Text

Initial Exam 2011-302 Final SRO Written Exam
	ML113112036
Person / Time
Site:	Oconee
Issue date:	11/07/2011
From:	; NRC/RGN-II
To:	;
References
	ES-401, Rev 9
	Download: ML113112036 (28)
	v • d • e

ES-401, Rev. 9 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: October 26, 2011 Facility/Unit: Oconee Region:

l/II/lIl/IV ReactorType:W/CE/BW/GE Start Time:

Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to complete the combined examination, and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months if you are only taking the SRO portion.

Applicant Certification All work done on this examination is my own.

I have neither given nor received aid.

Applicants Signature Results RO/SRO-OnlylTotal_Examination Values Applicants Scores

/

I Points Applicants Grade

/

I Percent

Oconee Nuclear Station 2011BONS SR0 NRC Examination Question:

76 (1 point)

Given the following Unit I conditions:

Large Break LOCA has occurred IA AND lB LPI pumps failed to start ICC tab in progress Which ONE of the following would result in atransferto the LOCA CD tab assuming the TSC is available and concurs with actions taken whenever required?

A.

Core SCM = 0°F stable B.

One RCP per loop placed in operation C.

1 C LPI pump aligned and operating D.

Steam Generator cooling available and both SGs have been fully d epressu rized Page 76 of 100

Oconee Nuclear Station 2011B ONS SRNRCExaminaon Question:

77 (1 point)

Given the following Unit I conditions:

Initial conditions:

Reactor in MODE 2 RC Makeup Flow = 45 gpm stable Pressurizer level = 220 stable Current conditions:

IHP-120 fails CLOSED Which ONE of the following describes:

1) how long (in minutes) before Pzr level will reach the level where Pzr heaters become inoperable

2) the reason for maintaining pressurizer level above the Pzr heater cutoff setpoint ASSUME NO OPERATOR ACTIONS A.

1. Approximately 96

2. Helps to ensure the ability to maintain RCS pressure such that the RCS loops remain subcooled during a loss of offsite power B.

1. Approximately 96

2. Helps to ensure that DNBR Safety Limit criteria will be met in the event of an unplanned loss of forced RCS flow C.

1. Approximately 75

2. Helps to ensure the ability to maintain RCS pressure such that the RCS loops remain subcooled during a loss of offsite power D.

I. Approximately 75

2. Helps to ensure that DNBR Safety Limit criteria will be met in the event of an unplanned loss of forced RCS flow Page 77 of 100

Oconee Nuclear Station 2011B UNS SRO NRC Examination Queston:

78 (1 point)

Given the following Unit I conditions:

Time = 1200 Reactor in MODE 5 A and B LPSW pumps failed due to a seismic event RCS temperature 131°F slowly increasing Time = 1205 Unusual Event declared in accordance with RP/1000/01 (Emergency Classification)

Time = 1430 Plant conditions require escalating the Emergency Plan classification to an ALERT Which ONE of the following:

1) is a condition that will require cross connecting with Unit 3s LPSW system?

2) states who has the responsibility to upgrade the classification at TIME = 1430 in accordance with RP/0/A1000/002 (Control Room Emergency Coordinator Procedure)?

A.

1. Loss of C LPSW Pump

2. TSC B.

1. Loss of C LPSW Pump

2. OSM C.

1. RCS temperature = 205°F slowly increasing

2. TSC D.

1. RCS temperature = 205° F slowly increasing

2. OSM Page 78 of 100

Oconee Nuclear Station 2011B ONS SR0 NRCExamination Question:

79 (1 point)

Given the following Unit I conditions:

Reactor in MODE 5 ALL LTOP requirements established in accordance with Tech Spec 3.4.12 (LTOP)

I HP-I 20 demand signal fails to 100%

Which ONE of the following describes the reason the failure will NOT result in exceeding RCS brittle fracture pressure limits?

A.

LTOP requires the HPI system to be deactivated therefore no HPI pumps will be injecting B.

Mechanical Travel Stop on IHP-120 limits flow such that the operator has 10 minutes to identify and mitigate the event C.

The PORV will act as a backup to the failed Administrative Control and prevent exceeding the brittle fracture limits D.

The dedicated LTOP operator is credited with identifying the failure and responding within 10 minute of the event initiation Page 79 of 100

Oconee Nuclear Station 201lB ONSSR0 NRC Examination Question:

80 (1 point)

Given the following Unit 3 conditions:

SGTR tab in progress Core SCM = 59°F increasing RCS cooldown in progress Group 2 Rod 4 100% withdrawn (did not insert when tripped)

RCS temperature = 550° F decreasing Which ONE of the following describes the actions directed by the Procedure Director in accordance with the SGTR tab in preparation for isolating the faulted Steam Generator?

A.

cooldown to 525°F 532°F, cooldown rate limits apply B.

coo ldown to 525° F 532° F, limited ONLY by Pzr level C.

cooldown to 450° F 525°F, cooldown rate limits apply D.

cooldown to 450°F 525°F, limited ONLY by Pzr level Page 80 of 100

Oconee Nuclear Station 2011BONSSRO NRCExaminatio,t Question:

81 (1 point)

Given the following Unit I conditions:

Initial conditions:

Startup in progress Control Rod Group 2 being withdrawn for startup 1 B RPS channel in Manual Bypass Current conditions:

I KVIA pan elboard input breaker trips OPEN 1 C RB pressure transmitter feeding RPS fails LOW Which ONE of the following describes:

1) the status of the IA RPS channel?

2) the MAXIMUM time (hours) allowed by Tech Spec 3.3.1 (RPS Instrumentation) to open ALL CRD breakers?

REFERENCE PROVIDED A.

1. Tripped

2. 6 B.

1. Tripped

2. 12 C.

1. NOT Tripped

2. 6 D.

1. NOTTripped

2. 12 Page 81 of 100

Oconee Nuclear Station 2011BONSSRONRCExaminatjon Question:

82 (1 point)

Given the following Unit 1 conditions:

Initial conditions:

Reactor in MODE 2 and returning to power following a maintenance shutdown Reactor power = 4% slowly increasing Control Rod Group I Rod 4 drops fully into the core Current conditions:

Reactor power = 3% stable Which ONE of the following describes:

1) the MAXIMUM time allowed by Tech Spec 3.1.4 (Control Rod Group Alignment) to verify Shutdown Margin is within limits?

2) the actions reciuired in accordance with APIIIA/17001001 (Unit Runback)?

A.

1. l5minutes

2. Maintain current power level until Control Rod repair and recovery are complete then proceed with OP/1/A/1102/001 (Controlling Procedure for Unit Startup)

B.

1.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

2. Maintain current power level until Control Rod repair and recovery are complete then proceed with OPIIIAIIIO2IOOI (Controlling Procedure for Unit Startup)

C.

1. l5minutes

2. Go to OP/i/NI 102/010 (Controlling Procedure for Unit Shutdown) and shutdown the reactor prior to Control Rod repair and recovery D.

1.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

2. Go to OP/I/A/I 102/010 (Controlling Procedure for Unit Shutdown) and shutdown the reactor prior to Control Rod repair and recovery Page 82 of 100

Oconee Nuclear Station 2011# ONS SRUNkCExaminatton Question:

83 (1 point)

Given the following Unit I conditions:

Initial Conditions:

Reactor power = 85% slowly increasing Delta Tc in HAND Current conditions:

ICS runback in progress Reactor power as indicated below

t. *4I 848 831 756 864 A

A A

A 125 125

+60 125

+60 100

+40 100 +40 100 +40 100 +40 80

+20 80

+20 60 0

60 0

60 o

60 0

40 20 40 20 40 20 40 20 20 40 20

-40 20

-40 20 40 0

0 60 0

60 0

60 V

V V

V 000 000 000 000

/ 1MB

/

1MB I

MB Which ONE of the following describes:

I) the reason forthe ICS runback?

2) the consequences of operating the unit under the conditions described above?

A.

I. Dropped Control Rod

2. Allowable Thermal Power limits of Tech Spec 3.4.4 (RCS Loops MODES I and 2) could be exceeded B.

1. Dropped Control Rod

2. Maximum Linear Heat Rate could be exceeded C.

I. RCP trip

2. Allowable Thermal Power limits of Tech Spec 3.4.4 (RCS Loops MODES I and 2) could be exceeded D.

I. RCP trip

2. Minimum DNBR limits could be exceeded Page 83 of 100 POWER RANGE NIS

Oconee Nuclear Station Question:

84 (1 point) 2011B ONS SRONRC Examination Given the following Unit I conditions:

RCS temperature = 545°F increasing Turbine Bypass Valves are in HAND and CLOSED AP/27 (Loss of Condenser Vacuum) in progress Steam Generator Tube leak rate = 20 gpm Condenser vacuum is as indicated below Which ONE of the following describes:

1) the RCS response to attempts to open the TBVs from the ICS Bailey stations in the Control Room?

2) actions required if the Atmospheric Dump Valves are required to perform the cooldown to LPI?

REFERENCE PROVIDED A.

1. The RCS heatup rate will be affected

2. Declare an Unusual Event AND make a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ENS notification B.

I. The RCS heatup rate will be affected

2. 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ENS notification ONLY C.

I. The RCS heatup rate will NOT be affected

2. Declare an Unusual Event AND make a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ENS notification D.

I. The RCS heatup rate will NOT be affected

2. 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ENS notification ONLY Page 84 of 100

Oconee Nuclear Station

- 2011B ONS SRO NRC Examination Question:

85 (1 point)

Given the following plant conditions:

ACB-3 closed Which ONE of the following is/are the MINIMUM condition(s) that would render the Underground Emergency Power Path inoperable in accordance with the basis of Tech Spec 3.8.1 (AC Sources Operating)?

A.

ONLY ACB-3 (Unit I EMER FDR) inoperable B.

BOTH ACB-3 AND ACB-4 (Unit 2 EMER FDR) must be inoperable C.

ONLY Breaker SI (STBY BUS I TO MFBI) inoperable D.

BOTH Breakers SI AND S2 (STBY BUS 2 TO MFB2) must be inoperable Page 85 of 100

Oconee Nuclear Station

-2lfllBONSSRUNRCExamination Question:

86 (1 point)

Which ONE of the following describes the:

1) status of an ES Instrument Channel in accordance with Tech Spec 3.3.5 (ES Input Instrumentation) whose Reactor Building Pressure actuation setpoint is found to be set at 3.6 psig?

2) requirement for ES Channel I Manual Initiation to be Operable in accordance with Tech Spec 3.3.6 (ESPS Manual Initiation)?

A.

1. Operable

2. Manual Actuation pushbutton on UBI must be Operable ONLY B.

1. Operable

2. Manual Actuation pushbutton on UBI must be Operable OR all components must be able to be manually aligned to their ES position within 10 minutes of ES actuation C.

1. Inoperable

2. Manual Actuation pushbutton on UBI must be Operable ONLY D.

1. Inoperable

2. Manual Actuation pushbutton on UBI must be Operable OR all components must be able to be manually aligned to their ES position within 10 minutes of ES actuation Page 86 of 100

Oconee Nuclear Station 2OIIBONSSRONRCExamination Question:

87 (1 point)

Given the following Unit 1 conditions:

Time = 1200:

Reactor power = 100%

IBRBSpumpOOS Time = 1201:

Seismic event I SAO9/C9 (RBCU B Cooler Rupture) actuated (valid) 1 TD de-energized Time= 1215 I SAO9/C9 required actions are complete There is NO additional evidence of damage from the seismic event

1) Containment is _(1)_?

2) The _(2)_ RBCU(s) is/are Operable?

Which ONE of the following completes the statements above?

A.

1. Operable

2. 1AONLY B.

1. Operable

2. lAand IC C.

1. Inoperable

2. 1AONLY D.

1. Inoperable

2. lAand IC Page 87 of 100

Oconee Nuclear Station 2011B ONSSRONRCExamiiwtion Question:

88 (1 point)

Given the following Unit I conditions:

ReactorinMODE3 Startup in progress Which ONE of the following states:

1) the MINIMUM Containment Cooling equip required to be OPERABLE in accordance with Tech Spec 3.6.5 (Reactor Building Spray and Cooling Systems?

2) if entry into MODE 2 is allowed when the LCO is NOT met while in MODE 3?

A.

I. Two RB Spray Trains and Three RB Cooling Trains

2. allowed B.

1. Two RB Spray Trains and Three RB Cooling Trains

2. NOT allowed C.

1.

One RB Spray Train and Two RB Cooling Trains ONLY 2.

allowed D.

1. One RB Spray Trains and Two RB Cooling Trains ONLY

2. NOT allowed Page 88 of 100

Oconee Nuclear Station 2011B ONSSRONRCExamination Question:

89 (1 point)

Given the following Unit I conditions:

Initial Conditions:

Reactor power = 100%

MSLBoccursonlASG BOTH channels of IA SG AFIS fail to actuate Current conditions:

AFIS cannot be Manually actuated ALL SCMs = 0°F stable due to the MSLB Which ONE of the following states the:

1) Safety Function that AFIS is credited to perform?

2) EOP tab that will direct the mitigating actions for this event?

A.

1. Maintain Containment pressure within design limits

2. EHT B.

1. Maintain Containment pressure within design limits

2. LOSCM C.

1. Prevent an inadvertent return to criticality

2. EHT D.

1. Prevent an inadvertent return to criticality

2. LOSCM Page 89 of 100

Oconee Nuclear Station 2011K ONS SRO NRCExamination Question:

90 (1 point)

Given the following Unit I conditions:

Initial conditions:

Reactor in MODE 6 Fuel offload in progress Penetration openings exist due to containment penetration work in progress Current conditions Control Room notified that a Fuel Assembly has been dropped 1SA-8 B-9 (PROCESS MONITOR RADIATION HIGH) actuates I RIA-3 (Fuel Transfer Canal Area Monitor) HIGH alarm actuates IRIA-49 (RB Gas) HIGH alarm actuates RB Evacuation Alarm sounds Which ONE of the following states the:

1) source of the AUTOMATIC operation of the RB Evacuation Alarm?

2)

Abnormal Procedure that contains the actions that are required to mitigate the initiating event?

A.

1. IRIA-3

2. APIIIAI1700IOO9 (Spent Fuel Damage)

B.

1. IRIA-3 2.

AP/1/AI1 700/018 (Abnormal Release of Radioactivity)

C.

1. IRIA-49 2.

AP/1/A/I 700/009 (Spent Fuel Damage)

D.

1. 1RIA-49 2.

AP/1/A/1 700/018 (Abnormal Release of Radioactivity)

Page 90 of 100

Oconee Nuclear Station 201lB ONS SRO NRCExamination-Question:

91 (1 point)

Given the following Unit I conditions:

Time-1200 Reactor power = 100%

Pressurizer temperature indicates as shown below iii iiiirinI 4423 3614 700 700 650 650 600 650 550 550 500 500 0

450 0

450 400 400 350 E

350 300 S

300 F

250 F

250 200 200 150 150 100 100 50 50 Which ONE of the following describes ALL Tech Spec 3.3.8 (PAM Instrumentation)

Condition(s) that apply (if any) at Time = 1200?

REFERENCE PROVIDED A.

NO Tech Spec 3.3.8 Condition applies B.

Condition A ONLY C.

Condition A and C ONLY D.

Condition A, C, and H Page 91 of 100

Oconee Nuclear Station 2011B NS SRO NRC Examination Question:

92 (1 point)

Given the following Unit 3 conditions:

Reactor in MODE 6 Core offload in progress Main Fuel Bridge is withdrawing a fuel assembly that appears to be binding The _(1) interlock will stop the withdrawal of the fuel assembly to prevent fuel damage and in accordance with OPIOIA/15061001 (Fuel and Component Handling),

(2)_ must either be present or give concurrence prior to bypassing the interlock.

Which ONE of the following completes the statement above?

A.

1. Fuel Overload (TS-1)

2. the Operations Shift Manager ONLY B.

1. Fuel Overload (TS-1)

2. any licensed SRO C.

I. Fuel Hoist Up/Down (TS-2)

2. the Operations Shift Manager ONLY D.

I. Fuel Hoist Up/Down (TS-2)

2. any licensed SRO Page 92 of 100

Oconee Nuclear Station 2011B UNS SRO NRC Examiiuttion Question:

93 (1 point)

Given the following plant conditions:

A GWD tank being released at 2/3 Station Limit I RIA-45 is approaching its alarm setpoint Which ONE of the following describes:

1) the MINIMUM RIA response that would indicate that the instantaneous release rates in accordance with SLC 16.11.2 (Radioactive Gaseous Effluents) were being approached?

2) The MINIMUM level of approval required byOP/l-2/A111041018 (GWD System) prior to initiating the 2/3 Station Release?

A.

1. EITHER of the other 2 units RIA-45 in alarm o+ $pv-t

2. Control Room SRO B.

1. BOTH of the other2 units RIA-45in alarm +

2. Control Room SRO C.

1. EITHER of the other 2 units RIA-45 in alarm 5e-po).I*

2. OSM ONLY D.

1. BOTH oftheother2 units RIA-45 in alarm

2. OSM ONLY Page 93 of 100

Oconee Nuclear Station 2011B ONS SRO NRC Examination Question:

94 (1 point)

Given the following plant conditions:

Unit I Reactor power = 100%

Unit 2 Reactor power = 100%

Unit 1 and Unit 2 Control Room SROs are both inside the Control Room Which ONE of the following activities is an acceptable activity while maintaining the oversight role of the Unit I Control Room SRO in accordance with OMP 2-01 (Duties and Responsibilities of On Shift Personnel)?

A.

Leave the Control Room area for 3 minutes without giving a complete turnover B.

Serve as the Reactivity Management SRO during Control Rod withdrawal C.

Serve as the Evolution SRO during a specific activity D.

Fill the NRC Communicator role Page 94 of 100

Oconee Nuclear Station 2011B ONS 51W NRC Examination Question:

95 (1 point)

Given the following Unit 2 conditions:

Initial conditions:

Time=0100 Refueling in progress FTC level =22 feet stable No water additions are being made to the system 2A LPI train is Operable and in service 2B LPI train is Operable Current conditions:

Time = 2300 Refueling SRO desires stopping the 2A LPI Pump to aid in inserting a fuel assembly Which ONE of the following:

1) states whether the 2A LPI pump may be stopped in accordance with O P12/All 502/007 (Operations Defueling /Refueling Responsibilities)?

2) describes the system(s) required to be operable in support of the Operability of a DHR loop in accordance with the basis of Tech Spec 3.9.4 (DHR and Coolant Circulation)?

A.

1. 2A LPI Pump may be stopped for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2. LPSW ONLY B.

1. 2A LPI Pump may be stopped for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2. LPSW and ECCW C.

1. 2A LPI Pump may NOT be stopped

2. LPSW ONLY D.

I. 2A LPI Pump may NOT be stopped

2. LPSWandECCW Page 95 of 100

Oconee Nuclear Station 2111lB ONS 5KG NRC Examination Question:

96 (1 point)

Given the following Unit I condition:

Reactor power = 100%

Critical Activity Plan as described in NSD 213 (Risk Management Process) is being implemented The Critical Activity Plan has reached a reciuired hold point Holding at this point in the Critical Activity Plan could cause a reactor trip In accordance with NSD 213 (Risk Management Process), which ONE of the following states the LOWEST level of management that has the authority to waive the hold that is required by the Complex Activity Plan?

A.

Station Manager B.

Superintendent of Operations C.

Operations Shift Manager D.

Control Room SRO Page 96 of 100

Oconee Nuclear Station 2011B ONS SRO NRCExamination Question:

97 (1 point)

Given the following Unit 2 conditions:

Date=10-1 Time=1200 A Tech Spec required surveillance on an instrument channel with a frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months has just been discovered NOT performed since 1200 on 9-26.

Which ONE of the following describes the status of the associated equipment in accordance with Tech Specs if the surveillance is NOT performed?

A.

Immediately declare the equipment Inoperable B.

Remains OPERABLE until no later than 10-2 at 0000 C.

Remains OPERABLE until no later than 10-2 at 0300 D.

Remains OPERABLE until no later than 10-2 at 1200 Page 97 of 100

Oconee Nuclear Station 2011B ONS SRONRC Examination Question:

98 (1 point)

Given the following Unit I conditions:

Initial conditions:

Reactor power = 100%

Current conditions:

RCS pressure = 1136 psig slowly decreasing CoreSCMO°F RB pressure = 11.6 psig slowly decreasing IA SG pressure = 1010 psig slowly decreasing lB SG pressure = 1008 psig slowly decreasing Which ONE of the following:

1) states whether Emergency Dose Limits are in effect?

2) describes the maximum (TEDE) dose (rem) that an NEO will be allowed to receive while performing a time critical task outside of the control room?

A.

1. Yes

2. 10 B.

1. Yes

2. 5 C.

1.No

2. 5 D.

1.No

2. 2 Page 98 of 100

Oconee Nuclear Station 2GlIB ONS SRO NRCExamintztion Question:

99 (1 point)

Given the following Unit I conditions:

Initial Conditions SBLOCA has occurred BOTH Main Feedwater pumps have tripped Rule 2 is complete ONE HPI train injecting Unit 3 is supplying the Aux Steam header Current conditions:

BOTH MDEFWPs have failed to start Which ONE of the following describes:

1) the actions that will be directed by the Procedure Director?

2) the reasons for the actions being directed?

A.

1. FULLY depressurize both Steam Generators

2. Initiates a rapid cooldown to LPI B.

1. FULLY depressurize both Steam Generators

2. Ensures Steam Generators do not become a heat source during cooldown C.

1. RAPIDLY depressurize both Steam Generators to 250 psig ONLY

2. Initiates a rapid cooldown to LPI D.

I. RAPIDLY depressurize both steam generators to 250 psig ONLY

2. ensures steam generators do not become a heat source during cooldown Page 99 of 100

Oconee Nuclear Station 2011B {)NS SRO NRC Examination Question: 100 (1 point)

Given the following plant conditions:

Time = 1200 Security Supervisor reports intruders have forced their way through the Vehicle Access Point (Security Point 1) near the complex using various weapons and have been seen heading towards the 525kv Switchyard Time = 1205 Security Supervisor reports intruders and their weapons are in the 525kv Switchyard AND the 230kv Switchyard Time = 1215 Intruders have gained access to the Unit 1&2 blockhouse and have rendered the contents useless Without using the Emergency Coordinator Judgment option, which ONE of the following:

1) states the EAL classification required by the conditions at Time = 1205?

2) states the EAL classification required by the conditions at Time = 1215?

REFERENCE PROVIDED A.

1. Alert

2. Site Area Emergency B.

1. Alert

2. General Emergency C.

1. Site Area Emergency

2. Site Area Emergency D.

1. Site Area Emergency

2. General Emergency Page 100 of 100

coe 2Lo2 ILT4O STUDENT REFERENCE LIST The following questions have student references:

12

- EOP Enclosure 5.18 17 - AP/34 Generator Capacity Curve 47-AP/Il End 5.IA Pg 5 81-Tech Spec3.3.1 84* RP/1000/OO1 91

- Tech Spec 3.3.8 1OO-RP/1000IOO1

Question 84 and 100 use the same reference.

Examination KEYfor: 2011B ONS SRO NRC Examin Question Answer Number 76 A

77 C

78 B

79 B

80 B

81 B

82 D

83 B

84 A

85 C

86 A

87 A

88 D

89 A

90 C

91 C

92 B

93 D

94 A

95 B

96 C

97 D

98 B

99 A

100 B

Printed 10/31/2011 7:17:32 AM Page 4 of4

ML113112036

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