ML082110233

Exam 05000338-08-301 Final SRO Written Exam with Answer Key & KAs

ML082110233
Person / Time
Site:	North Anna
Issue date:	06/30/2008
From:	NRC/RGN-II
To:
References
50-338/08-301, 50-339/08-301, ES-401 IR-08-301
Download: ML082110233 (129)

See also: IR 05000338/2008301

Text

Final Submittal

(Blue Paper)

AJ 0 Z~/H H 1lJA.?A-

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Senior Operator Written Examination

aI L/ST OF It!/fs ~

HAJS-WEL /~EY

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: June 24, 2008 Facility/Unit: North Anna/Units 1 & 2

Region: II Reactor Type: Westinghouse

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.

Applicant's Signature

Results

RO/SRO-Only/Total Examination Values / -- / -- Points

Applicant's Scores / -- / -- Points

Applicant's Grade / -- / --

Percent

NORTH ANNA 2008 RO/SRO WRITTEN EXAM

LIST OF KIA's & EXAM ANSWER KEY * FINAL

Page 1 of 3

1 001 02.4.31 I

2 003 A4.07 2

3 004 G2.2.3 3

4 005 Kl,06 4

5 866 Iet.82 5

6 007 A4JO 6

7 007 K3.01 7

8 008 AA2.24 8

9 008 K4.019

10 00902.4.4 10

11 010 K5.01 11

12 011 EK2.02 12

13 012 K6.04 13

14 013 AI.07 14

15 013 K4.lS 15

16 015 AK2.0116

17 016Kl.0217

18 017 A4.02 18

19 022 A2.06 19

-20 022 AK3.03 20

21 022 KI.04 21

22 025 AAI.12 22

23 026 A4.0123

24 026 AA2.01 24

25 026 K2.01 25

26 02702.2.4226

. 27 028 K3.0127

28 029 EKl.05 28

29 029 K4.03 29

30 032 AK3.01 30

31 033 K4.05 31

32 036 AAI.OI '32

33 039 02.1.3233

34 041 K6.03 34

35 054 AK3.01 35

36 055 A3.03 36

37 055 EAI.06 37

38 056 AA2.72 38

39 057 02.4.45 39

40 058 AKL0140

41 059 Kl.02 41

42 060 AA2.05 42

43 061 G2.4.3 43

44 061 K2.0144

NORTH ANNA 2008 RO/SRO WRITTEN EXAM

LIST OF KIA's & EXAM ANSWER KEY * FINAL

Page 2 of 3

45 062 G2.1.2745 A

46 062 K3.03 46 A

47 063 K4.0147 D

48 064 K3~02 48 D

49 065 AK3.03 49 B

50 071 A2.0250 A

51 073 AI.Ol 51 D

52 013 KS.02 52 D

53 976 J~,1.92 S3 C Pt.L.£'r£b

54 076 AK2.01 54 C

55 077 AAt.Ol 55 D

S6 078 A4.0156 C

57 078 K4.03 57 A

58 079 Kl.Ol 58 C

59 103 A3.0l 59 D

60 E03 EAI.2 60 D

61 EOS EIO.4 61 D

62 E~9 EA2.162 D

63 E12 EK2 .. 163 C

64 E15 EK2.1 64 D

65 E16 EIG.165 A

66 G2.1.20 66 A

67 G2.1.3767 C

68 02.1.41 68 D

69 G2,,2.169 A

70 02.2.3970 A

71 02.2.771 B

72 02.3.1572 C

73 02.3.473 C

74 02.4.3274 B

75 02.4.975 A

76 005 AA2.02 76 A

77 005 02.2.40 77 D

78 006 A2.03 78 D

79 001 G2.2.44 79 C

80 008 02.4.8 80 B

81 012 A2.04 81 D'

82 017 A2.02 82 B

83 025 AA2.03 83 C

84 026 02.1.784 C

~5 027 02.2.25 85 A

86 034 A2.03 86 B

87 038 EA2.I5 87 A

88 051 02.2.44 88 C

NORTH ANNA 2008 RO/SRO WRITTEN EXAM

LIST OF KIA's & EXAM ANSWER KEY* FINAL

Page 3 of 3

89 056 G2.2.3689 A

90 059 G7.1.23 90 C

91 061 AA2.04 91 D

92 062 AA2.05 92 -B-A

93 E13 02.4.20 93 A

94 G2.1.494 B

95 02.1.695 B

96 02.2.11 96 -9-B

97 02.2.35 97 B

98 02.3.698 A

99 G2.4.27 99 B

100 02.4.6 100 A

NAME _

North Anna Power Station

2008 SRO Exam

1.

Given the following:

• During a Unit 1 load reduction for 1-PT-34.3, Turbine Valve Freedom Test, the

following alarm is received:

• 1A-D1, ROD CONTROL URGENT FAILURE

• The Ramp has been held and power is approximately 93%.

• Tave is 2.5 0F higher than Tref.

Investigation reveals that a Logic Cabinet Oscillator Failure has occurred.

Which ONE of the following describes how this failure will affect the Rod Control

System, including the required action in accordance with the annunciator response

procedure?

A. Rod motion is NOT inhibited in 'Bank Select'; adjust Turbine load or use rods in

Bank Select to match Tave to Tref.

B. All rod motion is inhibited; adjust Turbine load ONLY to match Tave to Tref.

C. All rod motion is inhibited; adjust Turbine load or adjust RCS boron concentration to

match Tave to Tref.

D. Rod motion is NOT inhibited in 'Bank Select'; use rods in Bank Select ONLY to

match Tave to Tref.

1

North Anna Power Station

2008 SRO Exam

2.

Given the following:

Unit 1 cooldown and depressurization is in progress for refueling.

RCS temperature is 195 degrees F and slowly decreasing.

RCS pressure is 360 psig and slowly decreasing.

"A" and "C RCPs are running.

RHR is in service.

The crew observes the following indications:

• Annunciator 1C-G8, RCP 1A-B-C SEAL LEAK La FLOW is received.

Sealleakoff flow on all three RCPs is approximately 0.7 gpm and slowly

decreasing.

• All RCP Pump Radial Bearing temperatures are approximately 130 degreesF

and stable.

• All RCP Seal Water outlet temperatures are approximately 160 degrees F and

stable.

RCP standpipe alarms are all CLEAR.

Which ONE of the following is correct concerning operation of 1-CH-HCV-1307, RCP

Seal Bypass Isolation Valve?

A. Maintain closed and de-energized to address Appendix-R concerns.

B. Maintain closed and de-energized due to the potential for RCP seal damage.

C. Energize and open the valve to prevent overheating the #1 seals.

D. Energize and open the valve to prevent overheating pump radial bearing.

2

North Anna Power Station

2008 SRO Exam

3.

Which ONE of the following describes a NORMAL Unit 2 BAST alignment?

A. 'C' BAST through 1-CH-P-2D to Unit 2 Boric Acid Filter to Unit 2 BIT/Blender.

B. 'A' BAST through 1-CH-P-2A to Unit 2 Boric Acid Filter to Unit 2 BIT/Blender.

C. 'C' BAST through 1-CH-P-2D through recirc valve 1-CH-HCV-11 04 ONLY and back

to 'C' BAST.

D. 'B' BAST through 1-CH-P-2A to Unit 2 Boric Acid Filter to Unit 2 BIT/Blender.

3

North Anna Power Station

2008 SRO Exam

4.

Given the following:

• Unit 1 is in Mode 6.

• The unit has been shutdown for 11 days.

• Cavity level is 22 feet above the reactor vessel flange.

• RCS temperature is 109 degrees F.

• RHR Loop 1A is in service.

Which ONE of the following is the MINIMUM RHR flow requirement based on these

plant conditions, including the reason for this minimum flow requirement, in accordance

with 1-0P-14.1, Residual Heat Removal?

A. 2500 GPM; prevents flow induced chatter on SI Accumulator check valves.

B. 3000 GPM; satisfies Technical Specification minimum flow requirements in Mode 6.

C. 3000 GPM; prevents flow induced chatter on SI Accumulator check valves.

D. 2500 GPM; satisfies Technical Specification minimum flow requirements in Mode 6.

4

North Anna Power Station

2008 SRO Exam

5.

Given the following:

• Unit 1 is in Mode 4 with a plant cooldown to Mode 5 in progress.

• RCS Pressure is 720 psig.

• RCS temperature is 325°F.

Which ONE of the following states the power supply to 1-SI-MOV-1865A, 'A'

Accumulator Discharge Isolation Valve, and its required breaker position for the current

plant conditions?

480 Volt MCC ...

A. 1J1; breaker is closed.

B. 1H1; breaker is open.

C. 1H1; breaker is closed.

D. 1J1; breaker is open.

5

North Anna Power Station

2008 SRO Exam

6.

Given the following:

• Unit 1 is in Mode 3.

PRT level is 740/0 and INCREASING SLOWLY.

PRT pressure is 12 psig and INCREASING SLOWLY.

PRT temperature is 132°F and INCREASING SLOWLY.

• The following annunciators are LIT:

1B-H1, PRZ RELIEF TK HI TEMP

• 1B-G2, PRZ SAFETY W LINE HI TEMP

1B-H2, PRZ POWER RELIEF LINE HI TEMP

• Acoustic monitor indications are NORMAL.

Which ONE of the following identifies the cause of the conditions above, and includes

the method used to identify the affected component in accordance with annunciator

response procedures?

A. Pressurizer PORV leaking by;

Check tailpipe temperature indication to determine which PORV is leaking.

B. Pressurizer Safety Valve leaking by;

Check tailpipe temperature indication to determine which Safety Valve is leaking.

C. Pressurizer PORV leaking by;

Close block valves one-at-a-time to determine which PORV is leaking.

D. Pressurizer Safety Valve leaking by;

Check tailpipe temperatures with a contact pyrometer to determine which Safety

Valve is leaking.

6

North Anna Power Station

2008 SRO Exam

7.

Given the following:

• Unit 1 was initially at 100 % power at the end of core life.

Fuel failures have resulted in increased RCS activity (still within Tech Spec

limits).

A spurious Safety Injection (SI) occurred.

One train of SI failed to reset from the control room.

• Multiple PRZR PORV lifts occurred during the recovery.

PRT pressure is 115 psig.

Which ONE of the following identifies the current conditions in the Containment

including the raditation monitor indications in the Main Control Room?

A. Containment Sump level constant;

Containment Particulate and Gaseous Radiation Monitors constant.

B. Containment Sump level increasing;

Containment Particulate and Gaseous Radiation Monitors increasing.

C. Containment Sump level increasing;

Containment High Range radiation Monitors constant.

D. Containment Sump level increasing;

Containment High Range Radiation Monitors increasing.

7

North Anna Power Station

2008 SRO Exam

8.

Given the following:

• A reactor trip has occurred on Unit 1.

Safety Injection is actuated.

RCS pressure is 1200 psig.

Containment pressure has peaked at 16 psia and is slowly trending down.

Pressurizer level is 100 % *

The crew is performing 1-E-0, Reactor Trip or Safety Injection.

Which ONE of the following describes the method used to control RCS temperature

and the approximate Main Steam pressure maintained?

A. Condenser Steam Dumps; 1035 psig.

B. SG PORVs; 1005 psig.

C. SG PORVs; 1035 psig.

D. Condenser Steam Dumps; 1005 psig.

8

North Anna Power Station

2008 SRO Exam

9.

Given the following:

• Unit 1 is at 100% power.

CC Pump 1A is running and CC Pump 1B is in standby.

• 4160 V Bus 1H normal feeder is inadvertantly opened.

Which ONE of the following describes the AUTOMATIC operation of CC Pumps for this

event?

A. CC Pump 1B starts 15 to 20 seconds after Bus 1H is reenergized; CC Pump 1A

does NOT re-start.

B. CC Pump 1B starts when Bus 1H is deenergized; CC Pump 1A starts as soon as

Bus 1H is reenergized.

C. CC Pump 1B starts 15 to 20 seconds after Bus 1H is reenergized; CC Pump 1A

starts 15 to 20 seconds after Bus 1H is reenergized.

D. CC Pump 1B starts when Bus 1H is deenergized; CC Pump 1A restarts 15 to 20

seconds after Bus 1H is reenergized.

9

North Anna Power Station

2008 SRO Exam

10.

Given the following:

• A LOCA has occurred.

• The crew is performing 1-E-1, Loss of Reactor or Secondary Coolant.

• The following conditions exist:

• All SG pressures - 930 psig and slowly trending down.

• All SG levels - being controlled at 42% NR.

PZR level - off-scale high.

Containment Pressure - 23 psia.

RWST level - 32% and decreasing at 1% every 4 minutes.

RCS pressure - 1000 psig and stable.

Core Exit TCs - 500 degrees F.

RVLIS Full Range indication 74%.

Based on these indications, which ONE of the following procedure entry requirements

are met?

A. 1-ES-1.3, Transfer to Cold Leg Recirculation

B. 1-ES-1.2, Post-LOCA Cooldown and Depressurization

C. 1-ES-1.1, SI Termination

D. 1-FR-C.2, Response to Degraded Core Cooling

10

North Anna Power Station

2008 SRO Exam

11.

Given the following:

The RCS is solid in Mode 5.

The crew is preparing to draw a bubble in accordance with 1-0P-1.1, Unit

Startup From Mode 5 At Less Than 140 Degrees F To Mode 5 At Less Than

200 Degrees F.

PZR pressure is approximately 325 psig.

PZR temperature is 335 degrees F.

RCS temperature is 180 degrees F.

Assuming PZR Heatup rate is at the administrative limit of 1-0P-1.1, approximately

how long will it take to reach saturation conditions in the pressurizer, and what action

will be required when saturation conditions are reached?

A. 60 minutes; the letdown backpressure control valve potentiometer setpoint will be

increased.

B. 30 minutes; letdown flow will be manually increased.

C. 60 minutes; letdown flow will be manually increased.

D. 30 minutes; the letdown backpressure control valve potentiometer setpoint will be

increased.

11

North Anna Power Station

2008 SRO Exam

12.

Given the following:

• A Large Break LOCA has occurred on Unit 1.

• The crew has completed transition to 1-ES-1.3, Transfer to Cold Leg

Recirculation.

• RWST level is 14°A>.

Given these current plant conditions, which ONE of the following identifies the required

ECCS and Charging pump alignment after the initial swapover to Cold Leg

Recirculation is performed in accordance with 1-ES-1.3?

A. Low Head SI Pump flowing to Charging pumps ONLY; Charging Pump suction from

LHSI Pumps.

B. Low Head SI Pump suction from Containment Sump; Charging Pump suction from

RWST.

C. Low Head SI Pump suction from Containment Sump; Charging Pump suction from

LHSI Pumps.

D. Low Head SI Pump flowing to Charging pumps ONLY; Charging Pump suction from

RWST.

12

North Anna Power Station

2008 SRO Exam

13.

Given the following:

• A plant load reduction is in progress.

• Turbine First Stage Pressure Channel, 1-MS-PT-1446, sticks at 500~.

• Reactor power is currently 8%.

Which ONE of the following identifies the RPS permissive affected by this transmitter

failure, including the MINIMUM number of RCPs, which if lost, would cause a Reactor

Trip?

A. P-8 cannot be satisfied; the reactor would trip on loss of 2 RCPs.

B. P-7 cannot be satisfied; the reactor would trip on loss of ONLY 1 RCP.

C. P-7 cannot be satisfied; the reactor would trip on loss of 2 RCPs.

D. P-8 cannot be satisfied; the reactor would trip on loss of ONLY 1 RCP.

13

North Anna Power Station

2008 SRO Exam

14.

An event has occurred on Unit 1 resulting in core damage.

Containment pressure peaked at 28 psia.

Containment radiation peaked at 2E+5R/hr.

Current Plant parameters are as follows:

• RCS temperature is slowly trending down.

• All SGs are 150/0 Narrow Range and rising.

• AFW flow to each SG is 150 gpm.

• Containment pressure is 16 psia and slowly trending down.

• Containment radiation is 1E+4R/hr and slowly trending down.

Which ONE of the following identifies the AFW flow requirements in accordance with

1-E-0, Reactor Trip or Safety Injection, and the Adverse Containment criteria?

A. AFW may be reduced to 50 gpm to each SG since Containment pressure has

decreased to the current value.

B. AFW may be reduced to 50 gpm to each SG since Containment radiation has

decreased to the current value.

C. Total AFW flow must be maintained> 340 gpm because of the Containment

pressure transient.

D. Total AFW flow must be maintained> 340 gpm because of the Containment

radiation transient.

14

North Anna Power Station

2008 SRO Exam

15.

• The Unit is at 100% power.

• A failure of a semi-automatic tester board has occurred in the Solid State

Protection System resulting in a General Warning condition.

Which ONE of the following describes how the system is designed for the operator to

identify the condition and determine the affected Train?

A. A common Safeguards Trouble annunciator is provided in the control room;

RED GENERAL WARNING light in the affected train's logic cabinet will be

extinguished.

B. Train-specific Safeguards Trouble annunciators are provided in the control room;

RED GENERAL WARNING light in the affected train's logic cabinet will be

extinguished.

c. A common Safeguards Trouble annunciator is provided in the control room;

RED GENERAL WARNING light in the affected train's logic cabinet will be LIT.

D. Train-specific Safeguards Trouble annunciators are provided in the control room;

RED GENERAL WARNING light in the affected train's logic cabinet will be LIT.

15

North Anna Power Station

2008 SRO Exam

16.

Given the following:

Unit 1 is at 100% power.

• The following alarm is received:

1C-G7, RCP 1A-B-C SEAL LEAK HI FLOW

RCP 1B Seal Leakoff flow indicates 6 GPM.

• RCP 1B No.1 Seal DP indicates 220 psid and stable.

• Annunciator 1C-G2, RCP 1B STANDPIPE HI LEVEL is NOT LIT.

• Sealleakoff has lowered on RCP 1A and 1C.

Seal Return temperature is rising slowly.

Which ONE of the following identifies the RCP seal problem, including the required

actions in accordance with 1-AP-33.1, Reactor Coolant Pump Seal Failure?

A. RCP #1 seal;

monitor RCP bearing temperatures and initiate a plant shutdown to Hot Standby.

B. RCP #2 seal;

trip the reactor, trip the RCP, and isolate sealleakoff within 5 minutes.

C. RCP #1 seal;

trip the reactor, trip the Rep, and isolate seal leakoff within 5 minutes.

D. RCP #2 seal;

monitor RCP bearing temperatures and initiate a plant shutdown to Hot Standby.

16

North Anna Power Station

2008 SRO Exam

17.

The Unit is currently at 100% and stable. Control group heaters are operating

properly and one additional set of PRZR backup heaters are locked on.

Which ONE of the following malfunctions can occur WITHOUT affecting PRZR heater

status regardless of the position of the Pressurizer Level Control selector switch?

A. PRZR level ChanneI1-RC-LT-460 failing LOW.

B. PRZR level Channel 1-RC-LT-459 failing HIGH.

C. PRZR level ChanneI1-RC-LT-459 failing LOW.

D. PRZR level ChanneI1-RC-LT-460 failing HIGH.

17

North Anna Power Station

2008 SRO Exam

18.

Given the following:

• A LOCA has occurred on Unit 1.

1A Charging Pump is tripped.

• 1B Charging Pump is running.

• BOTH LHSI Pumps are tripped.

RCPs are running.

RCS pressure is 1600 psig and lowering.

• Containment pressure peaked at 21 psia and is now slowly trending down.

Core Exit TICs are 545 degrees F.

Which ONE of the following identifies the requirement for operation of RCPs in

accordance with 1-E-0, Reactor Trip or Safety Injection, including the reason?

A. Leave RCPs running because forced circulation provides sufficient core cooling.

B. Stop RCPs because continued operation will result in damage to the RCPs due to

loss of cooling water.

C. Stop RCPs because an inadequate core cooling condition could develop if RCPs

were tripped or lost later in the event.

D. Leave RCPs running because ECCS flow is inadeq-uate to ensure adequate core

cooling.

18

North Anna Power Station

2008 SRO Exam

19.

Given the following:

• Unit 1 is at 1000/0 power.

• The Mechanical Chiller has tripped and cannot be restarted.

• The crew enters 1-AP-35, Loss of Containment Air Recirculation Cooling.

Which ONE of the following identifies the Containment temperature that requires

entering the action statement for TS 3.6.5, Containment Air Temperature, and also

identifies the required actions to be taken for these plant conditions in accordance with

1-AP-35?

A. 115 degrees F; ensure Containment Air Recirc Fans are running with backdraft

dampers closed.

B. 105 degrees F; ensure steam chiller running or align Service Water to Containment

Air Recirc Fans.

C. 105 degrees F; ensure Containment Air Recirc Fans are running with backdraft

dampers closed.

D. 115 degrees F; ensure steam chiller running or align Service Water to Containment

Air Recirc Fans.

19

North Anna Power Station

2008 SRO Exam

20.

Given the following:

Unit 1 is at 100°Jlc> power following a refueling outage.

• The crew has isolated a Letdown line leak in accordance with 1-AP-16,

Increasing Primary Plant Leakage.

The crew is preparing to place Excess Letdown in service.

Excess Letdown will be aligned to the VCT.

Which ONE of the following identifies 1) an Excess Letdown Lineup restriction and 2)

the reason why reactor power must be monitored when placing excess letdown in

service in accordance with 1-0P-8.5, Operation of Excess Letdown?

A. Flow through ONLY one loop drain to prevent the possibility of bypassing 81 flow to

the 2 intact loops in a design basis accident;

a dilution may occur due to lower boron concentrations in the Excess Letdown

piping.

B. Excess Letdown Pressure must NOT exceed 75 psig to prevent overpressurizing

the VCT;

a dilution may occur due to lower boron concentrations in the Excess Letdown

piping.

C. Excess Letdown Pressure must NOT exceed 75 psig to prevent overpressurizing

the VCT;

a boration may occur due to higher boron concentrations in the Excess Letdown

piping.

D. Flow through ONLY one loop drain to prevent the possibility of bypassing 81 flow to

the 2 intact loops in a design basis accident;

a boration may occur due to higher boron concentrations in the Excess Letdown

piping.

20

North Anna Power Station

2008 SRO Exam

21.

Both Units are at 100%.

• A fault on the Unit 2B station service bus results in a Main Generator Lockout

and Reactor Trip.

• All Unit 2 Station Service Busses are deenergized due to the feeder breaker to

2B Station Service bus failing to open on the fault.

Which ONE of the following describes the status of Containment cooling to the Units?

A. Containment Air Recirc Fans remain running on BOTH Units; Chilled water flow to

Containment Air Recirc Fans is lost on Unit 2 ONLY.

B. Containment Air Recirc Fans remain running on BOTH Units; Chilled water flow to

Containment Air Recirc Fans is lost on BOTH Units.

C. Containment Air Recirc Fans trip on Unit 2; Chilled water flow to Containment Air

Recirc Fans is lost on Unit 2 ONLY.

D. Containment Air Recirc Fans trip on Unit 2; Chilled water flow to Containment Air

Recirc Fans is lost on BOTH Units.

21

North Anna Power Station

2008 SRO Exam

22.

Given the following:

Unit 1 has just entered Mode 4 with cooldown to Mode 5 in progress.

• RHR Pump 1A is in service.

The OATC notes the following:

RHR Pump 1A motor amps indicate 10 and stable.

1-RH-FCV-1605 in automatic indicates 100 0/ 0 demand.

Which ONE of the following identifies the status of the 1-RH-FCV-1605, RHR Heat

EXchanger Bypass Valve AND predicts the trend on Core Exit TCs?

A. 1-RH-FCV-1605 operating as designed;

Core Exit TCs stable.

B. 1-RH-FCV-1605 failed;

Core Exit TCs lowering.

C. 1-RH-FCV-1605 failed;

Core Exit TCs increasing.

D. 1-RH-FCV-1605 operating as designed;

Core Exit TCs increasing.

22

North Anna Power Station

2008 SRO Exam

23.

Given the following:

• A reactor trip and safety injection has occurred.

• RCS pressure is 1000 psig and stable.

• Containment pressure is 23 psia and rising slowly.

• The crew is performing 1-E-0, Reactor Trip or Safety Injection.

Which ONE of the following describes the appropriate operator action and the

SEQUENCE of the action required?

A. COA is not required, however Quench Spray is required; start Quench Spray

Pumps and then open Quench Spray discharge valves.

B. COA is required; manually actuate COA, stop RCPs, verify Quench Spray running,

and verify Containment Isolation Phase B.

C. COA is not required, however Quench Spray is required; open Quench Spray

Discharge Valves and then start Quench Spray Pumps.

O. COA is required; manually actuate COA, stop CC pumps, verify Quench Spray

running, verify Containment Isolation Phase B, and stop RCPs.

23

North Anna Power Station

2008 SRO Exam

24.

Given the following:

• The unit is operating at 100% power.

• CC Surge Tank level indication on 1-CC-LI-101 is 500/0 and lowering.

Which ONE (1) of the following is a possible source of the leak and the source of water

for maintaining CC System inventory?

A. Non-Regenerative Heat Exchanger; Condensate System

B. Non-Regenerative Heat Exchanger; PG water

C. 1A CC Heat Exchanger; Condensate System

D. 1A CC Heat Exchanger; PG water

24

North Anna Power Station

2008 SRO Exam

25.

Given the following on Unit 1:

Reactor Trip due to a LOCA.

• Safety Injection was actuated 11 minutes ago.

• COA was automatically actuated 7 minutes ago.

• RCS pressure is 1125 psig.

• RWST level is 720/0 and lowering.

Which ONE of the following describes the operational status of Inside Recirculation

Spray Pump 1-RS-P-1 B?

A. NOT running; power is available directly from 4160 volt bus 1J.

B. Running; power is supplied directly from 480 volt bus 1J1.

C. Running, power is supplied directly from 4160 volt bus 1J.

O. NOT running; power is available directly from 480 volt bus 1J1.

25

North Anna Power Station

2008 SRO Exam

26.

Given the following:

Unit 1 is operating at 100 % power.

• An instrument failure causes PORV 1-RC-PCV-1455C to lift.

RCS Pressure is recovering at a much slower rate than expected.

The operator closes the PORV Block Valve, 1-RC-MOV-1536, and pressure is

now 2100 psig and increasing as expected.

• All other equipment appears to be operating normally.

Which ONE (1) of the following describes the action(s) required within ONE hour in

accordance with Technical Specifications?

A. Maintain closed and maintain power to 1-RC-MOV-1536.

B. Restore RCS pressure to within limits of the COLR.

C. Verify P-11 interlock is in required state for existing unit condition ..

D. Maintain closed and remove power from 1-RC-MOV-1536.

26

North Anna Power Station

2008 SRO Exam

27.

Given the following:

Unit 1 was initially at 100 0/0.

Unit 1 experienced a large break LOCA

The crew placed 1-HC-HC-1, Hydrogen Recombiner in service on Unit 1

Containment.

• The Recombiner tripped within 5 minutes and could not be restarted.

Hydrogen concentration is now 3°~.

Given these plant conditions which ONE of the following identifies the required

operator response in accordance with 1-E-1, Loss of Reactor or Secondary Coolant?

A. Place 2-HC-HC-1, Hydrogen Recombiner, in service on Unit 1 Containment.

B. Place 1-HC-F-1, Containment Atmosphere Purge Blower, in service on Unit 1

Containment.

C. Place 2-HC-F-1, Containment Atmosphere Purge Blower, in service on Unit 1

Containment.

D. Vent Unit-1 containment through the Auxiliary Building Iodine Filters.

27

North Anna Power Station

2008 SRO Exam

28.

During an ATWS at 100 DA> Reactor Power, EOL conditions, which ONE of the following

actions will insert the MOST negative reactivity within the FIRST 30 seconds of the

ATWS?

A. Initiation of Emergency Boration

B. Manual Turbine Trip

C. Automatic Control Rod Insertion

D. Manual Control Rod Insertion

28

North Anna Power Station

2008 SRO Exam

29.

Given the following:

Both units are in Mode 5.

Containment.pur~e is in progress on each unit in preparation for Containment

entrv.wrlh bo+ll pvr?>e stJpply *to..i1S' I'Vf\(\ ,Yl3'

Unit 1 Manipulator Crane Area Radiation Monitor RM-162 indication is rising.

Unit 1 Containment Particulate and Gaseous Radiation Monitors, RM-159 and

160 are in alarm.

Unit 2 containment conditions are normal.

Which ONE of the following predicts the final status of Containment Purge after ALL

automatic actuations have taken place?

A. Purge Supply Fans 1-HV-F-4A and 1-HV-F-4B NOT running;

Containment Purge Supply isolation valves closed on BOTH units.

B. Purge Supply Fans 1-HV-F-4A and 1-HV-F-4B both running;

Unit 1 Containment Purge Supply isolation valves close.d;

Unit 2 Containment Purge Supply isolation valves open.

C. Purge Supply Fans 1-HV-F-4A and 1-HV-F-4B NOT running;

Unit 1 Containment Purge Supply isolation valves closed;

Unit 2 Containment Purge Supply isolation valves open.

D. Purge Supply Fans 1-HV-F-4A and 1-HV-F-4B both running;

Containment Purge Supply isolation valves closed on BOTH units.

29

North Anna Power Station

2008 SRO Exam

30.

Given the following conditions:

• A reactor startup is in progress and operators have just completed a rod pull.

• Both Intermediate Range channels indicate approximately 3 E -11 amps and

trending up.

• Source Range Channel N-31 indicates 1X103 CPS and is trending down slowly.

• Source Range Channel N-32 indicates approximately 6X103 CPS and trending

up slowly.

Which ONE of the following describes the required operator response in accordance

with 1-AP-4.1, Malfunction of Source Range Nuclear Instrumentation, and the reason

for the response?

A. Suspend the reactor startup; due to insufficient overlap between Source Range and

Intermediate Range channels.

B. Continue the reactor startup; the operable Source Range channel is adequate to

provide protection against a boron dilution event.

C. Suspend the reactor startup; with only one Source Range channel operable, there

is inadequate protection against an uncontrolled rod withdrawal.

D. Continue the reactor startup; the operable Source Range channel is adequate to

provide protection against an uncontrolled rod withdrawal.

30

North Anna Power Station

2008 SRO Exam

31.

Operators are performing a blended make-up to the Spent Fuel Pool (SFP)

following completion of cask loading operations.

• A calibration error results in 1-CH-FT-1114, PG Water to blender flow transmitter

indicating less than the actual flowrate.

Which ONE of the following predicts the effect on boron concentration of the blended

flow based on these plant conditions, and identifies the Technical Specification

minimum required boron concentration for the SFP?

A. Boron concentration of the blended flow will be greater than the calculated value;

2600 ppm.

B. Boron concentration of the blended flow will be less than the calculated value;

2500 ppm.

C. Boron concentration of the blended flow will be greater than the calculated value;

2500 ppm.

D. Boron concentration of the blended flow will be less than the calculated value;

2600 ppm.

31

North Anna Power Station

2008 SRO Exam

32.

Given the following:

Unit 1 is in Mode 6 with Core offload in progress.

• A fuel assembly becomes visibly damaged when removed from the core.

Containment radiation is rising slowly.

• The assembly is returned to its location.

Containment evacuation has been initiated.

Which ONE of the following identifies 1) the expected indications and 2) the crew's

response in accordance with O-AP-5.2, MGP Radiation Monitoring System?

A. Vent Stack 'B' Radiation Monitor indication increases;

Verify Containment Purge Exhaust automatically isolates when Vent Stack 'B'

Radiation Monitor exceeds alarm setpoint.

B. Vent Stack 'A' Radiation Monitor indication increases;

Verify Containment Purge Exhaust automatically isolates when Vent Stack 'A'

Radiation Monitor exceeds alarm setpoint.

C. Vent Stack 'A' Radiation Monitor indication increases;

Manually divert Containment Purge Exhaust through the Auxiliary Building Iodine

Filters

D. Vent Stack 'B' Radiation Monitor indication increases;

Manually divert Containment Purge Exhaust through the Auxiliary Building Iodine

Filters.

32

North Anna Power Station

2008 SRO Exam

33.

Which ONE of the following describes the reason for equalizing Main Steam pressure

when opening a Main Steam NRV that has been closed?

A. Prevent damage to valve internals due to excessive DP when opening the NRV.

B. Prevent excessive swell of SG volume.

C. Prevent themal overload of breaker for NRV due to excessive DP when opening the

NRV.

D. Prevent inadvertent Hi Steam Line Differential Pressure SI.

33

North Anna Power Station

2008 SRO Exam

34.

Given the following:

Unit 1 is at 100 % power.

• Rod Control is in MAN UAL.

• All other controls are in AUTO.

• A Turbine control valve failure results in a load rejection.

• Tavg - Tref deviation indicates 11 degrees F.

• 1M-D4, STEAM DUMP ARMED, is illuminated.

Which ONE of the following describes Steam Dump response?

A. Two banks of steam dumps are modulating open;

Two banks of steam dumps are closed.

B. One bank of steam dumps is tripped open;

One bank of steam dumps is modulating open.

C. Four banks of steam dumps are tripped open.

D. Two banks of steam dumps are tripped open;

One bank of steam dumps is modulating open.

34

North Anna Power Station

2008 SRO Exam

35.

Given the following:

Reactor power is 75°A>.

1B MFW Pump is out of service for pump coupling repairs.

• The following alarms are received:

• 1F-A4, MAIN FD PPS DISCH HDR LO PRESS

1F-A5, MAIN FD PP 1A-1B-1C AUTO TRIP

1F-F1/F2/F3, SG 1N1 B/1C LEVEL ERROR

• 1F-D1/D2/D3, STM GEN 1A11 B/1C FW<STrvl FLOW CH III-IV

• The BOP determines that 1C MFW Pump is tripped.

• The crew enters 1-AP-31, Loss of Feedwater.

Which ONE of the following describes the action required, and reason for the action?

A. Reduce load; prevent operating MFW pump motor windings from overheating due

to excessive current.

B. Trip the reactor; prevents damage to operating Main Feedwater Pump due to pump

runout flow and cavitation.

C. Trip the reactor; prevents a challenge to the Reactor Protection System from loss of

secondary heat sink.

D. Reduce load; reduces steam flow to within the capacity of the operating MFW

pump.

35

North Anna Power Station

2008 SRO Exam

36.

Initial Conditions:

• A Steam Generator Tube Leak is occurring on Unit 1.

• The crew is entering 1-AP-24, Steam Generator Tube Leak.

Condenser Air Ejector Radiation Monitor 1-SV-RM-121 is in Hi-Hi alarm.

Current conditions:

• Reactor Trip.

Safety Injection is actuated.

• The crew is performing actions of 1-E-O, Reactor Trip or Safety Injection.

Which ONE of the following describes the alignment of the Condenser Air Ejector

steam supply and exhaust for the current conditions? .

A. Exhaust isolated on Phase A isolation; steam supply to air ejectors isolated on

Phase A isolation.

B. Exhaust diverted to Containment on Phase A isolation; steam supply to air ejectors

isolated on Phase A isolation.

C. Exhaust diverted to Containment on HI-HI radiation; steam supply to air ejectors

isolated on HI-HI radiation.

D. Exhaust isolated on HI-HI radiation; steam supply to air ejectors isolated on HI-HI

radiation.

36

North Anna Power Station

2008 SRO Exam

37.

Given the following:

• A loss of all AC Power has occurred.

• The crew is performing actions of 1-ECA-O.O, Loss of All AC Power.

1H EDG has failed and CANNOT be restarted.

• The crew is performing 1-ECA-O.O, Attachment 4, Attempting to restore power to

1H (1J) Emergency Bus.

• Attempts to start EDG 1J are in progress.

RCP Seal Water Outlet temperature is 200°F and rising at 20F per minute.

Which ONE of the following describes the action required in accordance with ECA-O.O?

A. Place 1J EDG in MANUAL-LOCAL, press EMER GEN Alarm & Shutdown RESET

Button, and verify Shutdown Relay Status Light is lit. After one minute, place 1J

EDG in MANUAL - REMOTE and determine if the EDG starts.

B. Place Charging Pumps in PTL prior to attempting to start 1J EDG in MANUAL -

LOCAL.

C. Perform Attachment 3, RCP seal isolation, prior to attempting to start 1J EDG in

MANUAL- LOCAL.

D. Place 1J EDG in MANUAL-REMOTE, press EMER GEN Alarm & Shutdown

RESET Button, and verify Shutdown Relay Status Light is lit. After one minute,

place 1J EDG in MANUAL - LOCAL and determine if the EDG starts.

37

North Anna Power Station

2008 SRO Exam

38.

Given the following:

• AFW pump 1-FW-P-2 is tagged out to replace the overspeed trip tappet.

Unit 1 reactor trip from 100 % power.

• Severe weather causes a Loss of Off-Site power.

• An electrical fault on 1H Bus has caused a bus lockout.

Which ONE of the following describes the response of the AFW System during this

event?

A. 1-FW-P-3B starts as soon as the 4160 Volt emergency bus is energized;

AFW will be supplied to B SG.

B. 1-FW-P-3B starts approximately 20 seconds after the 4160 Volt emergency bus is

energized;

AFW will be supplied to C SG.

C. 1-FW-P-3B starts approximately 20 seconds after the 4160 Volt emergency bus is

energized;

AFW will be supplied to B SG.

D. 1-FW-P-3B starts as soon as the 4160 Volt emergency bus is energized;

AFW will be supplied to C SG.

38

North Anna Power Station

2008 SRO Exam

39.

The Unit is in MODE 3 preparing to startup.

Loss of vital bus 1-1 occurred and power has not yet been restored.

Station Emergency Manager just declared a Notification of Unusual Event.

Which ONE of the following describes the correct response and required notifications?

A. Monitor RCP temperatures due to loss of CC flow;

Notification of State and Local authorities is required within the next 15 minutes.

B. Monitor RCP temperatures due to loss of CC flow;

Notification of State and Local authorities is required within the next 60 minutes.

C. Monitor SG PORVs due to loss of condenser steam dumps;

Notification of State and Local authorities is required within the next 15 minutes.

D. Monitor SG PORVs due to loss of condenser steam dumps;

Notification of State and Local authorities is required within the next 60 minutes.

39

North Anna Power Station

2008 SRO Exam

40.

Given the following:

• Unit 1 is at 100 % power.

• All DC Bus voltages are approximately 131 VDC.

• The following alarm is received in the control room:

1H-B3, BATTERY CHGR 1-111 TROUBLE

Battery Charger 1-111 DC Output breaker has tripped and CANNOT be reset.

• DC Bus 1-111 voltage is 118 volts and lowering.

Which ONE of the following describes the action that will be taken to restore DC Bus

1-111 in accordance with 1-0P-26.4.3, Main Station Swing Battery Chargers 1C-1 and

1C-II Operation?

A. Place Swing Battery Charger 1C-I in service with the NORMAL/EQUALIZE switch in

EQUALIZE.

B. Place Swing Battery Charger 1C-II in service with the NORMAL/EQUALIZE switch

in NORMAL.

C. Place Swing Battery Charger 1C-II in service with the NORMAL/EQUALIZE switch

in EQUALIZE.

D. Place Swing Battery Charger 1C-I in service with the NORMAL/EQUALIZE switch in

NORMAL.

40

North Anna Power Station

2008 SRO Exam

41.

Given the following:

The plant is at 25°h power.

• A Condensate header rupture occurs, and the following conditions are present:

• All Main Feedwater pumps tripped.

10 seconds later SG levels are 300/0 narrow range and lowering.

• Reactor power remains at 25°h.

Which ONE of the following describes the operation of the Reactor Protection System

and the Auxiliary Feedwater (AFW) Pumps for this condition?

A. A reactor trip setpoint has NOT been exceeded; AFW Pumps are NOT running.

B. A reactor trip setpoint has been exceeded; AFW Pumps are running.

C. A reactor trip setpoint has NOT been exceeded; AFW Pumps are running.

D. A reactor trip setpoint has been exceeded; AFW Pumps are NOT running.

41

North Anna Power Station

2008 SRO Exam

42.

Given the following:

• Release of Waste Gas Decay Tank 1B is in progress.

• 1-GW-RI-178-1, Process Vent Normal Range Monitor, indication is rising.

• 1-GW-RI-178-2, Process Vent High Range Monitor, indication is just coming on

scale.

The following alarms are received:

• 2B-A5, PROCESS VENT VNT STACK A&B LOW RAD MON

ALERT/RAD

• 2B-B5, PROCESS VENT VNT STACK A&B HI HI RADIATION

Which ONE of the following describes the status of the Waste Gas Decay Tank

release lineup?

A. 1-GW-FCV-101 AND 1-GW-PCV-117 closed when 1-GW-RI-178-1 HI radiation

alarm was received.

B. 1-GW-FCV-101 remained open UNTIL 1-GW-RI-178-2 HI radiation alarm was

received. 1-GW-PCV-117 does NOT receive a close signal.

C. 1-GW-FCV-101 closed when 1-GW-RI-178-1 HI radiation alarm was received.

1-GW-PCV-117 does NOT receive a close signal.

D. 1-GW-FCV-101 AND 1-GW-PCV-117 remained open untiI1-GW-RI-178-2 HI

radiation alarm was received.

42

North Anna Power Station

2008 SRO Exam

43.

Given the following:

• A LOCA occurred on Unit 1 thirty minutes ago.

• The crew is performing 1-E-1, Loss of Reactor or Secondary Coolant.

• 1-RM-RMS-165 and 1-RM-RMS-166, Containment High Range Radiation

Monitors, both have amber and red lights illuminated in the control room.

Which ONE of the following describes the additional indications observed if an actual

high radiation condition exists?

A. SAFE/RESET green light on drawers LIT;

UNIT 1 CONT HI RANGE RADIATION TROUBLE annunciator received on Unit 2.

B. SAFE/RESET green light on drawers LIT;

UNIT 1 CONT HI RANGE RADIATION TROUBLE annunciator received on Unit 1.

C. SAFE/RESET green light on drawers NOT LIT;

UNIT 1 CONT HI RANGE RADIATION TROUBLE annunciator received on Unit 2.

D. SAFE/RESET green light on drawers NOT LIT;

UNIT 1 CONT HI RANGE RADIATION TROUBLE annunciator received on Unit 1.

43

North Anna Power Station

2008 SRO Exam

44.

Which ONE of the following states the power supplies to AFW Discharge MOVs,

1-FW-MOV-100A, B, C?

A. MCC 1J1-2N

B. 1A Semi-Vital Bus

C. 1B Semi-Vital Bus

D. MCC1H1-2N

44

North Anna Power Station

2008 SRO Exam

45.

In accordance with the applicable Fire Contingency Action (FCA) procedure, which

ONE of the following describes actions required to maintain power supply to the Unit-1

remote monitoring excore neutron flux detector (channel one) following a fire in the

given location?

A. Following a fire in the Main Control Room, supplied from Unit-2 vital bus inverter

2-1, which will be disconnected from vital bus 2-1.

B. Following a fire in Unit-1 emergency switchgear, supplied from Unit-2 vital bus

inverter 2-1, which will be disconnected from vital bus 2-1.

C. Following a fire in the Main Control Room, supplied from Unit-1 vital bus inverter

1-1, which will be disconnected from vital bus 1-1.

D. Following a fire in Unit-1 emergency switchgear, supplied from Unit-1 vital bus

inverter 1-1, which will be disconnected from vital bus 1-1.

45

North Anna Power Station

2008 SRO Exam

46.

Given the following:

• Both Units are at 100 % power.

• A Fire in RSST 'A' causes an overcurrent lockout on Transfer Bus D.

Which ONE of the following describes the battery chargers that are temporarily

deenergized?

A. 1-111 and 1-IV

B. 2-1 and 2-11

c. 2-111 and 2-IV

D.1-land1-11

46

North Anna Power Station

2008 SRO Exam

47.

If a loss of Battery Charger 1-1 were to occur, what would be the effect on the operation

of its associated inverter and the vital DC bus?

A. NO static switch automatic transfer; vital DC bus voltage initially decreases by

several volts and then continues to decrease at the same rate over time.

B. Static switch automatic transfer occurs; vital DC bus voltage initially decreases by

several volts and then continues to decrease at a faster rate over time.

C. Static switch automatic transfer occurs; vital DC bus voltage initially decreases by

several volts and then continues to decrease at the same rate over time.

D. NO static switch automatic transfer; vital DC bus voltage initially decreases by

several volts and then continues to decrease at a faster rate over time.

47

North Anna Power Station

2008 SRO Exam

48.

Given the following:

• A lightning strike has occurred resulting in a loss of the North Anna Switchyard.

• The 1J EDG Battery and Battery Charger are BOTH lost.

125 VDC Bus 1-1 is lost.

• A spurious SI occurs.

The crew has entered 1-E-O, Reactor Trip or Safety Injection, and manually

actuated SI.

Which ONE of the following describes the reason that no J Train ESF equipment is

running?

A. 1J EDG did NOT start due to loss of the DC fuel oil pump.

B. 1J EDG started, but the EDG output breaker did NOT close due to loss of DC field

flash capability.

C. 1J EDG started and the EDG output breaker is closed, but no control power is

available to 1J Bus load breakers.

D. 1J EDG did NOT start due to loss of power to both start circuits.

48

North Anna Power Station

2008 SRO Exam

49.

Unit 1 is operating at 100 % power.

• The following alarm is received:

• 1F-F8, SAND FLTR IA SUPPLY LO PRESS.

• The OATC notes instrument air pressure is 85 psig and rapidly decreasing.

• The crew initiates 1-AP-28, LOSS OF INSTRUMENT AIR.

• Instrument Air pressure continues to lower.

• The SRO directs tripping the reactor and closing Main Steam Trip Valves.

Which ONE of the following identifies the reason for manually closing the Main Steam

Trip Valves?

A. To avoid a High Steam Line Delta P safety injection due to closure of a single main

steam trip valve.

B. To avoid a High Steam Flow safety injection due to closure of a single main steam

trip valve.

C. To avoid a Lo-Lo SG level reactor trip due to closure of all main steam trip valves.

D. To avoid a High PZR Pressure reactor trip due to closure of all main steam trip

valves.

49

North Anna Power Station

2008 SRO Exam

50.

Given the following:

• The crew is preparing to release WGDT 1B.

• The maximum allowed flowrate per the release permit is 300 SCFM.

Which ONE of the following describes the preferred method for controlling the WGDT

release flow rate in accordance with 0-OP-23.2, WGDT and Waste Gas Diaphragm

Compressors?

A. 1-GW-FCV-101, WGDT to Process Vent, should be placed in AUTOMATIC and

adjusted to control flow rate at less than 3 SCFM.

B. 1-GW-FCV-1 01, WGDT to Process Vent, should be placed in MANUAL and'

adjusted to control flow rate at less than 3 SCFM.

C. 1-GW-FCV-101, WGDT to Process Vent, should be placed in AUTOMATIC and

adjusted to control flow rate at 290 i: 5 SCFM.

D. 1-GW-FCV-1 01, WGDT to Process Vent, should be placed in MANUAL and

adjusted to control flow rate at 290 i: 5 SCFM.

50

North Anna Power Station

2008 SRO Exam

51.

Given the following:

Each Unit has a containment vacuum pump running.

• 1-GW-RI-178-3, Process Vent particulate radiation Monitor indication spiked,

causing an ALERT and HIGH alarm to lock in.

Which ONE of the following describes the plant response?

A. ONLY the unit 1 vacuum pump discharge valve will automatically close.

B. ONLY the unit 1 vacuum pump will trip.

C. Both units' vacuum pumps will trip; discharge valves remain open.

D. Both units' vacuum pump discharge valves will automatically close.

51

North Anna Power Station

2008 SRO Exam

52.

Initial Conditions:

Operations noted a step increase on 1-CH-RM-128, Unit 1 Reactor Coolant

Letdown Monitor.

• Health Physics identified a hot spot in the letdown piping four (4) feet from

1-CH-RM-128 detector.

• General area survey taken at 1-CH-RM-128 detector was 60 mRem/hour prior to

flushing the hot spot.

• No Radiation Monitors in alarm.

Current Conditions:

Operations flushed the hot spot and relocated it to two (2) feet from

1-CH-RM-128 detector.

• 1-CH-RM-128 Hi alarm -LIT.

• Annunciator 1K-D2, Rad Monitor System Hi Rad Level- LIT solid.

Based on current conditions, which ONE of the following identifies the expected

general area survey at 1-CH-RM-128 detector, and also predicts the response of

Annunciator 1K-D2, if a high alarm subsequently occurs on 1-SV-RM-121, Condenser

Air Ejector Radiation Monitor?

A. 120 mRem/hour;

Annunciator 1K-D2 will remain LIT solid.

B. 240 mRem/hour;

Annunciator 1K-D2 will remain LIT solid.

C. 120 mRem/hour;

Annunciator 1K-D2 will blink and horn will sound until acknowledged.

D. 240 mRem/hour;

Annunciator 1K-D2 will blink and horn will sound until acknowledged.

52

North Anna Power Station

2008 SRO Exam

53.

Given the following:

• Unit 1 is at 100% power.

Three BC fans are running in SLOW speed and the fourth is in standby.

Computer alarms are received on several components cooled by the Bearing

Cooling System.

Subsequently, the following alarms are received 90 seconds apart:

1A-F4, BASIN TEMP HI/LOW

• 1T-C1, HYDROGEN TEMP OR CORE MONITOR

The crew enters 1-AP-19, Loss of Bearing Cooling Water, and verifies a Bearing

Cooling Pump is running.

Which ONE of the following describes the initial action required in accordance with

1-AP-19?

A. Bypass 1-BC-TCV-104, Generator Hydrogen Cooler TCV, to lower hydrogen

temperature.

B. Place Bearing Cooling in Lake - to - Lake Mode and verify the operation of the Circ

Water System to ensure cooling requirements are met.

C. Start available Bearing Cooling Tower Fans or shift fans to high speed; verify

Bearing Cooling temperatures are decreasing.

D. Verify Generator Hydrogen temperature is above the alarm setpoint and initiate a

plant load reduction until the alarm is clear.

53

North Anna Power Station

2008 SRO Exam

54.

Given the following:

• Unit 1 is at 40°A> power.

• The B SG has developed a 60 gpd tube leak.

• Operators are preparing to shutdown the Unit due to fuel failure resulting in ReS

activity increasing at a steady rate.

Based on these plant conditions, which ONE of the following identifies how

1-SV-RM-121, Condenser Air Ejector Radiation Monitor, and 1-MS-RI-191,

"B" SG N-16 Radiation Monitor, will respond as RCS activity increases?

A. 1-SV-RM-121 indication will not change;

1-MS-RI-191 indication will not change.

B. 1-SV-RM-121 indication will not change;

1-MS-RI-191 indication will increase.

C. 1-SV-RM-121 indication will increase;

1-MS-RI-191 indication will not change.

D. 1-SV-RM-121 indication will increase;

1-MS-RI-191 indication will increase.

54

North Anna Power Station

2008 SRO Exam

55.

Given the following:

Both units are at 100 % power.

Due to voltage and frequency fluctuations on the grid, the crew is performing

actions contained in 0-AP-8, Response to Grid Instability.

The crew has verified equipment operability.

Which ONE of the following describes the operation of the Main Generator Voltage

Regulators per 0-AP-8, and the condition that requires the offsite power source to be

declared inoperable?

A. Place voltage regulators in MANUAL; grid voltage decreases to 504 kV

B. Maintain voltage regulators in AUTO; grid voltage increases to 536 kV

c. Place voltage regulators in MANUAL; grid voltage increases to 536 kV

D. Maintain voltage regulators in AUTO; grid voltage decreases to 504 kV

55

North Anna Power Station

2008 SRO Exam

56.

Which ONE (1) of the following describes the operation of Instrument Air Compressor

"1-IA-C-1" when it is placed in AUTO?

A. Compressor will start and run continuously for an indefinite period of time.

Unloader valves will CLOSE when pressure drops to 103 psig. Unloader valves will

OPEN when pressure rises to 109 psig.

B. Compressor will start and run continuously for an indefinite period of time.

Unloader valves will CLOSE when pressure drops to 98 psig. Unloader valves will

OPEN when pressure rises to 106 psig.

C. Compressor will start and load when pressure drops to 98 psig. Compressor will

unload when pressure rises to 106 psig.

D. Compressor will start and load when pressure drops to 103 psig. Compressor will

unload and shut down when pressure increases to 109 psig.

56

North Anna Power Station

2008 SRO Exam

57.

Instrument Air Compressor 1-IA-C-1 has been running loaded for the past 15 minutes.

Which ONE of the following choices completes the following sentence?

Either a OR a will result in a trip of the Air Compressor.

A. Low Oil Pressure;

Cooling System Fault caused by low cooling system DP

B. High Discharge Pressure;

Cooling System Fault caused by high pressure on surge line .

C. High Discharge Pressure;

Cooling System Fault caused by low cooling system DP

D. Low Oil Pressure;

Cooling System Fault caused by high pressure on surge line

57

North Anna Power Station

2008 SRO Exam

58.

Given the following:

• A loss of Instrument Air is occurring on Unit 1.

• The immediate actions of 1-AP-28, Loss of Instrument Air, are complete.

• Instrument Air pressure is 90 psig and dropping slowly.

Which ONE of the following describes the compressor status and the action to be

taken based on the system pressure in accordance with 1-AP-28?

A. All Service Air Compressors running and loaded; all Instrument Air Compressors

running unloaded;

Isolate Instrument Air to Containment by closing 1-IA-TV-102A or 1-IA-TV-102B,

Containment Instrument Air Trip Valves.

B. All Service Air Compressors running and loaded; all Instrument Air Compressors

running unloaded;

Verify Instrument Air supplied to Containment by verifying open 1-IA-TV-1 02A and

1-IA-TV-102B, Containment Instrument Air Trip Valves.

C. All Instrument and Service Air Compressors running and loaded;

Isolate Instrument Air to Containment by closing 1-IA-TV-102A or 1-IA-TV-102B,

Containment Instrument Air Trip Valves.

D. All Instrument and Service Air Compressors running and loaded;

Verify Instrument Air supplied to Containment by verifying open 1-IA-TV-1 02A and

1-IA-TV-102B, Containment Instrument Air Trip Valves.

58

North Anna Power Station

2008 SRO Exam

59.

Given the following:

• A LOCA has occurred on Unit 1.

• The following conditions exist:

• RCS pressure is 1700 psig.

• Containment pressure has peaked at 21 psia and is now slowly decreasing.

• The crew is performing 1-E-0, Reactor Trip or Safety Injection.

• The RO is performing Attachment 5, Verification of Phase A Isolation.

• The following valves are identified as OPEN:

• 1-CH-MOV-1115B, RWST To Charging Pumps Isolation

1-CH-MOV-1289B, Normal Charging Line Isolation

• 1-IA-TV-102A, Containment Instrument Air Trip Valve

1-SW-MOV-108A, Service Water to CC Heat Exchanger Isolation

For the current plant conditions, which ONE of the following valves must be

repositioned to place it in the required accident configuration?

A. 1-SW-MOV-108A

B. 1-CH-MOV-1115B

C. 1-IA-TV-102A

D. 1-CH-MOV-1289B

59

North Anna Power Station

2008 SRO Exam

60.

Given the following:

• A LOCA has occurred on Unit 1.

The crew is performing 1-ES-1.2, Post LOCA Cooldown and Depressurization.

During the SI flow reduction sequence, the following conditions exist:

• All RCPs are stopped.

• Two Charging Pumps are running.

• RCS pressure is 1100 psig and stable.

• RCS Subcooling based on Core Exit TCs is 55°F

• Pressurizer level is 44%.

Containment pressure is 20.9 psia.

Which ONE of the following describes the response to these conditions in accordance

with 1-ES-1.2, and the reason for this response?

A. Continue the RCS cooldown while stopping one Charging Pump;

RCS subcooling is adequate to prevent loss of subcooling margin when one

Charging Pump is stopped.

B. One Charging Pump may be stopped ONLY IF at least one Low Head SI pump is

running;

RCS subcooling is NOT adequate to prevent loss of subcooling margin when one

Charging Pump is stopped.

C. Maintain PZR level stable or increasing while stopping one Charging Pump;

RCS subcooling is adequate to prevent loss of subcooling margin when one

Charging Pump is stopped.

D. Charging Pumps must remain running with flow aligned to the BIT;

RCS subcooling is NOT adequate to prevent loss of subcooling margin when one

Charging Pump is stopped.

60

North Anna Power Station

2008 SRO Exam

61.

Initial Conditions:

• Unit 1 tripped from 100°1'<> power due to a loss of all feed flow.

• Multiple failures caused a loss of all AFW.

Current conditions:

• ALL SG Wide Range levels are 12°1'<> and slowly lowering.

• RCS Hot Leg Temperatures are 5600F and slowly lowering.

Core Exit TCs are 565 0F and slowly lowering.

• Local actions have restored the capability to feed from AFW.

Which ONE of the following describes the method for recovery of Heat Sink in

accordance with 1-FR-H.1, Loss of Secondary Heat Sink, and includes the Basis for

that method?

A. Feed only ONE SG at 100 gpm;

Minimum flow to ensure adequate heat sink.

B. Feed all three SGs at 340 gpm total flow;

Minimum flow to ensure adequate heat sink.

C. Feed all three SGs at 340 gpm total flow;

Ensure symetric cooling during Natural Circulation.

D. Feed only ONE SG at 100 gpm;

Limit thermal stresses to SG components.

61

North Anna Power Station

2008 SRO Exam

62.

Given the following:

• A loss of off-site power due to a Tornado hitting the switchyard.

• The crew has stabilized the Unit using 1-ES-O.1, Reactor Trip Response.

• Operations Management has directed performance of a Natural Circulation

Cooldown.

Which ONE of the following procedures will be used to perform the RCS Cooldown,

and which ONE of the following is the MAXIMUM cooldown rate allowable in

accordance with the EOP that will be used?

A. ES-O.2A, Natural Circulation Cooldown with CRDM Fans; 15 degrees F/Hr.

B. ES-O.2B, Natural Circulation Cooldown without CRDM Fans; 25 degrees F/Hr.

C. ES-O.2B, Natural Circulation Cooldown without CRDM Fans; 15 degrees F/Hr.

D. ES-O.2A, Natural Circulation Cooldown with CRDM Fans; 25 degrees F/Hr.

62

North Anna Power Station

2008 SRO Exam

63.

Upon entry into 1-ECA-2.1, Uncontrolled Depressurization of All Steam Generators, the

crew determines that RCS cooldown rate is 10goF/Hr.

Which ONE (1) of the following identifies the requirement for controlling AFW flow in

accordance with 1-ECA-2.1?

A. Total flow is maintained >340 gpm until ANY SG narrow range level is >110/0.

B. Total flow is maintained >340 gpm until ALL 8G narrow range levels are >11 % *

C. Flow is reduced to 100 gpm to each 8G, and narrow range level in ALL 8G's is

controlled at less than 50%.

D. Flow is reduced to 100 gpm to each SG, and narrow range level in ALL 8G's is

controlled at greater than 11%.

63

North Anna Power Station

2008 SRO Exam

64.

Given the following:

• A small-break LOCA occurred on Unit 1.

The crew transitions to 1-E-1, Loss of Reactor or Secondary Coolant.

Which ONE of the following will FIRST cause an ORANGE condition on the

Containment CSF Status Tree?

A. Recirc Spray sump level at 4 feet 10 inches.

B. Annunciator 1J-A6, RX CONT SUMP HI LEVEL, is LIT.

C. Containment circular sump level indication off-scale high.

D. Recirc Spray sump level at 11 feet 10 inches.

64

North Anna Power Station

2008 SRO Exam

65.

A Small Break LOCA has occurred on Unit 1.

The following plant conditions exist:

Complications in recovery have resulted in some core damage.

Containment Pressure peaked at 22 psia and is slowly decreasing.

• The team has transitioned to 1-FR-Z.3, Response to High Containment

Radiation Level.

Which ONE of the following describes a strategy provided by 1-FR-Z.3 to mitigate the

condition?

A. Place Containment Atmosphere Filtration System in service.

B. Start Outside Recirc Spray pumps and injecting the CAT.

C. Start Inside Recirc Spray pumps and injecting the CAT.

D. Vent Containment via the Iodine Filter banks.

65

North Anna Power Station

2008 SRO Exam

66.

In Emergency Operating Procedure 1-E-O, Reactor Trip or Safety Injection, steps

designated with an asterisk (*) next to the step are _

these steps apply from the time they are encountered until _

A. Continuous Action Steps;

transition from 1-E-O is made

B. Decision Making Steps;

the EOP Network is exited

C. Decision Making Steps;

transition from 1-E-O is made

D. Continuous Action Steps;

the EOP Network is exited

66

North Anna Power Station

2008 SRO Exam

67.

In accordance with OP-AP-300, Reactivity Management, reactor power is required to

be reduced below 100°A> PRIOR to performing which ONE of the following evolutions?

A. Reducing Steam Generator Blowdown Flow Rate

B. Performing a blended makeup to the RCS

C. Operating the Steam Driven Aux Feed Pump Turbine

D. Raising Letdown temperature

67

North Anna Power Station

2008 SRO Exam

68. Given the following:

Unit 1 is shut down in preparation for Refueling in accordance with 1-0P-4.1,

Controlling procedure for Refueling.

In accordance with 1-0P-4.1, which ONE of the following choices describes

(1) the method of filling the Refueling Cavity

and

(2) which evolution constitutes the FIRST Core Alteration?

A. (1) Gravity fill from RWST, then LHSI pump

(2) Lifting of the Reactor Vessel Upper Internals

B. (1) LHSI pump ONLY

(2) Lifting of the Reactor Vessel Upper Internals

C. (1) LHSI pump ONLY

(2) Control Rod Drive Shaft unlatching

D. (1) Gravity fill from RWST, then LHSI pump

(2) Control Rod Drive Shaft unlatching

68

North Anna Power Station

2008 SRO Exam

69.

Given the following:

• An approach to criticality is in progress in accordance with 1-0P-1.5, Unit

Startup from Mode 3 to Mode 2.

• Source Range count rate prior to the last rod withdrawal was 4,000 CPS.

• Source Range count rate is now 7,000 CPS and slowly increasing.

Source Range startup rate is +0.3 OPM and stable.

• Two minutes have elapsed since the last rod withdrawal.

• Control Bank 'C' is at 110 steps.

Which ONE of the following describe the sequence of actions required by 1-0P-1.5?

A. Initiate Boration at greater than or equal to 10 gpm, then trip the reactor.

B. Allow Source Range count rate to stabilize, then continue rod withdrawal.

C. Insert Control Bank '0' to 5 steps, then trip the reactor.

O. Initiate Boration at greater than or equal to 10 gpm, then insert Control Bank '0' to 5

steps.

69

North Anna Power Station

2008 SRO Exam

70.

Given the following:

• Unit 1 is at 45% power.

• Plant startup is in progress.

• No other evolutions are in progress

Which ONE of the following parameter values requires Technical Specification action

within ONE (1) hour?

A. Containment air partial pressure 12.9 psia.

B. Quadrant Power Tilt Ratio 1.022.

C. RCS unidentified leakage is 1.20 gpm.

D. RWST temperature 38 degrees F.

70

North Anna Power Station

2008 SRO Exam

71.

Which ONE of the following Periodic Tests is designated as an Infrequently Conducted

or Complex Evolution?

A. Rod operability testing in accordance with 1-PT-17.1, Control Rod Operability.

B. Turbine overspeed trip test in accordance with 1-PT-34.5, Turbine-Generator

Overspeed Trip Test.

C. Turbine valve freedom test in accordance with 1-PT-34.3, Turbine Valve Freedom

Test.

D. Solid State Protection System testing in accordance with 1-PT-36.1A, Train A

Reactor Protection and ESF Logic Actuation Test.

71

North Anna Power Station

2008 SRO Exam

72.

Given the following:

Unit 1 is defueled and the fuel assembly insert shuffle is in progress.

• Annunciator 1K-D3, RAD MONITOR SYSTEM FAILURE TEST, actuates.

The new fuel storage area radiation monitor is noted to be pegged high and

unresponsive to source check.

• The fuel pit bridge radiation monitor indication has not changed.

Health Physics reports radiation levels in the fuel building have not changed.

Which ONE of the following describes the FIRST action that will be required in

accordance with O-AP-5.1, Common Unit Radiation Monitoring System?

A. Verify the fuel building ventilation exhaust is aligned to the charcoal filter.

B. Reset the new fuel storage area radiation monitor by pulling and reinserting fuses.

C. Place the fuel building radiation automatic interlock key switch in DISABLE within

two minutes.

D. Place the fuel building radiation automatic interlock key switch in ENABLE within

two minutes.

72

North Anna Power Station

2008 SRO Exam

73.

Which ONE of the following identifies the 10 CFR 20 annual limit for TEDE and also

identifies the EPIP 4.04 Emergency Exposure Limit for saving valuable equipment?

A. 5 rem;

25 rem

B. 3 rem;

10 rem

C. 5 rem;

10 rem

D. 3 rem;

25 rem

73

North Anna Power Station

2008 SRO Exam

74.

Given the following:

Both Units are at 1DD°A> power.

• The following alarm is received on Unit 2 Panel F:

• UNIT #1 ANN SYS POWER SUPPLY FAILURE

• The crew enters 1-AP-6, Loss of Main Control Room Annunciators.

Which ONE of the following describes requirements in accordance with 1-AP-6 if the

Unit 1 Annunciators are not immediately restored?

A. NOT required to station an additional operator to monitor the unit-1 PCS;

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

B. Station an additional operator to monitor the unit-1 PCS;

Log AFD every hour.

C. NOT required to station an additional operator to monitor the unit-1 PCS;

Log AFD every hour.

D. Station an additional operator to monitor the unit-1 PCS;

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

74

North Anna Power Station

2008 SRO Exam

75.

Given the following:

Unit 1 is in Mode 5.

• RCS Drain Down to Mid Loop is in progress in preparation for welding on a Hot

Leg opening.

RHR Pump 1A is in service.

• RHR Pump 1B is available.

During the drain down, RHR amps and discharge pressure begin fluctuating

erratically.

RCS temperature has risen from 121 degrees F to 127 degrees F.

The crew enters 1-AP-11, Loss of RHR, and stops the RCS drain down.

Which ONE (1) of the following describes the next actions that will be required in

accordance with 1-AP-11?

A. Reduce RHR flow to minimum required to maintain RCS temperature and/or raise

RCS level to ensure at least 10 inches above the Hot Leg centerline.

B. Reduce RHR flow to minimum required to maintain RCS temperature and maximize

CC flow to inservice RHR heat exchangers.

C. Stop RHR Pump 1A and initiate Attachment 8, Reflux Boiling to control RCS

temperature.

D. Stop RHR Pump 1A and immediately start RHR Pump 1B, then verify that RCS

temperature stabilizes.

75

North Anna Power Station

2008 SRO Exam

76.

Initial conditions:

• A spurious Turbine Runback occurred on Unit 1.

• Tave was 5.5 degrees F higher than Tref and rising.

Control Bank D rods were inserting at the required rate.

Current conditions:

• Reactor power 580/0.

• Steam Dumps closed.

• Rod Motion stopped.

• Tave and Tref are approximately equal and stable.

• Control Bank D Group Step counters are at 170 steps.

• All Control Bank D rods indicate approximately 170 steps, with the exception of

Rod H-8, which is at 184 steps.

A blown fuse is the cause of the mispositioned rod.

Which ONE of the following idenifies (1) the rod speed of rod H-8 PRIOR to the blown

fuse and (2) whether or not the H-8 control rod is operable?

A. 72 SPM ; H-8 is OPERABLE.

B. 64 SPM ; H-8 is INOPERABLE.

C. 72 SPM ; H-8 is INOPERABLE.

D. 64 SPM ; H-8 is OPERABLE.

76

North Anna Power Station

2008 SRO Exam

77.

Given the following:

Unit 1 is in Mode 6 with refueling cavity level at 289' 10".

Upper internals have been removed.

1A RHR pump is in operation with 1B RHR pump in standby.

• An electrical fault on 1H bus causes a loss of the bus.

Which ONE of the following describes the action required, and the basis for the action

in accordance with Technical Specifications?

A. Immediately initiate action to establish >/= 23 feet of water above the top of the

reactor vessel flange;

provides acceptable results in conjunction with actions to initiate containment

closure to limit radioactive release to the environment.

B. Immediately suspend any RCS makeup from sources with a boron concentration

less than that required by TS 3.9.1;

ensures that there will be NO RCS makeup without adequate mixing.

C. Immediately initiate action to establish >/= 23 feet of water above the top of the

reactor vessel flange;

ability to remove decay heat and ensure mixing of borated RCS water is degraded.

D. Immediately suspend any RCS makeup from sources with a boron concentration

less than that required by TS 3.9.1;

ensures that if RCS boron concentration is reduced due to RCS makeup,

acceptable margin for subcritical operation is maintained.

77

North Anna Power Station

2008 SRO Exam

78.

Given the following:

• Unit 1 has been at 100 % power for 12 months.

• The following alarms are received approximately 5 minutes apart:

• 1J-D7, ACCUM 1A-1B-1C HI-LO LEVEL

1J-D8, ACCUM 1A-1B-1C HI-LO PRESS

• SI Accumulator levels and pressures are as follows:

Level Pressure

1A 67% 655 psig

18 72°Al 670 psig

1C 590/0 610 psig

Given these levels and pressures which ONE of the following predicts the reason for

the alarms AND identifies the status of accumulator operability in accordance with

Technical Specifications?

A. Check valve leakage is occurring;

SI accumulators are all operable.

B. Vent valve leakage is occurring;

one SI accumulator is inoperable.

C. Vent valve leakage is occurring;

SI accumulators are all operable.

D. Check valve leakage is occurring;

one SI accumulator is inoperable.

78

North Anna Power Station

2008 SRO Exam

79.

The following conditions exist:

• Unit 1 is at 100% power.

• 1-SI-P-1 B, "B" Low Head Safety Injection Pump is tagged out for maintenance.

• The 1H Emergency Diesel Generator (EDG) is subsequently determined to be

inoperable due to the discovery that non-qualified parts were used the last time

maintenance was performed on the EDG.

Based on these plant conditions, which ONE of the following identifies the equipment

that must be declared inoperable AND the required action in accordance with

Technical Specifications?

A. Declare the 1H EDG and 1-SI-P-1A, "A" Low Head Safety Injection Pump

inoperable;

Verify correct breaker alignment and indicated power availability for each required

offsite circuit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

B. Declare the 1H EDG inoperable; 1-SI-P-1A, "A" Low Head Safety Injection Pump

remains operable;

Verify correct breaker alignment and indicated power availability for each required

offsite circuit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

c. Declare the 1H EDG and 1-SI-P-1A, "A" Low Head Safety Injection Pump

inoperable;

Verify correct breaker alignment and indicated power availability for each required

offsite circuit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

D. Declare ONLY the 1H EDG inoperable; 1-SI-P-1A, "A" Low Head Safety Injection

Pump remains operable;

Verify correct breaker alignment and indicated power availability for each required

offsite circuit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

79

North Anna Power Station

2008 SRO Exam

80.

Given the following:

• Both Units were initially at 100 DA> power with 1J EDG OOS.

• Operators began Unit 1 shutdown due to a steam leak inside Containment on the

BSG.

• 1-RC-PT-1444 failed high causing the associated PORV, 1-RC-PCV-1455C to

open.

• Attempts to close PORV 1-RC-PCV-1455C and the associated PORV Block

Valve, 1-RC-MOV-1536 were unsuccessful and operators tripped the Unit.

• The following occurred immediately following the reactor trip:

• B SG failed catastrophically inside Containment

• Off-site power was lost

• Low Head SI pump 1-SI-P-1A tripped on overcurrent during startup.

Power Supply estimates off-site power restoration in 1.5 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Which ONE of the following describes the procedure the operators will transition to

when leaving 1-E-0, Reactor Trip or Safety Injection, AND how power is required to be

restored to 1J Emergency Bus?

A. 1-E-1, Loss of Reactor or Secondary Coolant;

restore power to 1J Emergency Bus when off-site power becomes available.

B. 1-E-1, Loss of Reactor or Secondary Coolant;

restore power to 1J Emergency Bus using the SBO diesel.

C. 1-E-2, Faulted Steam Generator Isolation;

restore power to 1J Emergency Bus when off-site power becomes available.

D. 1-E-2, Faulted Steam Generator Isolation;

restore power to 1J Emergency Bus using the SBO diesel.

80

North Anna Power Station

2008 SRO Exam

81.

Unit 1 is at 100% power.

1K-G1, SFGDS PROT SYS TR A TROUBLE has been alarming intermittently.

Instrument Department has determined a 48VDC power supply in Train A is degrading

and will most likely fail completely in the near future.

Which ONE of the following describes the correct response?

Reference Provided

A. Online replacement of the power supply is permitted;

following power supply replacement the Reactor Trip Bypass Breaker may be

closed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to perform 1-PT-36.1A, Train A Reactor Protection and

ESF Logic Actuation Logic Test.

B. Online replacement of the power supply is NOT permitted;

be in Hot Standby within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

C. Online replacement of the power supply is NOT permitted;

be in Hot Standby within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

D. Online replacement of the power supply is permitted;

following power supply replacement the Reactor Trip Bypass Breaker may be

closed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to perform 1-PT-36.1A, Train A Reactor Protection and

ESF Logic Actuation Logic Test.

81

North Anna Power Station

2008 SRO Exam

82.

Given the following:

• A LOCA is in progress on Unit 1.

• All RCPs are stopped.

• RVLIS Full Range is 27°~.

Core Exit TCs are reading 1250 degrees F.

• ALL SG NR levels are OFF-SCALE low.

• NO source of SG feed has been established.

NO source of ECCS has been established.

• The crew has attempted secondary depressurization in accordance with FR-C.1,

Response to Inadequate Core Cooling, but the attempt was ineffective.

Given these plant conditions, which ONE of the following identifies the procedure

action to mitigate this event?

A. Immediately transition to SACRG-1, Severe Accident Control Room Guideline Initial

Response, BEFORE opening PZR PORVs and Block Valves, and other RCS Vent

Paths.

B. Remain in FR-C.1, open PZR PORVs and Block Valves, and other RCS Vent

Paths.

C. Open PZR PORVs and Block Valves, and other RCS Vent Paths and THEN

transition to SACRG-1, Severe Accident Control Room Guideline Initial Response.

D. Remain in FR-C.1, start one RCP in an idle loop.

82

North Anna Power Station

2008 SRO Exam

83.

Given the following:

Unit 1 is in Mode 5 with RCS draindown in progress.

• The crew observes 1B RHR Pump discharge flow and motor amps

oscillating.

The crew isolates known RCS drain paths and maximizes Charging flow.

RCS level continues to decrease.

• Annunciator E-A8, RHR SYSTEM La FLOW, is alarming intermittently.

Containment sump pumps are running continuously.

• An operator leaving Containment reports leakage observed from the PZR Surge

Line.

Which ONE of the following describes the procedural guidance that will mitigate these

plant conditions?

A. Perform 1-AP-17, Shutdown LOCA; initiate Attachment 8, Hot Leg Injection.

B. Perform 1-AP-11, Loss of RHR, Attachment 2, Minimum RCS Level for Indicated

Flow.

C. Perform 1-AP-17, Shutdown LOCA, Attachment 7, Cold Leg Injection.

D. Perform 1-AP-11, Loss of RHR, Attachment 3, Determining Acceptable RHR Flow

Reductions.

83

North Anna Power Station

2008 SRO Exam

84.

• Unit 1 is at 1000/0 power. Unit 2 is in Mode 5.

Unit 1 and 2 CC systems are split.

• The OATC reports the following alarms and indications:

• 1G-E8, CaMP COOL PP 1B AUTO TRIP

• 1G-B3, CC HX 1A-1B CC OUTLET La FLOW

1G-C3, CC HX OUTLET La PRESS

1C-C4, RCP 1A-B-C CC THERM BARR HI/La FLOW

• 1A-E6, RCP 1B VIBRATION ALERT/DANGER

RCP Thermal Barrier Heat Exchanger flow indicators all read 0 GPM.

• RCP Motor Bearing temperatures are 146°F and rising at 5°F per minute.

• 1B RCP Vibration readings:

• 2-3 mils Seismic

8-10 mils Proximity

Given these plant conditions, which ONE of the following identifies the required

procedure AND also identifies the Design Basis of the CC System in accordance with

the Technical Specification Bases?

A. 1-AP-15, Loss of Component Cooling;

TWO CC Subsystems are sufficient to accomplish a fast cooldown of one unit while

maintaining normal loads on the other unit.

B. 1-E-0, Reactor Trip or Safety Injection;

THREE CC Subsystems are sufficient to accomplish a fast cooldown of one unit

while maintaining normal loads on the other unit.

C. 1-AP-15, Loss of Component Cooling;

THREE CC Subsystems are sufficient to accomplish a fast cooldown of one unit

while maintaining normal loads on the other unit.

D. 1-E-0, Reactor Trip or Safety Injection;

TWO CC Subsystems are sufficient to accomplish a fast cooldown of one unit while

maintaining normal loads on the other unit.

84

North Anna Power Station

2008 SRO Exam

85.

Given the following:

Unit 1 is in Mode 3 during a plant cooldown.

Chemistry sample of the Quench Spray System Chemical Addition Tank

determines that NaOH concentration is 10% by weight.

Chemical Addition Tank contains approximately 5510 gallons.

• 1-QS-P-1 B, Quench Spray Pump 1B, is out of service.

Which ONE of the following describes how the current status of the Quench

Spray/Chemical Addition Tank affects the plant during a Design Basis LOCA in

accordance with the Technical Specification Bases?

A. Chemical Addition Tank NaOH concentration (10 % by weight) is outside of limits

which affects the pH of the resultant Containment sump water solution and the

ability to effectively remove Iodine following a DBA LOCA.

B. Chemical Addition Tank volume (5510 gallons) is outside of limits which affects the

ability to maintain Containment within design pressure limits and affects the ability

to maintain Iodine at acceptable levels following a DBA LOCA.

C. Inoperability of 1-QS-P-1 B will result in a Containment peak temperature higher

than the value calculated in the accident analysis for a DBA LOCA.

D. Inoperability of 1-QS-P-1 B will result in a Containment peak pressure higher than

the value calculated in the accident analysis for a DBA LOCA.

85

North Anna Power Station

2008 SRO Exam

86.

Given the following:

• Unit 1 core off-load in progress.

• The 3 most recently off-loaded irradiated fuel assemblies are stored as follows:

Assembly(En rich ment) Burnup Location

Assembly A (4.6%) 30,000 MWD/MTU Non-Matrix location

Assembly B (3.20/0) 30,000 MWD/MTU Low-Reactivity 5X5 matrix

Assembly C (3.2%) 20,000 MWD/MTU Low Reactivity 5X5 matrix

Which ONE of the following identifies the minimum required action in accordance with

Technical Specification 3.7.18, Spent Fuel Pool Storage AND the Bases for the action?

Reference Provided

A. ONLY ONE fuel assembly is required to be moved;

ensures that Keff will remain <0.95 for all postulated accidents assuming that the

soluble boron in the Spent Fuel Pool is at the TS 3.7.17, Fuel Storage Pool Boron

Concentration, minimum limit.

B. TWO fuel assemblies are required to be moved;

ensures that Keff will remain <0.95 for all postulated accidents assuming that the

soluble boron in the Spent Fuel Pool is at the TS 3.7.17, Fuel Storage Pool Boron

Concentration, minimum limit.

C. TWO fuel assembly are required to be moved;

ensures that Keff will remain <0.95 for all postulated accidents assuming NO

soluble boron in the Spent Fuel Pool.

D. ONLY ONE fuel assembly is required to be moved;

ensures that Keff will remain <0.95 for all postulated accidents assuming NO

soluble boron in the Spent Fuel Pool.

86

North Anna Power Station

2008 SRO Exam

87.

• Unit 1 has experienced a Steam Generator Tube Rupture.

• The crew is performing 1-ES-3.1, Post-SGTR Cooldown Using Backfill.

Core Exit TCs are 345°F

RCS Hot Leg Temperatures are 335°F

RCS Wide Range Pressure is 600 psig

1C RCP is running and the crew has commenced depressurizing the RCS.

Given the above plant conditions, which ONE of the following identifies the parameter

that will determine when the depressurization will be stopped, AND also provides the

Basis for controlling the rate of depressurization?

A. RCP number 1 seal differential pressure;

control the depressurization rate to ensure pressure control is not lost.

B. RCS Subcooling based on Core Exit TCs;

control the depressurization rate to ensure pressure control is not lost.

C. RCS Subcooling based on Core Exit TCs;

control the depressurization rate to minimize head voiding.

D. RCP number 1 seal differential pressure;

control the depressurization rate to minimize head voiding.

87

North Anna Power Station

2008 SRO Exam

88.

Given the following:

Unit 1 is at 100% power.

The following alarm is received:

• 1B-A5, CW PP 1A-1B-1C-1DAUTO TRIP

• CW Pump 1B motor indicates 0 amps

CW Pumps 1A, 1C, and 10 motors indicate 300-310 amps.

Condenser pressure is 3 inches Hg absolute and degrading slowly.

Which ONE of the following describes the mitigation strategy for the event in progress?

A. Perform 1-AP-13, Loss of One or More Circulating Water Pumps; reduce CW Pump

amps to prevent motor damage.

Perform 1-AP-14, Low Condenser Vacuum; guidance for estimating RCS boration

flow rates during a load reduction is NOT provided in 1-AP-14.

B. Perform 1-AP-13, Loss of One or More Circulating Water Pumps; contact HP to

determine if liquid waste release must be secured.

Perform 1-AP-14, Low Condenser Vacuum; guidance for estimating RCS boration

flow rates during a load reduction is NOT provided in 1-AP-14.

C. Perform 1-AP-13, Loss of One or More Circulating Water Pumps; contact HP to

determine if liquid waste release must be secured.

Perform 1-AP-14, Low Condenser Vacuum; guidance for estimating RCS boration

flow rates during a load reduction is provided in 1-AP-14.

D. Perform 1-AP-13, Loss of One or More Circulating Water Pumps; reduce CW Pump

amps to prevent motor damage.

Perform 1-AP-14, Low Condenser Vacuum; guidance for estimating RCS boration

flow rates during a load reduction is provided in 1-AP-14.

88

North Anna Power Station

2008 SRO Exam

89.

Given the following:

• Unit 1 is at 100 % power.

• 120 VAC Vital Bus Inverter 1-11 failed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago.

• 120 VAC Vital Bus 1-11 is being powered from its associated constant voltage

source transformer.

Which ONE of the following identifies the minimum Technical Specification LCOs that

contain required actions for these plant conditions, including the required

compensatory measures in accordance with the Technical Specification Bases?

Reference Provided

A. TS 3.8.7, Inverters - Operating, Limiting Action is required to be entered;

TS 3.8.9, Distribution Systems - Operating, Limiting Action is NOT required to be

entered;

Concurrent planned EDG maintenance is NOT allowed.

B. BOTH TS 3.8.9, Distribution Systems - Operating AND TS 3.8.7, Inverters -

Operating Limiting Actions are required to be entered;

Concurrent planned EDG maintenance is NOT allowed.

C. TS 3.8.9, Distribution Systems - Operating, Limiting Action is required to be

entered;

TS 3.8.7, Inverters - Operating, Limiting Action is NOT required to be entered;

Concurrent planned EDG maintenance can be performed.

D. BOTH TS 3.8.9, Distribution Systems - Operating AND TS 3.8.7, Inverters -

Operating Limiting Actions are required to be entered;

Concurrent planned EDG maintenance can be performed.

89

North Anna Power Station

2008 SRO Exam

90.

Given the following:

1-FR-H.1, Response to Loss of Secondary Heat Sink, is in progress.

• Attempts to establish Aux Feedwater flow are unsuccessful.

RCS Bleed and Feed has NOT been initiated.

• Main Feedwater flow has just been established and SG levels are as follows:

'1A' 40 % wide range and rising

• '1 B' 40% wide range and stable

• '1 C' 29 % wide range and lowering

Core exit Tes are stable.

• Containment pressure is 19.2 psia.

Which ONE (1) of the following describes the appropriate operator action?

A. Return to procedure and step in effect and continue efforts to establish AFW flow.

B. Perform Steps 14 through 23 of 1-FR-H.1 to initiate RCS bleed and feed.

C. Remain in 1-FR-H.1 until Core Exit TCs indicate a decreasing trend.

D. Remain in 1-FR-H.1 until all SG wide range levels indicate an increasing trend.

90

North Anna Power Station

2008 SRO Exam

91.

Given the following:

The Unit is in Mode 6.

Rod Unlatching is in progress.

Manipulator Crane radiation monitor, 1-RM-RMS-162, suddenly pegs high.

The following alarms are received:

• 1K-D2, RAD MONITOR SYSTEM HI RAD LEVEL

• 1K-D3, RAD MONITOR SYSTEM HI-HI RAD LEVEL

HP has confirmed that radiation levels on the refueling deck are normal and Operations

has declared 1-RM-RMS-162 inoperable.

Which ONE of the following describes the required actions in accordance with 1-AP-5,

Unit 1 Radiation Monitoring System?

A. Verify Control Room Bottled Air dump;

Core alterations may continue with 1-RM-RMS-162 inoperable. Continuous HP

coverage is required.

B. Verify Containment Ventilation Isolation;

Core alterations may NOT continue with 1-RM-RMS-162 inoperable.

C. Verify Control Room Bottled Air dump;

Core alterations may NOT continue with 1-RM-RMS-162 inoperable.

D. Verify Containment Ventilation Isolation;

Core alterations may continue with 1-RM-RMS-162 inoperable. Continuous HP

coverage is required.

91

North Anna Power Station

2008 SRO Exam

92.

Given the following:

• Both units are at 100 % power.

• 1-SW-P-1A and 1-SW-P-1 B are running.

• 2-SW-P-1 B is OOS.

1-SW-P-1 B trips and 2-SW-P-1A is started.

Which ONE of the following describes the Technical Specification action required, and

the Bases for the action?

A. Restore the Service Water Loop to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />;

Ensures design flows to the RS Heat Exchangers are achieved following a LOCA

with ONE additional failure.

B. Throttle Service Water to CC Heat Exchangers within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />;

Ensures design flows to the RS Heat Exchangers are achieved following a LOCA

with -NO additional failures.

C. Restore the Service Water Loop to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />;

Ensures design flows to the RS Heat Exchangers are achieved following a LOCA

with NO additional failures.

D. Throttle Service Water to CC Heat Exchangers within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />;

Ensures design flows to the RS Heat Exchangers are achieved following a LOCA

with ONE additional failure.

92

North Anna Power Station

2008 SRO Exam

93.

Given the following:

• A reactor trip has occurred on Unit 1.

• Following transition to 1-ES-0.1, Reactor Trip Response, the STA reports all

CSF status trees GREEN with the EXCEPTION of Heat Sink, which is YELLOW.

• The following SG conditions are observed:

• A SG pressure 1050 psig and stable.

• A SG level 25% NR and rising.

• B SG pressure 1150 psig and stable.

• B SG level 92% NR and rising.

• C SG pressure 1050 psig and stable.

C SG level 20% NR and rising.

• B MSIV indicates CLOSED.

• AFW flow is 160 GPM to each SG.

• The crew determines that entry to a Yellow Path procedure will help mitigate the

event.

Which ONE of the following describes the mitigation strategy used to restore the Heat

Sink Critical Safety Function to GREEN?

A. Perform 1-FR-H.3, Response to Steam Generator High Level; isolate AFW flow to

B SG. Initiate blowdown from B SG and DO NOT dump steam from B SG.

B. Perform 1-FR-H.2, Response to Steam Generator Overpressure; Isolate AFW flow

to B SG and do not restore AFW flow until a steam release path is established.

C. Perform 1-FR-H.2, Response to Steam Generator Overpressure; Verify Main

Feedwater Isolation. Dump steam from B SG to reduce Hot Leg temperatures.

D. Perform 1-FR-H.3, Response to Steam Generator High Level; Verify Main

Feedwater Isolation. Dump steam from B SG to reduce Hot Leg temperatures and

initiate blowdown from B SG.

93

North Anna Power Station

2008 SRO Exam

94.

Given the following:

• The date is 6/5/2008.

• Both Units are in Mode 1.

• Shift complement is at MINIMUM allowed by Technical Specifications.

• One of the Reactor Operators becomes ill and must be transported to the

hospital.

• TWO potential replacements are identified for call-in.

• BOTH replacements have been assigned to OPS Support for the last year.

The last times they were on shift are as follows:

Operator A Operator B

• 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on March 24 BOP 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on March 21 RO

• 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on February 23 BOP 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on March 20 RO

• 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on February 22 BOP 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on March 19 RO

• 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on January 19 BOP 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on March 18 RO

• 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on January 18 BOP 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> on January 5 WCC

Which ONE of the following identifies the Technical Specification requirement to

replace the Reactor Operator, and which operator will be selected as the replacement?

A. Action must be taken to ensure the Reactor Operator is replaced within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />;

Operator B will be selected.

B. Action must be taken to ensure the Reactor Operator is replaced within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />;

Operator A will be selected.

C. Action must be taken to ensure the Reactor Operator is replaced within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />;

Operator B will be selected.

D. Action must be taken to ensure the Reactor Operator is replaced within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />;

Operator A will be selected.

94

North Anna Power Station

2008 SRO Exam

95.

Given the following:

• The Shift Manager is in the control room discussing an upcoming evolution with

the Unit 2 Unit Supervisor.

• The Unit 1 Unit Supervisor is on a plant walkdown when the following events

occur:

Unit 1 experienced a spurious Turbine runback.

• While stabilizing the unit at 65% power, a turbine trip occurred.

The Unit 1 reactor did NOT trip, either automatically or manually from the

control room.

PZR PORV, 1-RC-PCV-1455C, is stuck OPEN.

• The associated block valve, 1-RC-MOV-1536, did NOT close when the

OATC took the control switch to close.

Safety Injection is actuated.

The Unit 1 Unit Supervisor was injured while returning to the control room

and needs medical assistance in the Turbine Building.

In accordance with DNAP-0509, Dominion Nuclear Procedure Adherence and Usage,

which ONE of the following identifies who will be the EOP 'Reader,' AND also identifies

the required EOP flowpath upon exiting 1-FR-S.1, Response to Nuclear Power

Generation/ATWS?

A. Unit 2 Unit Supervisor;

Go to 1-E-1, Loss of Reactor or Secondary Coolant.

B. Unit 2 Unit Supervisor;

Return to 1-E-O, Reactor Trip or Safety Injection.

C. Shift Manager;

Go to 1-E-1, Loss of Reactor or Secondary Coolant.

D. Shift Manager;

Return to 1-E-O, Reactor Trip or Safety Injection.

95

North Anna Power Station

2008 SRO Exam

96.

Given the following:

• Unit 1 is operating at 100 % power.

• The following alarm is received several times in a 10 minute period:

1D-H5, HIGH CAPACITY S/G BLOWDOWN TROUBLE

Local indication at the High Capacity S/G Blowdown Control Panel is normal.

• The Instrument Technician investigating the alarm determines that the

comparator card for the annunciator is failing.

• A replacement comparator card is unavailable and assistance has been

requested from Engineering.

• To restore functionality of the alarm in the interim a jumper must be installed.

Which ONE of the following procedures will govern the installation of the jumper, and

who, by title, must provide FINAL approval of the jumper?

A. OP-NA-200-1 001, Equipment Clearance Process; FSRC (formerly known as

SNSOC).

B. VPAP-1403, Temporary Modifications; Shift Manager.

C. OP-NA-200-1 001, Equipment Clearance Process; Shift Manager.

D. VPAP-1403, Temporary Modifications; FSRC (formerly known as SNSOC).

96

North Anna Power Station

2008 SRO Exam

97.

Given the following:

• A Unit 1 RCS heatup is in progress.

• RCS Tave is 342°F.

1H Emergency Diesel Generator is declared INOPERABLE due to failure of the

Shutdown Relay.

curren t

Which ONE of the following identifies (1) thefOPERATIONAL MODE and (2) the

Technical Specification requirements to enter the next higher Mode?

A. (1) Mode 3

(2) Change to Mode 2 may be performed provided the TS 3.8.1, AC Sources -

Operating, Action Statements for 1H EDG inoperability are satisfied. Risk

evaluation and NRC approval is NOT required.

B. (1) Mode 4

(2) Change to Mode 3 may be NOT performed without a risk evaluation and

approval from the NRC .

.C. (1) Mode 3

(2) Change to Mode 2 may be NOT performed without a risk evaluation and

approval from the NRC.

D. (1) Mode 4

(2) Change to Mode 3 may be performed provided the TS 3.8.1, AC Sources -

Operating, Action Statements for 1H EDG inoperability are satisfied. Risk

evaluation and NRC approval is NOT required.

97

North Anna Power Station

2008 SRO Exam

98.

Which ONE of the following describes the Release Permit approval process in

accordance with 0-OP-23.3, Waste Gas Decay Tanks & Waste Gas Diaphram

Compressors, AND also identifies the Technical Specification Bases for the maximum

radioactivity content in each gas storage tank?

A. Operations initiates the release request and Health Physics (HP) authorizes the

release permit;

an individual at the exclusion boundary will not exceed 0.5 rem total body exposure

in the event of an uncontrolled release of a tanks contents.

B. Chemistry initiates the release request and Health Physics (HP) authorizes the

release permit;

an individual at the exclusion boundary will not exceed 0.5 rem total body exposure

in the event of an uncontrolled release of a tanks contents.

C. Chemistry initiates the release request and Health Physics (HP) authorizes the

release permit;

an individual at the exclusion boundary will not exceed 0.1 rem total body exposure

in the event of an uncontrolled release of a tanks contents.

D. Operations initiates the release request and Health Physics (HP) authorizes the

release permit;

an individual at the exclusion boundary will not exceed 0.1 rem total body exposure

in the event of an uncontrolled release of a tanks contents.

98

North Anna Power Station

2008 SRO Exam

99.

Initial conditions:

• Unit 1 is in Mode 3 shutting down for a scheduled refueling.

• A fire is in progress in the Motor Driven AFW Pump House.

The Fire Brigade is at the scene.

Current conditions:

• The fire was burning for 12 minutes and is now extinguished.

• The 1B MDAFW Pump motor was destroyed by the fire.

Which ONE of the following describes the impact on Safe Shutdown Functions, and

whether E-Plan action is required in accordance with O-FCA-O, Fire Protection -

Operations Response?

A. The Reactor Heat Removal function required to get from Mode 4 to Mode 5 is

affected;

EPIP 1.01, Emergency Manager Controlling Procedure is NOT required to be

implemented.

B. The Reactor Heat Removal function required to get to Mode 4 is affected;

EPIP 1.01, Emergency Manager Controlling Procedure is required to be

implemented.

C. The Reactor Heat Removal function required to get to Mode 4 is affected;

EPIP 1.01, Emergency Manager Controlling Procedure is NOT required to be

implemented.

D. The Reactor Heat Removal function required to get from Mode 4 to Mode 5 is

affected;

EPIP 1.01, Emergency Manager Controlling Procedure is required to be

implemented.

99

North Anna Power Station

2008 SRO Exam

100.

• A LOCA has occurred on Unit 1.

• RCS pressure indicates 190 psig and stable.

• RCS temperature is 260 degrees F and lowering.

Containment pressure is 27 psia.

Low Head SI flow indicates 1200 gpm on each train.

• All equipment is operating as designed.

• The crew has just entered 1-ES-1.3, Transfer to Cold Leg Recirculation.

• The STA reports a RED path on the INTEGRITY CSF Status Tree.

Given these plant conditions, which ONE of the following describes the hierarchy of

requried procedure actions?

A. Remain in 1-ES-1.3 until transfer to Cold Leg Recirculation is complete through

step 8;

Transition to 1-FR-P.1 and verify that RCS pressure is below the Low Head SI

pump shutoff head, then return to 1-ES-1.3.

B. Remain in 1-ES-1.3 until transfer to Cold Leg Recirculation is complete through

step 8;

Transition to 1-FR-P.1 and perform the actions to stop the RCS cooldown, then

return to 1-ES-1.3.

C. Immediately transition to 1-FR-P.1, Response to Imminent Pressurized Thermal

Shock;

Verify that RCS pressure is below the Low Head SI pump shutoff head and then

return to 1-ES-1.3.

D. Immediately transition to 1-FR-P.1, Response to Imminent Pressurized Thermal

Shock;

Perform the actions of 1-FR-P.1 to stop the RCS cooldown and then return to

1-ES-1.3.

100

RTS Instrumentation

3.3.1

3.3 INSTRUMENTATION

3.3.1 Reactor Trip System (RTS) Instrumentation

LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1

shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1-1.

ACTIONS

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more Functions A.1 Enter the Condition Immediately

with one or more referenced in

required channels or Table 3.3.1-1 for the

trains inoperable. channel (s) or

train(s).

B. One Manual Reactor B.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

Trip channel OPERABLE status.

inoperable.

-OR

B.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />

C. One channel or train C.1 Restore channel or 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

inoperable. train to OPERABLE

status.

-

OR

C.2.1 Initiate action to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

fully insert all rods.

-AND (continued)

North Anna Units 1 and 2 3.3.1-1 Amendment 231/212

RTS Instrumentation

3.3.1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

C. (cont i nued) C.2.2 Place the Rod Control 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br />

System in a condition

incapable of rod

withdrawal.

D. One Power Range ------------NOTE-------------

Neutron Flux-High The inoperable channel may be

channel inoperable. bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

for surveillance testing and

setpoint adjustment of other

channels.

0.1.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

AND

0.1.2 Reduce THERMAL POWER 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />

to ~ 75% RTP.

OR

0.2.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

AND

---

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

Only required to be performed

when the Power Range Neutron

Flux input to QPTR is

inoperable.

0.2.2 Perform SR 3.2.4.2. Once per

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

OR

0.3 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />

North Anna Units 1 and 2 3.3.1-2 Amendment 231/212

RTS Instrumentation

3.3.1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

E. One channel ------------NOTE-------------

inoperable. The inoperable channel may be

bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

for surveillance testing of

other channels.

---

E.1 Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

OR

-

E.2 Be in MODE 3. 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />

F. One Intermediate Range F.1 Reduce THERMAL POWER 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

Neutron Flux channel to < P-6.

inoperable.

-OR

F.2 Increase THERMAL POWER 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

to > P-10.

G. Two Intermediate Range ------------NOTE-------------

Neutron Flux channels Limited plant cool down or

inoperable. boron dilution is allowed

provided the change is

accounted for in the

calculated SDM.

---

G.1 Suspend operations Immediately

involving positive

reactivity additions.

-

AND

G.2 Reduce THERMAL POWER 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

to < P-6.

North Anna Units 1 and 2 3.3.1-3 Amendment 231/212

RTS Instrumentation

3.3.1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

H. One Source Range ------------NOTE-------------

Neutron Flux channel Limited plant cooldown or

inoperable. boron dilution is allowed

provided the change is

accounted for in the

calculated SDM.

---

H.1 Suspend operations Immediately

involving positive

reactivity additions.

I. Two Source Range I .1 Open Reactor Trip Immediately

Neutron Flux channels Breakers (RTBs).

inoperable.

J. One Source Range J.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

Neutron Flux channel OPERABLE status.

inoperable.

OR

-

J.2.1 Initiate action to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

fully insert all rods.

AND

-

J.2.2 Place the Rod Control 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br />

System in a condition

incapable of rod

withdrawal.

North Anna Units 1 and 2 3.3.1-4 Amendment 231/212

RTS Instrumentation

3.3.1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

K. Required Source Range ------------NOTE-------------

Neutron Flux channel Plant temperature changes are

inoperable. allowed provided the

temperature change is

accounted for in the

calculated SDM.

---

K.l Suspend operations Immediately

involving positive

reactivity additions.

-AND

K.2 Perform SR 3.1.1.1. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

AND

-

Once per

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

thereafter

L. One channel ------------NOTE-------------

inoperable. The inoperable channel may be

bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

for surveillance testing of

other channels.

---

L.l Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

OR

-

L.2 Reduce THERMAL POWER 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />

to < P-7.

North Anna Units 1 and 2 3.3.1-5 Amendment 231/212

RTS Instrumentation

3.3.1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

M. One Reactor Coolant ------------NOTE-------------

Pump Breaker Position The inoperable channel may be

channel inoperable. bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

for surveillance testing of

other channels.

M.l Restore channel to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

OPERABLE status.

OR

M.2 Reduce THERMAL POWER 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />

to < P-7.

N. One Turbine Trip ------------NOTE-------------

channel inoperable. The inoperable channel may be

bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

for surveillance testing of

other channels.

N.l Place channel in trip. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

OR

N.2 Reduce THERMAL POWER 76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br />

to < P-8.

O. One train inoperable. ------------NOTE-------------

One train may be bypassed for

up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for

surveillance testing provided

the other train is OPERABLE.

0.1 Restore train to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

OPERABLE status.

OR

0.2 Be in MODE 3. 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />

North Anna Units 1 and 2 3.3.1-6 Amendment 231/212

RTS Instrumentation

3.3.1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

P. One RTB train ------------NOTES------------

inoperable. 1. One train may be bypassed

for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for

surveillance testing,

provided the other train

is OPERABLE.

2. One RTB may be bypassed

for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for

maintenance on

undervoltage or shunt trip

mechanisms, provided the

other train is OPERABLE.

3. One RTB train may be

bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

for concurrent

surveillance testing of

the RTB and automatic trip

logic, provided the other

train is OPERABLE.

---

P.1 Restore train to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

OPERABLE status.

OR

-

P.2 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />

Q. One or more channels Q.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

inoperable. required state for

existing unit

conditions.

OR

-

Q.2 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />

North Anna Units 1 and 2 3.3.1-7 Amendment 231/212

RTS Instrumentation

3.3.1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

R. One or more channels R.l Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

inoperable. required state for

existing unit

conditions.

-OR

R.2 Be in MODE 2. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />

S. One trip mechanism S.1 Restore inoperable 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

inoperable for one trip mechanism to

RTB. OPERABLE status.

-

OR

S.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br />

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.

SURVEILLANCE FREQUENCY

SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

SR 3.3.1.2 -------------------NOTE--------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

after THERMAL POWER is ~ 15% RTP.

Compare results of calorimetric heat 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

balance calculation to power range channel

output. Adjust power range output if

calorimetric heat balance calculation

result exceeds power range channel output

by more than +2% RTP.

North Anna Units 1 and 2 3.3.1-8 Amendment 231/212

RTS Instrumentation

3.3.1

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.3.1.3 -------------------NOTE--------------------

Not required to be performed until 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

after THERMAL POWER is ~ 15% RTP.

Compare results of the incore detector 31 effective

measurements to Nuclear Instrumentation full power days

System (NIS) AFD. Adjust NIS channel if (EFPD)

absolute difference is ~ 3%.

SR 3.3.1.4 -------------------NOTE--------------------

This Surveillance must be performed on the

reactor trip bypass breaker immediately

after placing the bypass breaker in

service.

Perform TADOT. 31 days on a

STAGGERED TEST

BASIS

SR 3.3.1.5 Perform ACTUATION LOGIC TEST. 31 days on a

STAGGERED TEST

BASIS

SR 3.3.1.6 -------------------NOTE--------------------

Verification of setpoint is not required.

Perform TADOT. 92 days

SR 3.3.1.7 -------------------NOTE-------------------

Not required to be performed for source

range instrumentation prior to entering

MODE 3 from MODE 2 until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after

entry into MODE 3.

Perform COT. 92 days

North Anna Units 1 and 2 3.3.1-9 Amendment 231/212

RTS Instrumentation

3.3.1

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.3.1.8 -------------------NOTE-------------------- -----NOTE-----

This Surveillance shall include Only required

verification that interlocks P-6 and P-I0 when not

are in their required state for existing performed wi thi n

unit conditions. previous 92 days

Perform COT. Pri or to reactor

startup

AND

Four hours after

reducing power

below P-6 for

source range

instrumentation

AND

Twelve hours

after reducing

power below P-I0

for power and

intermediate

range

instrumentation

AND

Once per 92 days

thereafter

SR 3.3.1.9 -------------------NOTES-------------------

1. Adjust NIS channel if absolute

difference ~ 3%.

2. Not required to be performed until

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after THERMAL POWER is

~ 50% RTP.

Compare results of the excore channels to 92 EFPD

incore detector measurements.

North Anna Units 1 and 2 3.3.1-10 Amendment 231/212

RTS Instrumentation

3.3.1

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.3.1.10 -------------------NOTE--------------------

This Surveillance shall include

verification that the time constants are

adjusted to the prescribed values.

Perform CHANNEL CALIBRATION. 18 months

SR 3.3.1.11 -------------------NOTE--------------------

Neutron detectors are excluded from CHANNEL

CALIBRATION.

Perform CHANNEL CALIBRATION. 18 months

SR 3.3.1.12 Perform CHANNEL CALIBRATION. 18 months

SR 3.3.1.13 Perform COT. 18 months

SR 3.3.1.14 -------------------NOTE--------------------

Verification of setpoint is not required.

Perform TADOT. 18 months

SR 3.3.1.15 -------------------NOTE--------------------

Verification of setpoint is not required.

Perform TADOT. Prior to

exceeding the

P-8 interlock

whenever the

unit has been in

MODE 3, i f not

performed wi thi n

the previous

31 days

North Anna Units 1 and 2 3.3.1-11 Amendment 231/212

RTS Instrumentation

3.3.1

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.3.1.16 -------------------NOTE--------------------

Neutron detectors are excluded from

response time testing.

Verify RTS RESPONSE TIME is within limits. 18 months on a

STAGGERED TEST

BASIS

North Anna Units 1 and 2 3.3.1-12 Amendment 231/212

RTS Instrumentation

3.3.1

Table 3.3.1-1 (page 1 of 5)

Reactor Trip System Instrumentation

APPLICABLE MODES

OR OTHER

SPECIFIED REQUIRED SURVEILLANCE

FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE

1. Manual Reactor Trip 1, 2 2 B SR 3.3.1.14 NA

3(a), 4(a), 5(a) 2 C SR 3.3.1.14 NA

2. Power Range Neutron Flux

a. Hi gh 1, 2 4 D SR 3. 3. 1. 1  :::; 110% RT P

SR 3.3.1.2

SR 3.3.1.3

SR 3.3.1.7

SR 3.3.1.11

SR 3.3.1.16

b. Low 4 E SR 3.3.1.1  :::; 26% RTP

SR 3.3.1.8

SR 3.3.1.11

SR 3.3.1.16

3. Power Range Neutron Flux Rate

a. High Positive Rate 1, 2 4 E SR 3.3.1.7  :::; 5.5% RTP

SR 3.3.1.11 with time

constant

~ 2 sec

b. High Negative Rate 1, 2 4 E SR 3.3.1.7  :::; 5.5% RTP

SR 3.3.1.11 with time

SR 3.3.1.16 constant

~ 2 sec

4. Intermediate Range Neutron Flux 2 F, G SR 3.3.1.1  :::; 40% RTP

SR 3.3.1.8

SR 3.3.1.11

5. Source Range Neutron Flux 2 H, I SR 3.3.1.1  :::; 1.3 E5 cps

SR 3.3.1.8

SR 3.3.1.11

SR 3.3.1.16

2 I, J SR 3.3.1.1  :::; 1.3 E5 cps

SR 3.3.1.7

SR 3.3.1.11

SR 3.3.1.16

K SR 3.3.1.1 NA

SR 3.3.1.11

(a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(b) Below the P-I0 (Power Range Neutron Flux) interlocks.

(c) Above the P-6 (Intermediate Range Neutron Flux) interlocks.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(e) With the Rod Control System incapable of rod withdrawal. In this condition, source range Function does

not provide reactor trip but does provide indication.

North Anna Units 1 and 2 3.3.1-13 Amendment 231/212

PC~f~T

RTS Instrumentation

3.3.1

Table 3.3.1-1 (page 2 of 5)

Reactor Trip System Instrumentation

APPLICABLE MODES

OR OTHER

SPECIFIED REQUIRED SURVEILLANCE

FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE

6. Overtemperature ~T 1, 2 3 E SR 3.3.1.1 Refer to

SR 3.3.1.3 Note 1 (Page

SR 3.3.1.7 3.3.1-16)

SR 3.3.1.9

SR 3.3.1.12

SR 3.3.1.16

7. Overpower ~T 1, 2 3 E SR 3.3.1.1 Refer to

SR 3.3.1.7 Note 2 (Page

SR 3.3.1.12 3.3.1-17)

8. Pressurizer Pressure

a. Low 1(f) 3 L SR 3.3.1.1 ~ 1860 psig

SR 3.3.1.7

SR 3.3.1.10

SR 3.3.1.16

b. Hi gh 1, 2 3 E SR 3.3.1.1 ~ 2370 psig

SR 3.3.1.7

SR 3.3.1.10

SR 3.3.1.16

9. Pressurizer Water Level-High 1(f) 3 L SR 3.3.1.1 ~ 93%

SR 3.3.1.7

SR 3.3.1.10

SR 3.3.1.16

10. Reactor Coolant Flow-Low 1(f) 3 per L SR 3.3.1.1 ~ 89%

loop SR 3.3.1.7

SR 3.3.1.10

SR 3.3.1.16

11. Reactor Coolant Pump (RCP) 1(f) 1 per M SR 3.3.1.14 NA

Breaker Position RCP

12. Undervoltage RCPs 1(f) 1 per L SR 3.3.1.6 ~ 2870 V

bus SR 3.3.1.10

SR 3.3.1.16

13. Underfrequency RCPs 1(f) 1 per L SR 3.3.1.6(9) ~ 56 Hz

bus SR 3.3.1.10

SR 3.3.1.16

14. Steam Generator (SG) Water 1, 2 3 per SG E SR 3.3.1.1 ~ 17%

Level-Low Low SR 3.3.1.7

SR 3.3.1.10

SR 3.3.1.16

(f) Above the P-7 (Low Power Reactor Trips Block) interlock.

(g) Required to be performed for Unit 2 only.

North Anna Units 1 and 2 3.3.1-14 Amendment 231/212

RTS Instrumentation

3.3.1

Table 3.3.1-1 (page 3 of 5)

Reactor Trip System Instrumentation

APPLICABLE MODES

OR OTHER

SPECIFIED REQUIRED SURVEILLANCE

FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS ALLOWABLE VALUE

15. SG Water Level-Low 1, 2 2 per SG E SR 3.3.1.1 ~ 24%

SR 3.3.1.7

SR 3.3.1.10

Coincident with Steam 1, 2 2 per SG E SR 3.3.1.1 ~ 42.5% full

Flow/Feedwater Flow Mismatch SR 3.3.1.7 steam flow at

SR 3.3.1.10 RTP

16. Turbine Trip

a. Low Auto Stop Oil Pressure 3 N SR 3.3.1.10 ~ 40 psig

SR 3.3.1.15

b. Turbine Stop Valve Closure 4 N SR 3.3.1.10 ~ 0% open

SR 3.3.1.15

17. Safety Injection (SI) Input 1, 2 2 trains o SR 3.3.1.14 NA

from Engineered Safety Feature

Actuation System (ESFAS)

lB. Reactor Trip System Interlocks

a. Intermediate Range Neutron 2 Q SR 3.3.1.11 ~ 3E-11 amp

Flux, P-6 SR 3.3.1.13

b. Low Power Reactor Trips 1 per R SR 3.3.1.5 NA

Block, P-7 train

c. Power Range Neutron Flux, 4 R SR 3.3.1.11 ~ 31% RTP

P-B SR 3.3.1.13

d. Power Range Neutron Flux, 1, 2 4 Q SR 3.3.1.11 ~ 7% RTP

P-10 SR 3.3.1.13 ~ 11% RTP

e. Turbine Impulse Pressure, 2 R SR 3.3.1.10 ~ 11% turbi ne

P-13 SR 3.3.1.13 power

19. Reactor Trip Breakers(i) 1, 2 2 trains P SR 3.3.1.4 NA

3 (a), 4 (a), 5 (a) 2 trains C SR 3.3.1.4 NA

20. Reactor Trip Breaker 1, 2 1 each S SR 3.3.1.4 NA

Undervoltage and Shunt Trip per RTB

Mechanisms

1 each C SR 3.3.1.4 NA

per RTB

21. Automatic Trip Logic 1, 2 2 trains o SR 3.3.1.5 NA

3 (a), 4 (a), 5 (a) 2 trains C SR 3.3.1.5 NA

(a) With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(h) Above the P-B (Power Range Neutron Flux) interlock.

(i) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

North Anna Units 1 and 2 3.3.1-15 Amendment 231/212

RTS Instrumentation

3.3.1

Table 3.3.1-1 (page 4 of 5)

Reactor Trip System Instrumentation

Note 1: Overtemperature ~T

The Overtemperature ~T Function Allowable Value shall not exceed the

following nominal trip setpoint by more than 2.0% of ~T span.

~ T :s; ~ To{ K1 - K2~ ~ : :~:~ [T - T'] + K3(P - PI) - f 1(~I) }

Where: ~T is measured RCS ~T, OF.

~To is the indicated ~T at RTP, OF.

s is the Laplace transform operator, sec-I.

T is the measured RCS average temperature, OF.

T is the nominal Tavg at RTP, ~ [*]OF.

I

P is the measured pressurizer pressure, psig

pi is the nominal RCS operating pressure, ~ [*] psig

KI ~ [*] K2 ~ [*]/oF K3 ~ [*]/psig

~I ~ [*] sec ~2 ~ [*] sec

f 1 (~I) = [*] {[*] - (q, - qb)} when qt - qb < [*] % RTP

0 when [*]% RTP ~ qt - qb ~ [*] % RTP

[*] {(qt - qb) - [*]} when qt - qb > [*]% RTP

Where qt and qb are percent RTP in the upper and lower halves

of the core, respectively, and qt + qb is the total THERMAL

POWER in percent RTP.

The values denoted with [*] are specified in the COLR.

North Anna Units 1 and 2 3.3.1-16 Amendment 245/226

RTS Instrumentation

3.3.1

Table 3.3.1-1 (page 5 of 5)

Reactor Trip System Instrumentation

Note 2: Overpower L1T

The Overpower L1T Function Allowable Value shall not exceed the following

nominal trip setpoint by more than 2% of ~T span.

Where: ~T is measured RCS ~T, OF.

~To is the indicated L1T at RTP, OF.

s is the Laplace transform operator, sec-I.

T is the measured RCS average temperature, OF.

T is the nominal Tavg at RTP, ~ [*]OF.

I

K4 ~ [*]

K5 ~ [*]jOF for increasing Tavg K6 ~ [*]jOF when T > T I

[*]jOF for decreasing Tavg [*]jOF when T ~ T I

The values denoted with [*] are specified in the COLR.

North Anna Units 1 and 2 3.3.1-17 Amendment 231/212

Spent Fuel Pool Storage

3.7.18

45000 .....---.....- -........- - - - . , - - -.......- -.......- - - . - - - - - - . - -......

40000 + - - - - t - - - - - - - + - - - - - - I - - - + - - - - - + - - - - - - + - - - - - + - # - - - - - - I I

35000 +-----+------+------1---+-----+-----r..l~-----+-------I

30000 + - - - - t - - - - - - - + - - - - - - I - - - + - - - - - - # - - - - - - + - - - - - + - - . ' - - - I

5'

I-

E

C

3:

~ 25000 +----t-------+------I----#-----+------+-----#---+------II

Q,

s

e Acceptable

'-

s

co

~

c

E 20000 + - - - - t - - - - - - - + - - - - - - I - # - - - + - - - - - + - - - # - - - - - + - - - - - + - - - - - - I I

Q)

tn

tn

<<

-;

s

u,

15000 + - - - - - + - - - - - - + - - - - # - - - - - 1 - - - + - - - - 1 - - - + - - - - - + - - - - + - - - - - 1

Unacceptable

10000 - I - - - - - t - - - - - # - - - - + - - - - - - I - ' l - - - + - - - - - + - - - - - + - - - - - + - - - - - - I

5000 +----.------+-----:lIl~---li_---f----+------+-----+-----1

O-t------+--------+---~~-- ......- - _ + _ - - _ + _ - - _ + - - _ _ t

1.4 1.8 2.2 2.6 3 3.4 3.8 4.2 4.6

Initial U-235 Enrichment (nominal w/o)

Acceptable: Acceptable for storage in non-matrix location or low reactivity location in matrix

configuration. May also be placed in high reactivity locations in matrix configuration.

Conditionally Acceptable: Acceptable for storage in non-matrix location, but must be placed

in high reactivity location if stored in matrix configuration.

Unacceptable: Must be stored in high reactivity location in matrix configuration. Surry spent

fuel must be stored in high reactivity locations in a matrix.

Figure 3.7.18-1 (page 1 of 1)

Burnup Credit Requirements

North Anna Units 1 and 2 3.7.18-3 Amendments 231/212

Inverters-Operating

3.8.7

3.8 ELECTRICAL POWER SYSTEMS

3.8.7 Inverters-Operating

LCO 3.8.7 The Train H and Train J inverters shall be OPERABLE.

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

One inverter may be disconnected from its associated DC bus

for ~ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform an equalizing charge on its

associated battery, provided:

a. The associated AC vital bus is energized from its constant

voltage source transformer; and

b. All other AC vital buses are energized from their

associated OPERABLE inverters.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. One inverter A.1 ---------NOTE--------

inoperable. Enter applicable

Conditions and

Required Actions of

LCO 3.8.9,

IIDistribution

Systems-Operatinq"

with any vital bus

de-energized.

---

Restore inverter to 7 days

OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

associated Completion

Time not met. AND

-

B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />

North Anna Units 1 and 2 3.8.7-1 Amendments 235/217

Inverters-Operating

3.8.7

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.8.7.1 Verify correct inverter voltage and 7 days

alignment to required AC vital buses.

North Anna Units 1 and 2 3.8.7-2 Amendments 231/212

Distribution Systems-Operating

3.8.9

3.8 ELECTRICAL POWER SYSTEMS

3.8.9 Distribution Systems-Operating

LCO 3.8.9 The following distribution subsystems shall be OPERABLE:

a. The Train H and Train J AC, DC, and AC vital buses; and

b. One AC and DC bus on the other unit for each required

shared component.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more A.l ---------NOTE--------

LCO 3.8.9.a AC Enter applicable

electrical power Conditions and

distribution Required Actions of

subsystem(s) LCO 3.8.4, IIDC

inoperable. Sources-Operating, II

for DC train(s) made

inoperable by

inoperable

distribution

subsystem(s).

Restore AC electrical 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

power distribution

subsystem(s) to AND

OPERABLE status.

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from

discovery of

failure to meet

LCO

North Anna Units 1 and 2 3.8.9-1 Amendments 231/212

Distribution Systems-Operating

3.8.9

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

B. One or more B.1 Restore AC vital bus 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

LCO 3.8.9.a AC vital subsystem(s) to

bus(es) inoperable. OPERABLE status. -

AND

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from

discovery of

failure to meet

LCO

C. One or more C.1 Restore DC electrical 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

LCO 3.8.9.a DC power distribution

electrical power subsystem(s) to -AND

distribution OPERABLE status.

subsystem(s) 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> from

inoperable. discovery of

failure to meet

LCO

D. --------NOTE---------- D.1 Declare associated Immediately

Separate Condition shared component(s)

entry is allowed 'for inoperable.

each AC subsystem.

---

One or more required

LCO 3.8.9.b AC

electrical power

distribution

subsystem(s)

inoperable.

E. --------NOTE---------- E.1 Declare associated Immediately

Separate Condition shared component(s)

entry is allowed for inoperable.

each DC subsystem.

---

One or more required

LCO 3.8.9.b DC

electrical power

distribution

subsystem(s)

inoperable.

North Anna Units 1 and 2 3.8.9-2 Amendments 231/212

Distribution Systems-Operating

3.8.9

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

F. Required Action and F.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

associated Completion

Time for Condition A, -AND

B, or C not met.

F.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />

G. Two or more G.1 Enter LCO 3.0.3. Immediately

LCO 3.8.9.a electrical

power distribution

subsystems inoperable

that result in a loss

of safety function.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.8.9.1 Verify correct breaker alignments and 7 days

voltage to required AC, DC, and AC vital

bus electrical power distribution

subsystems.

North Anna Units 1 and 2 3.8.9-3 Amendments 231/212

GENERIC FUNDAMENTALS EXAMINATION

EQUATIONS AND CONVERSIONS HANDOUT SHEET

EQUATIONS

P = Po 10SUR(t)

P = P o e(th)

Q = milh

A = A oe-At

Q= UAilT

• . 3

Q oc mNat Cire

il T ec th~at Cire

p = (Keff - 1)/K eff F=PA

SUR = 26.06/-17 ill = pAy

13 - p WPump -- milPu

't = -eff- -

Aeff p

E=IR

p=-+---

Q* 13eff

r 1 + Aeff r Thermal Efficiency = Net Work Out/Energy In

Q*= 1 x 10-4 sec g(Z2 - ZI) + (V22 - "1 2) + u(P 2 - PI) + (u2 - u.) + (q - w) = 0

gc 2gc

Aeff = 0.1 sec" (for small positive p)

gc = 32.2 lbm-ft/lbf-sec'

2 2

DRW oc <Ptip/ <Pavg

CONVERSIONS

1 Mw = 3.41 X 106 Btu/hr 1 Curie = 3.7 x 1010 dps

1 hp = 2.54 x 103 Btu/hr 1 kg = 2.21 Ibm

1 Btu = 778 ft-lbf 1 galwater = 8.35 Ibm

°C = (5/9)(OF - 32) 1 Wwater = 7.48 gal

OF = (9/5)(OC) + 32

-3-