ML101310308

Initial Exam 2010-301 Final SRO Written Exam

ML101310308
Person / Time
Site:	Oconee
Issue date:	05/04/2010
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
Download: ML101310308 (28)

Text

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:

04107/2010 Date: 04/07/2010 Facility/Unit: Oconee Region: II D II ~ III D IV D Reactor Type: W DeE LICE DBw~GE E1BWGE D LI 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. II have neither given nor received aid.

Applicants Signature Applicant's Results RO/SRO-Only/Total Examination Values RO/SRO-OnlylTotal 75 / ~25 / 100 100 Points Applicants Applicant's Scores / -- / -- Points Applicants Applicant's Grade /I -- / -- Percent

2010A NRC 2010A REACTOR OPERATOR EXAM SENIOR REACTOR NRC SENIOR EXAM I1 POINT POINT Question 76 Unit 22 initial conditions:

Unit

• Time=1300 Time = 1300

• Reactor power power == 100%

100%

Current conditions:

Current Time =1310

• Time=1310

• RCS pressure == 52 psig slowly decreasing

• Reactor Building pressure == 52 psig slowly decreasing decreasing

• All SCMs SCM's == 0°F OaF

• 2RIA-57 == 92 R/hr Rlhr slowly increasing

• 2RIA-58 == 45 R/hr Rlhr slowly increasing

• Average of 55 highest CETCsCETC's == 312°F decreasing decreasing

• NO RBCU's can be started NO RBCUs

• NO RBS Pumps Pumps can be started Based on the above conditions, which ONE of the following is the Emergency Action Level Classification?

REFERENCE PROVIDED A. Alert based on Loss of Fuel Clad Barrier and Potential Loss of Containment Barrier B. Alert based on Loss of RCS Barrier and Potential Loss of Containment Barrier C. Site Area Emergency based on Loss of RCS Barrier and Loss of Containment Barrier D. Site Area Emergency based on Loss of Fuel Clad Barrier and Loss of Containment Barrier

2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT 1

Question 77 Unit 11 plant conditions:

• Reactor power = = 100%

• CC CRD Return Flow = = 125 gpm slowly decreasing

• CC Return Flow =

= 563 gpm decreasing

• Letdown Temperature = = 138°F stable

• The following alarms have actuated:

1SA-91B-1 (CC CRD Return Flow Low).

o 1SA-9/B-1 o 1ISA-21C-1 SA-2/C-1 (HP Letdown Temperature High) o 1 SA-9/C-1 (CC Component Cooling Return Flow Low) 1SA-91C-1 Based on the above conditions:

(1) Which ONE of the following describes a required action from the associated ARG(s) to mitigate this event?

AND (2) If the ARG directed actions are NOT successful, which Abnormal Procedure is required to be entered first?

A. (1) Decrease letdown flow using 1 I HP-7 (LETDOWN CONTROL)

(2) AP/32 (Loss of Letdown)

B. (1)

(I) Decrease letdown flow using 1 1 HP-7 (LETDOWN CONTROL)

(2) AP/20 (Loss of Component Cooling)

C. (1) Verify CC Surge Tank level> 12 inches and start the standby CC pump (2) AP/32 (Loss of Letdown)

D. (1) Verify CC Surge Tank level> 12 inches and start the standby CC pump (2) AP/20 (Loss of Component Cooling)

2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT 1

Question 78 I initial conditions:

Unit 1 Datel2/0I

• Date = 12/01

• Time TimeO800= 0800

• Reactor Power = = 100%

• All Pressurizer heater breakers trip open and cannot be reclosed Current conditions:

• Date = 12/04

• Time = 2200 Based on the above conditions, which ONE of the following is the HIGHER RCS temperature (degrees F) that is in compliance with the requirements of Tech Specs AND the bases for the Pzr heater power supply requirements in TS 3.4.9 (Pressurizer)?

REFERENCE PROVIDED A. 320 I/ ensure ability to perform a subcooled cooldown while on natural circulation during an extended loss of power B. 320 / ensure ability to control pressure and remain subcooled during an extended loss of power C. 375 /I ensure ability to perform a natural circulation cool cooldown down during an extended loss of power D. 375 / ensure ability to control pressure and remain subcooled during an extended loss of power

2010A NRC SENIOR REACTOR OPERATOR EXAM 1I POINT Question 79 Unit 11 initial conditions:

• Reactor power = = 75% stable ICSinMANUAL

• ICS in MANUAL

• 1 lB B HPIP tagged out

• The following alarms actuate:

o 1SA-1/A1 (RPCHANNELATRIP)

ISA-I/Al (RP CHANNEL A TRIP) o 1SA-1/B1 (RPCHANNELBTRIP) 1SA-l/Bl (RP CHANNEL B TRIP)

Current conditions:

• Reactor power = = 34% slowly decreasing

• BOTH Main Feedwater pumps are operating SCMs =

• All SCM's 0°F stable

= OaF Based on the above conditions, which ONE of the following describes the EOP tab that will be directed first AND the guidance the SRO will provide to the RO?

A. UNPP I Trip the Main Turbine B. UNPP I/ Throttle Feedwater to control RCS temperature C. LOSCM I/ Fully depressurize BOTH Steam Generators D. LOSCM I/ Throttle Feedwater to control RCS temperature

2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT 1

Question 80 Unit 3 plant conditions:

• Date 4/5

• Time1100 Time = 1100

• 3KVID panelboard de-energized Current conditions:

Timel200

• Time = 1200

• DC panelboard 3DIC is de-energized Based on the above conditions, which ONE of the following states the actions required by Tech Spec 3.8.8 (Distribution Systems-Operating) AND the bases behind the different Completion Times for inoperable Vital Instrument and Control panelboards?

REFERENCE PROVIDED A. Restore either 3KVIC OR 3KVID within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I/ KVIA AND KVIB have shorter completion times due to being the source of power for the ES Digital Channels B. Restore either 3KVIC OR 3KVID within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> /I KVIA AND KVIB have shorter completion times due to providing power for SK and SL breakers protective relaying C. Enter LCO 3.0.3 immediately I/ KVIA AND KVIB have shorter completion times due to being the source of power for the ES Digital Channels D. Enter LCO 3.0.3 immediately /I KVIA AND KVIB have shorter completion times due to providing power for SK and SL breakers protective relaying

2010A NRC SENIOR REACTOR OPERATOR EXAM 1 POINT 1

Question 81 Unit 1I initial conditions:

• Reactor trip from 100% power

• Both Main Feedwater pumps trip

• EFDW pumps will not start Current conditions:

• Rule 3 in progress

• LOHT tab initiated

• ALL SCM's>SCMs> OaF0°F Based on the above conditions, which ONE of the following would result in a transfer out of the LOHT tab?

A. Pressurizer level = = 375 inches B. RCS heats up and results in ANY SCM = 0°F

= OaF C. HPI Forced Cooling is established and verified D. Condensate Booster Pump feed is established

2010A NRC 2010A SENIOR REACTOR OPERATOR EXAM NRC SENIOR EXAM I1 POINT Question 82 Unit 11 initial conditions:

• Startup in progress

• Reactor in in MODE MODE 33

• Source Source Range Nl's 22 &

NIs & 4 OOS OOS

• Source Range NIs Nl's 11 && 33 == 834 cps increasing increasing

• Wide Range NIs NI's I1 thru 4 == 5E-5% increasing Current conditions:

• Source Range NI-I NI-1 = = 0 cps

• 1SA-051A8 1SA-05/A8 (NI-1(NI-i TEST/FAIL) actuates Based on the above conditions, which ONE of the following describes the reason for the NI-i indications AND the Tech Specs impact on the startup?

NI-1 A. Loss of +15V+1 5V Power supply / Suspend the startup B. Loss of +15V+1 5V Power supply /I Startup may continue C. Source range becomes saturated I/ Suspend the startup D. Source range becomes saturated /I Startup may continue

2010A NRC SENIOR REACTOR OPERATOR EXAM NRC SENIOR EXAM I1 POINT Question 83 83 Unit I1 plant conditions:

• ALL SCM == 0°F O°F stable

• RCS pressure == 855 psig slowly decreasing

• LOCA CD tab in progress

• LPI suction source is the RBES

• HPI aligned for piggyback operation HPI aligned

• 1 1LP-15 LP-15 failed closed Based on the above conditions, which ONE of the following states...

states ...

(1) if LPI ES analog channels are allowed to be manually bypassed in accordance with the LOCA CD tab?

AND (2) the MAXIMUM allowed HPI flow if 1LP-15 ILP-15 will not open?

LPI ES _ _ be bypassed AND the MAXIMUM allowed HPI flow is _ _ gpm.

A. may /I 750 B. may NOT I/ 750 C. may I/ 500 D. may NOT /I 500

REACTOR OPERATOR EXAM 2010A NRC SENIOR REACTOR 1I POINT Question 84 Unit 11 initial conditions:

• Reactor power = = 70% stable

• 11B1 B1 RCP has been secured

• ICS is in manual Current conditions:

• Group 2 Rod 4 drops into core Based on the above conditions, which ONE of the following describes the direction that will be provided to the RO AND the maximum time allowed by AP/1 APII (Unit Runback) to carry out the directions?

Reduce Core Thermal Power to ~

< _ _ _ within _ _ _ hour(s).

A. 60% I 1I B. 60% I 2 C. 45% I 1 1 D. 45% I 2

2010A NRC SENIOR REACTOR OPERATOR EXAM 2010A NRC I1 POINT Question 85 Unit 22 initial Unit initial conditions:

• Reactor power == 100% 100% stable Current conditions:

Current

• Reactor trip occurs

• Main Turbine does NOT NOT trip Manual Turbine trip is unsuccessful

• Manual Based on the above conditions, which ONE of the following describes actions required by the EOP AND the MAXIMUM time allowed by NSD 202 (Reportability) prior to notifying the NRC?

A. Place BOTH EHC pumps in PULL TO LOCK I eight hours B. Place BOTH EHC pumps in PULL TO LOCK I four hours C. Initiate Rule 5 (MSLB) I eight hours D. Initiate Rule 5 (MSLB) I four hours

2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT 1

Question 86 Unit 1I initial conditions:

• Reactor in MODE 3

• 1 1A2 A2 and 11B2 RCP5 operating B2 RCPs Current conditions:

• RCS leakage = 140 gpm SCMs = 45°F stable

• All SCM's

• Pressurizer level = = 200 inches stable

• 1A2 RCP Motor Upper Guide Bearing temperature = 195°F slowly increasing

• 1 1 B2 RCP Motor Stator Temperature = 235°F slowly increasing Based on the above conditions, which ONE of the following describes the actions AP/1 6 (Abnormal Reactor Coolant Pump Operation) AND which EOP tab required by AP/16 RCPs are secured?

would provide guidance for a plant cooldown if ALL RCP's Trip the ...

A. 11A2 A2 RCP / Forced Cooldown B. 11A2 A2 RCP / LOCA Cooldown C. 11B2 B2 RCP / Forced Cooldown D. 1I B2 RCP / LOCA Cooldown

2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT 1

Question 87 Unit 3 plant conditions:

• Reactor power = = 100%

• 3A RBCU tagged out Based on the above conditions, which ONE of the following would require immediate entry into LCO 3.0.3 AND describes actions that are required once LCO 3.0.3 is entered in accordance with OMP 2-23 (Operations Shift Manager Rules Of Practice)?

A. 3LPSW-19 (3B RBCU INLET) fails closed I/ Must determine a time to begin power 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> reduction within 1 B. 3LPSW-19 (3B RBCU INLET) fails closed /I Must actually initiate a power reduction 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> within 1 C. 3A RBS Pump declared inoperable /I Within 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> determine a time to initiate power reduction D. 3A RBS Pump declared inoperable I/ Must actually initiate a power reduction within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1

2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT 1

Question 88 Plant initial conditions:

• All three ONS units reactor power = = 100%

• STBY Buses 1 1 AND 2 energized from Central Switchyard Current conditions:

• STBY Bus 1 1 locks out Based on the above conditions, which ONE of the following describes the operability of the Keowee Underground power path AND if Oconee Unit 1 1 experienced a LOCA/LOOP from where would the MFBs LOCAILOOP MFB5 receive power?

Keowee Underground Power path is _ _ _ and Unit 1 Iss MFBs would be energized from - - -

from A. OPERABLE / CT-1 CT-I B. OPERABLE /ICT-5 CT-5 C. NOT OPERABLE / CT-1 CT-l D. NOT OPERABLE I/ CT-5

2010A 2010A NRC NRC SENIOR OPERATOR EXAM SENIOR REACTOR OPERATOR EXAM I1 POINT POINT Question 89 89 Unit I1 plant Unit plant conditions:

• Reactor power == 20%20% stable

• IA Main Feedwater Pump in service 1A Main Based on the above conditions, which ONE ONE of the following will require entry into the EOP AND initial actions directed by the EOP describes the initial AND describes EOP if the NEO NEO dispatched to MSRV's is still MSRV's have reseated reports that one of the MSRVs verify ALL MSRVs still passing steam?

FDWPT Exhaust Vacuum == 23.2 inches HG I/ Transfer to EHT tab A. FDWPT B. FDWPT Exhaust Vacuum == 23.2 inches HG I/ Manually decrease SG pressure C. Feedwater pump bearing oil pressure == 3.1 psig I/ Transfer to EHT tab D. Feedwater pump bearing oil pressure == 3.1 D. 3.1 psig I/ Manually decrease SC SG pressure

2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT 1

Question 90 Unit 11 initial conditions:

• Reactor in MODE 6

• Spent Fuel Pool in Refueling Cooling Mode alignment

• Defueling in progress Current conditions:

• Fuel Transfer Canal level decreasing Based on the above conditions, which ONE of the following describes why AP/26 directs stopping all LPI pumps AND the reason the AP only requires establishing Containment Closure (vs. restoring containment to OPERABLE)?

A. Determine if leak is on discharge of LPI pumps / fuel handling accidents will NOT result in significant Containment pressurization B. Determine if leak is on discharge of LPI pumps I/ with an OPERABLE Containment the Main Purge system cannot be used to clean up RB atmosphere C. Allow closing of 1 1SF-I SF-2 /I fuel handling accidents will NOT result in 1SF-2 SF-1 and 1 significant Containment pressurization D. Allow closing of 1 1SF-I I SF-2 I/ with an OPERABLE Containment the Main SF-1 and 1 Purge system cannot be used to clean up RB atmosphere

SENIOR REACTOR OPERATOR NRC SENIOR 2010A NRC 2010A OPERATOR EXAM I1 POINT Question 91 Unit I1 plant conditions:

• Reactor power == 100%100%

1RC-1 fails open

• 1RC-1 open

• 11RC-3 will NOTNOT close Based on ONE of the following describes the initial on the above conditions, which ONE initial HP-120 (RC VOLUME CONTROL) valve position AND the action(s) response of I1HP-120 AP/44 (Abnormal Pressurizer Pressure Control)?

required by AP144 1

IHP-120 AP/44 will direct actions to _ __

HP-120 valve position will initially ___ AND AP144 approximately the same I trip the reactor and secure the 1A1 A. remain approximately IAI and 1A21A2 RCP's RCPs AP/29, decrease power to <70%, and B. remain approximately the same I enter AP129, secure the 1 A 1 RCP IAI C. fully open I trip the reactor and secure the 1A1 IA1 and 1A2 RCP's RCPs D. fully open I enter AP/29, decrease power to <70%, and secure the 1A1 1AI RCP

2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT 1

Question 92 Unit 3 initial conditions:

power=

• Reactor power = 100%

• The volume of active TSP required by SLC 16.6.10 (Trisodium Phosphate) is NOT met Current conditions:

• LOCAILOOP LOCA/LOOP occurs Based on the above conditions, which ONE of the following describes the consequence of the inadequate TSP volume AND when TSP performs its credited function?

A. ECCS acceptance criteria may be exceeded I/ During the injection phase B. ECCS acceptance criteria may be exceeded I/ During the recirculation phase C. Acceptable offsite dose limits may be exceeded I/ During the injection phase D. Acceptable offsite dose limits may be exceeded I/ During the recirculation phase

2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT 1

Question 93 Unit 3 initial conditions:

• power== 100%

Reactor power

• Fuel movement in Unit 3 Spent Fuel Pool Current conditions:

• 3RIA-6 (SFP) in HIGH alarm

• 3RIA-41 (SFP Gas) in HIGH alarm 3SA-81B9 (PROCESS MONITOR RADIATION HIGH) in alarm

• 3SA-8/B9 Based on the above conditions, which ONE of the following describes the Abnormal Procedure of the highest priority and the Outside Air Booster Fans that will be started as part of the mitigating actions?

A. AP/9 (Spent Fuel Damage) I/ Unit 3 Outside Air Booster Fans ONLY API9 (Spent Fuel Damage) I/ Unit 1 B. AP/9 I and 2 AND Unit 3 Outside Air Booster Fans APII8 (Abnormal Release of Radioactivity) /I Unit 3 Outside Air Booster Fans ONLY C. AP/18 D. API18 AP/18 (Abnormal Release of Radioactivity) /I Unit 1 1 and 2 AND Unit 3 Outside Air Booster Fans

2010A NRC SENIOR REACTOR OPERATOR EXAM 1I POINT Question 94 Which ONE of the following describes a condition that would require making a plant page to implement Emergency Dose Limits AND whether that leakage would be included when calculating RCS Pressure Boundary leakage leakacie (gpm) as defined in Tech Spec 3.4.13 (RCS Operational Leakage)?

A. 45 gpm SGTR / no B. 45 gpm SGTR / yes 45gpmSGTR C. 125 gpm RCS leak in RCP suction pipe weld / no D. 125 gpm RCS leak in RCP suction pipe weld / yes

2010A NRC SENIOR REACTOR OPERATOR EXAM 1I POINT Question 95 Unit 2 initial conditions:

• 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 Current conditions:

• Refueling SRO desires stopping the 2A LPI Pump to aid in inserting a fuel assembly

• 2A LPI pump has been in continuous operation for the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Based on the above conditions, which ONE of the following describes whether the 2A OPI2IA/1502/007 (Operations Defueling LPI pump may be stopped in accordance with OP/21A11502/007

/Refueling Responsibilities) and the Tech Spec bases for requiring only 1I OPERABLE IRefueling DHR loop in this condition?

A. 2A LPI Pump may be stopped for up to 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.

FTC level is within TS limits and provides adequate backup decay heat removal.

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

Spent Fuel Cooling system provides adequate backup decay heat removal.

C. 2A LPI Pump may NOT be stopped FTC level is below TS limits and cannot provide adequate backup decay heat removal.

D. 2A LPI Pump may NOT be stopped Spent Fuel Cooling system can NOT provide adequate backup decay heat removal.

2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT 1

Question 96 Unit 1I plant conditions:

• Reactor power = = 75% stable

• Regulating rods positioned in the Unacceptable region of the rod curves provided in the COLR Which ONE of the following describes the ...

conditions...

(1) direction that will be given to the OATC based on the above plant conditions ...

AND (2) consequences of continued power operations while in the Unacceptable Operation region of the rod curves in the COLR in accordance with the bases for forTS TS 3.2.1 (Regulating Rods Position Limits)?

RCS boration using _ _ is required AND...

reciuired to begin within 15 minutes AND ...

A. 1A BHUT I/ required shutdown margin may not exist B. 1A BHUT /I Quadrant Power Tilt limits may be exceeded C. Unit 1 I CBAST /I required shutdown margin may not exist D. Unit 1 1 CBAST I/ Quadrant Power Tilt limits may be exceeded

2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT 1

Question 97 Unit 3 plant conditions:

• LPI aligned to normal DHR mode using 3A LPI pump

• Both SG levels = = 65% OR increasing using 3A and 3B MDEFWP's MDEFWPs

• LR Cooldown pressure = = 290 psig stable

• 3TA 3T A and 3TB de-energized

• CETCs CETC's = = 196°F stable

• RCS Tcold = 205°F stable

• 3A LPI Cooler Outlet temperature = = 195°F stable Based on the above conditions, which ONE of the following describes the current plant MODE AND if the SG'sSGs can be used as a backup method of heat removal in accordance with Tech Specs?

MODE44 /I no A. MODE B. MODE 4 /I yes MODE55 I/ no C. MODE D. MODE 5 /I yes

2010A NRC SENIOR REACTOR OPERATOR EXAM I POINT 1

Question 98 Which ONE of the following describes the maximum dose (TEDE) that a non-volunteer RP/0/BI1 000/11 can receive while saving a life and whose approval is required per RP/O/B/1000/11 (Planned Emergency Exposure).

A. 10 rem 1/ Emergency Coordinator B. 10 rem 1/ Site Vice President C. 25 rem 1/ Emergency Coordinator D. 25 rem 1/ Site Vice President

2010A NRC 2010A SENIOR REACTOR OPERATOR NRC SENIOR OPERATOR EXAM EXAM I1 POINT Question 99 Plant conditions:

• All 33 Units reactor power == 100%

100%

• 1SA-3/B6 (FIRE ALARM) actuated 1SA-3/B6 (FIRE

• NEDs NEO's dispatched and 22 Powdex area) dispatched to the Turbine Building Basement (Unit I1 and area)

Current conditions:

• NEONEO reports: Fire location is TBB/K28. Heavy smoke and rolling flames (5-loft.)

(5-1 Oft.)

spreading out from the Powdex Alarm Panel Based on the above conditions, which ONE of the following describes the unit(s) requiring a reactor trip AND who is allowed to serve as a Fire Brigade leader in accordance with the bases of SLC 16.13.1 (Minimum Station Staffing Requirements)?

REFERENCE PROVIDED A. ALL units I/ SRO ONLY B. Unit 2 (only) I/ SRO ONLY C. ALL units I/ SRO OR an NEO NED with appropriate qualifications D. Unit 2 (only) I SRO OR an NEO D. NED with appropriate qualifications

2010A NRC 2010A SENIOR REACTOR OPERATOR EXAM NRC SENIOR EXAM 11 POINT POINT Question 100 100 Unit 11 initial conditions:

• Reactor power == 100% 100%

• 11RIA-59 reading 22 gpm gpm slowly increasing increasing

• AP/31 (Primary to to Secondary Leakage) in progress Current conditions:

• Reactor power == 75% decreasing 1RIA-59 reading 28 gpm increasing

• 1RIA-59 Based on the above conditions, which ONE of the following describes how the SRO will proceed AND the actions required ifif during the subsequent RCS cooldown if the (285" XSUR)?

isolated steam generator approaches overfill conditions (285 A. Continue shutdown under the direction of AP/31 I Initiate SG Blowdown B. Continue shutdown under the direction of AP/31API3I I/ Steam the SG to the condenser C. Go directly to SGTR tab I/ Initiate SG Blowdown D. Go directly to SGTR tab I Steam the SG to the condenser

Oconee 2010-301 Oconee Exam References 2010-301 Exam References RO Exam:

RO Exam:

Steam Tables Steam Unit 11 Loop Unit Loop A Narrow Narrow Range Range PT PT Plot Plot SROExam:

SRO Exam:

RP/O/8/10001001 RPIOIBII (Emergency Classificalion) 000/001 (Emergency Classification)

(TIS) 3.4.9 Technical Specification (T/S) 3.4.9 (Pressurizer)

TIS 3.8.8 (Distribution Systems T/S 3.8.8 Systems - Operating) 8-6 pages 2-28.

1SA-03 B-6 Alarm Response Guide 1SA-03

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