:

Reactor Head dropped three (3) feet during movement to the head stand in the containment basement.

A Supplemental employee is pinned beneath the Reactor Head lift rigging.

The initial Emergency Medical Technicians (EMTs) have reported that the individual is alive, but contaminated and will require an ambulance.

Additional EMTs have been dispatched in order to rescue the injured person.

No Press Release will be issued.

The general dose rates in the area of the injured person is 1.5 R/hr.

Based on current conditions:

1) What is the maximum allowable dose (TEDE) that can be authorized by the SEM to rescue the individual?

2) What is the maximum time requirement to report this event to the NRC?

(REFERENCE PROVIDED)

A. 1) 10 REM.

2) 8 Hours.

B. 1) 10 REM.

2) 1 Hour.

C. 1) 25 REM.

2) 8 Hours.

D. 1) 25 REM.

2) 1 Hour.

Question 21 Unit 1 and 2 are operating at 100% with all systems and cross-ties OPERABLE.

A Hostile Force has landed at the Low Level Intake Structure.

The Outside Watch has been taken hostage, and the Operations vehicle has been used to breach the protected area fence from the construction side into the plant.

Security Supervisor reports that they are currently engaging the hostile force in the Polishing Building. All personnel should remain clear of the Polishing Building. No other areas are affected at this time.

Explosions were heard from the vicinity of the Polishing Building.

Unit 1 and 2 reactors have been tripped in accordance with 0-AP-36.00, Station Security Land or Water Threat - Operations Response.

Other AP-36.00 actions are underway with no issues.

Which ONE of the following states the classification for this event?

(REFERENCE PROVIDED)

A. HG4.1, General Emergency.

B. HA2.1, Alert.

C. HA4.1, Alert.

D. HS4.1, Site Area Emergency.

Question 22 Unit 1 is operating at 100% power.

Unit 2 has experienced a Loss of Offsite power and a LBLOCA:

EDG 3 failed to start.

Containment Pressure is 44 psia and slowly rising.

Annunciator, 2B-B1, CS PP2A LOCKOUT OR OL TRIP is lit.

All RCPs have secured.

RCS pressure is 50 psig and steady.

Core Exit Thermocouple temperature: 610 oF and slowly rising.

RVLIS 44% and steady.

The Team has just established Cold Leg Recirculation in accordance with 2-ES-1.3, Transfer to Cold Leg Recirculation, (step 5 completed).

Oscillating Pump Amps and Discharge Pressure indication on the following: LHSI pump, 2-SI-P-1A; Inside Recirc Spray pump, 2-RS-P-1A; Outside Recirc Spray Pump, 2-RS-P-2A.

Which ONE of the following identifies the procedure that should be performed for the NEXT step?

A. Continue in ES-1.3, Transfer to Cold Leg Recirculation.

B. Go to FR-C.2, Response to Degraded Cooling.

C. Go to ECA-1.1, Loss of Emergency Coolant Recirculation.

D. Go to FR-Z.1, Response to Containment High Pressure.

Question 23 Unit 2 is stable at approximately 2% reactor Power following a Refueling Shutdown.

Main Steam Lines have been warmed, and the MSTVs are open.

Steam Dumps are in AUTO with 4% demand indicated.

The BOP is performing 2-OPT-FW-003, Turbine Driven Auxiliary Pump 2-FW-P-2, full flow test.

The following indications are noted:

2-FW-P-2 Feed Pressure light goes out.

Annunciator 2H-C8, AFW PP3B Lockout or OL Trip is lit.

AFW Flow: 140 gpm to each Steam Generator (420 gpm total).

S/G A/B/C Pressure: 400 psig and decreasing rapidly.

S/G Level: S/G A - 58% (WR), S/G B - 55% (WR), S/G C - 50% (WR), (All are lowering).

Containment Pressure: 10.5 psia and steady.

Team has just completed step 6 of E-0, Reactor Trip or SI.

Which ONE of the following identifies the required sequence of procedure transitions implemented in response to this event?

A. E-2 Faulted SG Isolation, E-1 Loss of Reactor or Secondary Coolant, ES-1.1 SI Termination.

B. FR-H.1 Response to Loss of Secondary Heat Sink, E-2 Faulted SG Isolation, ECA-2.1 Uncontrolled Depressurization of all SGs.

C. E-2 Faulted SG Isolation, FR-H.1 Response to Loss of Secondary Heat Sink.

D. E-2 Faulted SG Isolation, ECA-2.1 Uncontrolled Depressurization of all SGs.

Question 24 A LBLOCA occurred on Unit 1, followed by fuel failure. A Category 4 Hurricane has caused power lines to drop on numerous roadways, and tornadoes have been seen throughout Surry and James City County.

At 0400: A General Emergency has just been declared on FG1.1.

At 0410: State and Local authorities are notified in accordance with EPIP-2.01, Notification of State and Local Governments.

HP reports the following dose assessment data based on the release in progress:

Projected TEDE dose is 0.8 Rem at 2 miles.

Projected Thyroid CDE dose is 7.0 Rem at 2 miles.

Projected Thyroid CDE dose is 5.2 Rem at the Site Boundary.

The primary downwind sector is "C" with "B" and "D" as buffer sectors.

Which one of the following correctly answers the following questions:

1) What is the correct Protective Action Recommendation?

2) What is the latest time that the PAR must be made to the State?

(REFERENCE PROVIDED)

A. 1) Shelter-in-place: 2 Mile radius and 5 Miles downwind. 2) 0415.

B. 1) Expanded PAR: Derive from EPIP-4.07. 2) 0415.

C. 1) Shelter-in-place: 2 Mile radius and 5 Miles downwind. 2) 0425.

D. 1) Expanded PAR: Derive from EPIP-4.07. 2) 0425.

Question 25 Initial Conditions:

Unit 1 reactor has been tripped from 100% due to a LOCA.

The Team has just transitioned to ES-1.2, POST LOCA Cooldown and Depressurization.

Current Conditions:

Subcooling: 25oF and lowering.

AFW flow: 140 gpm to each S/G.

SG level: S/G A/B 70% WR and steady. S/G C 10% NR and rising.

Annunciator 1-RM-G8, CNDSR AIR EJCTR ALERT/FAILURE has just alarmed.

BOP confirms that 1-SV-RM-111 is at the Alert setpoint and rising.

The Team became concerned about conflicting indications and transitioned to ES-0.0, Rediagnosis.

Which ONE of the following describes the correct procedural flowpath from ES-0.0?

A. Go directly to E-3, Steam Generator Tube Rupture; then to ECA-3.1, SGTR with Loss of Reactor Coolant Subcooled Recovery.

B. Return to ES-1.2, POST LOCA Cooldown and Depressurization until SI signals have been blocked; then go to E-3, SGTR; then ECA-3.1, SGTR with Subcooled Recovery.

C. Return to ES-1.2, POST LOCA Cooldown and Depressurization until SI signals have been blocked; then go to E-3, SGTR; then ES-3.1, Post SGTR Cooldown using Backfill.

D. Go directly to E-3, SGTR; then go to ES-3.1, Post SGTR Cooldown using Backfill.

ES-401 Sample Written Examination Question Worksheet Form ES-401-5 SRO EXAM LIST OF ATTACHMENTS Attachment #

Attachment Description 1

Figure of Boric Acid Filter 2

Tech Spec 3.7 3

Tech Spec Table 3.7-2 4

ECA-2.1, step 2 5

VPAP-2802, section 6.3 Notifications 6

EPIP 1.06, Protective Action Recommendations

ES-401 Sample Written Examination Question Worksheet Form ES-401-5

ES-401 Sample Written Examination Question Worksheet Form ES-401-5 ECA-2.1, step 2

ES-401 Sample Written Examination Question Worksheet Form ES-401-5

ES-401 Sample Written Examination Question Worksheet Form ES-401-5 SRO EXAM LIST OF ATTACHMENTS Attachment #

Attachment Description 1

Figure of Boric Acid Filter 2

Tech Spec 3.7 3

Tech Spec Table 3.7-2 4

ECA-2.1, step 2 5

VPAP-2802, section 6.3 Notifications 6

EPIP 1.06, Protective Action Recommendations

ES-401 Sample Written Examination Question Worksheet Form ES-401-5

ES-401 Sample Written Examination Question Worksheet Form ES-401-5 ECA-2.1, step 2

ES-401 Sample Written Examination Question Worksheet Form ES-401-5

1 of 6 COMMON PURPOSE Give guidance to the Station Emergency Manager or Recovery Manager regarding determination of Protective Action Recommendations.

ENTRY CONDITIONS Any one of the following:

1) Activation by EPIP-1.05, RESPONSE TO GENERAL EMERGENCY.

2) Activation by CPIP-3.1, CERC AND CEOF ACTIVATION.

3) Activation by CPIP-6.0, LEOF RECOVERY MANAGER GUIDANCE.

4) As directed by the Station Emergency Manager or Recovery Manager.

REFERENCE USE SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS (WITH 5 ATTACHMENTS)

REVISION 10 PAGE

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 10 PAGE 2 of 6 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: ATTACHMENT 4, REFERENCE INFORMATION (SPS) and ATTACHMENT 5, SECTOR MAP may be used as applicable for reference purposes.

____ 1 INITIATE PROCEDURE:

By: ______________________________

Date: ____________________________

Time: ____________________________

____ 2 USE ATTACHMENT 1, PROTECTIVE ACTION RECOMMENDATION FLOWCHART SPS, TO DETERMINE INITIAL PAR NOTE: ATTACHMENT 2, AFFECTED SECTOR(S) MAP, is to be used for all PAR developments from this procedure. ATTACHMENT 2, AFFECTED SECTOR(S) MAP is not to be used for PARs developed IAW EPIP-4.07, PROTECTIVE MEASURES.

____ 3 IMPLEMENT ATTACHMENT 2, AFFECTED SECTOR(S) MAP:

a) Record time wind data acquired a)

b) Record average wind direction from, in degrees b)

c) Record average wind speed in mph c)

d) Record affected sectors d)

e) Mark affected sectors on map (use any writing implement available, e.g., pen, pencil, highlighter, etc.)

e)

f)

GO TO Step 6

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 10 PAGE 3 of 6 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED

____ 4 CHECK IF REVISED PAR RECEIVED FROM RAD/RAC:

a) Evaluate PAR results with RAD/RAC b) Approve EPIP-4.07, Attachment 3, Radiological Protective Action Recommendation:

1) Record Remarks (optional)

2) Approve Radiological PAR (sign report)

3) Record date and time report approved

c) GO TO Step 7

GO TO Step 5.

____ 5 UPDATE ATTACHMENT 2, AFFECTED SECTOR(S) MAP:

a) Check if TSC, LEOF or CEOF -

NOT ACTIVATED

a) GO TO Step 10.

b) Record time wind data acquired

c) Record average wind direction from, in degrees

d) Record average wind speed in mph

e) Record affected sectors f)

Mark new area(s) affected on map (use distinguishable markings from previous markings):

Include all downwind sectors from previous PARs for this event AND

All new downwind sectors for the PAR AND

Any downwind sectors through which the wind shift occurred

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 10 PAGE 4 of 6 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED

____ 6 COMPLETE ATTACHMENT 3, REPORT OF PROTECTIVE ACTION RECOMMENDATION:

a) Protective Action Recommendation:

1) Mark appropriate PAR box(s)

2) Record Mile radius and Miles downwind

3) Record Downwind Sectors b) Remarks/Approval Information:

1) Record Remarks (optional)

2) Approve PAR (sign report)

3) Record date and time report approved

____ 7 HAVE EMERGENCY COMMUNICATORS NOTIFY OFF-SITE AUTHORITIES OF PAR:

Virginia Emergency Operations Center (VEOC) notified IAW:

EPIP-1.06, PROTECTIVE ACTION RECOMMENDATIONS OR

EPIP-4.07, PROTECTIVE MEASURES

NRC notified IAW EPIP-2.02, NOTIFICATION OF NRC (notification made from Control Room or TSC, when activated)

NRC notified IAW EPIP-4.33, HEALTH PHYSICS NETWORK COMMUNICATIONS (notifications made from TSC or LEOF/CEOF only after NRC requests HPN be established)

____ 8 CHECK IF CURRENT PROTECTIVE ACTION RECOMMENDATION - INITIAL PAR

IF revised PAR, THEN GO TO Step 10.

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 10 PAGE 5 of 6 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED

____ 9 HAVE RADIOLOGICAL ASSESSMENT DIRECTOR (RAD) IMPLEMENT EPIP-4.07, PROTECTIVE MEASURES [RADIOLOGICAL ASSESSMENT COORDINATOR (RAC) IF IN LEOF/CEOF]

CAUTION: Previously issued Protective Action Recommendations should not be reduced until the threat is fully under control and after consulting with Commonwealth of Virginia emergency response organization.

NOTE: A Shelter-in-Place recommendation may supersede a Radiological Evacuation recommendation based on known impediments.

____10 CHECK THE FOLLOWING:

____11 CHECK EMERGENCY - TERMINATED

RETURN TO Step 10.

IF:

THEN do the following:

Revised PAR provided by RAD/RAC IAW EPIP-4.07, PROTECTIVE MEASURES RETURN TO Step 4

Average wind direction shifts to any new area(s)

(refer to ATTACHMENT 2, AFFECTED SECTOR(S) MAP)

RETURN TO Step 5

PAR in effect - UNCHANGED GO TO Step 11

NUMBER EPIP-1.06 PROCEDURE TITLE PROTECTIVE ACTION RECOMMENDATIONS REVISION 10 PAGE 6 of 6 STEP ACTION/ EXPECTED RESPONSE RESPONSE NOT OBTAINED

____12 TERMINATE EPIP-1.06:

Give completed EPIP-1.06, forms, and other applicable records to TSC Emergency Procedures Coordinator or LEOF Services Coordinator

Completed by:_____________________

Date:___________________________

Time:___________________________

- END -

1 of 1 NO NO NO NO Known impediments make evacuation dangerous Radiological release in progress or has occurred related to the event Shelter-in-Place:

2 Mile radius and 5 Miles downwind Current Dose Assessment results related to the event -

AVAILABLE Evacuate:

2 Mile radius and 5 Miles downwind Evacuate:

2 Mile radius and 5 Miles downwind Dose at or beyond 2 miles either:

5HP

TEDE OR

5HP

Thyroid CDE Dose at or beyond Site Boundary

5HP

Thyroid CDE Dose at or beyond Site Boundary

5HP

TEDE Release related to the event controlled or terminated Evacuate:

2 Mile radius and 5 Miles downwind Expanded PAR:

Derive from EPIP-4.07, PROTECTIVE MEASURES Evacuate:

2 Mile radius and 5 Miles downwind and recommend implementation of Potassium Iodide (KI) strategies for the general public. The projected dose at the VLWHERXQGDU\\LV

Rem Thyroid CDE.

Evacuate:

2 Mile radius and 5 Miles downwind Shelter-in-Place:

2 Mile radius and 5 Miles downwind Start NO NO NO YES YES YES YES YES YES YES Graphics No: NB214 NUMBER EPIP-1.06 ATTACHMENT TITLE PROTECTIVE ACTION RECOMMENDATION FLOWCHART SPS ATTACHMENT 1

REVISION 10 PAGE NOTE:

The radiological release related statements below do NOT apply if a radiological release is occurring due to routine, normal plant operations and NOT related to the event.

1 of 1 NUMBER EPIP-1.06 ATTACHMENT TITLE AFFECTED SECTOR(S) MAP ATTACHMENT 2

REVISION 10 PAGE NOTE: Rounding shall be used when determining affected sectors using wind direction.

For example: Wind Direction (degrees from) 11.5 to 11.9 would be rounded up to 12.0.

Wind Direction (degrees from) 11.1 to 11.4 would be rounded down to 11.0.

Average Wind Direction and Average Wind Speed Data:

At ____________, Wind Direction From ___________, Wind Speed ____________, Sectors _______________

(24-hr time) (degrees) (in mph)

At ____________, Wind Direction From ___________, Wind Speed ____________, Sectors _______________

(24-hr time) (degrees) (in mph)

At ____________, Wind Direction From ___________, Wind Speed ____________, Sectors _______________

(24-hr time) (degrees) (in mph)

At ____________, Wind Direction From ___________, Wind Speed ____________, Sectors _______________

(24-hr time) (degrees) (in mph)

AVERAGE WIND DIRECTION (Degrees) From AFFECTED SECTORS 349 - 11 H, J, K 12 - 33 J, K, L 34 - 56 K, L, M 57 - 78 L, M, N 79 - 101 M, N, P 102 - 123 N, P, Q 124 - 146 P, Q, R 147 - 168 Q, R, A 169 - 191 R, A, B 192 - 213 A, B, C 214 - 236 B, C, D 237 - 258 C, D, E 259 - 281 D, E, F 282 - 303 E, F, G 304 - 326 F, G, H 327 - 348 G, H, J A

B C

D E

F G

H J

K L

M N

P Q

78.75° 258.75° 33.75° 213.75° 236.25° 146.25° 303.75° R

10 5

2 281.25° 168.75° 123.75° 101.25° 56.25° 348.75° 11.25° 326.25° 191.25° Graphics No. SB1217E

1 of 1 NUMBER EPIP-1.06 ATTACHMENT TITLE REPORT OF PROTECTIVE ACTION RECOMMENDATION ATTACHMENT 3

REVISION 10 PAGE PAR MESSAGE # ________

NOTE:

Transmit to Virginia EOC only using the VEOC ARD.

IF VEOC ARD nonfunctional, THEN use VEOC autodial or direct dial (804) 674-2400 or (804) 310-8868.

IF all means of communications with VEOC nonfunctional, THEN use Insta-Phone.

This is Surry Power Station with a(n) Drill Message Emergency Message for Protective Action Recommendation. Use the Report of Protective Action Recommendation form to copy this message.

(READ SLOWLY)

PROTECTIVE ACTION RECOMMENDATION:

SHELTER-IN-PLACE: ____ Mile radius 360° and ____ Miles downwind in the following sectors:

EVACUATE: ____ Mile radius 360° and ____ Miles downwind in the following sectors:

BEYOND 10 MILE EPZ:

Evacuate Area: _____ Centerline in degrees; _____Distance in Miles; _____ Width in feet Shelter-in-place: ____ Centerline in degrees; _____Distance in Miles; _____ Width in feet POTASSIUM IODIDE:

Recommend implementation of Potassium Iodide (KI) strategies for the general public.

The projected dose at the site boundary is > 5 Rem Thyroid CDE.

The time is ______________ (24-hr time).

This is ________________________________________________________ / Emergency Communicator.

Message received by: Virginia EOC Watch Officer (name) ______________________________________.

This is Surry Power Station out at __________________ (24-hr time) on _____________________ (date).

REMARKS (OPTIONAL) / APPROVAL INFORMATION [DO NOT READ]

NOTE: Shelter-in-Place may be recommended as a result of controlled releases, evacuation impediments or other known conditions which make evacuation dangerous.

REMARKS: ________________________________________________________________________________

APPROVED BY: ___________________________________________ ______________ / _________

Station Emergency Manager or Recovery Manager Date Time

1 of 1 NUMBER EPIP-1.06 ATTACHMENT TITLE REFERENCE INFORMATION (SPS)

ATTACHMENT 4

REVISION 10 PAGE KNOWN EVACUATION IMPEDIMENTS:

Refers to already known conditions, for example:

Severe weather such as hurricanes, tornados, flooding, or blizzards.

Traffic issues such as inadequate roads, major accident(s).

An attack on an off-site infrastructure such as water, power lines, transportation, communication systems, and public institutions including schools, post offices and prisons.

It is not expected that Protective Action Recommendation (PAR) development be delayed by attempting to obtain information from outside resources.

PAR NOTIFICATION TIMES:

The initial PAR must be included with the initial notification of a General Emergency, which must be made to the State within 15 minutes following declaration of the General Emergency.

Notification of a revised PAR must be made to the State within 15 minutes of its development.

SECTORS/

WIND DIRECTION:

Downwind sectors may be determined from Attachment 4, Downwind Sector Table.

Wind direction is always given in degrees from.

SHELTERING IN PLACE:

There is no dose threshold for recommending sheltering-in-place.

Sheltering-in-place may be recommended as a result of controlled releases, evacuation impediments or other known conditions which make evacuation dangerous.

A controlled release is a short-term release, which is a controlled evolution and the release duration can be accurately determined (such as containment venting).

PREVIOUSLY ISSUED PAR:

Previously issued Protective Action Recommendations should not be reduced until the threat is fully under control and after consulting with Commonwealth of Virginia emergency response organization.

1 of 1 NUMBER EPIP-1.06 ATTACHMENT TITLE SECTOR MAP ATTACHMENT 5

REVISION 10 PAGE Williamsburg Newport News James City County Isle of Wight County York County A

B C

D E

F G

H J

K L

M N

P Q

78.75° 258.75° Surry 33.75° 213.75° 236.25° 146.25° 303.75° R

10 5

2 James River James River 626 10 638 10 634 682 616 653 10 10 650 617 617 627 621 626 627 621 621 673 677 678 10 10 10 618 626 626 626 620 31 640 618 610 610 659 31 637 637 636 665 634 634 633 783 634 617 626 631 616 626 622 644 31 31 650 650 628 627 676 702 686 675 703 281.25° 168.75° Colonial Parkway Colonial Parkway Old Williamsburg Road 123.75° 60 173 143 60 64 64 64 105 64 60 143 143 60 238 637 238 Ft. Eustis 101.25° Madison Washington Lee Taylor Back River Harrison Mulberrry Island Rd.

64 60 143 199 641 60 199 132 143 132 31 199 31 632 31 31 615 614 5

5 615 199 615 617 Jamestown 56.25° 64 143 348.75° 60 132 615 614 613 5

613 199 11.25° Main Road 326.25° 191.25° Graphics No. SB1217D

NRC VALIDATION ANSWER SHEET NRC Validation Page 1 Question #

Answer SRO 1

C 2

C 3

B 4

C 5

A 6

C 7

B 8

B 9

C 10 D

11 D

12 D

13 A

14 C

15 C

16 D

17 D

18 C

19 A

20 C

21 D

22 C

23 D

24 A

25 A

ML14219A748

Text

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