ML13296A028

Initial Exam 2013-301 Final SRO Written Exam

ML13296A028
Person / Time
Site:	Hatch
Issue date:	10/18/2013
From:	Division of Nuclear Materials Safety II
To:	Southern Nuclear Operating Co
References
Download: ML13296A028 (129)

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: E. I. HATCH 2013-301 SRO NRC EXAM MASTER EXAM th, 19 Date: September 2013 Facility/Unit: Plant E. I. Hatch Region: I II X iii IV Reactor Type: W CE BW GE X 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 SRQ portion.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicants Signature Results RO/SRO-Only/Total Examination Values / / Points Applicants Scores / / Points Applicants Grade / / Percent

ILT-08 SRO NRC EXAM

1. 201003A2.09 001 UNIT 1 Reactor Startup is in progress with control rod 22-43 at position 12.

o Reactor Pressure is 780 psig A malfunction in the CRD system results in the following:

o Charging Water Pressure is 890 psig o CRD ACCUMULATOR PRESS LOW OR LEVEL HIGH, (603-148) o HCU 22-43 local Accumulator pressure is 910 psig o Highest CRDM temperature is 240°F LAW 34AB-C1 1-00 1, Loss of CRD System, the next REQUIRED action, and the BASES for the action, is to A immediately scram the reactor JAW 34AB-C71-001-1, Scram Procedure, because withdrawn control rods may fail to completely scram at lower reactor pressures B. immediately scram the reactor lAW 34AB-C71-001-1, Scram Procedure, because withdrawn control rods may experience slower scram times due to over heating C. restore charging water header pressure to 940 psig within 20 minutes because withdrawn control rods may fail to completely scram at lower reactor pressures D. restore charging water header pressure to 940 psig within 20 minutes because withdrawn control rods may experience slower scram times due to over heating

ILT-08 SRO NRC EXAM

2. 203000K6.02 001 UNIT 2 is operating at RTP.

At 12:55 125V DC CABINET 2D, 2R25-S004 is deenergized and the following annunciators are actuated:

o LOSS OF OFF SITE POWER, (652-102) o 4160V BUS 2E OR 600V BUS 2C DC OFF, (652-115) o BATIERY VOLTS LOW OR FUSE TROUBLE, (652-119) o BATFERY CHARGER MALFUNCTION, (652-120)

At 13:00 a LOCA on UNIT 2 occurs.

At 13:02 ONLY the RHR pumps will have automatically started and be available for LPCI injection.

A. AandB B. AandD Cv B and C D. CandD 2

ILT-08 SRO NRC EXAM

3. 204000K1.15 001 UNIT 2 is at RTP with 2G31-COO1A, A RWCU Pump in service.

At 12:00 the following annunciator illuminates:

RWCU SYS LEAK, (602-421)

The above annunciator actuates when RWCU System differential flow exceeds the setpoint of gpm.

At 12:01, the A RWCU Pump will A 56; have tripped B. 56; continue operating C. 60; have tripped D. 60; continue operating 3

ILT-08 SRO NRC EXAM

4. 205000K5.02 001 Unit 2 is shutdown with the A loop of RHR in Shutdown Cooling (SDC).

RWCU is in service controlling reactor water level.

The following occurs:

Time Event 10:00 2G31-F033, RWCU Dump valve, fails open and cannot be closed 10:35 RWL is two (2) inches AND 2G31-F033 is isolated 10:40 An operator restores RWL to normal At 10:40, with NO additional operator action, 2E1 1-F008, RHR SDC Suction valve, will and the RHR pump will A have traveled close; have tripped B. have traveled close; still be operating C. remain open; have tripped D. remain open; still be operating 4

ILT-08 SRO NRC EXAM

5. 205000K5.03 001 Unit 1 is in Mode 4 with Shutdown Cooling in service.

The following conditions exist:

o Recirculation Pumps Secured o RHR B Pump flow 5500 gpm o All other RHR Pumps Standby lAW 34S0-E1 1-010-1, Residual Heat Removal System, which ONE of the following identifies the MiNIMUM corrected reactor water level that must be maintained by the OATC?

A. +32 B. +34 C. +42 D +54 5

ILT-08 SRO NRC EXAM

6. 206000A 1.08 001 Unit 2 is shutdown with HPCI operating in Pressure Control mode.

An event occurs causing CST level to start decreasing.

The leak is isolated with current CST level stable at 20 inches.

Five (5) minutes after CST level stabilizes at 20 inches, 2E41 -F004, CST Suction valve, will and HPCI will be operating A. have traveled closed; in Pressure Control mode B have traveled closed; on Minimum Flow C. still be open; in Pressure Control mode D. still be open; on Minimum Flow 6

ILT-08 SRO NRC EXAM

7. 209001K3.01 001 Following a Loss of Coolant Accident (LOCA) on Unit 1 AND a loss of all RHR pumps.

Both Core Spray pumps and RHR Service Water (RHRSW) pump ID are operating to maintain reactor water level. The following plant conditions currently exist:

o RPV level -65 inches and steady o Core Spray pump 1A flow 2100 gpm o Core Spray pump lB flow 4200 gpm o RHRSW pump 1D flow 4000 gpm Subsequently, lE 4160 VAC bus de-energizes.

Which ONE of the choices below completes the following statement?

After lE 4160 VAC bus de-energizes, RPV water level will start decreasing at a rate equivalent to a loss of approximately gpm of injection flow.

A 2100 B. 4200 C. 6100 D. 8200 7

ILT-08 SRO NRC EXAM

8. 209001K3.03 001 Unit 2 was operating at 100% RTP when the following alarms are received:

o 601-107, Core Spray Sys II Logic Power Failure, alarm, ILLUMINATED o 601-310, Core Spray Sys I Logic Power Failure, alarm, ILLUMINATED Subsequently, a break inside the Drywell results in the following:

o Drywell pressure 1.9 psig slowly rising o RWL -108 inches and steady o RHR pumps Running on minimum flow Which ONE of the choices below completes the following statements?

The Emergency Diesel Generators automatically start.

The Core Spray pumps be manually started.

A. will NOT; can NOT Bb will NOT; can C. will; can NOT D. will; can 8

ILT-08 SRO NRC EXAM

9. 211000K2.02 001 Unit 2 is at 100% power when a loss of a 600 VAC Motor Control Center (MCC) occurs.

The following equipment indications exist:

o 2E1 1-F009, RHR SDC Suction Vlv Indication is available o 2E11-FO15B, RHR Inboard Injection Vlv Indication is available o 2E21-FO15B, Core Spray Test Vlv Indication is NOT available o RPS Alternate Power Available Light Indication is NOT available With these indications, If SBLC injection is required, SLC pump will START and SBLC squib valve(s) will fire.

A ONLY the 2A; ONLY ONE B. ONLY the 2A; BOTH C. ONLY the 2W; ONLY ONE D. ONLY the2B BOTH 9

ILT-08 SRO NRC EXAM

10. 212000A3.02 001 Given the following plant conditions on Unit 2:

o Reactor Water Level Narrow Range, 2B21-NO8OB, has failed downscale.

F&II&1 BI B2 I 2B21- 2B21 NOSOB NOSOD 2B21- I T2B21-1 N6SOB I N6SOD TI 2C71A-K6B K6D Trip Logic 2C71A- 2C71A-6B I 2C71A-Ki j

(. 2C71A-

>KI4DJ9 Which ONE of the following describes the Reactor Protection System (RPS) Response?

The 2C71A-K14B relay will be The solenoids for the Backup Scram Valves will be A. Deenergized; Energized B Deenergized; Deenergized C. Energized; Energized D. Energized; Deenergized 10

ILT-08 SRO NRC EXAM

11. 212000A4.15 001 UNIT 2 is operating at 90% RTP when a transient occurs resulting in the following conditions:

o Reactor Pressure is currently 930 psig (highest reached 1100 psig) o RWL is currently +37 inches (lowest reached -65 inches)

The following indications exist on 2H1 1-P602 panel:

ASDA ASDB 2B31-SOO2A 2B31 -S002B 2R22-SOO1 2R22-S002 Fc7 PULL TO STAR LOCK U

NOTE: All green lights above are ILLUMINATED All red lights above are EXTINGUISHED With the above conditions, The ASD A and B Input Breakers The risk of thermal stratification will be REDUCED by A responded as designed; resetting the reactor scram B. responded as designed; maximizing CRD flow C. did NOT respond as designed; resetting the reactor scram D. did NOT respond as designed; maximizing CRD flow 11

ILT-08 SRO NRC EXAM

12. 215001A4.03 001 Unit 2 is operating at 100% RTP with the A Channel Transversing In-Core Probe (TIP) inserted in the core.

o Steam is being discharged into Unit 2 Reactor Building o The steam is confirmed to be coming from the TIP room o A manual scram is inserted o RWL lowers to -20 before being restored to +9 inches o Five (5) minutes after a manual withdrawal command was initiated, the status of the A Channel TIP is indicated below:

Five (5) minutes after the manual withdrawal command was initiated, the EXPECTED location of the A TIP is in the position, and Based on the above conditions, the A TIP Shear valve to be fired LAW 34AB-C71-001-2, Scram Procedure.

AY In Shield; is REQUIRED B. In Shield; is NOT REQUIRED C. Indexer (Parked);

is REQUIRED D. Indexer (Parked);

is NOT REQUIRED 12

ILT-08 SRO NRC EXAM

13. 215002G2.4.4 001 Unit 2 operating at 62% of RTP and performing a rod pattern adjustment.

The current step is to withdraw Control Rod (CR) 42-39 from position 28 to position 30.

After releasing the rod movement control switch the following indications exist:

o 603-202, REM UPSCALE OR iNOPERATiVE o 603-23 8, ROD OUT BLOCK o Rod Withdraw Permissive light is EXTINGUISHED o CR 42-39 settles at position 34 With the above plant conditions, the operator is REQUIRED to enter A. 34AB-C71-001-2, Scram Procedure, and scram the reactor B. 34AB-C1l-005-2, Control Rod Insertion Methods, and drive in CR 42-39 to position 02 C. 34G0-OPS-065-0, Control Rod Movement, and immediately return CR 42-39 to its correct position D 34AB-C 11-004-2, Mispositioned Control Rods, and recover CR 42-39 per reactor engineering recommendations 13

ILT-08 SRO NRC EXAM

14. 215003K4.05 001 Unit 2 is starting up with the following indications observed at 2H1 1-P603:

The following lights are iLLUMINATED:

-IRMAthruH-IN

- IRM A thru H RETRCT PERMIT

- IRM A thru H SELECT

- POWER ON IRMA IRUB SELECT sLiicr IRMC Ill, rTj uwo SELECI I

RUt SEI.ECT RUG I RUH SELECIj SELECT iMIV ° I I DRNE o All Source Range Monitors (SRM) and Intermediate Range Monitors (IRM) were selected and driven in following a scram 3 days ago.

The Drive Out button is depressed for 15 seconds and then released with NO change occurring in these indications.

Based on the above conditions the MINIMUM action(s) required to withdraw the IRMs is to A. depress the Drive Out button an additional time B depress the Drive In button, then depress the Drive Out button C. clear the Retract Permit light, then depress the Drive Out button D. depress the Power On button twice, then depress the Drive Out button 14

ILT-08 SRO NRC EXAM

15. 215004K1.02 001 A Unit 2 reactor startup is in progress with the following indications:

o All IRMs are indicating between 20/125 60/125 on Range 6 HIGHEST indicating SRMs:

o SRMA 1.5xlO c

5 ps o SRM B 8.0 x iO cps mEouE[]

ROO ROD IN OUT ROD MOVEMENT CONTROL Li With the above indications, the Reactor Manual Control ROD OUT light will be due to A. EXTINGUISHED; SRM A ONLY B EXTINGUISHED; BOTH SRM A and SRM B C. ILLUMINATED; SRM A ONLY D. ILLUMINATED; BOTH SRM A and SRM B 15

ILT-08 SRO NRC EXAM

16. 215005A4.06 001 Which one of the following completes the statement below regarding the Power Range Neutron Monitoring System Operability?

JAW 34SV-C51.-003-l, LPRM Operational Status, each APRM must have a MINIMUM of Operable LPRMs, with AT LEAST Operable LPRMs per axial level to be considered operable.

A. 14; 1

B. 14; 3

C. 17; 1

D 17; 3

16

ILT-08 SRO NRC EXAM

17. 217000K5.06 001 34SV-E51-002-2, RCIC Pump Operability Surveillance, is in progress on Unit 2.

The MINIMUM RCIC turbine speed required for prolonged operation which ensures adequate oil pressure for proper turbine governor operation is rpm.

During RCIC pump operation, the Torus water temperature will increase at a rate of approximately °F/hr.

A. 3000; 3

B. 3000; 30 0 2000; 3

D. 2000; 30 17

llT-08 SRO NRC EXAM

18. 218000K3.01 001 Unit 2 was at 100% RTP when the following occurred concurrently:

o Loss of Coolant Accident (LOCA) o A complete Loss of Off Site Power (LOSP)

At 0800, the following conditions exist:

o Reactor water level 95?, DECREASING 2 per minute o Reactor pressure 900 psig, DECREASING 25 psig per minute o Drywell pressure 4.0 psig, slowly INCREASiNG The following ADS panel indications concurrently exist:

Based on the above conditions and with NO additional operator actions, which ONE of the choices below completes the following statement?

At 0820, ONLY will be injecting into the RPV.

A. HPCI B Core Spray and RHR C. HPCI and the Cond. Booster Pumps D. Core Spray, RHR and the Cond. Booster Pumps 18

ILT-08 SRO NRC EXAM

19. 223001A3.05 001 Unit 2 experiences a transient from 100% RTP with SPDS out of service.

The following conditions occur:

o HPCI Equipment Room Temp High is 155°F o RWL is +37 inches (lowest RWL reached +9 inches) o Drywell Pressure is 1.9 psig Based on the above conditions, the valves will AUTOMATICALLY isolate, and the associated valves can be verified isolated by monitoring indications on A PCIV Group II; 2H1 1-P601 and P700 panels B. PCIV Group II; ONLY 2H1 1-P601 panel C. PCIV Group ifi; 2H11-P601 and P700 panels D. PCIV Group ifi; ONLY 2H1 1-P601 panel 19

ILT-08 SRO NRC EXAM

20. 223002A2.11 001 Unit 2 Main Control Room has been evacuated.

Local SBLC injection is required due to an ATWS condition.

When initiating SBLC from outside the Control Room, A. 2G3 1-FOOl, RWCU Inboard Isolation, must be closed from the valve breaker on 2R24-S022, 250V D.C. MCC 2B-ESS DIV 1 B. 2G3 1-FOOl, RWCU Inboard Isolation, will automatically close when a SBLC pump is started C 2G31-F004, RWCU Outboard Isolation, must be closed from the valve breaker on 2R24-S022, 250V D.C. MCC 2B-ESS DIV 1 D. 2G31-F004, RWCU Outboard Isolation, will automatically close when a SBLC pump is started 20

ILT-08 SRO NRC EXAM

21. 226001K6.04 001 Unit 2 is operating at 100% RTP when the following annunicator is received:

o 601-333, JOCKEY PUMP SYS A DISCH PRESS LOW o Jockey Pump System A discharge pressure is 45 psig Based on the above conditions, a Core Spray Jockey Pump receive an automatic start signal.

If this condition is NOT corrected, the potential exist to drain of RHR Drywell Spray piping.

A. will; BOTH divisions B will; ONLY one (1) division C. will NOT; BOTH divisions D. will NOT; ONLY one (1) division 21

ILT-08 SRO NRC EXAM

22. 233000K4.06 001 Unit 2 is in a refueling outage when a rupture of the Fuel Pool Cooling and Cleanup (FPCC) return line to the fuel pool occurs.

Which ONE of the following identifies the FPCC pump low suction pressure trip setpoint and a design feature which will minimize the inventory loss from the Fuel Pool?

A 8 psig; The Anti-Siphon check valves on the return lines re-position B. 8psig; The Diffusers on the return lines become uncovered C. 18 psig; The Anti-Siphon check valves on the return lines re-position D. l8psig; The Diffusers on the return lines become uncovered 22

ILT-08 SRO NRC EXAM

23. 239001K5.05 001 Unit 2 is at 5% RTP with the Reactor Mode switch in STARTUP when the following annunciator is received:

o 603-214, MAIN STEAM LINE FLOW A HIGH The MINIMUM listed value that will cause 603-2 14, MAIN STEAM LINE FLOW A HIGH, alarm to be received is The Main Steam Line High Flow isolation signal bypassed in STARTUP.

A. 170 psid; is B 170 psid; is NOT C. 137 psid; is D. 137 psid; is NOT 23

ILT-08 SRO NRC EXAM

24. 239002K2.01 001 Which ONE of the following combinations are the power supplies to the Unit 2 SRV solenoids?

A 2R25-SOOl, 125V DC CABINET 2A and 2R25-S002, 125V DC CABINET 2B B. 2R25-S002, 125V DC CABINET 2B and 2R25S003, 125V DC CABINET 2C C. 2R25-S003, 125V DC CABINET 2C and 2R25-S004, 125V DC CABINET 2D D. 2R25-S004, 125V DC CABINET 2D and 2R25-S005, 125V DC CABINET 2E 24

ThT-08 SRO NRC EXAM

25. 241000K3.03 001 Unit 2 is operating at 15% RTP with the Main Turbine in Chest Warming.

Subsequently, throttle pressure transmitters malfunction causing all Main Turbine Bypass Valves to fully open.

When the Main Turbine Bypass Valves open, indicated Reactor Water Level will INITIALLY________

Selecting the Close Valves button on the Turbine HMI screen CLOSE the Main Turbine Bypass valves.

A. decrease; will NOT B. decrease; will C increase; will NOT D. increase; will 25

ILT-08 SRO NRC EXAM

26. 245000K4.10 001 Which ONE of the choices below completes the following statement?

During a main turbine trip, all extraction non-return (ENR) check valves supplying steam to the feedwater heaters will and the 2N11-FOO4A&B, 2nd Stage MSR Reheat Steam Supply Valves, will A. remain open; remain open B. remain open; automatically close C automatically close; remain open D. automatically close; automatically close 26

ILT-08 SRO NRC EXAM

27. 259002A4.08 001 Unit 2 is at 50% power, performing a Startup.

o Reactor Feed Pump Turbine (RFPT) 2B is in service in automatic control Due to intermittent problems with the 2A RFPT M/A station, 2C32-R6O1A, Maintenance has taken 2C32-R6O1A to the maintenance shop for repair.

The Shift Supervisor directs placing the 2A RFPT in service lAW 34S0-N21-007-2, Condensate and Feedwater System, section 7.3.7, RFPT Alternate Startup.

The reason that the 2A RFPT speed will initially be stopped at 1000 RPM is to In this mode of operation, the Speed Setter switch can raise the 2A RFPT speed to a MAXIMUM value of_______

A allow oil temperature to increase; 5800rpm B. allow oil temperature to increase; 3500rpm C. verify proper operation of the trip circuit; 5800rpm D. verify proper operation of the trip circuit; 3500rpm 27

ILT-08 SRO NRC EXAM

28. 261000A2.07 001 An electrical fault on Unit 2 results in 2R25-S036, ESSENTIAL CABINET 2A, de-energizing.

The effect the loss of this bus will have on the Unit 2 SBGT System is that 2T46- FOO1A, SBGT Filter Inlet & 2T46-FOO2A, SBGT Fan 2A Disch Dampers will fail With regards to SBGT system the crew will enter A Open; 34AB-R25-002-2, Loss Of Instrument Buses, and manually start 2B SBGT fan B. Open; 34AB-T22-003-2, Secondary Containment Control, and confirm automatic start of 2B SBGT System C. Closed; 34AB-R25-002-2, Loss Of Instrument Buses, and manually start 2B SBGT fan D. Closed; 34AB-T22-003-2, Secondary Containment Control, and confirm automatic start of 2B SBGT System 28

JLT-08 SRO NRC EXAM

29. 261000K1.03 001 JAW 31E0-EOP-012-2, Primary Containment Control (PC Flow Chart), the MAXIMUM listed Suppression Pool Water Level that ALLOWS venting of the Suppression Chamber using the Standby Gas Treament System is A. 190 inches B. 210 inches C 290 inches D. 340 inches 29

ThT-08 SRO NRC EXAM

30. 262001K6.03 001 Unit 2 is operating at 100% RTP.

o 4160 VAC 2E, 2R22-S005, is powered from Startup Auxilary Transformer (SAT) 2C Subsequently, GENERATOR PROTECTION CIRCUIT ENERGIZED, (65 1-206), annunciator is received.

Generator amps MUST be below a MAXIMUM of__________________ in 2 minutes, or a Main Generator trip will occur.

If the Main Generator trips and with NO operator actions, the MAXIMUM number of Station Service Buses that will be ENERGIZED is A. 6,466 amps; Four (4)

B. 6,466 amps; Zero (0)

C. 20,232 amps; Four (4)

D 20,232 amps; Zero (0) 30

ILT-08 SRO NRC EXAM

31. 262002G2.4.4 001 Unit 2 is operating at 90% RTP.

At 10:00, a loss of electrical power results in the following conditions: (this is a partial list) o Reactor power begins increasing at 0.2% per minute o Loss of rod position information system (RPIS) o Loss of RWL and RPV pressure recorders on 2H1 1-P603 o Main Condenser vacuum is 27.5 in. Hg vac, lowering at 0.2 in. Hg vac per minute At 10:02, maintenance is dispatched to investigate the electrical power loss.

At 10:04, with the above plant conditions, entry into , is REQUIRED.

A. 34AB-R25-00l-2, Loss of Vital AC, and 34AB-C71-001-2, SCRAM Procedure B. 34AB-R25-002-2, Loss of Instrument Buses, and 34AB-C71-001-2, SCRAM Procedure C 34AB-R25-001-2, Loss of Vital AC, and 34AB-N21-001-2, Loss of Feedwater Heating D. 34AB-R25-002-2, Loss of Instrument Buses, and 34AB-N21-001-2, Loss of Feedwater Heating 31

ThT-08 SRO NRC EXAM

32. 263000A3.01 001 The Unit 2 Station Service Battery Charger amps can be monitored on Panel If 600 VAC 2C, 2R23-5003, deenergizes, the associated 600 VAC supply breakers to the 125/250 VDC Station Service Battery Chargers AUTOMATICALLY open.

A. 2H11-P651; will B. 2H1lP65l; will NOT Cv 2H11-P655; will D. 2H11-P655; will NOT 32

ILT-08 SRO NRC EXAM

33. 264000G2.2.42 001 Unit 2 is in MODE 2 with EDG 2A semi-annual surveillance in progress. The EDG 2A mode switch is in TEST and is paralleled to the bus.

The following conditions occur:

o EDG 2A Lube Oil Temperature increases and peaks at 235°F o EDG 2A Jacket Coolant Temperature increases and peaks at 200°F o EDG2Atrips EDG 2A received a trip signal from LAW TS REQUIRED to be operable for the current plant mode.

A. Lube Oil Temperature; ONLY one Unit 2 EDG is B Lube Oil Temperature; BOTH Unit 2 EDGs are C. Jacket Coolant Temperature; ONLY one Unit 2 EDG is D. Jacket Coolant Temperature; BOTH Unit 2 EDGs are 33

ILT-08 SRO NRC EXAM

34. 268000A1.02 001 Unit 2 Radwaste is performing a discharge to the canal.

The Radwaste discharge to the canal if dilution flow drops to 9,500 gpm AND if a specific discharge is terminated, permissible with the existing permit.

A. will automatically terminate; NO restarts are B will automatically terminate; ONLY one (1) restart is C. must be manually terminated; NO restarts are D. must be manually terminated; ONLY one (1) restart is 34

ILT-08 SRO NRC EXAM

35. 286000K2.02 001 An earthquake occurs resulting in the following plant conditions:

o Fire header piping ruptures lowest header pressure reached was 87 psig o 1E 4160 VAC Bus DEENERGIZES (cannot be restored) o 2F 4160 VAC Bus DEENERGIZES (cannot be restored)

Assuming that this is the LOWEST pressure achieved, which ONE of the following predicts how the fire pumps respond?

A. ONLY the electric fire pump starts B ONLY the A and B diesel fire pumps start C. ONLY the electric fire pump and the A diesel fire pump starts D. BOTH the A and B diesel fire pumps and the electric fire pump starts 35

1LT-08 SRO NRC EXAM

36. 295001AK2.06 001 Unit 2 is operating at 96% RTP with 92% Core Flow when a malfunction occurs resulting in the following conditions:

o The 2K Condensate Booster pump (CBP) trips o The 2A Reactor Feedwater pump trips o +24 inches is the lowest Reactor Water Level during the transient Plani Fhiicli U2 Power/Flow Map (2804 MWth)

APRM TP S.im L:n

/II) RI( ,I(

-L Spid Linukr PiniiV ti !fl (ii. I Iu MIbm IH i + 46.2)

Core Flow (% of Rated) Rd. 4GOOPS1)o52 After the plant stabilizes and with NO operator action, the plant will be operating at approximately on the Power To Flow Map above.

A Point A B. PointB C. Point C D. PointD 36

ILT-08 SRO NRC EXAM

37. 295003AK1.02 001 Unit 2 RHR Loop A is in Suppression Pool Cooling mode.

At 12:00, A LOSS OF OFF SiTE POWER occurs on Unit 2.

At 12:10, Plant conditions are:

o Emergency buses ENERGIZED o Reactor water level: -80 inches (stable) o RPV pressure: 980 PSIG o Drywell pressure: 1.9 PSIG (stable)

At 12:15, and with NO operator action, A. ALL RHR and RHRSW pumps will be off B ALL RHR pumps will be running and ALL RHRSW pumps will be off C. ONLY the RHR and RHRSW pumps which were running prior to 12:00 will be running D. ONLY the RHR pumps which were running prior to 12:00 will be running and ALL RHRSW pumps will be ff 37

llT-08 SRO NRC EXAM

38. 295004G2.1.7 001 Unit 2 is operating at 100% RTP when the following panel indications occur:

Subsequently, o Unit 2 Reactor is manually scrammed o Main turbine is manually tripped o Main Generator output breakers are opened o 4160 VAC Station Service Buses 2A-2D DEENERGIZED when the Main Generator output breakers were opened For the above conditions:

4160 VAC Station Service Buses, 2A-2D, respond as expected.

If needed for RWL control, can be used for injection.

A. did; RCIC B did; HPCI C. did NOT; RCIC D. did NOT; F{PCI 38

ILT-08 SRO NRC EXAM

39. 295005AK3.02 001 Unit 2 is operating at the end of the current fuel cycle.

The function of the End Of Cycle Recirc Pump Trip (EOC-RPT) on a Main Turbine trip, is to provide additional margin to the The used for determining the thermal power at which the EOC-RPT function is activated.

A. Average Planar Linear Heat Generation Rate (APLHGR) Thermal limit; APRMs are B. Average Planar Linear Heat Generation Rate (APLHGR) Thermal limit; Main Turbine First Stage Pressure is C. Minimum Critical Power Ratio (MCPR) Safety limit; APRMs are D Minimum Critical Power Ratio (MCPR) Safety limit; Main Turbine First Stage Pressure is 39

ILT-08 SRO NRC EXAM

40. 295006AA1.01 001 Unit 1 is in a refueling outage.

o Reactor Mode Switch position REFUEL o SRM Shorting Links INSTALLED Subsequently, the following occurs:

o 1C IRM fails upscale.

What is the expected status of the 1H1 l-P603 panel WHITE RPS Scram Group A and B lights?

RPS Scram Group A WHITE lights are expected to be RPS Scram Group B WHITE lights are expected to be A. EXTINGUISHED; EXTINGUISHED B EXTINGUISHED; ILLUMINAThD C. ILLUMINATED; EXTINGUISHED D. ILLUMINATED; ILLUMINATED 40

ILT-08 SRO NRC EXAM

41. 295009AK1.02 001 Unit 1 is at 35% RTP with the 1A RFPT in service, when a malfunction results in a reduction in Feedwater flow and a lowering RWL.

Speed Limiter #1 will FIRST be activated when for at least 15 seconds and is designed to maintain A. RWL reduces to +20 inches; NPSH for the Recirc Pumps B. RWL reduces to +20 inches; Plant availability ONLY C Total feedwater flow reduces to less than 20%;

NPSH for the Recirc Pumps D. Total feedwater flow reduces to less than 20%;

Plant availability ONLY 41

ILT-08 SRO NRC EXAM

42. 295010AA2.06 001 Unit 2 was operating at 100% RTP when a leak occurred inside the drywell.

At 9:55, the reactor is shutdown.

At 10:00, the following conditions exist:

o Bulk Average Drywell Temperature is 140°F, increasing at 5°F per minute o Drywell Pressure is 1.0 psig, increasing at 0.5 psig per minute Given that the leak remains constant, the Primary Containment temperature and pressure rate of increase at 10:05, will be the rate at 10:00.

At 10:05, JAW 34AB-T23-002-2, Small Pipe Break Inside Primary Containment, RPV water level corrections REQUIRED to be performed.

A. higher than; are NOT B higher than; are C. the same as; are NOT D. the same as; are 42

ILT-08 SRO NRC EXAM

43. 295012AK3.O1 001 Unit 2 is at 100% RTP when Drywell (DW) Temperature starts slowly increasing.

The following DW cooling fans are in STANDBY (ALL other DW cooling fans are operating with their control switches in RUN):

o 2T47-BOO8B o 2T47-BOO9B With the current DW cooling fan alignment, 2T47-BOO8B be MANUALLY started to provide additional DW cooling.

Exceeding the Primary Containment Design Temperature of may result in the degradation of the Primary Containment structure under accident loads.

A. CAN; 281°F B. CAN; 340°F C. CANNOT; 28 1°F L CAN NOT; 340°F 43

ILT-08 SRO NRC EXAM

44. 295013G2.4.18 001 Unit 1 is operating at 75% with the following conditions:

o Safety Relief Valve (SRV) IGI? is leaking o Torus temperature 102°F, and increasing slowly The LOWEST Torus temperature which REQUIRES placing the Rx Mode Switch in Shutdown occurs at a Torus temperature of The EOP bases for placing the Rx Mode Switch in Shutdown at this Torus temperature is A. 111°F; to ensure the MINIMUM NPSH is maintained for RCTC and ECCS pumps taking a suction from the Torus B 111°F; because this value EXCEEDS the MAXIMUM allowed by Unit 1 Technical Specifications C. 121°F; to ensure the MINIMUM NPSH is maintained for RCIC and ECCS pumps taking a suction from the Torus D. 121°F; because this value EXCEEDS the MAXIMUM allowed by Unit 1 Technical Specifications 44

ThT-08 SRO NRC EXAM

45. 295016AA2.07 001 The Unit 2 control room has been abandoned and 31RS-OPS-O01-2, Shutdown From Outside Control Room, is being implemented.

Which ONE of the choices below completes the following statements?

Torus pressure can be determined using JAW EOPs, if Unit 2 Torus pressure is determined to be 10.5 psig, REQUIRED to be initiated from outside the Control Room.

A. SPDSintheTSC; BOTH Torus and Drywell Sprays are By SPDS in the TSC; ONLY Torus Spray is C. a permanently mounted gauge on the 87 level of the Reactor Building; BOTH Torus and Drywell Sprays are D. a permanently mounted gauge on the 87 level of the Reactor Building; ONLY Torus Spray is 45

ILT-08 SRO NRC EXAM

46. 295017AA 1.05 001 Unit 2 is operating at 65% RTP, currently shutting down due to suspected fuel leakers.

Subsequently, a steam leak occurs in the Turbine Building resulting in the following:

o 10:00 A Valid Group 1 Isolation signal is generated NO Group 1 Isolation valves change position (Automatically nor Manually) o 10:12 Offsite radioactivity release rate increases to 0.75 mRlhr Which ONE of the choices below completes both statements?

At 10:12, the Offsite radioactivity release rate above the entry condition of 31E0-EOP-014-2, RR RADIOACTIVITY RELEASE CONTROL, EOP flowchart.

At 10:15, the PRIMARY Display on SPDS for the Group 1 Status Indicator box will have BACKGROUND.

A is; aRED B. is; an ORANGE C. is NOT; aRED D. is NOT; an ORANGE 46

ILT-08 SRO NRC EXAM

47. 295018AK3.06 001 Unit 2 is operating at 5% power with PSW/RBCCW Hx dP adjusted to 12 psid.

Subsequently, two (2) RBCCW pumps fail and will NOT run.

NOTE: 2P41-F491, PSW Outlet Valve From RBCCW Hx With the two (2) RBCCW pumps failed, annunciator, HX PSW/RBCCW DIFF PRESS LOW, (650-238), be ILLUMINATED.

To RETURN the PSW/RBCCW Hx dP to 12 psid, the SO will throttle 2P41-F491 in the direction.

A. will; CLOSE B. will; OPEN C. will NOT; CLOSE D will NOT; OPEN 47

ILT-08 SRO NRC EXAM

48. 2950 19AA2.02 001 Unit 1 is operating at 100% power.

o ALL Nitrogen backup system valves to the Non-Interruptible Essential Air Header have been DANGER TAGGED in the closed position Subsequently, the following occurs:

o Unit 1 experiences a loss of all Unit 1 Station Service Air Compressors o The air cross-tie valve between Unit 1 and Unit 2 CANNOT be opened due to a bent stem.

Based on the current plant conditions, which ONE of the following identifies the FINAL MSIV position?

A. The Inboard and Outboard MSIVs will remain OPEN.

B. The Inboard Outboard MSIVs will eventually drift CLOSED.

C The Inboard MSIVs will remain OPEN; The Outboard MSIVs will eventually drift CLOSED.

D. The Inboard MSIVs will eventually drift CLOSED; The Outboard MSIVs will remain OPEN.

48

ILT-08 SRO NRC EXAM

49. 295021G2.2.40 001 Unit 2 is shutdown with the following conditons:

o Rxpressure 134 psig o 2A Rx Recirculation pump Running o 2B Rx Recirculation pump Off Which ONE of the choices below completes BOTH the following statement?

lAW Tech Spec 3.4.7, Residual Heat Removal (RHR) Shutdown Cooling System Hot -

Shutdown the MINMUM number of RHR Shutdown Cooling (SDC) subsystems REQUIRED to be operable, (without requiring entry into a Required Action Statement)

(RAS), is Also, JAW with Tech Spec 3.4.7 and with current plant conditions, RHR SDC subsystem is required to be in operation.

A. one; one B. one; neither C. two; one D*f two; neither 49

ThT-08 SRO NRC EXAM

50. 295023AA2.03 001 Unit 2 is in a Forced Refueling outage due to several fuel leakers in the core.

The Refueling crew is removing a failed fuel bundle from the Unit 2 reactor to the Unit 1 Fuel Prep Machine (FPM).

The Bridge Operator is currently traveling in the Transfer Canal with one of the failed bundles in the normal Full Up position, when the Refueling Bridge becomes stuck in the Transfer Canal.

Maintenance is in the process of determining why the Refueling Bridge will NOT move.

Subsequently, the Unit 2 Main Steam line plugs fail causing the Reactor Cavity and Fuel Pool water levels to decrease.

o Releases from the exposed failed bundle results in increasing Radioactive Airborne contamination levels on the Refuel Floor.

o Radiation levels on the Refuel Floor reach 1200 mr/hr JAW 34AB-G41-002-2, Decreasing Rx Well/Fuel Pool Water Level, Health Physics is directed to establish a manned control point of the Unit 2 Reactor Building.

When water level drops to the Main Steam lines, the fuel seated in the FUEL POOL RACKS will_______

A. on the 203 elevation; still be covered B. on the 203 elevation; be uncovered C outside; still be covered D. outside; be uncovered 50

ILT-08 SRO NRC EXAM

51. 295024EA2.06 001 A steam line break inside the Drywell has occurred on Unit 1.

0 Drywell pressure is 15.5 psig and slowly increasing o Torus pressure is 14.1 psig and slowly increasing o Subquently Drywell Sprays are placed in service at 4,300 gpm flow The Torus water temperature will heat up At this Drywell Spray flow rate, a uniform Drywell spray pattern A uniformly throughout the Torus due to the design of the downcomers; will NOT be guaranteed B. uniformly throughout the Torus due to the design of the downcomers; will be guaranteed C. directly under the leak due to the energy being added directly to the Torus water in that area; will NOT be guaranteed D. directly under the leak due to the energy being added directly to the Torus water in that area; will be guaranteed 51

ILT-08 SRO NRC EXAM

52. 295025G2.1.27 001 Which ONE of the choices below completes the following statements?

JAW TS 3.4.3, Safety/Relief Valves (S/RVs), the SRV Safety function requires a MINIMUM of SRVs to be operable.

If reactor pressure peaks at 1300 psig, the Reactor Coolant System Safety Limit pressure have been exceeded.

A. 10; will B 10; will NOT C.5; will D.5; will NOT 52

ILT-08 SRO NRC EXAM

53. 295026EK3,04 001 An ATWS is in progress on Unit 2 with 31E0-EOP-01 1-2, RCA RPV Control (ATWS),

flowchart in progress.

Which ONE of the choices below completes the following statements?

JAW EOP definitions the reason SBLC is injected before exceeding the BuT Curve (Graph 5) is to ensure that Hot Shutdown Boron Weight is injected before exceeding the At 8% RTP, the HIGHEST listed Torus temperature at which operation on the BITT Curve (Graph 5) will continue to be in the SAFE area is Reference Provided A. Primary Containment Pressure Limit; 130°F B. Primary Containment Pressure Limit; 140°F; 0 Heat Capacity Temperature Limit; 130°F D. Heat Capacity Temperature Limit; 140°F; 53

ILT-08 SRO NRC EXAM

54. 295028EA1.03 001 Unit 2 was at 100% power when a small leak occurred inside the Drywell (DW).

The following conditions now exist:

o Drywell Pressure: 2.2 psig o HIGHEST Drywell Temperature Point: 240°F Which ONE of the choices below completes the following statement?

JAW 31E0-EOP-100-2, Miscellaneous Emergency Overrides, the2A DW Chiller A. is NOT allowed to be restarted, because this DW temperature is above the allowed winding temperature for restart of the DW Cooling Fan Motors B. is NOT allowed to be restarted, because at this DW temperature the potential for a rupture in the DW coolers exist Cv is allowed to be restarted. The operator must first place the LOCA override switch to BYPASS and then reset the 86 Lockout relay at the DW Chiller breaker D. is allowed to be restarted. The operator must first reset the 86 Lockout relay at the DW Chiller breaker and then place the LOCA override switch to BYPASS 54

ILT-08 SRO NRC EXAM

55. 295030EK1.02 001 Unit 2 is operating at 100% power when a Loss of Coolant Accident occurs.

o The High Pressure Coolant Injection system is being used to control RPV water level o The 2A RHR pump is placed in Suppression Pool Cooling o 2A RHR pump flow 7,000 gpm o Torus Level 135 inches o Torus Temperature 225°F o Torus Pressure 8 psig Which ONE of the following choices completes this statement?

RHR pump 2A operation is in the region of the RHR NPSH Limit graph and Reference Provided A. safe; flow must be maintained at or below its current flow rate B. safe; flow is required to be increased to maximize suppression pooi cooling C. unsafe; reducing flow will NOT restore operation to the safe area of the graph D unsafe; reducing flow to 5,000 gpm will restore operation to the safe area of the graph 55

TLT-08 SRO NRC EXAM

56. 295031EA1.05 001 Unit 2 is at 100% RTP when the following occurs:

o All normal Feedwater is lost o RWL is -50 inches PUMP SUCTION PUMP DISCH TURB INLET TURB LXII TURB SPEED PRESS PRESS PRESS PRESS 2E51 -R610 2E51-R604 2E51-R601 ZES1.R602 2E51-R603 I25VDC CAB ZA 15VDC CAB A 1255DC CAB A I2SSDC CAB 2A I2SVDC CAB 2A PF.LAMPIKE(

PF L1GIif ON STPOINT OFF FLOW Based on the above indications, the RCIC flow controller should be A. left in Automatic, and RCIC injection flow will start increasing reactor vessel level B. left in Automatic, but RCIC should be tripped because it is pumping 500 gpm through a feedwater line break C placed in Manual, and the controller output should be increased until discharge pressure is greater than 985 psig D. placed in Manual, but the controller output should be decreased until RCIC flow is 400 gpm.

56

ILT-08 SRO NRC EXAM

57. 295035EA1.01 001 Unit 2 is operating at 100% RTP when a Feedwater transient results in a full Secondary Containment isolation. The following Unit 2 indications currently exist:

o SBGT 2A running o SBGT 2B running o 2T46-R604A, Rx Bldg. dP -0.75 inches 2H 0

o 2T46-R604B, Rx Bldg. dP -0.70 inches H0 2

Which ONE of the choices below completes the following statements?

JAW 34S0-T46-001-2 Standby Gas Treatment System, the operator is REQUIRED to to limit the release of radioactive material.

JAW 31E0-EOP-014-2, SC Secondary Containment Control, RR Radioactivity Release Control flowchart, an entry condition exist.

A. place one SBGT in standby; does B place one SBGT in standby; does NOT C. operate both SBGTs; does D. operate both SBGTs; does NOT 57

ILT-08 SRO NRC EXAM

58. 295037EK2.12 001 Unit 1 was operating at 100% power when a reactor scram occurred.

IMMEDIATELY following the scram, the APRMs indicate reactor power is at 5%.

o Standby Liquid Control (SBLC) has NOT been injected.

10 minutes LATER Rod Worth Minimizer (RWM) displays the following:

SLi[ LIST OK SEQUENCE SQA I BlWS MODE OPERAtE 131 O(KS Will DRAW STEP 1 IOWER BELOW LPSI ALL ROI)S IN: NO SI IU1DOWN: YLS ROI)S NOT FULL-IN: 018 1,151 RODS lX1i Based on these conditions, which ONE of the following completes both of these statements?

JAW 31E0-EOP-103-1, Control Rod Insertion Methods, RWM REQUIRED to be bypassed to insert control rods.

With the current control rod configuration, the reactor remain subcritical under ALL conditions, without boron injection.

A is; will B. is; will NOT C. is NOT; will D. is NOT; will NOT 58

ILT-08 SRO NRC EXAM

59. 295038EK1.01 001 A core damaging event occurs on Unit 1 which results in the release of radioactive IODINE to the public.

The part of the human body which is the most significantly impacted by the release of radioactive IODINE is the The NPO will determine the Projected Offsite dose to the public using A. skin; 73EP-EIP-0 15-0, Offsite Dose Assessment B. skin; 73EP-EIP-018-0, Prompt Offsite Dose Assessment C. thyroid; 73EP-EIP-015-0, Offsite Dose Assessment D thyroid; 73EP-EIP-0 18-0, Prompt Offsite Dose Assessment 59

ILT-08 SRO NRC EXAM

60. 300000A2.O1 001 Unit 2 is operating at 15% RTP with Air Dryer, 2P52-D1O1B, DANGER Tagged out of service.

Subsequently, a malfunction with Air Dryer, 2P52-D1O1A, results in downstream air pressure slowly decreasing and stablilizing at 40 psig.

When the air pressure downstream of 2P52-D1O1A reaches 40 psig, will have automatically CLOSED.

JAW 34AB-P51-001-2, Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System, RWL will be controlled using the A. 2P52-F015, Non-Essential Inst. Air Isolation Valve; 2N2 1-Fl 11, S/U Level Control Valve B 2P52-F015, Non-Essential Inst. Air Isolation Valve; 2N2 1-Fl 10, S/U Level Control Bypass Valve C. 2P52-F565, Rx Bldg Inst N 2 To Non-Tnt Air El. 185 Isol Valve; 2N2 1-Fl 11, S/U Level Control Valve D. 2P52-F565, Rx Bldg Inst N 2 To Non-Int Air El. 185 Isol Valve; 2N2 1-Fl 10, S/U Level Control Bypass Valve 60

ILT-08 SRO NRC EXAM

61. 300000K1.03 001 Unit 2 is shutting down for a refueling outage.

o Instrument Air has been aligned to the Drywell (DW) o At 10:00 a pneumatics header line breaks inside the DW causing an air flow rate of 50 SCFM Which ONE of the following choices completes this statement?

The DW pneumatics header isolation valves associated with the broken header automatically isolate A. will; immediately B will; following a 10 minute delay C. will NOT; because the Instrument Air flow is less than the DW Pneumatics isolation setpoint D. will NOT; because the flow element is upstream of where the Instrument Air ties into the DW Pneumatics header 61

ILT-08 SRO NRC EXAM

62. 400000A1.01 001 Unit 2 is operating at 100% RTP with the 2A and 2B RBCCW pumps in service.

Subsequently, the following occurs:

o 600VAC 2D Bus supply breaker trips due to a bus fault o Maintenance has NOT identified the location of the fault Which ONE of the choices below correctly completes the following statements?

Ten (10) minutes after the bus fault, RBCCW flow to the Drywell will be before the 600VAC 2D Bus supply breaker tripped.

The operator will monitor RBCCW flow to the Drywell at Panel A. significantly lower than; 2H1 l-.P602 B. significantly lower than; 2H1 1-P650 C. approximately the same as; 2H1 l-P602 D approximately the same as; 2H1 1-P650 62

TLT-08 SRO NRC EXAM

63. 500000EK2.07 001 Unit 2 has experienced an accident that results in these Primary Containment parameters:

o Drywell (DW) Hydrogen concentration 8%

o DW Oxygen concentration 7%

o DW pressure 24 psig and slowly increasing o Torus level 155 inches With the above conditions and JAW 31EO-PCG-OO1-2, Primary Containment Gas Control chart:

The operator is required to vent the the containment atmosphere using the A. DW to reduce the flammability of; CAD Loop System two (2) inch valves B. DW to reduce the flammability of; EMERGENCY Vent System eighteen (18) inch valves C Torus to reduce the flammability and scrub; CAD Loop System two (2) inch valves D. Torus to reduce the flammability and scrub; EMERGENCY Vent System eighteen (18) inch valves 63

ILT-08 SRO NRC EXAM

64. 600000AK1.O1 001 An electrical fire is reported on Unit 1 in the IF 4160 VAC bus.

The fire suppression that is available in this room is A. automatically actuated Carbon Dioxide agent B. automatically actuated Halon agent C manually actuated Carbon Dioxide agent D. manually actuated Halon agent 64

ILT-08 SRO NRC EXAM

65. 700000AK2.03 001 BOTH units are operating at 100% power when a grid disturbance occurs.

The following indications occur on 1S40-R600, 230 KV voltmeter, on panel 1H1 1-P653:

Time 1S40-R600 10:00 236kV 10:05 236kV 10:10 232kV 10:15 224kV The NCC has notified the control room crews that 230 KV Bus voltage cannot be maintained above the normal minimum voltage.

lAW 34AB-S 11-001-0, Operation With Degraded System Voltage, which ONE of the following is the EARLIEST time 230 kV Bus voltage is BELOW the normal minimum voltage AND a REQUIRED action for this voltage?

A. 10:10; Transfer Station Service Buses to their alternate supply.

B 10:10; Initiate a one hour Required Action Statement C. 10:15; Transfer Station Service Buses to their alternate supply D. 10:15; Initiate a one hour Required Action Statement 65

ILT-08 SRO NRC EXAM

66. G2.1.1 OO JAW NMP-OS-007, Conduct of Operations, EXCLUDING shift turnover walkdowns:

The Operator at the Controls (OATC) is required to walkdown the front Control Room panels a MINIMUM of every The waflcdowns required to be documented in the Unit Control Log.

Ar two (2) hours; are B. two (2) hours; are NOT C. one(l)hour; are D. one(l) hour; are NOT 66

ILT-08 SRO NRC EXAM

67. G2.1.8 001 Unit 2 is operating at 100% RTP.

JAW 34S0-B31-0O1-2, Reactor Recirculation System, which ONE of the following describes the MINIMUM qualification and the coordination requirements for changing Recirc Pump A?!

speed locally?

A Nuclear Plant Operator In Training (NPOIT) can perform the LOCAL speed adjustment if A. a licensed Nuclear Plant Operator is present at the local ASD A Cabinet and communication with the Control Room is NOT required B. a licensed Nuclear Plant Operator is present at the local ASD A Cabinet and notifies the Control Room only after the speed adjustment has been made C. an active Senior Reactor Operator is present at the local ASD A Cabinet and notifies the Control Room only after the speed adjustment has been made D an active Senior Reactor Operator is present at the local ASD A Cabinet and in constant communication with the Main Control Room 67

ILT-08 SRO NRC EXAM

68. G2.1.20 001 JAW NMP-OS-007-OO1, Conduct of Operations Standards and Expectations, under normal, stable plant conditions, performing ARP steps out of order A. IS allowed with NO other NPO concurrence required B. IS allowed but ONLY after the concurrence of an additional NPO C IS NOT allowed since ARP steps are to be performed in the sequence they are written D. IS NOT allowed since ALL procedures are to be performed in the sequence they are written 68

ThT-08 SRO NRC EXAM

69. G2.2.21 001 Unit 1 is in day 20 of a 27 day planned Refueling outage.

Motor replacement is complete for 1EI 1-FOO7B, RHR Minimum Flow valve, and the operability surveillance is in progress.

lAW 34SV.El 1-002-1, RHR Valve Operability, To time 1E1 1-FOO7B OPEN, the NPO will START the stopwatch when the When 1E1 1-FOO7B has traveled OPEN, the valve stem position indication REQUIRED to be confirmed LOCALLY.

A control switch is placed to OPEN; is B. control switch is placed to OPEN; is NOT C. red light FIRST illuminates; is D. red light FIRST illuminates; is NOT; 69

ILT-08 SRO NRC EXAM

70. G2.2.22 001 Unit 2 is operating at 90% power.

At 10:00:

o Drywell (DW) pressure is 1.0 psig.

o DW pressure begins going up at 0.05 psig/minute lAW Tech Spec Limiting Condition for Operation (LCO) 3.6.1.4, Drywell Pressure, which ONE of the choices below completes the following statements?

With the above trend, the EARLIEST listed time that an entry into a Required Action Statement (RAS) for DW pressure is DW pressure is required to be restored to within limit NO later than from entering the RAS.

A. 10:04; 15 minutes B. 10:04; 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. 10:16; 15 minutes D 10:16; 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 70

ILT-08 SRO NRC EXAM

71. G2.2.36 001 Unit 2 is operating at 100% RTP in Type A Secondary Containment.

The following equipment has been inoperable for one day (RAS written):

o SBGT 2A breaker will NOT reset Which ONE of the following maintenance activities, if it resulted in tripping the feeder breaker to the MCC, would REQUIRE entry into an additional Tech Spec RAS for the SBGT System?

Troubleshooting on the feeder breaker to A. Reactor Bldg MCC-2D, 2R24-5014 B. Reactor Bldg MCC-2A, 2R24-S013 Cv Reactor Bldg MCC-2B, 2R24-5012 D. Reactor Bldg MCC-2C, 2R24-S01 1 71

ILT-08 SRO NRC EXAM

72. G2.3.11 001 Which ONE of the following is the BASIS for restarting the Reactor Building (RB) Ventilation when executing 31E0-EOP-014-2, SC Secondary Containment Control RR Radioactivity Release Control

?

t Restarting the RB Ventilation maintains AND assures a release from the RB Ventilation System is monitored prior to exiting the A. equipment operability ONLY; Main Stack B. equipment operability ONLY; Reactor Building Stack C. control of RB temperature and pressure; Main Stack Df control of RB temperature and pressure; Reactor Building Stack 72

ILT-08 SRO NRC EXAM

73. G2.3.13 001 Unit 1 is shutting down for a refueling outage.

o A normal Ihitial Drywell (DW) entry at power is required.

Which ONE of the choices below completes the following statement JAW 31 GO-OPS-005-O, Primary Containment Entry.

Before a normal Initial DW entry is allowed, Oxygen (02) concentration must be at least and reactor power must be less than or equal to A. 19.5%;

15%

B 19.5%;

10%

C. 23.5%;

15%

D. 23.5%;

10%

73

ILT-08 SRO NRC EXAM

74. G2.4.16 001 Unit 2 has experienced a complete loss of offsite power (LOSP).

The following conditions exist on Unit 2:

o ONLY 4160 VAC bus 2E is energized o Drywell pressure is currently 1.0 psig and rising 0.1 psig per minute o RWL is -5 inches slowly increasing o 34AB-R22-003-2, Station Blackout, in progress o 31E0-EOP-010-2, RC Flow Chart, in progress With the above conditions, actions in the takes precedent over actions in any other procedure.

34AB-R22-003-2, Station Blackout procedure, will be EXITED when a MINIMUM of 4160V Emergency buses are energized on Unit 2.

A 34AB-R22-003-2, Station Blackout procedure; two (2)

B. 34AB-R22-003-2, Station Blackout procedure; three (3)

C. EOP procedures; two (2)

D. EOP procedures; three (3) 74

ILT-08 SRO NRC EXAM

75. G2.4.5 001 A Fuel Handling accident on Unit 1 results in a radioactive release.

The type of procedure that will provide the DETAILED guidance for notifying state and local agencies of the Fuel Handling accident release is If a conflict exists between a Fleet procedure and a Site procedure, the governing guidance will come from the procedure.

A. NMP-EP, Nuclear Management Procedures for Emergency Preparedness; Site B NMP-EP, Nuclear Management Procedures for Emergency Preparedness; Fleet C. NMP-RP, Nuclear Management Procedures for Radiation Protection; Site D. NMP-RP, Nuclear Management Procedures for Radiation Protection; Fleet 75

JLT-08 SRO NRC EXAM

76. 201006A2.06 001 Unit 2 is at 70% RTP.

o Rod Worth Minimizer (RWM) is NOT in Sequence Control Mode o A ** group control rod at position 36 is selected o A malfunction in APRM D occurs o APRM D is currently reading 4%

o NO operator action has been taken With the above conditions, the mode of operation for RWM will be Low Power Setpoint, (LPSP).

JAW with 31G0-OPS-006-0, Conditions, Required Actions and Completion Times, for APRM D, the Shift Supervisor and Shift Manager will in the Required Action Sheet boxes below.

SSSIGN /TSAACTIVE SM SIGN A. less than; sign B less than; initial (signature is NOT allowed)

C. greater than; sign D. greater than; initial (signature is NOT allowed) 76

ILT-08 SRO NRC EXAM

77. 209001G2.4.49 001 Unit 1 was operating at 100% RTP when a transient resulted in the following:

Date 4/10/2013 Time 12:00 o Reactor scram, all rods fully insert o Drywell pressure: 0.7 psig o Reactor water level: -102 inches, decreasing o Reactor pressure: 475 psig o Both Core Spray (CS) systems are in standby due to a failure of ALL Core Spray Instrumentation Initation logic Based on the current above plant conditions:

As a MINIMUM, the operator will start both CS pumps lAW TECH SPEC, the EARLIEST listed time that REQUIRES Unit 1 to be in mode 4 is 4/12/2013 at Reference Provided A , but will NOT open 1E21-FOO5A/B, Discharge valves; 02:00 B. , but will NOT open 1E21-FOO5AIB, Discharge valves; 03:00 C. and WILL open 1E21-FOO5AIB, Discharge valves; 02:00 D. and WILL open 1E21-FOO5AIB, Discharge valves; 03:00 77

ThT-08 SRO NRC EXAM

78. 215003A2.05 001 Unit 2 Reactor startup is in progress.

The following IRM readings have been observed while switching up from range 6 to range 7:

IRM Channel Range 6 Range 7 A 75 8.0 B 60 0.0 C 75 8.0 D 70 6.0 E 70 8.5 F 50 5.0 G 65 9.0 H 70 8.5 lAW 34G0-OPS-001-2, Plant Startup, and with the above IRM data, Acceptable overlap is confirmed on IRMs.

The LOWEST level of authority required to continue the reactor startup is the A six (6);

Shift Supervisor B. six(6);

Shift Manager C. seven (7);

Shift Supervisor D. seven (7);

Shift Manager 78

ILT-08 SRO NRC EXAM

79. 218000A2.05 001 Unit 2 was operating at 100% RTP when the following electrical malfunctions occur:

o The bus supplying NORMAL power to the ADS Valves deenergizes o 125/250 VDC Switchgear 2B (2R22-S017), deenergizes o 125 VDC 2D, 2R25-S004, deenergizes Subsequently, a transient results in the following:

o RWL (-)30 inches o Reactor pressure 650 psig o Torus pressure 20 psig o Torus level 120 inches o Torus temperature 170°F With the above conditions:

If the control switch for 2B21-FO13M, ADS valve, is placed to the open position, the 2B21-FO13M open.

JAW EOPs, entry into 31E0-EOP-108-2, Alternate RPV Depressurization, REQUIRED to reduce Reactor pressure.

Reference Provided A. will; is B. will; is NOT 0 will NOT; is D. will NOT; is NOT 79

ILT-08 SRO NRC EXAM

80. 261000A2.08 001 Unit 2 is operating at 100% RTP when the following occurs:

o 10:00 Fire alarm received on Unit 2 Control Building SO dispatched to investigate o 10:02 Loss of 24/48V DC Cabinet 2A, 2R25-S015, occurs o 10:03 SO reports 24/48V DC Cabinet 2A, 2R25-S015 is on fire o 10:17 SO reports 2R25-S015 fire is EXTINGUISHED, however, 2R25-S015 is severly damaged JAW 34AB-R22-001-2, Loss Of DC Buses, at 10:05, without any operator actions, the TOTAL number of SBGT fans running is lAW NMP-EP-1 10, Emergency Classification Determination and Initial Actions, the fifteen (15) minute clock for declaring an emergency STARTS at At four (4);

10:00 B. four(4);

10:03 C. three (3);

10:00 D. three(3);

10:03 80

ILT-08 SRO NRC EXAM

81. 26300002.4.8 001 Unit 2 is in Startup with the following conditions:

o Reactor pressure is 80 psig and steady An event occurs resulting in the following:

o The Supply breaker to 600 V Bus 2C trips and can NOT be re-closed o RWL is 15 increasing 1 per minute (lowest level reached 10)

Given these conditions, which ONE of the following completes both statements?

lAW Tech Specs, a Required Action Statement MUST be entered for In order to restore the associated Station Service Battery Chargers to service and JAW 34AB-R23-001-2, Loss of 600 Volt Emergency Bus, energizing 600 VAC bus 2C using the 4160/600V 2CD Transformer is A 600VAC 2C ONLY; NOT allowed B. 600VAC 2C ONLY; allowed C. 600VAC 2C AND also for Instrument Bus 2A; NOT allowed D. 600VAC 2C AND also for Instrument Bus 2A; allowed 81

ILT-08 SRO NRC EXAM

82. 290001A2.02 001 Unit 2 is operating at 100% RTP operating in TYPE A Containment.

A SO reports that one (1) of the Unit 2 Reactor Building (RB) Blowout panels is damaged and is NOT fully closed and sealed.

o Unit 2 Reactor Building (RB) dP is +0.02 inches WC and steady Operations and Engineering are reviewing recent performances of 34SV-T22-002-0, Secondary Containment Integrity, and determines the 31 day surveillance was last performed on July 19.

Todays date is September 19.

Entry into 34AB-T22-002-2, Loss Of Secondary Containment Integrity, REQUiRED at this time.

JAW TS, without performing a Risk Evaluation, the LATEST time allowed to perform 34S V-T22-002-0 before requiring entry into a RAS, is A is; 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B. is; 31 days C. is NOT; 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> D. is NOT; 31 days 82

ILT-08 SRO NRC EXAM

83. 290003G2.4.4 001 At 08:58, Unit 1 is operating at 7% RTP ready to transfer the Reactor mode switch to RUN?!.

At 09:00, an event occurs causing Refueling Floor ARMs to indicate the following:

1D21-K6O1A, Reactor head laydown area, 52 mr/hr 1D21-K6O1B, Refueling Floor Stairway, 25 mr/hr 1D21-K6O1D, Refueling Floor, 24 mr/hr 1D21-K6O1E, Drywell Shield Plug, 22 mr/hr 1D21-K601M, Spent Fuel Pool & New Fuel Storage, 40 mr/hr At 09:03, Unit 1 NPO reports 1Z41-CO12B, Control Room HVAC Filter Fan, will NOT run.

LCO 3.7.4 Main Control Room Environmental Control (MCREC) System, RAS is entered.

At 09:05, Refueling Floor HP notifies the control room that High Radiation trash was being moved on the Refueling Floor and had caused the higher than normal radiation conditions.

At 09:07, the High Radiation trash has been removed from the Refueling Floor. The ABOVE ARMs are now indicating NORMAL values.

At 09:15, the operating crew is ready to transfer the Reactor Mode switch to RUN At 09:00, an entry condition existed for At 09:15, with 1Z41-CO12B inoperable and without performance of a Risk Assessment, Tech Specs allow transferring the Reactor Mode switch to the RUN position.

Reference Provided A. ONLY 34AB-T22-003-1, Secondary Containment Control; will B. ONLY 34AB-T22-003-1, Secondary Containment Control; will NOT C. BOTH 34AB-T22-003-1, Secondary Containment Control, AND 31 EO-EOP-0 14-1, SC/RR, EOP Flowchart; will D BOTH 34AB-T22-003-1, Secondary Containment Control, AND 31 EO-EOP-0 14-1, SC/RR, EOP Flowchart; will NOT 83

ILT-08 SRO NRC EXAM

84. 295004AA2.02 001 Unit 2 is operating at 100% power with the following electrical lineup:

o The 30 amp DC breaker tripped for ACB 135554, 4160V Bus 2 tEI Normal Supply breaker o The 30 amp DC breaker CANNOT be closed o 4160V Bus 2E is on Alternate Supply from SAT 2C o 4160V Bus 2F is on Normal Supply from SAT 2D o 4160V Bus 2G is on Normal Supply from SAT 2D With the above conditions; JAW TS Bases 3.8.1, tTAC Sources Operating, entry into a TS Required Action Statement (RAS) REQUIRED.

ACB 135554 breaker have a trip signal due to the loss of the 30 amp DC breaker.

A is NOT; will NOT B. is NOT; will, C. is; will NOT, D. is; will 84

ILT-08 SRO NRC EXAM

85. 295007AA2.01 001 Unit 2 is operating at 100% RTP, when a reactor pressure transient occurs resulting in the following:

o 603-114, REACTOR VESSEL PRESSURE HIGH illuminates Subsequently, Drywell Floor Drain leakage increases to 55 gpm The REACTOR VESSEL PRESSURE HIGH alarm setpoint is psig.

lAW NMP-EP-1 10, Emergency Classification Determination and Initial Action, the HIGHEST Emergency Classification that will be declared based on Drywell Floor Drain leakage is Reference Provided A. 1060; an Alert Emergency B. 1060; a Site Area Emergency C 1055; an Alert Emergency D. 1055; a Site Area Emergency 85

ILT-08 SRO NRC EXAM

86. 295012G2.4.11 001 Unit 2 was operating at 100% RTP when a loss of Drywell cooling occurred.

lAW 34AB-T47-O012, Complete Loss of Drywell Cooling:

The crew is required to enter when any peak temperature listed in Attachment 1 has been exceeded for a MINIMUM of A. 34G0-OPS-013-2, Normal Plant Shutdown; 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. 34G0-OPS-013-2, Normal Plant Shutdown; 30 minutes C. 34GOOPS-014-2, Fast Reactor Shutdown; 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D 34G0-OPS-014-2, Fast Reactor Shutdown; 30 minutes 86

ILT-08 SRO NRC EXAM

87. 295016G2.2.37 001 An event results in the Main Control Room being abandoned.

Control of Unit 2 is established at the Unit 2 Remote Shutdown Panel (RSDP).

31RS-OPS-001-2, Shutdown From Outside Control Room, is in progress.

o ALL RSDP Emergency Transfer Switches are in the EMERGENCY position Subsequently, Unit 2 Drywell pressure increases to 3.0 psig.

A SO reports the following:

o RHR pump 2A is NOT running Maintenance reports RHR pump 2A Lockout Relay has TRIPPED.

The procedure that contains the guidance for whose AUTHORITY is required to reset the RHR pump 2A Lockout Relay is With the RSDP Emergency Transfer Switches in the EMERGENCY position, RHR pump 2B is A. NMP-OS-007-001, Conduct of Operations Standards and Expectations; operable B. NMP-OS-007-00l, Conduct of Operations Standards and Expectations; inoperable BUT available C. 31 GO-OPS-02 1, Manipulation of Controls and Equipment; operable D? 31G0-OPS-021, Manipulation of Controls and Equipment; inoperable BUT available 87

ILT-08 SRO NRC EXAM

88. 295019G2.1.28 001 Unit 2 was operating at 100% RTP when an event occurred resulting in the following:

o Normal pneumatic supply to the Unit 2 Drywell is lost o NO High pressure OR Low pressure injection system will operate Section 7.3.1, Emergency Nitrogen Supply Operation, of 34S0-P70-001-2, Drywell Pneumatics System, has been completed and is supplying Emergency Nitrogen to the Drywell.

o RWL is -186 inches and slowly decreasing After performing section 7.3.1, Emergency Nitrogen Supply Operation, the MAXIMUM number of SRVs that will be supplied Nitrogen from the Emergency Nitrogen Bottles is With RWL at -186 inches and decreasing, Reactor pressure is REQUIRED to be controlled using EOP flowchart A. 11; RC RPV Control (Non-ATWS), RC/P path B. 11; CP- 1 Point F, Steam Cooling path C.5; RC RPV Control (Non-ATWS), RC/P path 4 5; Dr CP-1 Point F, Steam Cooling path 88

ILT-08 SRO NRC EXAM

89. 295023AA2.02 001 Fuel movement is in progress on Unit 1.

Currently a fuel bundle is on the Main Grapple over the Fuel Pool area.

While over the Unit 1 Fuel Pool, the Main Grapple malfunctions releasing the irradiated fuel bundle and punctures the Fuel Pool liner.

Fuel Pool water level decreases and stabilizes at 22 feet.

The dropped fuel bundle is damaged and bubbles are observed floating to the surface.

Subsequently, a Secondary Containment isolation occurs due to the conditions on the Refuel Floor.

With the above Fuel Pool water level, LCO TS 3.7.8, Spent Fuel Storage Pool Water Level, met.

lAW 31E0-EOP-014-1, SC/RR, the Unit 1 Reactor Building HVAC fans ALLOWED to be restarted.

A. is still; are B is still; are NOT C. is NOT; are D. is NOT; are NOT 89

ILT-08 SRO NRC EXAM

90. 295024BA2.02 001 UNIT 1 was operating at 100% RTP when a steam leak in the Drywell resulted in the following:

0 Drywell average temperature is 255°F o Drywell pressure is 5.0 psig o Torus pressure is 4.0 psig With the above plant conditions, if Drywell Sprays are INITIATED, there is an increased risk of Subsequently, the NPO reports that ALL RWL instruments are simultaneously displaying erratic indication, an Emergency Depress will be ordered from ONLY.

Reference Provided A. damaging the Primary Containment Vent system due to exceeding the capacity of the Torus to Drywell Vacuum Breakers; 31E0-EOP-016-1, CP-2 RPV Flooding B. damaging the Primary Containment Vent system due to exceeding the capacity of the Torus to Drywell Vacuum Breakers; 31EO-EOP-015-1, CP-1 Emergency RPV Depressurization C de-inerting the containment due to opening the Reactor Building to Torus vacuum breakers before the operator can secure sprays; 31 EO-EOP-0 16-1, CP-2 RPV Flooding D. de-inerting the containment due to opening the Reactor Building to Torus vacuum breakers before the operator can secure sprays; 31E0-EOP-015-1, CP-1 Emergency RPV Depressurization 90

ILT-08 SRO NRC EXAM

91. 295032EA2.03 001 UnIt 1 is operating at 100% RTP, when an unisolable steam leak occurs in the plant.

o Main Control Room indications and alarms indicate rapidly increasing temperature in the Southwest Diagonal o A NPO reports the temperature in the Southwest Diagonal is above Maximum Safe Operating Temperature This increasing temperature is a result of a steam leak on the system.

JAW 31E0-EOP-014-1, SC/RR, EOP flowchart, the SS is REQUIRED to perform A. HPCI; 34G0-OPS-014-1, Fast Reactor Shutdown B. HPCJ; point A of the RC EOP flowchart C. RCIC; 34G0-OPS-014-1, Fast Reactor Shutdown D RCIC; point A of the RC EOP flowchart 91

ILT-08 SRO NRC EXAM

92. 295037G2.4.49 001 Unit 1 was operating at 100% power when a transient occurred resulting in the following:

o All control rods did not fully insert o Reactor power 8%

o Reactor Water Level 9 inches o Drywell pressure 2.2 psig o Torus water temperature 125°F o Both Recirculation pumps are operating at minimum speed JAW RC-1 and based on the above conditions, the OATC REQUIRED to trip the Recirculation pumps.

Based on the above conditions, and lAW EOP Flowcharts RCA and CP-3 Overrides, REQUIRED to be entered.

NOTE:

31EO-EOP-1 13-1, Terminating And Preventing Injection Into The RPV 31E0-EOP-1 14-1, Preventing Injection Into The RPV From Core Spray And LPCI Reference Provided A. is NOT; ONLY EOP-114-1 is B. is NOT; BOTH EOP-113-1 andEOP 114-1 are C. is; ONLY EOP-114-1 is D is; BOTH EOP-113-1 and EOP 114-1 are 92

ThT-08 SRO NRC EXAM

93. 700000AA2.07 001 Unit 1 is operating at 100% RTP.

The load dispatcher reports degraded grid conditions with the following indications present for the LAST ONE MINUTE:

o Generator frequency 59.7 hertz o 1H11-P653 VOLTMETER 1S40-R600 225 KV o 4160 VAC BUS 1E 3695 volts o 4160 VAC BUS iF 3690 volts o 4160 VAC BUS 1G 3685 volts o 652-122, 4160V BUS 1E VOLTAGE LOW ILLUMINATED o 652-222, 4160V BUS iF VOLTAGE LOW ILLUMINATED o 652-322, 4160V BUS 1G VOLTAGE LOW ILLUMINATED With the above plant conditions, lAW 34AB-S1 1-001-0, Operation With Degraded System Voltage, after 30 minutes, a MINIMUM of REQUIRED to be supplied from the Emergency Diesel Generator(s) on Unit 1.

A. Main Turbine blade damage may occur due to off frequency operation; one (1) 4160 V Emergency bus is B. Main Turbine blade damage may occur due to off frequency operation; two (2) 4160 V Emergency busses are C Emergency Bus loads may be damaged by degraded voltages; one (1) 4160 V Emergency bus is D. Emergency Bus loads may be damaged by degraded voltages; two (2) 4160 V Emergency busses are 93

ThT-08 SRO NRC EXAM

94. G2.1.3 001 At 13:55, Unit 2 was operating at 100% RTP when a Feedwater transient occurred.

At 14:00, the OATC inserted a manual scram.

At 17:45, the ON-COMING Shift Supervisor (SS) is reviewing the shift logs.

o The ON-COMING SS previously worked seven (7) days ago Which ONE of the choices below completes both statements?

JAW NMP-OS-007-001, ?Conduct of Operations Standards and Expectations??, prior to assuming shift, the ON-COMING SS is REQUIRED to review the previous of shifts log.

JAW REG-025, One, Four, and Eight Hour Reporting Requirements of 10 CFR 50.72, the NRC must be notified of this event NO LATER THAN A. three (3) days; 21:59 B three (3) days; 17:59 C. seven (7) days; 21:59 D. seven (7) days; 17:59 94

ILT-08 SRO NRC EXAM

95. G2.1.36 001 Unit 2 is in REFUEL with core reload in progress.

JAW 34FH-OPS-OO1-O, Fuel Movement Operation, which ONE of the choices below correctly completes the following statements?

For core reload, the Unit 2 Reactor Mode switch is REQUIRED to be in the The fuel movement prerequisites must be completed A Refuel position and LOCKED; at EACH shift change (12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift) during fuel movement B. Refuel position and LOCKED; ONLY once during the refueling outage (prior to the initial fuel movement)

C. Refuel position ONLY (NOT locked);

at EACH shift change (12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift) during fuel movement D. Refuel position ONLY (NOT locked);

ONLY once during the refueling outage (prior to the initial fuel movement) 95

ILT-08 SRO NRC EXAM

96. G2.2.18 001 JAW 31 GO-OPS-024-O, Outage Safety Assessment, which ONE of the following completes both statements?

The individual responsible for completing the Outage Safety Assessment is the Planned entry into an ORANGE (moderate risk) condition REQUIRES approval of the A. respective Unit Operator at the Controls (OATC);

Work Management Director ONLY B respective Unit Operator at the Controls (OATC);

Work Management Director AND the Plant Manager C. Shift Technical Advisor (STA);

Work Management Director ONLY D. Shift Technical Advisor (STA);

Work Management Director AND the Plant Manager 96

ILT-08 SRO NRC EXAM

97. G2.2.39 001 Unit 1 is operating at 100% RTP.

At 0800, the 1A Diesel Generator is declared inoperable.

lAW TS 3.8.1 AC Sources Operating, the LATEST ALLOWABLE time to complete the initial TS REQUIRED portions of 34SV-SUV-013-0, Weekly Breaker Alignment Checks, due to the inoperable Diesel Generator is lAW TS SR 3.0.2, the subsequent performance time of 34SV-SUV-013-0 is MET if it is completed within times the interval specified in the RAS Completion Time.

A. 0829; 2.0 B. 0829; 1.25 C. 0859; 2.0 D 0859; 1.25 97

ILT-08 SRO NRC EXAM

98. G2.3.4 001 A Unit 1 Primary system line break is discharging to the environment and CANNOT be isolated from the Main Control Room.

The Shift Manager has declared a General Emergency due to dose rates exceeding 1,000 mr/hr beyond the site boundary.

An Authorization To Exceed 10CFR2O exposure limits will be needed to rescue an injured operator attempting to isolate the line.

There are NO volunteers to perform the life saving rescue.

The Health Physic Manager has arrived in the TSC.

The OSC & TSC facilities have NOT been activated at this time.

JAW NMP-EP-1 10, Emergency Classification Determination and Initial Action, the is responsible for authorizing EXCEEDING the 10CFR2O exposure limits.

JAW 73EP-EIP-017-0, Emergency Exposure Control, and with the above conditions, the HIGHEST listed exposure that can be authorized for the rescue is A. Shift Manager; 10 REM.

B Shift Manager; 25 REM.

C. Health Physic Manager; 10 REM.

D. Health Physic Manager; 25 REM 98

ThT-08 SRO NRC EXAM

99. G2.4.38 001 A Site Area Emergency has been declared due to an event on Unit 1.

JAW NMP-EP-1 10, Emergency Classification Determination and Initial Action, which ONE of the following identifies one of the responsibilities of the Emergency Director that CAN be delegated to another individual?

A. The decision to dismiss nonessential personnel from the site after assembly and accountability has been completed.

B Directing the activation of the emergency organization (ERO callout).

C. Recommending Protective Actions (PARS) to offsite authorities.

D. Authorizing the use of Potassium Iodide (KI) tablets.

99

ILT-08 SRO NRC EXAM 100. G2.4.4 001 Unit 1 is at 100% power with the lB EDG tagged out of service for repairs.

The following sequence of events occurs:

o 11:30 Offsite power is lost to Unit 1 ONLY o 11:35 SO reports 1A EDG Lube Oil Pressure of 20 psig, lowering 0.5 psig 1mm o 11:45 1 C EDG trips on Differential Lockout Which ONE of the choices below completes the following statement?

The EARLIEST listed time which entry into 34AB-R43-001-1, Diesel Generator Recovery, is REQUIRED is At 12:05, the required emergency classification is Reference Provided A. 11:40; an Alert Emergency B 11:40; a Site Area Emergency; C. 11:45; an Alert Emergency D. 11:45; a Site Area Emergency End of Test 100

ILT-08 SRO NRC EXAM Answers 0

1 201003A2.09 1 A 2 203000K6.02 1 C 3 204000K1.15 1 A 4 205000K5.02 1 A 5 205000K5.03 1 D 6 206000A1.08 1 B 7 209001K3.01 1 A 8 209001K3.03 1 B 9 211000K2.021 A 10 212000A3.02 1 B 11 212000A4.15 1 A 12 215001A4.03 I A 13 215002G2.4.4 1 D 14 215003K4.05 1 B 15 215004K1.02 1 B 16 215005A4.06 1 D 17 217000K5.06 1 C 18 218000K301 1 B 19 223001A3.05 I A 20 223002A2.11 1 C 21 226001K6.04 1 B 22 233000K406 1 A 23 239001K5.05 1 B 24 239002K2.01 I A 25 241000K3.03 1 C 26 245000K4.10 1 C 27 259002A4.08 1 A 28 261000A2.07 1 A 29 261000K1.03 1 C 30 262001K6.03 I D 31 262002G2,4.4 1 C 32 263000A3.01 I C 33 264000G2.2.42 1 B 34 268000A1.02 1 B 35 286000K2.02 1 B 36 295001AK2.06 1 A 37 295003AK1.02 1 B 38 295004G2.1.7 1 B 39 295005AK3.02 1 D 40 295006AA1.01 1 B 41 295009AK1.02 1 C 42 295010AA2.06 1 B 43 295012AK3.O1 1 D 44 295013G2.4.18 1 B 45 295016AA2.07 1 B 46 295017AA1.05 1 A 47 295018AK3.06 1 D

Answers m o 48 295019AA2.02 1 C 49 295021G2.2.40 1 D 50 295023AA2.03 1 C 51 295024EA2.06 1 A 52 295025G2.1.27 1 B 53 295026EK3.04 1 C 54 295028EA1.03 1 C 55 295030EK1.02 1 D 56 295031EA1.05 I C 57 295035EA1.01 I B 58 295037EK2.12 I A 59 295038EK1.01 I D 60 300000A2.O1 1 B 61 300000K1.03 I B 62 400000A1.01 I D 63 500000EK2.07 1 C 64 600000AK1.01 1 C 65 700000AK2.03 1 B 66 G2.1.1 1 A 67 G2.1.8 1 D 68 G2.1.20 1 C 69 G2.2.21 1 A 70 G2.2.22 1 D 71 G2.2.36 1 C 72 G2.3.11 1 D 73 G2.3.13 1 B 74 G2.4.16 1 A 75 G2.4.5 1 B 76 201006A2.06 1 B 77 20900 1G2.4.49 1 A 78 215003A2.05 1 A 79 218000A2.05 1 C 80 261000A2,08 1 A 81 263000G2.4.8 1 A 82 290001A2.02 1 A 83 290003G2.4.4 1 D 84 295004AA2.02 1 A 85 2950O7AA201 1 C 86 295012G2.4.11 1 D 87 295016G2.2.37 1 D 88 295019G2.1.28 I D 89 295023AA2.02 1 B 90 295024EA2.02 1 C 91 295032EA2.03 1 D 92 295037G2.4.49 I D 93 700000AA2.07 I C 94 G2.1.31 B

ci) -

C D 00 00 C 00 O C

C C

C C

NRC SRO REFERENCES SRO EXAM

1. Unit 2 EOP Graph 5, BuT Curve

2. Unit 2 EOP Graph 12A, RHR NPSH Limit, (Torus Water Level At or Above 146) &

Unit 2 EOP Graph 12B, RHR NPSH Limit, (Torus Water Level Below 146 9

3. Unit 1 TS 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation &

Unit 1 TS 3.5.1 Emergency Core Cooling System (ECCS)

4. Unit 2 EOP Graph 7, Pressure Suppression Pressure

5. Table 6 of34AB-T22-003-1, Secondary containmnent (ontrol &

Unit 1 TS 3.7.4 Main Control Room Environmental Control (MCREC) System

6. NMP-EP-11O-GLO2, Figure 1 Fission Product Barrier Matrix

7. Unit 1 EOP Graph 8 Drywell Spray Initiation Curve

8. Unit 1 EOP Graph 5 Boron Injection Initiation Temperature Curve

9. NMP-EP-11O-GLO2, Emergency Classification & Initial Actions , Attachment 2 Hot Initiating Condition Matrix Evaluation Chart, A C Power Section

GRAPH 5 UNIT 2 BORON INJECTION INITIATION TEMPERATURE 170 160 TORUS 150 WATER TEMP 140

(°F) 130 120 110 100 0 2 4 6 8 10 12 14 16 18 20 REACTOR POWER (%)

NOTE: May use SPDS Emergency Displays in place of this Graph.

GRAPH 12A UNIT 2 RHR Pump NPSH Limit (Suppression Pool Water Level At or Above 146)

TORUS TEMP

(°F) 0 2000 4000 6000 8000 10000 12000 FLOW (gpm)

NOTE: May use SPDS Emergency Displays in place of this Graph.

Suppression Chamber Pressure.

Safe operating region is below the applicable pressure line.

GRAPH 12B UNIT 2 RHR Pump NPSH Limit (Suppression Pool Water Level Below 146)

TORUS TEMP

(°F)

FLOW (gpm)

NOTE: May use SPDS Emergency Displays in place of this Graph.

Suppression Chamber Pressure.

Safe operating region is below the applicable pressure line.

ECCS Instrumentation 3.3.5.1 3.3 INSTRUMENTATION 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation LCO 3.3.5.1 The ECCS instrumentation for each Function in Table 3.3.5.1-i shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5.1-1.

ACTIONS

---

NOTE--

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.l Enter the Condition Immediately inoperable, referenced in Table 3.3.5.1-1 for the channel.

B. As required by Required B.i Action A.i and referenced 1. Only applicable in in Table 3.3.5.1-1. MODES 1, 2, and 3.

2. Only applicable for Functions 1 .a, 1 .b, 2.a, and 2.b.

Declare supported i hour from discovery feature(s) inoperable, of loss of initiation capability for feature(s) in both divisions AND (continued)

HATCH UNIT 1 3.3-34 Amendment No. 266 I

ECCS instrumentation 3.3.5.1 AC1IONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B2 NOTE Only applicable for Functions 3.a and 3.b.

Declare High Pressure 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discoverj Coolant Injection of loss of HPCI (HPCI) System initiation capability inoperable.

AND B.3 Place channel in trip. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C. As required by Required C.1 NOTES-Action A.1 and referenced 1. Only applicable in in Table 3.3.5.1-1. MODES 1, 2, and a.

2 Only applicable for Functions 1.c, 2.c, 2.d, and 2.f.

Declare supported 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery feature(s) inoperable, of loss of initiation capability for feature(s) in both divisions AND C.2 Restore channel to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

(continued)

HATCH UNIT 1 3.3-35 Amendment No. 266

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

0. As required by Required 0.1 NOTE Action A.1 and referenced Only applicable if HPCI in Table 3.3.5.1-1. pump suction is not aligned to the suppression pool.

Declare HPCI System 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery inoperable, of loss of HPCI initiation capability AND 0.2.1 Place channel in trip. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OR 0.2.2 Align the HPCI pump 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> suction to the suppression pool.

E. As required by Required El NOTES----

Action A.1 and referenced I Only applicable in in Table 3.3.5.1-1. MODES 1,2, and 3.

2. Only applicable for Functions 1.d and 2g.

Declare supported 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery feature(s) inoperable of loss of initiation capability for subsystems in both divisions AND E.2 Restore channel to 7 days OPERABLE status.

(continued)

HATCH UNIT 1 3.3-36 Amendment No. 266

ECOS instrumentatIon 3.3.5.1 AGTIONS (continued)

CONDITION REQUIRED ACTiON COMPLETION TIME F. As required by Required Ri Declare Automatic 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery Action A.i and referenced Depressurization of loss of ADS in Table 3.3.5.1-1. System (ADS) valves initiation capability in inoperable, both trip systems AND R2 Place channel in trip. 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> from discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC) inoperable AND 8 days G As required by Required Gi Declare ADS valves 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discoverj Action A.1 and referenced inoperable, of loss of ADS in Table 3.3.5.1-1. initiation capability in both trip systems AND G.2 Restore channel to 96hoursfrorn OPERABLE status. discovery of inoperable channel concurrent with HPCI or RCIC inoperable AND 8 days H. Required Action and H.1 Declare associated Immediately associated Completion supported feature(s)

Time of Condition B, C, D, inoperable.

E, F, or G not met.

HATCH UNIT 1 3.3-37 Amendment No. 266 I

Table 115.1-1 (page 1 of 5)

Emergency Core Cooling System Instrumentation APPLICABLE CONDITIONS MODES REQU[RED REFERENCED OR OTHER CHANNELS FROM SPECIFIED PER REQUIRED FUNCTION CONDITIONS FUNCTION ACTION A.1 Core Spray System

a. Reactor Vessel 1, 2, 3, 4(b) B Water Level Low 4(a) 5(a)

Low Low, Level 1

b. Diyiell Pressure - 1, 2, 3 4(b) B High c Reactor Steam 1, 2. 3 4 C Dome Pressure -

Low (Injection Permissive) 4(3), 5(e) 4 B

d. Core Spray Pump 1,2, 3, 1 per E Discharge Flow -

4(a), 5(a) subsystem Low (Bypass)

ECCS Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 151 ECCS Operating LCO 15.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six of seven safety/re 11eV valves shall be OPERABLE APPLICABIUTY: MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.

ACTIONS NOTE LCO 3.O.4.b is not applicable to HPCI.

CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A.1 Restore low pressure 7 days injection/spray subsystem ECCS injection/spray inoperable, subsystem to OPERABLE status.

B. Required Action and 8.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not AND met.

B2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C. HPCI System inoperable. C.1 VeriD by administrative 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> means RCIC System is OPERABLE.

a C.2 Restore HPCI System 14 days to OPERABLE status.

(continued)

HATCH UNIT I 3.5-1 Amendment No. 246

ECCS Operating 3.5.1 ACTiONS continued)

CONDITION REQUIRED ACTiON COMPLETION TIME

0. HPC System inoperable. 0.1 Restore HPCI System 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to OPERABLE status.

AND OR One low pressure ECCS injection/spray subsystem 0.2 Restore low pressure 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is inoperabe. ECCS injectionlspray subsystem to OPERABLE statu&

E. Two or more ADS valves El Be in MODE 3, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> inoperable.

AND OR E.2 Reduce reactor steam 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Required Action and dome pressure to associated Compietion 150 psg.

Time of Condition C or 0 not met.

F. Two or more low pressure Fl Enter LCO 3.0.3. Immediately ECCS injection/spray subsystems inoperable.

Q HPCI System and two or more ADS valves inoperable.

HATCH UNIT 1 35-2 Amendment No 204

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AREA RADIATION MONITORS on IHII-P600, 1D21-P600 REFUEL FLOOR AREA I Reactor head laydown area (1D21-K6OIA) 50 1000 2 Refueling Floor Stairway (1 D21 -K601 B) 50 1000 3 Refueling Floor (1 D21-K601 D) 50 1000 4 Drywell Shield Plug (1D21-K601E) 50 1000 5 Spent Fuel Pool & New Fuel Storage (1D21-K601M) 50 1000 203 ELEVATION AREA 6 RB 203 Working Area (1D21-K601X) 50 1000 185 ELEVATION AREA 7 Spent Fuel Pool Demin. Equip (1D21-K601C) 150 1000 8 Fuel Pool Demin. Panel (1D21-K617) 50 100 158 ELEVATION AREA 9 RB 158 Working Area (1 D21-K601 K) 50 1000 10 Rx Wtr Sample Rack Area 158 (1D21-K6OIL) 50 1000 130 ELEVATION NORTH AREA 11 TIP Area (1 D21-K601 F) 50 1000 12 North CRD HCU (1D21-K601P) 50 1000 13 TIP Probe Drives Area (1 D21 -K601 U) 100 1000

MCREC System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Main Control Room Environmental Control (MCREC) System LCO 3.7.4 Two MCREC subsystems shall be OPERABLE.

NOTE The main control room boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1,2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRV5).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MCREC subsystem A.1 Restore MCREC 7 days inoperable, subsystem to OPERABLE status.

B. Two MCREC subsystems B.1 Restore control room 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable due to boundary to inoperable control room OPERABLE status.

boundary in MODE 1, 2, or3.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A or B AND not met in MODE 1, 2, or 3.

C.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)

HATCH UNIT 1 3.7-8 Amendment No. 225

MCREC System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and NOTE associated Completion Time LCO 3.0.3 is not applicable.

of Condition A not met during movement of irradiated fuel assemblies in Di Place OPERABLE Immediately the secondary containment, MCREC subsystem in during CORE pressurization mode.

ALTERATIONS, or during OPDRVs.

D.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND D.2.2 Suspend CORE Immediately ALTERATIONS.

AND D.2.3 Initiate action to Immediately suspend OPDRVs.

E. Two MCREC subsystems E.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

(continued)

HATCH UNIT I 3.7-9 Amendment No. 225

MCREC System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two MCREC subsystems ----------NOTE------------

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated fuel assemblies in the secondary containment, F.1 Suspend movement of Immediately during CORE irradiated fuel ALTERATIONS, or during assemblies in the OPDRVs. secondary containment.

AND F.2 Suspend CORE Immediately ALTERATIONS.

AND F.3 Initiate action to Immediately suspend OPDRVs.

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GRAPH 5 UNIT 1, BORON INJECTION INITIATION TEMPERTURE 0

REACTOR POWER (%)

NOTE: May use SPDS Emergency displays in place of this Graph.

I AC[DC POWER

1. Loss of all AC power indicated by:

a. Loss of power to or from Startup Auxiliary Transformers (SAT) 1/2C and 1!2D resulting in loss of all off-site electrical power to 4160 VAC Emergency Buses 1/2E, 1/2F, and l/2G for greater than 15 minutes AND

b. Failure of emergency diesel generators to supply power to emergency busses.

AND EITHER

2. Restoration of at least one 4160 VAC Emergency Bus, 1/2E, 112F, or 1/2G, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of time of loss is NOT likely.

OR

3. Fuel Clad Barrier Evaluation indicates continuing degradation (Loss or Potential Loss) of core cooling

SS1 Loss of All Offsite Power AND Loss of All Onsite AC Power to Essential Busses (Pg. 48)

1. Loss of all AC power indicated by:

a. Loss of power to or from Startup Auxiliary Transformers (SAT) 1/2C and 1!2D resulting in loss of all off-site electrical power to 4160 VAC Emergency Buses 1/2E, 1/2F, and i/2G for greater than 15 minutes AND

b. Failure of diesel generators to supply power to emergency busses.

AND

c. Restoration of at least one 4160 VAC Emergency bus, 1!2E, 1/2F, or 1/2G, has NOT occurred within 15 minutes of time of loss of all AC power SS3 Loss of All Vital DC Power (Pg. 51) 1.. Loss of Vital DC power to 125/250 VDC Bus 1/2R22-S016 and 1/2R22-S017 indicated by bus voltage indications less than 105/2 10 VDC for greater than 15 minutes.

SA5 AC power capability to Essential Busses reduced to a single power source for greater than 15 minutes such that any additional single failure would result in STATION BLACKOUT. (Pg. 57)

1. a. AC power capability to 4160 VAC Emergency Buses 1/2E, 1!2F, and 1/2G reduced to a single power source for greater than 15 minutes AND

b. ANY additional single failure will result in station blackout.

HATCH 2O133O1 ILT-08 SRO NRC EXAM Answers ID Points 0 1 201003A2.09 1 1.00 A 2 203000K6.02 1 1.00 C 3 204000K1.15 1 1.00 A 4 205000K5.02 1 1.00 A 5 205000K5.03 1 1.00 D 6 206000A1.08 1 1.00 B 7 209001K3.01 1 1.00 A 8 209001K3.03 1 1.00 B 9 211000K2.02 1 1.00 A 10 212000A3.02 1 1.00 B 11 212000A4.15 1 1.00 A 12 215001A4.03 1 1.00 A 13 215002G2.4.4 1 1.00 D 14 215003K4.05 1 1.00 B 15 215004K1.02 1 1.00 B 16 215005A4.06 1 1.00 D 17 217000K5.06 1 1.00 C 18 218000K3.01 1 1.00 B 19 223001A3.05 1 1.00 A 20 223002A2.11 1 1.00 C 21 226001K6.04 1 1.00 B 22 2330001(4.06 1 1.00 A 23 239001K5.05 1 1.00 B 24 239002K2.01 1 1.00 A 25 241000K3.03 1 1.00 C 26 245000K4.10 1 1.00 C 27 259002A4.08 1 1.00 A 28 261000A2.07 1 1.00 A 29 261000K1.03 1 1.00 C 30 262001K6.03 1 1.00 D 31 262002G2.4.4 1 1.00 C 32 263000A3.01 1 1.00 C 33 264000G2.2.42 1 1.00 B 34 268000A1.02 1 1.00 B 35 286000K2.02 1 1.00 B 36 295001AK2.06 1 1.00 A 37 295003AK1.02 1 1.00 B 38 295004G2.1.7 1 1.00 B 39 295005AK3.02 1 1.00 D 40 295006AA1.01 1 1.00 B 41 295009AK1.02 1 1.00 C 42 295010AA2.06 1 1.00 B 43 295012AK3.O1 1 1.00 D 44 295013G2.4.18 1 1.00 B 45 2950 16AA2.07 1 1.00 B 46 295017AA1.05 1 1.00 A 47 2950 18AK3.06 1 1.00 D

1. ID Points 0 48 295019AA2.02 1 1.00 C 49 295021G2.2.40 1 1.00 D 50 295023AA2.03 1 1.00 C 51 295024EA2.06 1 1.00 A 52 29502502.1.27 1 1.00 B 53 295026EK3.04 1 1.00 C 54 295028EA1.03 1 1.00 C 55 295030EK1.02 1 1.00 D 56 295031EA1.05 1 1.00 C 57 295035EA1.01 1 1.00 B 58 295037EK2.12 1 1.00 A 59 295038EK1.01 1 1.00 D 60 300000A2.O1 1 1.00 B 61 300000K1.03 1 1.00 B 62 400000A1.01 1 1.00 D 63 500000EK2.07 1 1.00 C 64 600000AK1.01 1 1.00 C 65 700000AK2.03 1 1.00 B 66 G2.1.1 1 1.00 A 67 G2.1.8 1 1.00 D 68 G2.1.20 1 1.00 C 69 02.2.21 1 1.00 A 70 G2.2.22 1 1.00 D 71 G2.2.36 1 1.00 C 72 02.3.11 1 1.00 D 73 02.3.13 1 1.00 B 74 G2.4.16 1 1.00 A 75 G2.4.5 1 1.00 B 76 201006A2.06 1 1.00 B 77 20900102.4.49 1 1.00 A 78 215003A2.05 1 1.00 A 79 218000A2.05 1 1.00 C 80 261000A2.08 1 1.00 A 81 263000G2.4,8 1 1.00 A 82 290001A2.02 1 1.00 A 83 29000302.4.4 1 1.00 D 84 295004AA2.02 1 1.00 A 85 295007AA2.01 1 1.00 C 86 295012G2.4.11 1 1.00 D 87 29501602.2.37 1 1.00 D 88 29501902.1.28 1 1.00 D 89 295023AA2.02 1 1.00 B 90 295024EA2.02 1 1.00 C 91 295032EA2.03 1 1.00 D 92 295037G2.4.49 1 1.00 D 93 700000AA2.07 1 1.00 C 94 G2.1.3 1 1.00 B

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