Text

281/2017-301 Final SRO Written Exam - Delay Release 2 Yrs
	ML17354B295
Person / Time
Site:	Surry
Issue date:	12/20/2017
From:	; NRC/RGN-II
To:	;
References
	50-280/OL-17-01, 50-281/OL-17-01
	Download: ML17354B295 (39)
	v • d • e

SURRY 2017 NRC EXAM - SRO

Question: 76

Initial Conditions:

Unit 1 and Unit 2 were operating at 100%.

Loss of offsite power to the station.

# 2 EDG started and loaded.

#1 and #3 EDGs tripped on overspeed and both have extensive crankcase damage.

Crew enters 1-ECA-0.0, Loss of All AC.

Current Conditions (5 minutes later):

Unit 1 RCS pressure is 1600 psig and lowering slowly.

Unit 1 Containment Pressure is 10.4 psia and steady.

Annunciator JB-F3, SFGDS AREA SUMP HI LVL is LIT.

Annunciator 0-RMA-D6, VENT STACK #2 PART ALERT/HI is LIT.

Per ECA-0.0 which ONE of the following describes:

1) What procedural guidance will the crew use to restore power to 1 J bus?

2) Following power restoration to 1J bus and subsequent ECA-0.0 steps, which procedure will

ECA-0.0 direct entry to?

A. 1) 1-ECA-0.0, Loss of ALL AC Power, step 5.

2) ECA-0.2, Loss of All AC Power Recovery with SI Required.

B. 1) 1-ECA-0.0, Loss of ALL AC Power, step 5.

2) ECA-1 .2, LOCA Outside Containment.

C. 1) 0-AP-17.06, AAC Diesel Generator Emergency Operations.

2) ECA-0.2, Loss of All AC Power Recovery with SI Required.

D. 1) 0-AP-17.06, AAC Diesel Generator Emergency Operations.

2) ECA-1 .2, LOCA Outside Containment.

Page 76 of 100

SURRY 2017 NRC EXAM SRO -

Question: 77

Given the following:

Unit 1 and Unit 2 are at 100% power:

Component Cooling pumps, 1-CC-P-i B, and i-CC-P-iD are running with normal CC lineup.

The following annunciators alarm at the same time:

o 1K-H4, 4KV EMERGBUS STUB BUS TIE BKR TRIP.

o 1K-E7, CC PPS DISCH HDR LO PRESS.

The BOP reports that the 1] Stub bus tie breaker has tripped open.

Which ONE of the following completes the following statement:

To comply with Technical Specifications, power must be restored to the affected RHR pump within

a maximum time of _(i)_ days. The basis of the RHR system is to (2)

A. 1) 14

2) provide cooling water (heat sink) for the removal of

residual and sensible heat from the Reactor Coolant

system

B. 1) 7

2) bring the RCS from conditions of 350°F and pressures

between 400 and 450 psig to cold shutdown conditions

C. i) 7

2) provide cooling water (heat sink) for the removal of

residual and sensible heat from the Reactor Coolant

system

D. 1) i4

2) bring the RCS from conditions of 350°F and pressures

between 400 and 450 psig to cold shutdown conditions

Page 77 of 100

SURRY 2017 NRC EXAM SRO -

Question: 78

Initial Conditions:

Unit 1 is in Refueling Shutdown with the B RHR HX and B RHR pump in service.

Component Cooling pumps 1-CC-P-iA and 1-CC-P-lB are running.

The following Annunciators are LIT:

o 0-VSP-D7, CC SURGE TK Hl-LO-LVL

o 1K-E7, CC PPS DISCH HDR LO PRESS

Fl-i-i OOB, CC Supply Hdr Flow HDR B, has risen.

Fl-i-li OB, RHR HX B CC Outlet Hdr B Flow, is stable.

i-DG-P-iA, Primary Drain Xfer Pump, is in Hand and running continuously.

CC Surge Tank level is lowering.

Refueling Cavity level is 26 feet and stable.

Current Conditions:

In accordance with ARP 1 K-E7, the following actions are complete:

o All CC pumps are in PTL

o Charging and Letdown have been secured.

o CC Surge Tank level continues to lower.

o Local actions have been directed to establish makeup to the CC System and isolate the

leak.

Which ONE of the following describes:

1) The component that must be isolated to stop the leak.

2) The procedure used to control RCS Temperature.

A. 1) B RHR pump seal cooler.

2) i-AP-27.00, Loss of Decay Heat Removal Capability.

B. 1) Primary Drain Transfer Tank Vent Chiller Condenser.

2) i-AP-15.00, Loss of Component Cooling.

C. 1) Primary Drain Transfer Tank Vent Chiller Condenser.

2) i-AP-27.00, Loss of Decay Heat Removal Capability.

D. 1) B RHR pump seal cooler.

2) i-AP-15.00, Loss of Component Cooling.

Page 78 of 100

SURRY 2017 NRC EXAM - SRO

Question: 79

Unit 1 and Unit 2 were operating at 100% when the following occurred:

0700: A spurious SI caused Unit 1 Reactor Trip and SI.

0702: A tornado touched down in the switchyard causing a loss of offsite power to both Units.

0703: Annunciator 2K-H2, BUS 2H UNDERVOLT alarmed, and an NLO was sent to investigate.

0709: NLO reports:

EDG 2 supply breaker 25-H3 has a lockout indicated.

2H switchgear has heavy smoke coming from it, and appears to be damaged.

No fire is present.

0710: Crew has transferred EDG 3 to supply 2J bus.

0717: Control Ops personnel in the switchyard reports the following:

Extensive damage to Transformers #1, #2, and 34.5 KV switchyard.

Time to restore offsite power is unknown at this time.

Which ONE of the following answers the questions below?

1) What is the highest EAL the Shift Manager will declare?

2) After bus 1H is reenergized, when will AFW pump 1-FW-P-3A auto-start?

(REFERENCE PROVIDED)

A. 1) Alert. 2)140 seconds.

B. 1) Alert. 2)10 seconds.

C. 1)UnusualEvent. 2)loseconds.

D. 1) Unusual Event. 2)140 seconds.

Page 79 of 100

SURRY 2017 NRC EXAM - SRO

Question: 80

Initial Conditions:

Unit 2 operating at 70% power.

A non-isolable rupture occurs on Unit 2 Instrument Air header.

The reactor automatically trips.

The Crew transitions to 2-ES-0.1, Reactor Trip Response.

A Loss of Oft-Site power occurs on swapover to the RSSTs.

Current Conditions: (2 minutes later)

The Crew has taken no action since entry into 2-ES-0.1.

Which ONE of the following states the FIRST Function Restoration Procedure whose entry conditions

will be met?

A. 2-FR-C.3, Response to Saturated Core Cooling.

B. 2-FR-H.4, Response to Steam Generator High Pressure.

C. 2-FR-l.1, Response to Pressurizer High Level.

D. 2-FR-H.5, Response to Steam Generator Low Level.

Page 80 of 100

SURRY 2017 NRC EXAM SRO -

Question: 81

The Crew has completed actions of ECA-1 .2, LOCA Outside Containment.

Pressurizer level is 35% and lowering.

Steam Generator Narrow Range levels are 30% and rising.

Subcooling is 35 °F and slowly lowering.

RCS pressure is 1400 psig and lowering.

Which ONE of the following procedures will be perlormed next?

A. ES-i.i, SI Termination.

B. ES-i .2, Post LOCA Cooldown and Depressurization.

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

D. E-i, Loss of Reactor or Secondary Coolant.

Page 81 of 100

SURRY 2017 NRC EXAM - SRO

Question: 82

Given the following indications:

CBC

B ems

120 - 120

110 110

100 100

F F

U 90 U 90

L 80 L 80

L L

70 70

0 60

w 60 w

E 50 F 50

R R

40 40

P P

R 30 R 30

1 20 #4 20

10 10

0

I

PWRRNGAVG FLUX My Rod Rods Rod4o-

NI-I-Ale Nl-1-428 NI-l-43B Nt-l-44B On Bottom On Bottom Rod

CHI CHII CHIlI CHIl/ De

Which ONE ot the following describes:

1) The status of control rod D4.

2) LCO requirements.

A. 1) Dropped.

2) Reduce Hi Flux Trip setpoint 85% in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

B. 1) Dropped

2) Verify position using in-core detectors once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

C. 1) CERPI Failed.

2) Verify position using in-core detectors once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

D. 1) CERPI Failed.

2) Reduce Hi Flux Trip setpoint 85% in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Page 82 of 100

SURRY 2017 NRC EXAM - SRO

Question: 83

Initial Conditions:

Unit 1 is operating at 100%.

PRZR LVL-CH SEL switch positioned to CH3!CH2.

PRZR Level channels all reading 53% and stable.

CHG LINE FLOW 1-CH-Fl-1 122A reads 85 gpm and stable.

CHG FLOW CNTRL 1-CH-FC-1122C indicates as shown.

Current Conditions:

The following annunciators alarm at the same time:

o 1C-C6, PRZR HTRS CONT GRP CAB LO AIR FLOW.

o 1C-E8, PRZR LO LVL HTRS OFF & LETDOWN ISOL.

o 1 E-G6, PRZR LO LVL CH 2.

1-RC-LI-1 460, PRZR LEVEL CH 2 indicates pegged low.

All Pressurizer Heaters have deenergized. CHG FLOW CNTRL

1.CH.FCV.1122

Pressurizer pressure is 2220 psig and slowly lowering. - tEYIC-59G

With no operator actions, which ONE of the following completes the following statements?

1) Over the next several minutes the Demand signal of CHG FLOW CNTRL, 1 -CH-FC-1 1 22C will

_(1)_ from its initial value.

2) Per Tech Specs: If Pressurizer pressure exceeds its DNB limit, then pressure must be restored

within a maximum time of _f2)_ hour(s) or power must be reduced to less than 5%.

A. 1) rise 2) 2

B. 1) rise 2) 1

C. 1) lower 2) 2

D. 1) lower 2) 1

Page 83 of 100

SURRY 2017 NRC EXAM SRO -

Question: 84

Given the following:

Both Units are at 100% power.

A fire in the Main Control Room (MCR) results in heavy smoke in the MCR.

MCR ventilation is secured, and the heavy smoke is limited to the MCR.

The Crew enters 0-AP-48.00, Fire Protection Operations Response.

If Main Control Room Evacuation becomes necessary which ONE of the following describes:

1) _(1)_ will be used to direct actions for MCR Evacuation.

2) The EAL classification is (2).

(REFERENCE PROVIDED)

A. 1) 0-FCA-1 .00, Limiting MCR Fire

2) Unusual Event

B. 1) LFFG1 Operations Response

2) Alert

C. 1) LFFGI Operations Response

2) Unusual Event

D. 1) 0-FCA-1.00, Limiting MCR Fire

2) Alert

Page 84 of 100

SURRY 2017 NRC EXAM - SRO

Question: 85

Initial Conditions:

Unit 1 has experienced a Loss of All AC Power.

1-ECA-0.1, Loss Of All AC Power Recovery Without SI Required, is complete.

Current Conditions:

Tave is 547°F.

Annunciator 1 D-B5, ICCM SYSTEM FAILURE, is LIT due to failed power supplies on Channels

A and B.

All Reactor Coolant Pumps are unavailable due to a prolonged loss of seal cooling.

The Shift Manager has directed a cooldown to less than 200°F within 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months due to

impending severe weather conditions.

Which of the following states the required procedural transition for Unit 1?

A. Go to 1-ES-0.2, Natural Circulation Cooldown. Initiate RCS cooldown, then transition to

1-ES-0.4, Natural Circulation Cooldown with Steam Void in Rx Vessel (W/O) RVLIS.

B. Go to 1-ES-0.4, Natural Circulation Cooldown with Steam Void in Rx Vessel (W/O

RVLIS).

C. Go to 1-ES-0.2, Natural Circulation Cooldown. Initiate RCS cooldown, then transition to

1-ES-0.3, Natural Circulation Cooldown with Steam Void in RxVessel

D. Go to 1-ES-0.3, Natural Circulation Cooldown with Steam Void in Rx Vessel.

Page 85 of 100

SURRY 2017 NRC EXAM - SRO

Question: 86

Given the following:

0800: Unit 1 is operating at 100%.

0805: VCT pressure is 15 psig and lowering rapidly due to an un-isolable leak.

0807: RCP Seal Injection flow is 2.5 gpm/RCP and fluctuating.

0807: The following Annunciators are LIT:

o iD-El, VCT HI-LO PRESS.

o iD-Hi, VCT LO-LO LVL.

o 1C-D3, E3, F3 RCP 1A (B,C) SHAFT SEAL WTR LO IN] FLOW.

0810: All Charging pump Red Bkr lights are lit, and all Charging pumps are fluctuating between

20 60 amps.

-

0845: The Crew trips the reactor to comply with Technical Specifications.

Which of the following completes the statements below?

1) Immediately after E-0 immediate actions are complete, 1-AP-9.00, RCP ABNORMAL

CONDITIONS, (1) require the RCPs to be secured.

2) In accordance with VPAP-2802 the NRC should be notified no later than (2) of the same

day.

(REFERENCE PROVIDED)

A. 1)does 2)1610

B. 1)doesnot 2)1610

C. i)does 2)1245

D. 1)does not 2)1245

Page 86 of 100

SURRY 2017 NRC EXAM SRO -

Question: 87

Given the following:

The reactor is operating at 100% power.

A SG Faults inside Containment.

Containment pressure rapidly rises to a peak of 40 psia.

All attempts of the Crew to trip the reactor from the MCR FAIL.

Which ONE of the following states:

1) The criteria that must be met that will allow exit from FR-S.1, Response to Nuclear

Generation/ATWS?

2) EAL Classification.

REFERENCE PROVIDED

A. 1) Gamma-Metric Wide Range <5% AND lowering.

2) Alert, SA2.1.

B. 1)PR Nls<5%ANDIRSUR-0.5DPM.

2) Alert SA2.1.

C. 1) Gamma-Metric Wide Range <5% AND lowering.

2) SAE, SS2.1.

D. 1) PR NIs <5% AND IR SUR -0.5 DPM.

2) SAE, SS2.1.

Page 87 of 100

SURRY 2017 NRC EXAM - SRO

Question: 88

Initial Conditions:

Unit 1 is operating at 10% power with a startup on hold.

1-SV-Rl-111, Condenser Air Ejector RM, Alert and High alarms received.

The RO notes RCS pressure and PRZR level dropping rapidly, trips the reactor and initiates SI.

Current Conditions:

RWST level 95%, and lowering.

RCS Pressure 1460 psig, and lowering.

RCS Subcooling 119°F, and lowering.

Parameter SIG A SIG B SIG C

NR Level (%) 0 stable 37 rising 36 rising

WR Level (3/4) 48 lowering 68 rising 67 rising

Pressure (psig) 445 lowering 985 lowering 985 lowering

AFW Flow (gpm) 205 stable 193 stable 194 stable

Which ONE of the following states the procedure used to bring the Unit to CSD?

A. ECA-3.1, SGTR with Loss of Reactor Coolant Subcooled Recovery.

B. ECA-3.2, SGTR with Loss of Reactor Coolant Saturated Recovery.

C. ES-3.1, Post SGTR Cooldown Using Backfill.

-

D. ES-3.2, Post SGTR Cooldown Using Blowdown.

-

Page 88 of 100

SURRY 2017 NRC EXAM - SRO

Question: 89

Initial Conditions:

Unit 1 operating at 100% power.

Unit 2 is in CSD with RCS temperature 186°F, making preparations for refueling.

The Main Steam tag-out has been hung and verified.

Flooding is reported in Unit 1 Turbine Basement, Southeast corner.

The Crew Enters 0-AP-13.00, Turbine Building or MER 3 Flooding.

Current Conditions:

The Crew has closed the CC HX SW Supply MOVs, 1-SW-MOV-102A and 1-SW-MO V-i 02B.

A report is received that flooding has stopped.

Mechanical Maintenance estimates 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to repair.

Unit 2 RCS temperature 192°F and rising at 40°F/hr.

Which ONE of the following describes the EAL classification for this event?

REFERENCE PROVIDED

A. Alert,CA3.1.

B. NOUE, CU 3.1.

C. Alert,HA1.4.

D. NOUE, HU 1.4.

Page 89 of 100

SURRY 2017 NRC EXAM - SRO

Question: 90

Given the following:

Unit 1 has completed a refueling outage and has commenced startup.

The crew is ready to start 1-GOP-i .2, Unit Startup, RCS Heatup from 195°F to 345°F.

RCS temperature is being maintained 190°F to 195°F.

RCS pressure is being maintained 300 psig to 350 psig.

Which one of the following describes:

1) How Containment Vacuum is initially established?

2) Why Containment Vacuum is required to be established prior to exceeding 350 °F!450 psig?

A. 1) Containment Vacuum pumps.

2) Above this temperature and pressure, containment integrity is required to

ensure that any release from containment will be restricted to those leakage

paths and leak rates assumed in the accident analysis.

B. 1) Containment Vacuum pumps.

2) Below this point there is no significant amount of flashing steam and

therefore there would be no significant pressure buildup in containment if

there is a LOCA.

C. 1) Containment Hogger.

2) Above this temperature and pressure, containment integrity is required to

ensure that any release from containment will be restricted to those leakage

paths and leak rates assumed in the accident analysis.

D. 1) Containment Hogger.

2) Below this point there is no significant amount of flashing steam and

therefore there would be no significant pressure buildup in containment if

there is a LOCA.

Page 90 of 100

SURRY 2017 NRC EXAM - SRO

Question: 91

Initial Conditions:

Unit 1 just lowered to 70% reactor power due to control rod H14, Control Bank D, Group 1,

dropping to 181 steps.

At the end of the down power, D control bank rods are at 168 steps; control rod H14 is at 122

steps.

Current Conditions (14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months later):

Reactor power and D bank control rod positions have been maintained constant.

Control rod H14 has been repaired.

Control rod recovery begins at time 0500.

Which ONE of the following identifies:

1) The time control rod H14 will be considered OPERABLE.

2) The Basis for the speed of rod recovery is to prevent exceeding in the affected fuel

assembly.

A. 1) 2200.

2) FH, Enthalpy Rise Hot Channel Factor

B. 1) 1600.

2) EQ (Z), Heat Flux Hot Channel Factor

C. 1) 2200.

2) EQ (Z), Heat Flux Hot Channel Factor

D. 1) 1600.

2) FH Enthalpy Rise Hot Channel Factor

Page 91 of 100

SURRY 2017 NRC EXAM - SRO

Question: 92

Concerning the Discharge Tunnel Radiation Monitor, 1-SW-RM-120.

Which ONE of the following describes the guidance for:

1) The frequency of requited surveillance testing.

2) Alternative means of monitoring following Radiation Monitor failure.

A. 1) Off Site Dose Calculation Manual (ODCM).

2) Tech Spec Table 3.7-5, Automatic Functions Operated from Radiation Monitor Alarm.

B. 1) Off Site Dose Calculation Manual (ODCM).

2) Off Site Dose Calculation Manual (ODCM).

C. 1) Tech Spec 4.18, MCR Emergency Ventilation System Testing

2) Tech Spec Table 3.7-5, Automatic Functions Operated from Radiation Monitor Alarm.

D. 1) Tech Spec 4.18, MCR Emergency Ventilation System Testing

2) Off Site Dose Calculation Manual (ODCM).

Page 92 of 100

SURRY 2017 NRC EXAM - SRO

Question: 93

Given the following:

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 lB.

Annunciator 0-RMA-C5, Process Vent Rad Mon Trbl is received.

The BOP reports that the 1-GW-Rl-130A, Process Vent Particulate Indicator, green Operate

light is NOT LIT.

Which ONE of the following completes the statements:

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

2) The Tech Spec Basis for the quantity of radioactivity in the Waste Gas Decay Tanks is based on

providing assurance that in the event of an uncontrolled release of the WGDT, the resulting total

body exposure at the exclusion boundary will not exceed in an event of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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

2) 5.0 rem

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

2) 0.5 rem

C. 1) 1 -GW-FCV-1 60, Ctmt Vac Pump Disch Hdr Isol

2) 5.0 rem

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

2) 0.5 rem

Page 93 of 100

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SURRY 2017 NRC EXAM SRO -

Question: 94

Unit 1 is shutdown with a Cooldown to CSD in progress.

RCS pressure is at 1900 psig.

C RCS loop Tc is 500 °F.

Which ONE of the following completes the statements:

1) When 1 -FW-P-2, TDAFW pump, is started the FEED PRESS light should be LIT when

discharge pressure is at least psig.

2) In accordance with Tech Spec 3.6 Basis, the Emergency Condensate Storage Tank, 1-CN-TK-

1, has sufficient capacity to remove residual heat for hours.

A. 1) 500

2) 12

B. 1) 800

2) 12

C. 1) 500

2) 8

D. 1) 800

2) 8

Page 94 of 100

SURRY 2017 NRC EXAM - SRO

Question: 95

Given the following:

Unit 2 is in Refueling with core off-load in progress.

The Manipulator Crane is enroute to the Upender with a Fuel Assembly.

Halfway to the Upender the following occur:

o Annunciator 2B-A3, CTMT SUMP HI LVL.

o 2-RM-J2, MANPLTR CRN ALERT.

o The Refueling SRO reports that Refueling cavity is dropping rapidly.

In accordance with 2-AP-22.01, Loss of Refueling Cavity Level which of the following describes:

1) The preferred location where the fuel assembly shall be placed.

2) The maximum time the closure team has to establish containment closure?

A. 1) In a horizontal position in the upender. 2) 45 minutes

B. 1) Back into the Reactor Vessel. 2) 45 minutes

C. 1) In a horizontal position in the upender. 2)60 minutes

D. 1) Back into the Reactor Vessel. 2) 60 minutes

Page 95 of 100

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SURRY 2017 NRC EXAM SRO

-

Question: 96

Given the following:

Unit 1 is in CSD with all the RCS loops isolated.

Pressurizer level is being maintained at 60%.

Seal injection is in service to the A RCP.

Which ONE of the following completes the following statements in accordance with 1-OP-RC-016,

Reactor Coolant System Loop A Fill?

1) In accordance with 1-OP-RC-016, Reactor Coolant System Loop A Fill, SR channel(s)

must be OPERABLE during the fill of A Loop.

2) In accordance with Tech Specs, the loop stop valves must be opened within two (2) hours of the

of A Loop fill.

A. 1) both

2) completion

B. 1) both

2) start

C. 1) one

2) completion

D. 1) one

2) start

Page 96 of 100

SURRY 2017 NRC EXAM - SRO

Question: 97

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 °F, Tref is 571.0 °F.

Annunciator JE-E3, Delta Flux Deviation, is lit.

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

The SRO directs Emergency Boration to be performed per 1-AP-3.00, Emergency Boration. When the

RO attempted to open 1 -CH-MOV-1 350, Emergency Borate MOV; the MOVs breaker tripped on

overcurrent.

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 J-AP-3.00.

2) The most restrictive LCO, for this CONDITION?

(REFERENCE PROVIDED)

A. 1) Manually open 1 -CH-FCV-1 11 3A, Boric Acid to Blender, and locally open 1 -CH

228, Manual Boration valve.

2) Delta flux.

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

2) Delta flux.

C. 1) Manually open 1 -CH-FCV-1 11 3A, Boric Acid to Blender, and locally open 1 -CH

228, Manual Boration valve.

2) Insertion limits.

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

2) Insertion limits.

Page 97 of 100

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SURRY 2017 NRC EXAM - SRO

Question: 98

Two workers have been assigned to repair a broken cable on the fuel transfer cart.

Worker #1 worked the spring outage at North Anna and received 763 mrem. Dose from Surry is

400 mrem. Total dose (TEDE) to date is 1163 mrem.

Worker #2 works only at Surry. Total dose (TEDE) to date is 800 mrem.

The cable repair is estimated to take 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months to complete.

Per the RWP, the general area dose rate at the repair site is 350 mrem/hr.

The Department Manager, and the Manager, Radiological Protection and Chemistry approval

has been granted.

Which ONE of the following states:

1) Which worker will require a dose upgrade prior to performing the work?

2) The Site VP required to approve the dose upgrade.

(REFERENCE PROVIDED)

A. 1) #1.

2) is not

B. 1) #1.

2) is

C. 1) #2.

2) is not

D. 1) #2.

2) is

Page 98 of 100

SURRY 2017 NRC EXAM SRO

Question: 99

Initial Conditions:

EDG 2 is out of service for maintenance.

A Loss of Offsite Power occurs.

EDG 3 fails to start.

2-ECA-0.0, Loss of All AC Power, is entered by the crew.

Current Conditions

All SG levels are at 15% NR and stable.

Annunciator 2B-E6, IA LO HDR PRESS I IA COMPR1 TRBL, has alarmed.

Instrument air pressure on P1-IA-i 00 is 50 psig and lowering rapidly.

The crew is at 2-ECA-0.0 Step 25, Depressurize All Intact SGs to 300 psig.

The SRO has directed the operator to dump steam from S!G A per ECA-0.0, Attachment 8, LOCAL

OPERATION OF SG PORV(s).

Which ONE of the following answers the questions below:

1) The preferred method for local operation of SG PORV(s) involves aligning the bottled air supply

and controlling a pressure control valve located in the_(i)_?

AND

2) What is the reason for stopping the depressurization at 300 psig?

A. 1. Main Steam Valve House

2. Preclude injection of accumulator nitrogen into the RCS.

B. 1. Containment Spray Pump House.

2. Preclude injection of accumulator nitrogen into the RCS.

C. 1. Main Steam Valve House.

2. Minimize RCS inventory loss.

D. 1. Containment Spray Pump House.

2. Minimize RCS inventory loss.

Page 99 of 100

SURRY 2017 NRC EXAM - SRO

Question: 100

An Alert has been declared.

Which ONE of the following responsibilities can the Station Emergency Manager (SEM) delegate prior

to TSC and LEOF Activation?

A. Authorization of Emergency Exposure to Plant Personnel.

B. Declaration of the Emergency Classification Upgrade.

C. Initiation of EPIP-1 .02, Response to Alert.

D. Protective Action Recommendations (PAR) to the State.

Page 100 of 100

SRO EXAM

LIST OF AUACHMENTS

Attachment # Attachment Description

1 VPAP-2802: 6.3.4, 6.3.5

2 TS FIG 3.12-3 AFD LIMTS

3 VPAP-2101

Separate EAL Charts

Separate STEAM TABLES

1

AUACHMENT 1

DOMINION VPAP-2802

REVISION 43

PAGE 84 OF 233

i. Discovery that an undeclared or misclassified event or condition met au the

following criteria: we erR nmsi Hill

Exceeded an Emergency Action Level (EAL) as specified in EflP-l.0l,

Emergency Manager Controlling Procedure

The basis for the emergency class no longer exists at the time of discovery

No other reasons exist for an emergency declaration

In addition, the following shall be notifled:

Department of Emergency Management (at approximately the same time)

Director Nuclear Protection Services and Emergency Preparedness

Louisa/Sury County Administrator

j. A cyber attack that adversely imparted safety-related or important to safety

functions, security function, or emergency preparedness functions (including

ofisite communications); or that compromised support systems and equipment

resulting in adverse impacts to safety. security. or emergency preparedness

functions within the scope of 10 CUR 73.54. jio CIRhiThuuIH.

63.4 Four-hour Notifications

NOTE: Some conditions, indicated by See EPIP-I.Ol. may exceed an Emergency Action

Level (EAL) as specified in EPIP-I .01, Emergency Manager Controlling Procedure.

If a condition exceeds an EAL. EPEPs control State and rtderal agency notifications.

If an event or condition does not exceed an EAL it may still be reportable in

accordance with this procedure.

a. As soon as practical. hut within four hours, the Shift Manager shall notify the NRC

Operations Center via the ENS of:

2

AUACHMENT 1

DOMINION VPAP-2802

REVISION 43

PAGE 5 OF 233

NOTE: if a unit enters a limiling condition for operation aCO) and a unit shutdown is stalled

due to the [CO. the event is reportable even if shutdown is not completed. [COs

tetn]rnated by a unit shutdown for an unrelated reason are still reportable ir the

condition would not have been corrected within the LCO time limit for .shcn.down,

I. Initiation of plant shutdown treduction of power or 1ernperature required by

Technical Specifications. The initiation of plant shutdown does not include

mode changes trequired by Technical Specifications if initiated after the pLant is

already in a shutdown condition. See EPIP-l.0t. 110 CF o.nIbI:2)i:,

1* (FR 036 MiREG 1*22 Item 3,111

2. Any event that results in a Technical Specifications safety timit violation and

requires a reactor shut down shall be feported in accordance with 10 CFR

50.72(bx2)(i); see also Steps 6.24.3 {Norlh Anna) and &25.3 Surry

110 (ER SUJ6icii, 1b:iitAJ

3. Any event that results or should have resulted in ECCS discharge into the RCS

as a result of a valid signal except when the actuation results From and is part of

a pie-planned sequence during testing or reactor operation. rID CER 5*.72ih2iibiA:iJ

4. Any event or condition that results in actuation ci the reactor protection system

tRPS) when the reactor is critical except when actuation results from and is part

of a pre-planned sequence during testing or reactor operation.

10 CFR 50.TZibi2)I)IftiI

NOTE: Notification to other government agencies has been or will be made is not

necessarily an automatic notification to the NRC. Refer to NUREG 1022, Event

Reporting Guidelines 10 CFR 50.72 and 50.73, for discussions and examples

(e.g.. newsworthy events, environmental events, spurious, emergency siren actuations)

or contact Station Licensing if clarification is needed. tN11WG-1Dfl.SQcü 3.2.121

5, Any event or situation, related to the heatth and safety of the public or onsite

personnel, or protection of the environment, for which a news release is

planned, or notification to other government agencies has been or will be made.

Such an event may include an onsite Fatality or inadvertent release ci

radioactively contaminated materials. [Commitment 3.2.121 rio (FR 5*32ibji2,i:i1

3

AUACHMENT 1

DOMENION VPAP-2802

REVISION 13

PAGE 86 OF 233

6, ISFSI Non-emergency Four-Hour Notifications shall include, if available at

time of notification: irncriimii

The callers name and call back telephone number

A description of the event, including time and dale

The exact location of the event

The quantities, and chemical and physical forms of the spent fuel, HLW or

reactor related Greater than Class C (GTCC) waste involved

Any personnel radiation exposure data

7. An action taken in an emergency that departs from a license condition. technical

specification, or certificate of compliance when the action is immediately

needed to protect the public health and safety and no licensed action that

provides adequate or equivalent protection is immediately apparentsee

Step 6.15.7.1. 11* CFR 72.751b:Ic1)1

8. Groundwater Protection Voluntary Communication Notifications to other

government agencies may be reportable under 10 CFR 50.72(b)(2)xi)

requirement for a 4-hour notification to the NRC operations center based upon

the following guidance:

hFa licensee is notifying a local, state, or other federal agency in accordance

with an existing law, regulation. or ordinance, then the licensee should make

ils notification to the NRC under the 50.72 notification requirement.

If a licensee is informally communicating with a local, slate, or other federal

agency (i.e., not under a specific law, regulation or ordinance), [hen the

licensee has discretion as to whether to informally communicate with NRC

(e.g., through the site resident inspector and/or regional NRC office) or

formally through the 50.72 notification process. II due to the site-specific

circumstances or heightened sensitivity to the issue at that site, the issue is

likely to produce strong media interest, then the licensee should consider

notifying NRC under the 50.72 requirement because this is actually the

underlying intent of the regulation.

4

AUACHMENT 1

DOMINION VPAP-2802

REVISION 43

PAGE 87 OF 233

b. Any person at the Station who observes smoke originating from Station equipment

being released into the outdoor atmosphere shall notify the Shift Manager as soon

as possible.

I. If the smoke is not from a fire and there are no certified visible emissions

evaluators available to determine the opacity of the smoke being released to the

outdoor atmosphere, the Shift Manager or other Station personnel shall take the

appropriate steps to determine the source, cause, and duration of the smoke

being released.

Once all of the pertinent information regarding the release of smoke has been

obtained, the Electric Environmental Services tESS) must he notified

immediately.

The ESS will report the release of smoke into the outdoor atmosphere to the

appropriate DEQ regional ollice as soon as practical, hut no later than four

daytime business hours of the occurrence, with all of the pertinent

information, lithe DEQ regional office determines that it is necessary to

obtain smoke readings after receiving all of the pertinent information, the ESS

will dispatchaceititied visibleemissions evaluatortotheStation to determine

the opacity of the snioke being reLeased into the outdoor atmosphere.

2. The E.S.S will prepare and submit any written reports to the DQ regional office

regarding the release of smoke into the outdoor atmosphere.

c. When informed by Security or Radiation Protection of events related to the

shipment or onsite storage of Category I or Category 2 radioactive material (refer

to Appendix A to 10 CFR Part 37 Physical Protection of Category 1 and

-

Category 2 Radioactive Materials), notify the NRCs Operations Center

3Oi8l65IOO) upon:

I. Determination that a shipment of Category 2 quantities of radioactive material

is lost or missing I1OCFR371IJb1

ilnil

If after 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months since the determination that the shipment was lost or missing

and the radioactive material has not been located and secured, immediately the

NRCs Operations Center

5

AUACHMENT 1

DOMENION VPAP-2802

REVISION 43

PAGE gg OF 233

2. Discovery of any unauthorized entry that resulted in the actual or attempted

threat sabotage, or diversion of Category I or Category 2 quantity of

radioactive material jio CW3737fl

3. Discovery of any suspicious activity related to the possible theft, sabotage, or

diversion of Category I or Category 2 quantities of radioactive material

110 (FR 3757ih1

d. When informed by Security of cyher attack that:

I. Could have caused an adverse impact to safety-related or important to safety

functions, security function, or emergency preparedness functions (including

ofisite communications); or that could have compromised support systems and

equipment, which ilcompromised, could have adversely impacted safety,

security, or emergency preparedness functions within the scope of

10 CFR 7154.

2. After discovery of a suspected or actual attack initiated by personnel with

physical or electronic access to digital computer and communication system

and networks within the scope of 10 CFR 73.54.

3. After notification of a local, State, or other Federal agency of an event related

to implementation of the licensees cyber security program for digital computer

and communication system and networks within the scope of 10 CFR 7154.

110 (FR 73.fla$2fl

6.3.5 Eight.hour Notifications

NOTE: Any event or condition that occurred within three years of the date of discovery.

Applicable to 63.5.a.1., 6.15.a,2.. 6.3.5.a.5. and 6.15.a7.

a. As soon as practical, but within eight hours, the Shift Manager shall notify the NRC

Operations Center via the ENS of:

I. Any condition that results in the condition of the Station, including its principal

safety harriers, being seriously degraded. jio (FR 5O.fltbI(3PIIHA))

2. Any event or condition that results in the Station being in an unanalyzed

condition that significantly degrades plant safety. 110 CFR 50.72ib3iibiI1i1

6

AUACHMENT 1

DOMINION VPAP-2802

REVISION 43

PAGE 89 OF 233

3. Any event that results in the LimIting Safety System settings for automatic

protective devices to not function as required,

4. Any event or condition that results in valid actuation of any of the following

systems, except when the actuation resuLts from and is part of a pre-planned

sequence during testing or reactor operation: t1C5[i32bp3ii:h:ii1i1

Reactor Protection System (RPS) tRPS actuation with the reactor cfitical

-

may be reportable within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months under IOCFR 5Ct.72(bX2iv){3). see

Step 6.14.aA.

General containment isolation signals affecting containment isolation valves

in more than one system or multipe Main Steam Isolation VaWes (MStVs

Emergency Core Cooling Systems (ECCS) including HHSI and LHSI (ActuaL

discharges are reportable within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months under tO CFR 50.72ib)t2)tivXA), see

Step63A.a.3i

Auxiliary Feedwater System

Containment heat removal and depressurization systems including

Containment spray and fan cooler systems

a Emergency Diesel Generators tEDGs)

5. Any event or condition that at the time of discovery could have prevented the

fulfillment of the safety function of structures or systems that are needed to:

a Shutdown the reactor and maintain it in a safe shutdown condition

Remove residual heat

a Control the release of radioactive material: or

a Mitigate the consequences of an accident. See EP1P-lOl.

6, Any event requiring the transport of a radioactively contaminated person to an

off-site medical facility for treatment. See also Step 6.282.

flU CER 5U32 b3j xi md JO CFR 72.75 4cf(3J

7

AUACHMENT 1

DOMENION VPAP-2802

REVISION 43

PAGE 90 OF 233

7. Any event that resnits in a major loss of emergency assessment capability,

oH-site response capability, or off-site oomrnunications capability. te.g,

signilicant portion of conttro[ room indication, Emergency Notilication System.

or otfsile notification systernl. Eqwpnient important to emergency response and

emergency respomse facilities are listed in the attachments of EP-AA-303,

Equipment Important to Emergency Response. See Attachment 3. Emergency

Response Unavailability Reportable Actions Levels, for reportable action level

criteria.

Emergency Assessment Capabitity

Offsite Response Capability

Ofisite Communications Capability

See EPIP-LOl. 110 CFR32ib3iiin

8. Any instanced:

A defect in any spent fueL storage cask structure, system, or component [hat is

important to safety iw CER 7l75cti

or

A significant reduction in the elfectiveness of an spent fuel storage cask

confinement system during use of the storage cask iwcFRm7sc2

See EPIP- LU I.

9. Alter receipt or collection of information regarding observed behavior,

activities, or statements that may indicate intelligence gathering or pie-

operational planning related to a cyber attack against digitat computer and

communication system and networks within the scope 10 CFR 73.51.

IO CFR 73.ThjN.

b. If an Alert. Site Mea Emergency, or General Emergency is declared:

I. The Station Coordinator Emergency Preparedness shall prepare a Summary

Report from information in completed Emergency Plan Implementing

Procedures. Control Room logs, and interviews with persons involved with the

declaration and response, as appropriate. Sec Attachment 6, Example DEM

Summary Report.

2. The Site Vice President, Director Nuclear Station Safety and Licensing, or

Plant Manager (NucLear) shall approve the report.

8

AUACHMENT 1

DOMENION VPAP-2802

REVISION 13

PAGE 91 OF 233

3. Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after termination of the event. NucLear Emergency Preparedness

shail ensure the report is deLivered to the Slate Coordinator of the Virginia

Department of Emergency Management. [NA sr .uj

c. If, on Dominion property ot at LaIe Anna Dam, there is a Dominion employee or

contractor fatality including cardiac arrest or an event in which three or more

Dominion employees or contractors are hospitalized:

1. The Shift Manager shall notify Supervisor NudearSile Safety (Station) with the

following inlormalion:

Number of fatalities

o The ernptoycr of those killed

The circumstances of the event

The exient of injuries

2. NucLear Site Safety (Station) shall notify OSHA as specified in Step 63.5.c.3.

ML17354B295

Text

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