ML12191A177

Initial Exam 2012-301 Final SRO Written Exam

ML12191A177
Person / Time
Site:	Farley
Issue date:	07/09/2012
From:	NRC/RGN-II
To:	Southern Nuclear Operating Co
References
50-348/12-301, 50-364/12-301
Download: ML12191A177 (153)

Text

ES-401-8 Site-Specific SRO Written Examination ILT-35 SRO NRC Exam Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: 6128/2012 Facility/Unit: FARLEY Units I & 2 Region: I D II tEl Ill D IV D Reactor Type: W tEl CE D BW 0 GE 0 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 overafl, with 70.00 percent or better on the SRO-only items if given in conjunction with the RD exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.

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

Applicants Signature Results ROJSRO-Only/Total Examination Values 75 / 25 / 100 Points Applicants Scores / / Points Applicants Grade / / Points

r A-e *(;eA9

- Answers ID 0 1 002K6.06 I D 2 OO3AA1.072 A 3 003G2.1.23 3 B 4 003K6.024 A 5 004A1.105 B 6 005A2.02 6 B 7 005AK2.02 7 D 8 005K5.02 8 B 9 006K4.119 B 10 007EG2.1.20 10 D 11 007K5.02 11 B 12 008A3.06 12 C 13 008AK3.04 13 B 14 008K3.03 14 C 15 009EK2.03 15 D 16 010A4.03 16 D 17 O11EA2.0817 A 18 0111<2.01 18 D 19 0121<1.06 19 A 20 012K6.0620 C 21 013K2.01 21 D 22 014A2.0422 C 23 017K5.0223 B 24 022AG2.4.34 24 C 25 022K3.0225 A 26 024AA1.06 26 D 27 025AK3.02 27 D 28 0261<1.01 28 C 29 027AK 1.02 29 A 30 029EK1.0330 B 31 029G2.2.3931 D 32 032AA2.05 32 D 33 033A3.02 33 A 34 033AK3.01 34 A 35 034K1.01 35 A 36 035K3.01 36 C 37 038EG2.4.47 37 C 38 039K4.02 38 D 39 O4OAA1.1139 D 40 054AA2.03 40 A 41 055EA2.0241 D 42 057AA1.0l 42 C 43 058AK1.01 43 B 44 059A3.0244 A 45 O61AK1.01 45 A 46 061K6.0246 A 47 062A1.0347 B 48 062AA1.07 48 A Page: 1 of 3 5131,201-2

49 062K3.0249 B 50 063G2.2.44 50 B 51 064K1.0451 B 52 064K4.0452 B 53 065AK3.03 53 D 54 067AG2.4.8 54 C 55 068A4.04 55 D 56 073A2.01 56 C 57 076K2.08 57 A 58 078A4.01 58 D 59 078K2.01 59 C 60 079K4.01 60 A 61 103A3.01 61 A 62 G2.1.1 62 C 63 G2.1.4 63 A 64 G2.2.40 64 C 65 G2.2.41 65 C 66 G2.3.1266 D 67 G2.3.5 67 B 68 G2.3.7 68 B 69 G2.4.1469 B 70 G2.4.43 70 D 71 G2.4.5071 C 72 WEO4EK2.2 72 A 73 WEO5EK2.1 73 B 74 WEO9EG2.420 74 D 75 WE13EK3.475 A SECTION 1 (75 items) 75.00 76 003AG2.2.22 76 D 77 005G2.4.30 77 C 78 006A2.0278 A 79 008A2.01 79 C 80 010G2.4.45 80 A 81 O11EA2.1481 A 82 024AG2.4.46 82 A 83 025AA2.05 83 13 84 026A2.03 84 B 85 026AG2.2.25 85 D 86 034K4.01 86 B 87 056AG21.7 87 D 88 067AA2.08 88 C 89 072G2.2.36 89 B 90 016A2.01 90 B 91 G2.1.891 C 92 G2.2.1 92 D 93 G2.2.1593 A Page: 2 of 3

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1. Unit I is operating at 95% power.

Which one of the following completes the statements below regarding FT-424, RCS LOOP B FLOW, transmitter?

CONSIDER EACH CASE SEPARATELY AND THAT EACH RUPTURE IS 100%

IF one LOW-pressure tap to FT-424 ruptures, a RCS LOOP LOW FLOW RxTrip (I) occur.

IF one HIGH-pressure tap to FT-424 ruptures, a RCS LOOP LOW FLOW Rx Trip (2) occur.

(1) (2)

A. WILL will NOT B. will NOT will NOT C. WILL WILL D. will NOT WILL ILT-35 SRO NRC Exam 6/28/2012 Page 1 of 100

2. Unit 1 is stable with the following conditions:

• Rods were in Manual.

• Reactor power was 58% and stable.

• AFD on all channels was 0.0% +/- 0.1%.

Subsequently, a single control rod drops which results in the following indications/conditions:

• Control Bank B Rod K4 rod bottom light is LIT.

• The Nuclear Instruments display the following indications within 2 minutes with no operator action:

PERCENT FULL N-41B N-42B N-43B N-44B POWER indication 38% 55% 50% 54%

PERCENT FLUX N-41C N-42C N-43C N-44C DIFF indication [see below] (-) 0.1% (+) 0.4% (+) 0.1%

Which one of the following completes the statements below?

N-41C, PERCENT FLUX DIFF, indication will read (1)

FC3, PR HI FLUX-RATE ALERT, (2) be in alarm.

(1) (2)

A. 0.0% +/- 0.4% will NOT B. 0.0% +/- 0.4% WILL C. more negative than (-) 1.0% will NOT D. more negative than (-) 1.0% WILL ILT-35 SRO NRC Exam 6/28/2012 Page 2 of 100

3. The foHowing conditions exist on Unit I

• UOP-1.1, Startup Of Unit From Cold Shutdown To Hot Standby, is in progress.

• RCS temperature is 150°F.

• RCS pressure is 340 psig.

• All SG water temperatures are GREATER THAN 50°F above each of the RCS cold leg temperatures.

• The crew is preparing to start the first RCP; 1 B RCP will be started first.

Which one of the following satisfies the requirements for the lowest RCP #1 Seal Differential Pressure (DP) and Cold Pressurizer Level that will permit starting the lB RCP in accordance with UOP-1.1?

Pl-155A, lB RCP Ll-462,

1. 1 SEAL PRESS PRZR LVL A. 215 psid 30%

B. 215 psid 21%

C. 195 psid 30%

D. 195 psid 21%

ILT-35 SRO NRC Exam 6/2812012 Page 3 of 100

4. A Loss of all AC Power has occurred on Unit I and the crew is performing Attachment 3 of ECP-O.O, Loss of All AC Power.

Which one of the following completes the statements below in accordance with the bases for ECP-O.O, Loss of All AC Power?

The reason that the Seal Water Injection Filter Isolation valves are closed is to (1)

The reason that the RCP Thermal Barrier Return isolation valves are closed is to (2)

A. 1) protect the RCP seals and shaft

2) protect the CCW system from steam formation B. I) prevent filling the VCT and a potential radioactive release within the Auxiliary building.

2) protect the CCW system from steam formation C. 1) protect the RCP seals and shaft

2) prevent filling the VCT and a potential radioactive release within the Auxiliary building.

D. I) prevent filling the VCT and a potential radioactive release within the Auxiliary building.

2) protect the RCP seals and shaft LT-35 SRO NRC Exam 6/28/2012 Page 4 of 100

5. A Unit 1 Startup is in progress from a Mid-cycle forced outage. The following conditions exist:

• The Reactor is in Mode 1, MOL.

• A letdown malfunction has occurred.

• AOP-16.O, CVCS Malfunction, is in progress.

• Excess letdown is being placed into service using SOP-2.7, Chemical And Volume Control System Excess Letdown.

• Excess letdown was LAST in service at BOL of the current Cycle.

Which one of the following completes the statements below regarding the operation of the excess letdown system?

An ineffective flush on the excess letdown system will result in a (1)

The Online Calorimetrics TOTAL RX THERM OUTPUT value on the IPC (2) be affected when Excess Letdown is placed in service.

(1) (2)

A. dilution WILL B. boration WILL C. dilution will NOT D. boration will NOT ILT-35 SRO NRC Exam 6/28/2012 Page 5 of 100

6. Unit 1 is performing a Startup from Cold Shutdown. The following conditions exist:

. The RCS is solid.

. SOP-i .3, Reactor Coolant System Filling And Venting Vacuum Method, is in progress.

• HIK-142, RHR TO LTDN HX controller, setting is at 80% demand.

• PK-145, LP LTDN PRESS controller, is in AUTO.

• RCS pressure is 340 psig and

• RCS temperature is 177°F and

• LP letdown is aligned to B Train RHR.

The air supply to HCV-142 actuator has been severed and the valve has repositioned to its failed position.

Which one of the following completes the following statements?

The RHR suction Relief valves (1) Lift. (Assume no operator actions)

The required actions are to (2)

(1) (2)

A. WILL adjust HIK-603B, 1 B RHR DISCH VLV, to raise RHR flow B. WILL adjust FK-122, CHG FLOW to reduce charging flow C. will NOT adjust FK-122, CHG FLOW to raise charging flow D. will NOT stop the lB RHR pump ILT-35 SRO NRC Exam 6/28/2012 Page 6 of 100

7. Unit 1 is at 70% power. The following conditions exist:

• Rod H2, Control Bank D Group I rod, is 10 steps lower then the rest of CB D rods.

• Operators are preparing to realign the rod in accordance with AOP-19.0 Attachment 2, Misaligned Rod Recovery or Maintenance Testing.

Which one of the following completes the statements below?

AOP-19.0 will require the crew to open the lift coil disconnect switches for Control Bank D non-affected (1)

As a result of this action, (2) , will alarm when Rod H2 is withdrawn.

(1)

(2)

A. Group 1 rods ONLY FF2, ROD CONT SYS NON-URGENT FAILURE B. Group 1 rods ONLY FF1, ROD CONT SYS URGENT FAILURE C. Group 1 and Group 2 rods FF2, ROD CONT SYS NON-URGENT FAILURE D. Group 1 and Group 2 rods FF1, ROD CONT SYS URGENT FAILURE ILT-35 SRO NRC Exam 6/28/2012 Page 7 of 100

8. The following conditions exist on Unit 1:

• RCS pressure is 500 psig.

• 1A RHR system is being prepared for RCS cooldown alignment using SOP-7.0, Residual Heat Removal System.

• The 1A RHR pump is running on recirculation for sampling.

• Pl-600A, 1A RHR PUMP DISCH PRESS, is 260 psig.

• MOV-3185A, CCW to IA RHR HX, has been shut to warm-up RHR.

Which one of the following completes the statements below in accordance with SOP-7.0?

The 1A RHR pump is permitted to run on recirculation with MOV-3185A closed foraMAXlMUMtimeof (1)

This time limit precludes the potential for pump damage (2)

(I) (2)

A. 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> because CCW to the seal cooler is isolated B. 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> due to cavitation C. 0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> because COW to the seal cooler is isolated D. 0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> due to cavitation ILT-35 SRO NRC Exam 6/28/2012 Page 8 of 100

9. An automatic Safety Injection has actuated on Unit 1.

The conditions that caused the Safety Injection to actuate are now clear.

Which one of the following completes the statements below?

ONLY (1) permits RESET of the Safety Injection signal when the SI RESET A(B)

TRN pushbutton is depressed.

To allow a subsequent automatic Safety Injection Actuation to occur the (2)

(1) (2)

A. a 60 second time-delay relay ESS STOP RESET pushbutton on the sequencer(s) that ran must be depressed B. a 60 second time-delay relay Reactor Trip Breakers must be closed C. the P-4, Reactor Trip Interlock, ESS STOP RESET pushbutton on the sequencer(s) that ran must be depressed D. the P-4, Reactor Trip Interlock, Reactor Trip Breakers must be closed ILT-35 SRO NRC Exam 6/2812012 Page 9 of 100

10. The crew has manually tripped the Unit 2 reactor from 100% due to thrust bearing wear measurements reaching 40 mils on the Main Turbine per SOP-28.1, Turbine Generator Operation. The following conditions exist:

• The MAIN TURB EMERG TRIP switch was positioned to TRIP for 8 seconds.

• All Governor valves are CLOSED.

• All Throttle Valves are OPEN.

• The Main Generator output 500 KV BKRs 1002 & 1102 are closed.

Which one of the following completes the statements below?

In accordance with ESP-0.1, Reactor Trip Response, the Main Generator output 500 KV BKRs are required to be opened (1) the Main Turbine is tripped.

The reason the procedure directs placing the REVERSE POWER switch in the BYPASS position is to (2)

(1) (2)

A. IMMEDIATELY when bypass the FAST DEAD BUS TRANSFER circuit and allow re-energizing the RCP buses from the Start Up Transformers, if not already aligned B. IMMEDIATELY when allow the breakers to be manually opened without a reverse power signal C. 30 seconds after bypass the FAST DEAD BUS TRANSFER circuit and allow re-energizing the RCP buses from the Start Up Transformers, if not already aligned D. 30 seconds after allow the breakers to be manually opened without a reverse power signal ILT-35 SRO NRC Exam 6/28/2012 Page 10 of 100

I

11. Unit I is solid in Mode 5, preparing to form a pressurizer steam space (drawing a bubble). The following conditions exist:

• UOP-1 .1, Startup of Unit from Cold Shutdown to Hot Standby, is in progress.

• Vacuum refill will NOT be performed.

• RCS pressure is 325-375 psig and -.

• lB RCP is running.

• A Train RHR is in service with low pressure letdown aligned.

• RCS is in solid plant pressure control with pressurizer temperature at 178°F.

• All PRZR heaters have been energized.

Which one of the following completes the statements below per UOP-1 .1?

The condition that is monitored to demonstrate the PRZR is saturated is (1)

As the bubble is being formed, PRT level will (2)

(1) (2)

A. Letdown flow lowering remain constant B. RCS Pressure rising remain constant C. RCS Pressure rising slowly rise D. Letdown flow lowering slowly rise LT-35 SRO NRC Exam 6/28/2012 Page 11 of 100

12. Unit I has experienced a spurious SI. The following conditions exist:

• EEP-0.0, Reactor Trip Or Safety Injection, is in progress.

• DFOI, IA S/U XFMR TO 1 F 4160 V Bus, has tripped open.

• A Train is the ON-SERVICE Train.

• I B Spent Fuel Pool Cooling Pump (SFPC) has just been started per EEP-0.0 Attachment 2, Automatic Actions Verification.

Subsequently, the IC CCW pump has TRIPPED on an Overcurrent condition.

Which one of the following completes the statements below?

The lB CCW pump (1) automatically start.

The kW loading of the CCW pump will/would be (2) the 1 B SFPC Pump.

(1) (2)

A. WILL approximately EQUAL TO B. will NOT approximately EQUAL TO C. WILL GREATER than D. will NOT GREATER than ILT-35 SRO NRC Exam 6/28/2012 Page 12 of 100

13. A vapor space LOCA has occurred on Unit 2 and the crew has transitioned to EEP-1 .0, Loss of Reactor or Secondary Coolant.

In accordance with the bases of EEP-1 .0, which one of the following statements identifies the reason why the RCPs are required to be stopped if the EEP-1 .0 Foldout Pages RCP Trip Criteria is met?

A. Because the additional RCP heat input may exceed the capacity of one ESF train if a loss of off-site power subsequently occurs.

B. Because RCP trips within different time frames produce different effects on final peak clad temperatures.

C. To maximize the high pressure safety injection flow rate.

D. To protect the RCP seal package.

ILT-35 SRO NRC Exam 6128/2012 Page 13 of 100

14. Unit 1 is at 84% power when a rupture of the IA RCP Thermal Barrier occurs.

Which one of the following completes the statements below?

HV-3184, CCW DISCH RCP TRM BARR ISO, will automatically close at (1)

In accordance with LB3, RCP THRM BARR ISO HV-3184 AIR PRESS LO, an immediate shutdown of the Reactor and IA RCP (2) required.

(1) (2)

A. 160 gpm is NOT B. 160 gpm C. 75 psig is NOT D. 75 psig IS ILT-35 SRO NRC Exam 6/28/2012 Page 14 of 100

15. A Unit 1 automatic Reactor Trip has occurred as a result of a 200 gpm RCS leak. The following conditions exist:

ESP-1 .2, Post LOCA Cooldown and Depressurization, is in progress.

RCS temperature trend is as follows:

TIME: 09:00 09:30 10:00 (now)

RCS Cold Leg Avg Temp: 535°F 480°F 440°F Which one of the following completes the statements below per ESP-1 .2?

Based only on the trend above, the cooldown rate at 10:00 is (1) allowable limits.

(2) to complete the required cooldown.

(1) (2)

A. greater than The combined effects of HHSI and break flow are ALONE sufficient B. greater than In addition to the effects of HHSI and break flow, Steam Dumps will be needed C. within The combined effects of HHSI and break flow are ALONE sufficient D. within In addition to the effects of HHSI and break flow, Steam Dumps will be needed ILT-35 SRO NRC Exam 6/28/2012 Page 15 of 100

16. Unit 1 is at 100% power. The following conditions exist:

• PT-445, PRZR PRESS, fails HIGH.

Which one of the following completes the statements below?

Initially, the pressurizer PORV (1) will automatically open; This PORV will (2) when actual RCS pressure drops below 2000 psig.

(1) (2)

A. PCV-444B remain open B. PCV-444B automatically close C. PCV-445A remain open D. PCV-445A automatically close ILT-35 SRO NRC Exam 6/28/2012 Page 16 of 100

17. A Large Break LOCA has occurred on Unit 1. EEP-1 .0, Loss of Reactor or Secondary Coolant, is in progress. The following timeline of events has occurred:

09:30: An RCS Leak required a manual Reactor Trip and Safety Injection per AOP-1 .0, RCS Leakage.

10:00: Containment pressure rose from 6.8 psig to 29 psig.

11:00: ESP-1 .3, Transfer to Cold Leg Recirculation, was completed.

Which one of the following states the EARLIEST time ESP-1 .4, Transfer to Simultaneous Cold and Hot Leg Recirculation, is required to be implemented?

A. 17:00 B. 17:30 C. 18:30 D. 19:00 ILT-35 SRO NRC Exam 6/28/2012 Page 17 of 100

18. Unit 2 is in Mode 4 with the following conditions:

A Train is the ON-SERVICE Train.

Both Trains of RHR are in service in a shutdown cooling alignment.

Following a 2G 4160 volt bus fault, the bus is de-energized and remains de-energized for trouble shooting and repairs.

Which one of the following lists the ECCS pumps which are DE-ENERGIZED due to the fault?

Charging Pump RHR Pump A. 2B 2A B. 2B 2B C. 2C 2A D. 2C 2B ILT-35 SRO NRC Exam 6/28/2012 Page 18 of 100

19. Unit 2 is operating at 38% power. The foHowing conditions exist:

• STP-62.0, Main Turbine Valve Operability Test, is in progress.

• Throttle Valve (TV) #3 has just been discovered stuck at 100% open.

Immediately after the discovery noted above, a malfunction occurs within the Main Turbine Lube Oil system causing:

• KH2, TURB BRG OIL PRESS LO, alarm.

• P1-4019, TURB BRG OIL PRESS, indicates 4 psig.

Which one of the following completes the statement below?

An automatic Reactor Trip (1) occur because (2)

(1) (2)

A. WILL Auto-Stop Oil Header low oil pressure will input to the Reactor Protection System (RPS)

B. WILL the RPS coincidence of 3 of 4 Throttle Valves is met C. will NOT the RPS coincidence of 4 of 4 Throttle Valves is NOT met D. will NOT Reactor Power is below the P-9 setpoint ILT-35 SRO NRC Exam 6/28/2012 Page 19 of 100

20. Unit 2 is performing a Startup. The following conditions exist:

• ReactorPoweris6%.

• RCS Tavg is 554°F.

• Steam Dumps are in STM PRESS mode.

• PK-464, STM HDR PRESS, controller is in automatic.

• PT-447, TURB FIRST STG PRESS, fails HIGH.

Which one of the following describes the impact of PT-447 failure?

A. FA3, SR LOSS OF DET VOLTAGE, clears.

B. The Steam Dumps will automatically CLOSE.

C. The Pressurizer High Level Rx Trip will automatically UNBLOCK.

D. AMSAC actuation circuit will be enabled, turbine power input to 0-20 is satisfied.

LT-35 SRO NRC Exam 6/28/2012 Page 20 of 100

21. Which one of the following describes the power supply(ies) for the Bi F ESF/LOSP Sequencer?

A. Either 120V Regulated AC Panel 10 OR 120V Vital AC Panel IA (balanced between both, if available).

B. Either 125V DC Bus 1A (normal) OR 125V DC Bus 2A (alternate).

C. 120V Vital AC Panel 1A ONLY.

D. 125V DC Bus 1A ONLY.

ILT-35 SRO NRC Exam 6/28/2012 Page 21 of 100

22. Unit 1 is at 14% power. The following conditions exist:

• All Control Bank D (CB D) rods indicate 180 steps by DRPI and Group Step counters.

• Rods are in Manual.

The OATC placed the IN-HOLD-OUT switch to the OUT position for 14 seconds before noting that CB D rod H-2 did NOT move (still at 180 steps).

The SM reports that repairs will take several hours to complete.

Which one of the following completes the statements below?

Rod H-2 will be misaligned by (1)

AOP-19.0, Malfunction of Rod Control System, (2) permit inserting CB D to match the position of rod H-2 while waiting to complete the repairs.

(1) (2)

A. 11 or 12 steps does NOT B. 14 or l5steps does NOT C. 11 or 12 steps DOES D. 14 or 15 steps DOES ILT-35 SRO NRC Exam 6/28)2012 Page 22 of 100

1

23. A Unit 2 cooldown and depressurization is in progress in accordance with ESP-1 .2, Post LOCA Cooldown And Depressurization. The following conditions exist:

• Both trains of Subcooled Margin Monitoring have failed.

• Containment Pressure peaked at 13 psig, but is now 6 psig.

• lB RCP is running.

• PRZR level is 50%.

• RCS LOOP WR PRESSURE instruments indicate as follows:

PT-402 855 psig PT-403 952 psig

• RCS temperature indications are as follows:

TRAIN A TR-0413, RCS HOT CETC MONITOR LEG TEMP (lB LOOP) (TMAX mode) 493°F 508°F Which one of the following completes the statements below in accordance with ESP-1 .2?

RCS sub-cooling is (1)

SI REINITIATION (2) required.

(1) (2)

A. 20°F is NOT B. 20°F IS C. 35°F is NOT D. 35°F IS ILT-35 SRO NRC Exam 6/28/2012 Page 23 of 100

24. The Control Room has been evacuated due to a fire. The following conditions exist:

• AOP-28.2, Fire in the Control Room, is in progress.

• All required component controls have been transferred to the LOCAL position at the Hot Shutdown panel (HSDP).

• PRZR level is 16% and 4.

Which one of the following completes the statements below?

Letdown (1) automatically isolate if PRZR level continues to fall.

The operator (2) from the HSDP.

(1) (2)

A. will NOT should close LCV-459 & LCV-460, LTDN LINE ISO, valves B. will NOT should close HV-8149A1B/C, LTDN ORIF ISO, valves C. WILL will NOT be capable of restoring letdown D. WILL WILL be capable of restoring letdown ILT-35 SRO NRC Exam 6/28/2012 Page 24 of 100

25. A small steam line break has occurred on Unit 1. The following conditions exist:

Containment temperature has risen to 126°F.

Containment pressure has risen to 12 psig.

Which one of the following completes the statements below?

The Containment Cooler discharge ductwork POST-LOCA Dropout Plates are (1)

The accuracy of PT-952, CTMT PRESS, (2) be affected by the Containment Air Temperature.

(1) (2)

A. CLOSED will NOT B. OPEN will NOT C. CLOSED WILL D. OPEN WILL ILT-35 SRO NRC Exam 6/28/2012 Page 25 of 100

26. Unit 1 is in a Refueling Outage with fuel being loaded into the core.

Which one of the following completes the statements below?

The MINIMUM temperature that ensures the Boric Acid Storage Tanks (BAT) remain FUNCTIONAL in accordance with TR 13.1.6, Borated Water SourcesShutdown is TIS-107 &TIS-109, IA and lB BAT temperature indicators, are located on the Temperature Location A. 35°F 121 near the boric acid batching station B. 35°F 100 in the BAT room C. 65°F 121 near the boric acid batching station D. 65°F 100 in the BAT room LT-35 SRO NRC Exam 6/28/2012 Page 26 of 100

27. Which one of the following describes the LOWEST pressure that will cause an automatic cJosure of MOV-8701A, 1C RCS LOOP TO 1A RHR PUMP, and the reason for that interlock as described in Tech Spec 3.4.14, RCS Pressure Isolation Valve (PIV)

Leakage, BASES?

Pressure Reason lAW Tech Spec Bases 3.4.14 A. 450 psig Prevents overtifling and overpressurization (125% of design) of the PRT.

B. 450 psig Prevents overpressurization (125% of design) of the RHR system.

C. 700 psig Prevents overfilling and overpressurization (125% of design) of the PRT.

D. 700 psig Prevents overpressurization (125% of design) of the RHR system.

ILT-35 SRO NRC Exam 6/28/2012 Page 27 of 100

28. Which one of the following completes the statements below for Unit 1 following a Large Break LOCA?

The Containment Sump Suction valves for the (1) will automatically open on a LO-LO RWST condition.

The IA RHR and IA CS pumps (2) share a common suction strainer/flow path when aligned to the Containment sump.

(1) (2)

A. CS Pumps (MOV-8826/8827 A/B) do NOT B. CS Pumps (MOV-8826/8827 A/B) DO C. RHR Pumps (MOV-881 1/8812 A/B) do NOT D. RHR Pumps (MOV-881 1/8812 A/B) DO LT-35 SRO NRC Exam 6/28/2012 Page 28 of 100

29. Unit 2 is at 100%. The following conditions exist:

• PK-444A, PRZR PRESS REFERENCE controller, AUTO operation has failed.

• AOP-100, Instrument Malfunction, required actions have been completed.

• PK-444A is in manual and controlling RCS pressure at 2235 psig.

• Both PRZR Spray Valve controllers are in Auto.

• All PRZR Backup heaters are in the ON position.

Subsequently, an instantaneous 15% Load Rejection occurs.

Which one of the following completes the statements below?

The load rejection will initially cause Tl-450, PRZR SRG LINE, temperature to (1)

To control RCS pressure the operator must (2) the OUTPUT on PK-444A.

(1) (2)

A. LOWER LOWER B. LOWER RAISE C. RISE LOWER D. RISE RAISE ILT-35 SRO NRC Exam 6/28/2012 Page 29 of 100

30. Unit I has experienced an Anticipated Transient Without a Trip (ATWT). -

• FRP-S.l, Response to Nuclear Power Generation/ATWT, is in progress.

• The reactor was tripped LOCALLY.

• Two (2) Shutdown Bank Rods remain at the 228 position on DRPI.

• The NORMAL Emergency Boration flow path has been aligned.

Which one of the following completes the statements below in accordance FRP-S.I?

V The MINIMUM required flow indication on Fl-hO, BORIC ACID EMERG BORATE, is (1)

A MINIMUM of (2) via the Emergency Boration flow path is required to be injected for the control rods which are not fully inserted.

(1) (2)

A. 30 gpm 2500 gallons B. 30 gpm 5000 gallons C. 92 gpm 2500 gallons D. 92 gpm 5000 gallons ILT-35 SRO NRC Exam 6/28/2012 Page 30 of 100

31. The following conditions exist on Unit 2:

• Fuel movement inside containment is in progress.

• CTMT Main Purge is in HIGH speed.

• SFP Ventilation is in service.

• R-24A, CTMT PURGE, radiation monitor failed HIGH.

• The CTMT Main Purge supply valves did not close and will not close when the handswitches are taken to the CLOSE position.

Which one of the following completes the statements below?

Fuel movement inside containment (1) per TS 3.9.3, Containment Penetrations.

When securing CTMT Main Purge per SOP-12.2, Containment Purge and Pre-Access Filtration System, the reason one AUX BLDG MN EXH FAN is required to be secured is to prevent (2)

(1) (2)

A. MAY continue an automatic trip of SFP ventilation on low air flow B. must be IMMEDIATELY suspended an automatic trip of SFP ventilation on low air flow C. MAY continue damaging the Aux Bldg exhaust plenum D. must be IMMEDIATELY suspended damaging the Aux Bldg exhaust plenum ILT-35 SRO NRC Exam 6/28/2012 Page 31 of 100

32. Unit 2 Reactor startup is in progress in accordance with UOP-1 .2, Startup of Unit From Hot Standby to Minimum Load. The following conditions exist:

Intermediate Range power indications are stable at the following values:

Nl-35 3 x 10-11 amps Nl-36 5 x 10-11 amps Which one of the following conditions will result in a reactor trip at this time?

A. The operator places the SR channel Nl-31 HV Manual ON/OFF switch in HV OFF.

B. IR channel NI-35 becomes undercompensated and reads 5 x 1010 amps.

C. IR channel N 1-36 becomes overcompensated and reads 1 x 1011 amps.

D. SR channel NI-31 fails high.

ILT-35 SRO NRC Exam 6/28/2012 Page 32 of 100

33. Unit 1 has completed a core offload and is currently defueled. The following conditions exist:

Both SFP Cooling pumps are running in accordance with SOP-54.0, Appendix 1, OPERATION OF BOTH SFP COOLING TRAINS.

A failure of the IA Spent Fuel Pool Cooling (SFPC) Pump Seal occurs.

The leak rate is 30 gpm.

Which one of the following completes the statements below?

If NO OPERATOR action is taken, the SFP inventory loss will stop due to (1).

AFTER this inventory loss has stopped, the SFP will be re-filled using the (2)

(1) (2)

A. the uncovering of the pumps suction RWST piping B. the siphon breaker RWST C. the uncovering of the pumps suction Demineralized Water System piping D. the siphon breaker Demineralized Water System ILT-35 SRO NRC Exam 6/28/2012 Page 33 of 100

34. Unit 1 startup is in progress in accordance with UOP-1 .2, Startup of Unit From Hot Standby to Minimum Load. The following conditions exist:

• SR Nuclear Instruments indicate 1500 cps.

• Control Bank C is at 50 steps.

• N-36, Intermediate Range, loses Control Power.

Which one of the following completes the statement below?

The startup will terminate because Procedure title:

TS 3.3.1, Reactor Trip System (RTS) Instrumentation A. the reactor has automatically tripped.

B. T.S. 3.3.1 requires an IMMEDIATE manual trip since two source range neutron flux channels are inoperable.

C. T.S. 33.1 requires an IMMEDIATE suspension of positive reactivity since reactor power is currently> P-6 and < P-10 with one intermediate range neutron flux channel inoperable.

D. T.S. 3.3.1 requires an IMMEDIATE plant shutdown to Mode 3 since thermal power is < P-10, and one intermediate range neutron flux channel is inoperable.

ILT-35 SRO NRC Exam 6/28/2012 Page 34 of 100

35. Which one of the following completes the statements below per TR 13.9.3, Manipulator Crane?

The Manipulator Cranes GRIPPER OVERLOAD cut off limit is (1)

This GRIPPER OVERLOAD cut off limit provides protection to the (2)

(1) (2)

A. <2850 lbs Core internals B. <2850 lbs Manipulator Bridge Structure C. <1850 lbs Core internals D. < 1850 lbs Manipulator Bridge Structure ILT-35 SRO NRC Exam 6/28/2012 Page 35 of 100

36. Unit I is in Mode 3 warming up the Main Steam lines using SOP-17.O, Main and Reheat Steam. The following conditions exist:

• RCS Temp is 547° F.

• All MSIV Bypass valves are OPEN.

• All MS BYP WARMUP VLVs (VOI9AIB/C) are OPEN.

• Steam header pressure and each SG pressures are approximately equal.

• Steam Dumps are in STM PRESS mode.

• PK-464, STM HDR PRESS, controller is in automatic.

Immediately after all MSIVs are opened:

• A Steam Leak is reported in the Turbine Building.

• All SG MSIVs are immediately closed from the MCB.

Which one of the following predicts how RCS temperature will respond?

RCS temperatures will A. remain at 547° F B. continuously lower C. rise to 552° F and then stabilize at 552° F D. lower to 543°F, then rise and stabilize at 547°F ILT-35 SRO NRC Exam 6/28/2012 Page 36 of 100

37. A manual Reactor Trip and Safety Injection was manually initiated on Unit 1.

At 10:00: the following indications were available during diagnostics of EEP-0.0, Reactor Trip or Safety Injection:

• AFW flow is controlled at an equal value for all SGs to control RCS temperature.

• Containment pressure is 1 .2 psig.

• All MSIVs are open.

IA lB 1C

• SG levels: 49% 33% 35%

• SG level trends: rising rapidly slowly rising slowly rising At 11:00: the crew has progressed through the actions of EEP-3.0, Steam Generator Tube Rupture. The following conditions exist.

• Containment pressure is still 1 .2 psig.

• Normal charging has been aligned.

• Pressurizer level is 40% and rising.

1A lB 1C

• SG levels: 39% 41% 40%

• SG level trends: slowly lowering slowly rising stable Which one of the following describes the required actions to minimize RCS to secondary leakage per EEP-3.0?

REFERENCE PROVIDED A. RAISE charging flow ONLY B. LOWER PRZR Pressure ONLY C. Energize PRZR heaters ONLY D. BOTH LOWER PRZR Pressure AND RAISE charging flow ILT-35 SRO NRC Exam 6/28/2012 Page 37 of 100

38. Unit 1 is operating at 18% power with the following conditions:

• The Main Generator has been tied to the grid.

• Rods are in Manual.

• Steam Dumps are in STM PRESS mode.

• PK-464, STM HDR PRESS, controller is in automatic.

A Governor Valve malfunction occurred causing a step rise in steam flow. The following response/conditions resulted:

• The Main Turbine was manually tripped.

• RCS temperatures fell to the listed values and are all currently rising:

IA lB IC

- TAVG RCS LOOP 539°F 542°F 543°F Which one of the following completes the statements below?

The TS 3.4.2, RCS Minimum Temperature for Criticality, limiting condition of operation value (1) exceeded.

As the RCS temperature rises, the steam dumps (2) automatically re-open.

(1) (2)

A. was NOT WILL B. was NOT will NOT C. WAS WILL D. WAS will NOT ILT-35 SRO NRC Exam 6/28/2012 Page 38 of 100

39. A steam leak which caused a 20% mismatch in Turbine and Rx power has occurred in the Turbine Building.

All required actions of AOP-14.0, Secondary System Leakage, have been completed.

The following conditions exist:

• The Reactor was tripped using the CRDM MG set supply breakers because the Reactor Trip Breakers failed to open.

• ESP-0.1, Reactor Trip Response, is in progress.

• RCS Tavg is 540°F and j%

• SGNRlevelsareasfollows: 1A lB 10 58% 60% 58%

Which one of the following completes the statements below?

The Feed Regulating Valves (1) automatically CLOSED.

The SGFPs will be coasting down (2)

(1) (2)

A. HAVE to a stable 3200 RPM B. HAVE to less then 500 RPM C. have NOT to a stable 3200 RPM D. have NOT to less then 500 RPM ILT-35 SRO NRC Exam 6/28/2012 Page 39 of 100

40. Unit 2 is operating at 36%, the following conditions exist:

Condenser Vacuum is degrading.

IA SGFP is the ONLY SGFP pump running.

Which one of the following completes the statements below?

The low condenser vacuum automatic trip setpoint for the 1A SGFP is (1)

Both MDAFW pumps will (2)

A. 1)5.9 psia

2) auto-start immediately when the 1A SGFP automatically trips B. 1)10.8psia

2) auto-start immediately when the IA SGFP automatically trips C. 1)5.9psa

2) NOT immediately auto-start; they will eventually auto-start when at least one SG level drops below 28%

D. 1) 10.8 psia

2) NOT immediately auto-start; they will eventually auto-start when at least one SG level drops below 28%

LT-35 SRQ NRC Exam 6/28/2012 Page 40 of 100

41. Unit 1 was operating at 98% power when a Loss of ALL AC Power occurred. Twenty (20) minutes later, the following plant conditions exist:

• All efforts to restore AC power have failed.

• DC loads have been minimized per Attachment 4 of ECP-0.0, Loss of All AC Power.

• RCS pressure is 1765 psig and -.

• Containment pressure is 1 .9 psig and .

• RCS Loop THOT is 595°F in all 3 loops and 4.

• RCS Loop TCOLD is 551°F in all 3 loops and 4.

• Core exit TCs indicate approximately 600°F and %L slowly.

• SG NR levels are as follows: IA lB 10 18% 32% 30%-

Which one of the following completes the statements below?

Adequate Natural Circulation (1) currently exist.

When the step to Reduce intact SGs pressure to 260 psig is reached, the SG Atmospheric Relief valves are required to be controlled (2) per ECP-0.0.

(1) (2)

A. does NOT remotely from the 100 Lower Equipment Room B. does NOT locally at the valve C. DOES remotely from the 100 Lower Equipment Room D. DOES locally at the valve ILT-35 SRO NRC Exam 6/28/2012 Page 41 of 100

42. Unit I is at 100% power, with the Reactor Makeup Water (RMW) system in the following condition:

• The MKUP MODE SEL SWITCH is in AUTO and the MKUP MODE CONT SWITCH red light is LIT.

• IA RMW pump is running.

• lB RMW pump is in AUTO.

A malfunction occurs resulting in the following indications:

• WDI, IA INV FAULT, comes into alarm.

• IA INVERTER EPB ammeter reads 0 amps.

Local IA Inverter indications are as follows:

• BATTERYINPUTBKR TRIPPED

• INVERTEROUTPUTBKR CLOSED

• BYPASS SOURCE POWERING LOAD light NOT lit

• IN SYNC light NOT lit

• BYPASS SOURCE AVAILABLE light LIT Which one of the following completes the statements below in accordance with WD1 alarm response procedure?

In order to re-energize the associated Vital Instrument Panel, the operator must (1)

The lB RMW pump (2) the 1A Vital Instrument Panel is re-energized.

A. 1) depress the BYPASS SOURCE TO LOAD pushbutton

2) will start and is required to be stopped when B. 1) depress the BYPASS SOURCE TO LOAD pushbutton

2) will remain stopped and will NOT be capable of an automatic start until C. 1) place the MANUAL BYPASS switch to the BYPASS SOURCE TO LOAD position

2) will start and is required to be stopped when D. 1) place the MANUAL BYPASS switch to the BYPASS SOURCE TO LOAD position

2) will remain stopped and will NOT be capable of an automatic start until ILI-35 SRO NRC Exam 6/28/2012 Page 42 of 100

43. Which one of the following completes the statement below in accordance with the CAUTION listed in FNP-1-ECP-O.O, Loss of All AC Power?

CAUTION: If power is not restored to the 125V DC battery chargers on each train wfthin THEN TIME CONSEQUENCE A. 30 minutes the TDAFW Pump will become unreliable B. 30 minutes there may not be enough DC capacity to start a DG and sequence needed loads C. 90 minutes the TDAFW Pump will become unreliable D. 90 minutes there may not be enough DC capacity to start a DG and sequence needed loads ILT-35 SRO NRC Exam 6/28/2012 Page 43 of 100

44. Unit 2 is at 85% reactor power and stable, holding for chemistry with the following conditions:

• Rod control is in MANUAL.

• Main FRV original positions are 68% open.

Subsequently, a 200 MW load rejection occurs.

Which one of the following predicts the final status of the Main Feed Regulating Valves (FRV5) position and SG water level?

The Main FRVs will return to a position of (1)

Each SG NR water level will return to (2)

(1) (2)

A. less than 68% open the original level B. 68% open the original level C. less than 68% open a level less than the original level D. 68% open a level less than the original level ILT-35 SRO NRC Exam 6/28/2012 Page 44 of 100

45. A LOCA has occurred on Unit 2, and the following conditions exist:

• Containment pressure peaked at 22 psig and is now 4.

• R-27A, CTMT HIGH RANGE, is reading 1 RIhr.

Which one of the following completes the statements below?

RE-il, CTMT PARTICULATE (OH 1), indication (1) a valid indication of containment conditions.

The yellow ALERT pushbutton on RE-27A (2) lit.

(1) (2)

A. is NOT is NOT B. is NOT IS C. IS is NOT D. IS IS ILT-35 SRO NRC Exam 6128/2012 Page 45 of 100

1

46. Unit I is in MODE 3 with the following conditions:

At 10:00:

• The TDAFW and lB MDAFW pumps are NOT running.

• 1A MDAFW pump is running.

• FCV-3227A, MDAFWP TO 1A SG, is 25% open.

At 10:15:

Light smoke has just been reported coming from 1A MDAFW pump motor and the pump was secured.

At 10:24:

• DF-1O, 1A MDAFW pump supply breaker, is racked out.

• SG NR levels have lowered to: IA lB 10 26% 36% 29%

Which one of the following completes the statements below?

(1) is/are running.

The minimum required action(s) that will allow FCV-3227A to return to 25%

open is/are to (2 A. 1) ONLY the lB MDAFW pump

2) place the MDAFWP FCV 3227 RESET B TRAIN handswitch to RESET B. 1) The 1 B MDAFW and the TDAFW pumps

2) place the MDAFWP FCV 3227 RESET B TRAIN handswitch to RESET

0. 1) ONLY lB MDAFW pump

2) first raise ALL SG water levels above the Lo-Lo level setpoint, THEN place the MDAFWP FCV 3227 RESET A TRAIN and B TRAIN handswitches to RESET D. 1) The lB MDAFW and the TDAFW pumps

2) first raise ALL SG water levels above the Lo-Lo level setpoint, THEN place the MDAFWP FCV 3227 RESET A TRAIN and B TRAIN handswitches to RESET ILT-35 SRO NRC Exam 6/28/2012 Page 46 of 100

47. A dead bus transfer will be performed in accordance with SOP-36.3, 600, 480, AND 208/1 20 Volt AC Electrical Distribution System, Appendix 13, iS 600V Load Center Operation, to energize the IS 600V Load Center from its Alternate Supply.

The following conditions exist:

• The Jockey pump is running.

• The Motor Driven Fire pump and both Diesel Driven Fire pumps are FUNCTIONAL and in their normal standby alignment.

During the dead bus transfer the 1 S 600V Load Center will be de-energized for 30 minutes to allow electrical maintenance to be performed on the iS 600V Load Center.

Which one of the following completes the statements below?

The control power to the (1) will be temporarily lost during the performance of Appendix 13 of SOP-36.3.

When the IS 600V Load Center is initially de-energized, the Fire Protection system header pressure will (2)

(1) (2)

A. 1C Diesel Generator decrease, and then increase B. 20 Diesel Generator decrease, and then increase C. IC Diesel Generator not be affected D. 2C Diesel Generator not be affected ILT-35 SRO NRC Exam 6/28/2012 Page 47 of 100

48. Unit 1 is operating at 100% power. The following conditions exist:

• SGBD is on service.

• #1 WMT release is in progress.

• The service water pond level has dropped to 179 feet, 10 inches.

Which one of the following predicts the plant response to the low pond level?

A. SW Dilution Flow on FR-4107, SW DILUTION FLOW, will lower; and RCV-023B, SGBD Dilution Discharge Valve, will automatically close.

B. SW Dilution Flow on FR-4107, SW DILUTION FLOW, will lower; and RCV-018, Liquid Waste Discharge Valve, will automatically close.

C. SW Pressure on Pl-3001A & B, SW TO COW HX HDR PRESS, will lower; and PCV-562 and 563, Dilution Bypass Valves, will fully open.

D. SW Pressure on Pl-3001A & B, SW TO COW HX HDR PRESS, will lower; and MOV-538 and 539, Master Recirculation Isolation Valves, will fully open.

ILT-35 SRO NRC Exam 6/28/2012 Page 48 of 100

49. Both units are operating at 100% power with the following conditions:

• STP-80.6, DG 1-2A 24 HOUR LOAD TEST, is in progress.

• The 1-2A DG is running at full load and is paralleled to the 2F 4160V bus.

• A Loss of Off-Site Power has occurred with a Safety Injection on Unit 1.

• 1-2A DG UNIT SELECTOR SWITCH is in the UNIT I & 2 position.

Which one of the following completes the statements below?

The 1-2A DG (1) automatically shift to isochronous control.

DF-08-2, 1-2A DG OUTPUT BKR, to 2F 4160V bus (2) automatically OPEN.

(1) (2)

A. WILL will NOT B. WILL WILL C. will NOT will NOT D. will NOT WILL ILT-35 SRO NRC Exam 6/28/2012 Page 49 of 100

1

50. Unit 1 is in MODE 1. The following conditions exist:

Only one of the AUX BLDG DC battery chargers is operating in EQUALIZE mode.

The AUX BLDG DC Bus indications on the EPB are as follows:

A TRAIN B TRAIN DC BUS Voltage 130 Volts 137 Volts BATT CHARGER AMPERES 120 Amps 85 Amps Which one of the following completes the statements below describing the operation of the DC electrical system?

Based on the indications above, the B Train Battery Charger is in the (1) mode of operation.

(2) is/are operating WITHIN the voltage and amperage limits of SOP-37.1, 125 Volt D.C. Auxiliary Building Distribution System.

(1) (2)

A. EQUALIZE ONLY A Train B. EQUALIZE BOTH Trains C. FLOAT ONLY A Train D. FLOAT BOTH Trains ILT-35 SRO NRC Exam 6/28/2012 Page 50 of 100

51. A Loss of All AC has occurred on Unit 1.

• LB-18, lB 125V DC BUS BATT BKR, has tripped open.

• An Emergency Start of the 2C DG is required using SOP-38. 1, Emergency Starting of a Diesel Generator.

Which one of the following completes the statements below?

2C DG MUST be started (1)

DJO6-1, UNIT 1 2C DG OUTPUT BKR, (2) capable of being closed from the EPB.

(1) (2)

A. from the DG Local Control Panel IS still B. from the DG Local Control Panel is NOT C. by overriding the Air Start Solenoids IS still D. by overriding the Air Start Solenoids is NOT ILT-35 SRO NRC Exam 6/28/2012 Page 51 of 100

52. A Loss of Off-site Power has occurred.

Which one of the following describes the 1 B PRZR heater operation and the required Diesel Generator capacity margin for energizing pressurizer heaters in accordance with ESP-0. 1, Reactor Trip Response?

A.

• Group I B heaters are available for automatic operation ONLY after manually aligning LC IC to LC 1E.

• A margin of 125 kW per bank is required.

B.

• Group I B heaters are available for automatic operation ONLY after manually aligning LC 1 C to LC 1 E.

• A margin of 300 kW per bank is required.

C. Group I B heaters are available for automatic with no operator action.

• A margin of 125 kW per bank is required.

D.

• Group 1 B heaters are available for automatic with no operator action.

• A margin of 300 kW per bank is required.

LT-35 SRO NRC Exam 6/28/2012 Page 52 of 100

53. Unit 1 is at 100% power. The following conditions exist:

• An Instrument Air line rupture has occurred in the 121 Piping Penetration Room which has resulted in a complete depressurization of the line.

• BKI, PENE RM TO ATMOS A TRN AP HI-LO, is in alarm.

• KD1, IA TO PENE RM PRESS LO, is in alarm.

Which one of the following completes the statement below describing the long term effects of the PRZR level response without any operator action?

Pressurizer level will A. lower until Letdown automatically isolates, then will slowly rise B. rise until the Charging pumps cavitate, then will slowly lower C. lower continuously until a Safety Injection occurs D. rise continuously until a Reactor Trip occurs LT-35 SRO NRC Exam 6/28/2012 Page 53 of 100

54.A Unit I Reactor Trip and Safety Injection has occurred from 100% power following n electrical grid disturbance. The following conditions exist:

ONLY the Immediate Operator Actions of EEP-0.0, Reactor Trip Or Safety Injection, are complete.

Subsequently, a fire is reported in the 600V/208V MCC 1 E.

Which one of the following describes how AOP-29.0, Plant Fire, is required to be implemented with the remainder of EEP-0.0?

AOP-29.0 is required to be implemented (1) the remainder of EEP-0.0.

Per AOP-29.0, Table 1, the implementation of (2) is required.

REFERENCE PROVIDED (1) (2)

A. at the same time as Attachment 12 B. instead of Attachment 12 C. at the same time as Attachment 9 D. instead of Attachment 9 ILT-35 SRO NRC Exam 6/28/2012 Page 54 of 100

55. Which one of the following describes how the automatic closure feature of RCV-1 8, WMT DISCH TO ENVIRONMENT, is required to be tested prior to commencing the release per SOP-50.1, Liquid Waste Processing System Liquid Release from Waste Monitor Tank?

A. The OPERATION SELECTOR is positioned to the CHECK SOURCE position to simulate a HIGH ALARM condition.

B. The OPERATION SELECTOR will be positioned to the LEVEL CAL position, and the RANGE SELECTOR will be positioned to the HV position to simulate a HIGH ALARM condition.

C. The instrument power fuses on the front of the radiation monitor are removed and re-inserted to cause RCV-18 to trip closed.

D. The potentiometer setting is adjusted down to create a HIGH ALARM condition.

ILT-35 SRO NRC Exam 6/28/2012 Page 55 of 100

56. Unit 1 is at 100% power with the following conditions:

A Train is the ON-SERVICE Train.

B Train CCW is running to support charging pump operations.

BOTH fuses on the front of R-17B, CCW SUCTION TRN A, drawer are LIT.

Which one of the following completes the statements below?

RCV-3028, CCW SRG TANK VENT, (1) automatically close.

The required actions are to (2) in accordance with FHI, RMS HI-RAD.

(1) (2)

A. will NOT close RCV-3028 and cycle RCV-3028 and document in the Control Room Log once every eight hours B. will NOT close RCV-3028 and Shift to B Train as the ON-SERVICE Train C. WILL cycle RCV-3028 and document in the Control Room Log once every eight hours D. WILL shift to B Train as the ON-SERVICE Train ILT-35 SRO NRC Exam 6/28/2012 Page 56 of 100

57. Which one of the following identifies the power supply for Unit I MOV-51 5, SW TO TURB BLDG ISO A TRN?

600V AC MCC (1) , which is normally supplied by the (2) Startup Transformer.

(1) (2)

A. iN 1A B. iT lB C. iN lB D. IT 1A ILT-35 SRO NRC Exam 6/28/2012 Page 57 of 100

58. Urt 1 has experienced a rupture in the Instrument Air header. The following sequence of events occurred:

At 10:00:

• The air leak was located and isolated.

• PI-4004B, INST AIR PRESS, had lowered to a minimum of 48 psig and is rising.

At 10:15:

• Instrument Air pressure returns to normal.

Which one of the following completes the statements below with NO additional operator actions?

At 10:15, V903, ESSENTIAL IA HDR AUTO ISO, valve is (1)

The pressure of the Instrument Air system at 10:15 will be (2)

(1) (2)

A. CLOSED 110-125 psig B. CLOSED 90-105 psig C. OPEN 110-l25psig D. OPEN 90-105 psig ILT-35 SRO NRC Exam 6/28/2012 Page 58 of 100

59. Which one of the following states the normal power supply for the 2B Station Service Air Compressor?

A. 600V LC 2A B. 600VLC2G C. 600V LC 2Q D. 600V MOO 2B ILT-35 SRO NRC Exam 6/28/2012 Page 59 of 100

60. Unit 2 has experienced a rupture in the Service Air header.

Which one of the following completes the statements below?

V901, SERVICE AIR HDR AUTO ISO, will automatically close at the setpoint of (1)

In order to open V901, the local RESET push button on the (2) must be depressed after the Service Air header pressure is back above the setpoint.

(1)

(2)

A. 80 psig AIR COMP SQL VALVE LOCAL CONT STATION B. 70 psig AIR COMP SQL VALVE LOCAL CONT STATION C. 8opsig AIR COMP SEQUENCER PANEL D. 70 psig AIR COMP SEQUENCER PANEL ILT-35 SRO NRC Exam 6/28/2012 Page 60 of 100

61. Unit 1 is at 100% power when the following error occurs:

• CTMT Mini-Purge Supply and Exhaust fans are running for a batch release in accordance with SOP-12.2, Containment Purge and Pre-access Filtration System.

• During replacement of a faulty MCB Phase A handswitch, a MANUAL Phase A signal is inadvertently generated.

Which one of the following predicts the plant response and completes the statements below?

CTMT Mini-Purge supply and exhaust fans (1) automatically stop.

The (2) will be isolated.

(1) (2)

A. will NOT Control Room Ventilation System (HV-3649A1B/C, HV-3622, HV-3623)

B. will NOT SGBD Sample isolations from containment (HV-3328, HV-3329, HV-3330)

C. WILL Control Room Ventilation System (HV-3649A/B/C, HV-3622, HV-3623)

D. WILL SGBD Sample isolations from containment (HV-3328, HV-3329, HV-3330)

ILT-35 SRO NRC Exam 6/2812012 Page 61 of 100

62. Which one of the following completes the statements below in accordance with NMP-OS-007-OO1, Conduct of Operations Standards and Expectations?

The Operator At The Controls (1) permitted to utilize the computer to electronically sign off steps in a tagging order.

The SRO assigned the role of Control Room Command Function (2) permitted to assume the Operator At The Controls position if it becomes necessary for the operator currently assigned that position to perform other duties within the Control Room Area.

(1) (2)

A. IS NOT IS NOT B. IS NOT IS C. IS ISNOT D. IS IS ILT-35 SRO NRC Exam 6/28/2012 Page 62 of 100

63. An RO was temporarily re-assigned to work in the Work Control Center from December 16, 2011 until May 10, 2012.

• The RO worked as a Control Room Operator on a normal shift rotation from January 1,2011 until December 15, 2011.

• All required medical certifications and training requirements are maintained.

• The individual has dosimetry.

• Due to other obligations this RO will NOT be available to stand any watches between the following dates:

Dec 16, 2011 through Jan 31, 2012.

MarOl,2ol2through May09, 2012.

Which one of the following completes the statements below in accordance with NMP-TR-406, License Administration?

On FEB 1, 2012, the RDs license (1) active.

In order to cover shift on May 10, the M1NMUM requirement(s) the RO must fulfill within the FIRST QUARTER of 2012 is to be in a required licensed shift position for (2)

(1) (2)

A. IS five (5) shifts of twelve (12) hours B. IS 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and must also include a plant tour documented in the Control Room Log C. is NOT five (5) shifts of twelve (12) hours D. is NOT 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and must also include a plant tour documented in the Control Room Log ILT-35 SRO NRC Exam 6/28/2012 Page 63 of 100

64. Unit 1 is in MODE 1. The following conditions are reported:

• STP-9.O, RCS LEAKAGE TEST, has been completed.

• The RCS leak rate is 2.5 gpm.

• PRT level is rising.

Which one of the following completes the statement below in accordance with TS 3.4.13, RCS Operational LEAKAGE?

The leakage is defined as (1) leakage.

Entry into a REQUIRED ACTION statement of TS 3.4.13 (2) required.

(1) (2)

A. Identified B. Unidentified IS C. Identified is NOT D. Unidentified is NOT ILT-35 SRO NRC Exam 6/28/2012 Page 64 of 100

65. The WEBTOP display for D175009 Sheet I is as follows:

Document No. Sheet No. Title REVISION D175009 001 Sampling System CURRENT, 32.0 D175009 001 Sampling System LATEST, 33.0 Refer to the enclosed D175009 Sheet I to answer the question below.

Which one of the following completes the statements below in accordance with NMP-AP-001, Development and Control of Southern Nuclear Procedures?

The drawing provided to you (D175009 Sheet 1), (1) an approved version to use, based on the WEBTOP display information above.

The T on SV-3332, PRZR LIQ SAMPLE ISO (Location A-5) signifies that the marked valve will automatically close upon receipt of a (2) signal.

REFERENCE PROVIDED (1) (2)

A. is NOT Phase A Containment Isolation B. is NOT Penetration Room High Pressure C. IS Phase A Containment Isolation D. IS Penetration Room High Pressure ILT-35 SRO NRC Exam 6/28/2012 Page 65 of 100

66. An entry into the Rx Vessel Maintenance Sump is required on Unit 1. The following description of the activity/plant conditions exist:

• No work on the Moveable Incore Detector System (MIDS) will be performed.

• The incore tubing remains connected to the seal table.

• ALL of the MIDS thimble tubes ARE INSERTED into their normal position.

• The detectors are currently stored in the shield wall.

Which one of the following completes the statements below in accordance with RCP-O.2, UNIT I Reactor Vessel Maintenance Sump Entry, Appendix B?

The storage location of the MIDS detectors is normally determined from (1)

The MINIMUM requirement for controlling the Main Power Switch on the MIDS Control Panel is a(n) (2)

(1) (2)

A. a local check at the MID drive box in containment Caution Tag B. the Incore Control Panel located in the MCR Caution Tag C. a local check at the MID drive box in containment LHRA padlock D. the lncore Control Panel located in the MCR LHRA padlock LT-35 SRO NRC Exam 6/28/2012 Page 66 of 100

67. Unit 2 is at 30% power with the following conditions:

• R-15A, SJAE EXH, radiation monitor is in alarm.

• AOP-2.0, Steam Generator Tube Leakage, is in progress.

• The leaking SG has NOT yet been identified.

Which one of the following completes the statements below?

R-15A indications (1) trend down when SJAE Filtration is placed on service.

(2) will identify the leaking SG.

(1) (2)

A. will NOT R-60A (BC) MS ATMOS REL B. will NOT R-70A (B, C), SG TUBE LEAK DET C. WILL R-60A (B,C) MS ATMOS REL D. WILL R-70A (B, C), SG TUBE LEAK DET LT-35 SRO NRC Exam 6/28/2012 Page 67 of 100

1

68. Unit 1 is in a refueling outage with the following conditions:

• Fill and vent of the IC Charging pump per Appendix F of SOP-2.1, Chemical And Volume Control System Plant Startup and Operation, is in progress.

• The operator is signed on to the current RWP, has the required dosimetry, and meets the dressout requirements to do this job.

• The operator will be required to uncap V464, LCV-1 I 5D OUTLET LINE VENT, attach a drain hose, and open V464, which is above the Boron Injection Tank.

• The ONLY HP posting is a Radiation Area (yellow and magenta) posting at the entrance to the Charging Pump hallway.

Which one of the following identifies the MINIMUM requirements for this activity?

A. Before the operator connects the drain hose, an initial HP survey of the area near V464 IS required; however, HP is NOT required to be present while the operator is venting the system.

B. Before the operator connects the drain hose, an initial HP survey of the area near V464 IS required; HP IS also required to be present while the operator is venting the system.

C. An initial survey of the area near V464 is NOT required before the operator connects the drain hose; however, HP IS required to be present while the operator is venting the system.

D. An initial HP survey of the area near V464 is NOT required before the operator connects the drain hose; HP is also NOT required to be present while the operator is venting the system.

ILT-35 SRO NRC Exam 6/28/2012 Page 68 of 100

69. A Rx trip has occurred on Unit I The following conditions exist:

• The Immediate Operator Actions of EEP-O.O, Reactor Trip Or Safety Injection, are complete.

• IA SG Main Steam Safety Valve is stuck OPEN.

• IBSGhasaSGTR.

• SG NR levels are as follows: 1A lB IC 13% 12% 14%

Which one of the following completes the statement below in accordance with SOP-O.8, Transient Response Procedure Users Guide?

The Unit Operator is permitted to isolate AFW flow to (I) prior to the step within EEP-O.O to control AFW flow.

Notifying the Shift Supervisor (2) required prior to taking early operator action.

(1) (2)

A. 1ASG,butNOT1BSG, IsNOT B. IA SG, but NOT lB SG, IS C. BOTH 1A&IBSG isNOT D. BOTH1A&IBSG IS ILT-35 SRO NRC Exam 6/28/2012 Page 69 of 100

70. An Alert has been declared. The Emergency Director (ED) has directed the shift communicator to notify offsite agencies using NMP-EP-1 11, Emergency Notifications.

During ROLL CALL, ONLY the following organizations have answered:

Georgia EMA (GEMA) at Atlanta EOC.

Early County.

The ED has just handed the shift communicator the approved and transmitted copy of the Electronic Notification Form.

Which one of the following completes the statements below in accordance with NMP-EP-111?

ROLL CALL (1) required to continue.

The communications system that should be used next to contact those State and County agencies which could not be contacted via the ENN-Southern Linc Radio is the (2) .

(1) (2)

A. IS still Emergency Notification System (ENS) phone set B. IS still Commercial Telephone lines C. is NOT Emergency Notification System (ENS) phone set D. is NOT Commercial Telephone lines ILT-35 SRO NRC Exam 6128/2012 Page 70 of 100

71. Unit I has had a LOCA and the following condition exists:

Containment pressure has risen to 23 psig and is stable.

Which one of the following completes the statements below?

EE5, CTMT ISO PH B, (1) in alarm.

MOV-8112, RCP SEAL WTR RTN ISO, (2) closed.

(1) (2)

A. IS IS B. IS isNOT C. is NOT IS D. is NOT is NOT ILT-35 SRQ NRC Exam 6/28/2012 Page 71 of 100

72. Which one of the following states the FIRST system to be isolated from the RCS in the attempt to isolate an RCS leak outside containment, and which RCS parameter is monitored to confirm that a leak has or has NOT been isolated in accordance with ECP-1 .2, LOCA Outside Containment?

First system isolated RCS parameter A. RHR RCS Pressure B. RHR Przr level C. RCP seal injection RCS Pressure D. RCP seal injection Przr level LT-35 SRO NRC Exam 6/28/2012 Page 72 of 100

I

73. A Reactor Trip has occurred on Unit 1. The following conditions exist:

B Train SSPS is in TEST.

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

FRP-H.1 Attachment 1, Main Feedwater Bypass Valves Automatic Closure Defeat, has been completed.

1A SGFP has been aligned and is feeding the SGs.

Subsequently, an automatic SI occurs.

Which one of the following completes the statement below which describes the effects on the 1A SGFP and support conditions per FRP-H.1?

IASGFP (1) automaticallytrip.

Service Water cooling to the Turbine Building (2) isolate.

(1) (2)

A. WILL will NOT B. WILL WILL C. will NOT will NOT D. will NOT WILL LT-35 SRO NRC Exam 6/28/2012 Page 73 of 100

74. Unit 1 has tripped following a Loss of All AC Power. The following conditions exist:

• ECP-O.O, Loss of All AC Power, was entered.

• 1-2A DG was started and aligned to the emergency buses before the steps to defeat auto start of safeguards equipment and isolate RCP seals were entered.

• CCW and charging flow to the RCP seals was lost for 25 minutes.

• A Safety Injection has NOT previously been actuated or initiated.

• ESP-O.2, Natural Circulation Cooldown To Prevent Reactor Vessel Head Steam Voiding, is currently in progress.

• RCP support conditions have been established.

• A RCP seal status evaluation has NOT been performed.

Which one of the following completes the statements below per ESP-O.2?

A RCP (1) be IMMEDIATELY started.

IF an SI actuation were to subsequently occur while in ESP-O.2, EEP-O.O, Reactor Trip or Safety Injection, (2) required to be re-entered.

(1) (2)

A. CAN is NOT B. CAN IS C. can NOT is NOT D. can NOT IS ILT-35 SRO NRC Exam 6/28/2012 Page 74 of 100

75. The following conditions exist for Unit 1:

• FRP-H.2, Response to Steam Generator Overpressure, is in progress.

• Containment pressure is 4.5 psig and slowly decreasing.

• RCS temperature is 585°F.

1A lB 1C

• SG Pressure 1200 psi 9 1190 psi 9 1250 psi 9

• SG NR Levels 25% 30% 98%

Which one of the following completes the statement below per FRP-H.2?

Releasing steam A. is NOT permitted from only 1C SG because water may be in its steam line.

B. is NOT permitted from ANY SG because the main steam piping is interconnected and water may be in the steam lines.

C. will FIRST be attempted using IC Atmospheric Relief Valve because 1C SG has the highest pressure.

D. will FIRST be attempted using the TDAFW Pump in order to draw steam from multiple SGs.

ILT-35 SRO NRC Exam 6/28/2012 Page 75 of 100

76. Unit 1 is at 100% power with the following conditions:

• Core conditions are MOL, 12,000 MWD/MTU.

• Control Bank D group step counters indicate 225 steps.

• Control Bank D, rod P8 drops to 145 steps.

• It will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to re-align rod P-8 with the Control Bank D rods.

Which one of the following statements describes the BASES for reducing THERMAL POWER to less than or equal to 75% in accordance with Tech Spec 3.1.4, Condition B, One rod not within alignment limits, REQUIRED ACTION B.2.2?

A. Removes the requirement to determine QPTR.

B. Minimizes the effect of a Control Rod ejection accident.

C. Eliminates the requirement to re-evaluate specific accident analysis.

D. Ensures local Linear Heat Rate increases will not exceed core design criteria.

ILT-35 SRO NRC Exam 6/28/2012 Page 76 of 100

77. The following conditions exist on Unit 1:

At 10:00:

• lB RHR pump is in service for the RCS cooldown.

• TR6O4B, lB RHR PUMP DISCH TEMP, is indicating 250°F for lB RHR HX INLET temperature.

At 10:05:

• 1 B RHR pump trips due to overcurrent.

At 10:15:

• 1A RHR pump is started and core cooling is restored.

Which one of the following completes the statements below?

(1) INOPERABLE per Tech Spec 3.5.3, ECCS Shutdown.

A(n) (2) notification to the NRC Operations Center (NRCOC) is required per EIP-8.0, Non-Emergency Notifications.

REFERENCE PROVIDED (1) (2)

A. Only lB RHR pump is 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> B. Only lB RHR pump is 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C. Both 1A lB RHR pumps are 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> D. Both 1A lB RHR pumps are 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> TLT-35 SRO NRC Exam 6/28/2012 Page 77 of 100

78. A LOCA occurred on Unit I and the crew established cold leg recirculation per ESP-I .3, Transfer to Cold Leg Recirculation.

Subsequently, an LOSP occurred and the B Train Emergency busses - IG, 1J, and IL 4160V busses, remain de-energized.

After several hours, the Control Room team is performing ESP-1 .4, Transfer to Simultaneous Cold and Hot Leg Recirculation.

Which one of the following completes the statements below?

Simultaneous cold and hot leg recirculation (1) be established lAW ESP-1.4.

At the step to Check simultaneous cold and hot leg recirculation in progress, the Control Room team is required to (2)

(1) (2)

A. CAN return to EEP-I .0 B. can NOT return to EEP-I .0 C. CAN remain in ESP-I.4 D. can NOT remain in ESP-1.4 ILT35 SRO NRC Exam 6/28/2012 Page 78 of 100

79. Unit 118 in Mode 3, preparing for Reactor startup in accordance with UOP-1 .2, Startup of Unit From Hot Standby to Minimum Load. The following conditions exist:

At 10:00:

• Both Trains of COW were in operation.

• B Train of COW was the ON-SERVICE Train.

• During a review of STP-23.3, IC Component Cooling Water Pump Quarterly inservice Test, it was discovered that the IC COW pump failed the STP due to high vibrations being in the REQUIRED ACTION range.

• Repairs to 10 CCW pump were expected to take 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

At 11:00:

• ON-SERVICE Trains were swapped and A Train of COW is the ON-SERVICE Train.

At 11:30:

• DFO4, 10 COW PUMP, breaker was racked out.

At 16:30:

• 10 CCW PUMP was repaired and declared OPERABLE.

Which one of the following identifies the earliest time that Mode 2 was allowed to be entered in accordance with Tech Specs?

Mode 2 entry was allowed to be entered REFERENCE PROVIDED A. at 10:00 B. at 11:00 C. at 11:30 D. at 16:30 LT-35 SRO NRC Exam 6/28/2012 Page 79 of 100

80. Unit 1 was performing a rapid ramp down from 85% to 55% power with the following conditions:

• A malfunction occurred resulting in PCV-444B, PRZR PORV, orening.

• PCV-444B handswitch has been taken to CLOSE, the GREEN light is LIT.

• PRT parameters were rising, but are now stable.

• RCS pressure is slowly rising.

• The following annunciators are being evaluated:

- HCI, PRZR PRESS HI-LO

- HC2, PRZR HI-LO PRESS ALERT Which one of the following completes the statements below?

The setpoint for annunciator HC2, PRZR HI-LO PRESS ALERT, is (1) psig (rate compensated).

PCV-444B (2) OPERABLE per Tech Spec 3.4.11, Pressurizer Power Operated Relief Valves (PORVs).

(1) (2)

A. 1865 IS B. 1865 is NOT C. 1850 IS D. 1850 is NOT ILT-35 SRO NRC Exam 6/28/2012 Page 80 of 100

81. EEP-1 .0, Loss of Reactor or Secondary Coolant, is in progress on Unit 2. The following conditions exist:

• RCS Pressure is 15 psig.

• LHSI flow is 3300 gpm on each Train.

• RCS Cold leg temperatures are 225° F.

• Containment radiation levels are 12 RIhr.

Containment pressure peaked at 28 psig and is now reading 3.5 psig.

• The integrated dose levels inside containment have NOT been verified.

Which one of the following completes the statement below?

The required response to a valid RED PATH condition for the RCS Integrity Status Tree is to Procedure titles:

EEP-1 .0, Loss of Reactor or Secondary Coolant FRP-P.1, Response to Imminent Pressurized Thermal Shock (PTS) Conditions A. immediately enter FRP-Pi; and when directed, the crew will return to the EEP-1.0 step in progress when EEP-1 .0s use was suspended B. immediately enter FRP-P.1; and when directed, the crew will return to EEP-1.0 beginning at step 1, regardless of the step in progress when EEP-1 .0s use was suspended C. remain in EEP-1 .0; Do not transition to FRP-P.1.

Adverse containment criteria CAN be exited at this time if a channel check is completed.

D. remain in EEP-1 .0; Do not transition to FRP-P.1.

Adverse containment criteria CANNOT be exited at this time if a channel check is completed ILT-35 SRO NRC Exam 6/28/2012 Page 81 of 100

82. Unit 1 is stable at 55% power, after a rapid ramp down, with the following conditions:

• Control Bank D is at 115 steps.

• Control Bank D Rod K1O is stuck at 144 steps.

• Control Rods have been placed in Manual.

• STP-29.5, Shutdown Margin Calculation in Modes 1 and 2 (TAVG > 547°F),

shows current Shutdown Margin is 1.67% deltaKlK.

• An Emergency Boration is in progress.

Which one of the following completes the statements below?

FE2, CONT ROD BANK POSITION LO-LO, annunciator (1) in alarm.

Per the BASES of TRM 13.1.1, Shutdown Margin (SDM)- Modes 1 and 2, the most limiting accident for Shutdown Margin requirements is based on a (2)

REFERENCE PROVIDED A. 1)isNOT

2) Steam Line Break accident B. 1)isNOT

2) Control Rod Ejection accident C. 1)IS

2) Steam Line Break accident D. 1)IS

2) Control Rod Ejection accident ILT-35 SRO NRC Exam 6/28/2012 Page 82 of 100

83. Unit I is shutdown with the following conditions:

• The RCS level is 1 foot below the flange.

Reactor Head stud detensioning is in progress.

• 1A RHR pump begins to cavitate and is shutdown.

• Actions to restore RHR are in progress.

Which one of the following completes the statements below?

In accordance with Tech Spec 3.9.5, Residual heat Removal (RHR) and Coolant Circulation -- Low Water Level, Surveillance Requirement (SR) 3.9.5.1, one RHR loop must be in operation and circulating reactor coolant at aflowrateof (1)

The BASES for the SR 3.9.5.1 flow requirement is that this value is the minimum flow to prevent (2 (1) (2)

A. 1750 gpm thermal and boron stratification in the core B. 3000 gpm thermal and boron stratification in the core C. 3000 gpm RHR discharge pressure from exceeding 110% of design during an RCS over pressurization event D. 1750 gpm RHR discharge pressure from exceeding 110% of design during an RCS over pressurization event ILT-35 SRO NRC Exam 6/28/2012 Page 83 of 100

84. Unit I is at 100% power with th8 following conditions:

At 10:00:

• PT-950, CTMT PRESS (Channel 1), was declared INOPERABLE.

• PT-950 was positioned as required by Tech Spec 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, for continuous operation with an inoperable channel.

At 11:00:

• The Surveillance Test for PT-953, CTMT PRESS (Channel 4), is required to performed at this time.

be Which one of the following completes the statements below?

At 10:00, the Tech Spec REQUIRED ACTION was to place the channel in (1)

At 11:00, during the time that the Surveillance Test is being performed on PT-953, a valid automatic Containment Spray actuation (2) occur.

(1) (2)

A. trip CAN still B. bypass CAN still C. trip CANNOT D. bypass CANNOT LT-35 SRO NRC Exam 6/28/2012 Page 84 of 100

85. Unit I is in Mode 3 with the following conditions:

• A Train is the ON-SERVICE Train.

• HV-3096A, CCW TO/FROM EVAP PKGS & H2 RECOMB, is stuck open and will NOT close.

• HV-3096B, COW TO/FROM EVAP PKGS & H2 RECOMB, is functioning properly.

Which one of the following completes the statements below?

HV-3096A & B are required to isolate upon receipt of an (1)

In accordance with Tech Spec 3.7.7, Component Cooling Water (CCW) System, the A Train CCW system is currently (2)

A. 1) SI signal ONLY

2) OPERABLE B. I) SI signal ONLY

2) NOT OPERABLE C. 1) SI signal OR LO LO Surge Tank level

2) OPERABLE D. I) SI signal OR LO LO Surge Tank level

2) NOT OPERABLE ILT-35 SRO NRC Exam 6/28/2012 Page 85 of 100

86. Which one of the following completes the statements below?

In accordance with TRM 13.9.4, Crane Travel- Spent Fuel Storage Building, the MA)(IMUM load allowed to travel over the fuel assemblies in the SFP is (1)

Bases for TRM 13.9.4 states that the restriction on movement of loads in excess of the above weight over other fuel assemblies in the SFP ensures that in the event that a load is dropped (2)

(1) (2)

A. 3000 lbs no activity release will occur B. 3000 lbs distortion of fuel in the storage racks will not result in a critical array C. 3250 lbs no activity release will occur D. 3250 lbs distortion of fuel in the storage racks will not result in a critical array ILT-35 SRO NRC Exam 6/28/2012 Page 86 of 100

87. The following conditions exist on Unit 1:

• ECP-0.0, Loss of All AC Power, is in progress.

• Depressurization of ALL intact Steam Generators has been initiated.

In accordance with ECP-0O, which one of the following completes the statements below?

The Steam Generator depressurization is required to be stopped if (1)

When transitioning from ECP-0.0, a parameter that will be monitored to determine the required recovery procedure is (2)

A. 1) Pressurizer level falls to 12%

2) RCS Pressure B. 1) all intact SG narrow range levels fall to 30%

2) RCS Pressure C. 1) Pressurizer level falls to 12%

2) RCS Subcooling D. 1) all intact SG narrow range levels fall to 30%

2) RCS Subcooling ILT-35 SRO NRC Exam 6128/2012 Page 87 of 100

1 i

88. Unit I is at 100% power with the following conditions:

The 1A Control Room Air Conditioning system (CRACS) is Tagged Out.

At 10:00:

• The Rover reports a fire in the I B CRACS system.

At 10:17:

• The fire is extinguished.

• The lB CRACS system is damaged and cannot be restarted.

Subsequently, control room temperatures reached 105°F before temporary cooling was established.

Which one of the following completes the statements below?

At 10:17, a(n) (1) emergency classification is required in accordance with NMP-EP-110-GLO1, FNP EALs ICs, Threshold Values and Basis.

The FSAR design limit maximum temperature for the Control Room equipment was (2)

REFERENCE PROVIDED (1) (2)

A. ALERT exceeded B. NOUE exceeded C. ALERT NOT exceeded D. NOUE NOT exceeded ILT-35 SRO NRC Exam 6/28/2012 Page 88 of 100

89. Maintenance is preparing to de-energize R-5, SFP RM, for troubleshooting and repair on Unit 1.

At 10:00:

• An electrical lead is lifted that disables the alarm function of R-5, however, the rad monitor indication is reading correctly and is still valid.

At 10:30:

The power supply to R-5 is de-energized and Tagged Out.

Which one of the following completes the statements below?

The first time that R-5 rad monitor was no longer FUNCTIONAL, in accordance with TRM 13.3.4, Radiation Monitoring Instrumentation, was at (1)

De-energizing R-5 (2) cause the Penetration Room Filtration System to automatically start.

(1) (2)

A. 10:00 WILL B. 10:00 will NOT C. 10:30 WILL D. 10:30 will NOT ILT-35 SRO NRC Exam 6/28/2012 Page 89 of 100

90. Unit I is performing a Reactor startup in accordance with UOP-1 .2, Startup of Unit From Hot Standby to Minimum Load. The following conditions exist:

• Reactor power is stable at 6%.

• LT-459, PRZR LVL, has failed HIGH.

Which one of the following completes the statements below?

The REQUIRED ACTIONS of Tech Spec 3.3.1, Reactor Trip System (RTS)

Instrumentation, Function 9, Pressurizer Water Level - High, (1) required to be performed at this time.

The Tech Spec 3.3.1 BASES for the High Pressurizer Water Level reactortripistoprovide (2)

A. (1) ARE (2) a backup to the Pressurizer High Pressure reactor trip B. (1) are NOT (2) a backup to the Pressurizer High Pressure reactor trip C. (1)ARE (2) the primary protection for a Loss of Turbine Load event D. (1)areNOT (2) the primary protection for a Loss of Turbine Load event ILT-35 SRO NRC Exam 6/28/2012 Page 90 of 100

91. Unit I has tripped from 100% power with the following conditions:

• A Site Area Emergency has been declared by the Emergency Director due to a Loss of ALL Offsite Power and Onsite AC Power to Essential Busses.

• The TSC and OSC are fully staffed.

• The TSC has been declared OPERATIONAL.

• A Systems Operator is being dispatched from the OSC to perform actions in the Diesel Building.

• There are no hazards on the route to the Diesel Building and there are no hazards in the Diesel Building.

Which one of the following completes the statements below?

In accordance with EIP-14.0, Personnel Movement, Relocation, Re-entry, and Site Evacuation, the MINIMUM required actions to authorize dispatching the Systems Operator to the Diesel Building are listed in the (1)

On back shifts, weekends, and Holidays during non outage periods, all personnel on site that are not assembling in the OSC, the Control Room, or another Emergency Response Facility will assemble in the (2) in accordance with EIP-10, Evacuation and Personnel Accountability.

(1) (2)

A. Re-entry Guideline Visitors Center Auditorium Figure 3 B. Re-entry Guideline Fire Training Facility Figure 3 C. Relocation Guideline Visitors Center Auditorium Figure 1 D. Relocation Guideline Fire Training Facility Figure 1 ILT-35 SRO NRC Exam 6/28/2012 Page 91 of 100

92. Unit I is in MODE 3 preparing for initial Reactor startup after a core reload lAW UOP-I .2, Startup of Unit from Hot Standby to Minimum Load.

The following conditions exist:

• The current RCS boron sample is 1540 ppm.

• Both Shutdown banks have been withdrawn.

• All RCPs are running and the RCS is at normal operating pressure and temperature.

• FT-I 68, TOTAL MAKEUP FLOW TO CHG/VCT, has FAILED LOW.

The crew is at the step in UOP-1.2 to dilute the RCS to the Hot Shutdown boron concentration.

Which one of the following completes the statements below?

The required method to dilute per SOP-2.3, Chemical and Volume Control System Reactor Makeup Control System, is to (1)

In accordance with NMP-AD-006, Infrequently Performed Tests and Evolutions, a Reactor startup per UOP-l .2 (2) classified as an Infrequently Performed Test or Evolution (IPTE).

A. I) Perform a Manual Makeup to the charging pump suction.

Verify the dilution AUTOMATICALLY stops when batch integrator setpoint is reached.

2) is NOT B. 1) Perform a Manual Makeup to the charging pump suction.

Verify the dilution AUTOMATICALLY stops when batch integrator setpoint is reached.

2) IS C. 1) Verify a RMW pump running Open FCVII4B, RMW to Blender Open FCVII3B, MKUP TO CHG PUMP SUCTION Manually secure dilution when complete

2) is NOT D. 1) Verify a RMW pump running Open FCVI 14B, RMW to Blender Open FCV113B, MKUP TO CHG PUMP SUCTION Manually secure dilution when complete

2) IS ILT-35 SRQ NRC Exam 6/28/2012 Page 92 of 100

93. During a system Tagout, a Motor-Operated Valve (MOV) was manually closed (locally at the valve) and its breaker was turned OFF. (Both the handwheel and the breaker were included on the Tagout.)

The MOV is a normally closed valve, whose function is to automatically open on a Safety Injection signal.

The maintenance was completed and the Tagout was subsequently cleared.

The following conditions currently exist:

• The MDV is closed.

• No work was performed on the MOV.

• The MDV power supply breaker is closed and the GREEN valve position light is illuminated.

Which one of the following identifies the status of the MOV and the post maintenance testing requirements in accordance with SOP-O.O, General Instructions to Operations Personnel?

A. The MOV is NOT OPERABLE. The MDV must be electrically stroked one full cycle.

B. The MDV is OPERABLE. Remote observation of valve stroking is allowed.

C. The MOV is OPERABLE. Local observation of valve stroking is required.

D. The MOV is NOT OPERABLE. A system flow test is required.

ILT-35 SRO NRC Exam 6/28)2012 Page 93 of 100

94. Unit I is at 100% power with the following conditions:

At 10:00:

• R-14, PLANT VENT, radiation monitor is INOPERABLE.

• #4 Waste Gas Decay Tank (WGDT) release is in progress.

• #8 WGDT has high activity and is at 60 psig.

At 10:15:

• #8 WGDT relief valve fails open.

• The crew closes RCV-14, GDT DISCH TO PLANT VENT.

Which one of the following completes the statements below?

For release of #4 WGDT with R-14 INOPERABLE, the minimum action(s) required in accordance with the ODCM is/are (1)

After RCV-14 is closed, the #8 WGDT relief valves discharge flow path (2) isolated.

REFERENCE PROVIDED A. 1) ACTION 37 and ACTION 35 2)15 B. 1) ACTION 37 and ACTION 35

2) is NOT C. 1)ACTION35ONLY

2) IS D. I)ACTION 35 ONLY

2) is NOT ILT-35 SRO NRC Exam 6/28/2012 Page 94 of 100

95. Which one of the following completes the statements below in accordance with EIP-14, Personnel Movement, Relocation, Re-entry, and Site Evacuation?

The emergency exposure limit for a life-saving activity during a declared emergencyis (1) REMTEDE.

Emergency exposure limits shall only be authorized by the (2)

(1) (2)

A. 10 HP Supervisor B. 25 HP Supervisor C. 25 Emergency Director (ED)

D. 10 EmergencyDirector(ED)

ILT-35 SRO NRC Exam 6/28/2012 Page 95 of 100

96. FRP-H.1, Response to Loss of Secondary Heat Sink, is in progress on Unit I with the following conditions:

• The operators are initiating RCS Bleed and Feed.

• PCV-444B, PRZR PORV, and its associated Block Valve are OPEN.

• PCV-445A, PRZR PORV, will NOT open.

• Restoration of SG feed capability is imminent.

Which one of the following completes the statements below?

In accordance with the BASES of FRP-H.1, opening one PORV (1) provide sufficient RCS bleed flow for adequate RCS heat removal.

After SG feed flow is restored (2)

(1) (2)

A. WILL immediately go to EEP-1, Loss of Reactor or Secondary Coolant B. may NOT immediately go to EEP-1, Loss of Reactor or Secondary Coolant C. WILL remain in FRP-H.I until at least one SG narrow range level is >31%

D. may NOT remain in FRP-H.1 until at least one SG narrow range level is>31%

ILT-35 SRO NRC Exam 6/28/2012 Page 96 of 100

97. Unit I is at 100% power with the following conditions:

At 10:00:

• A problem in the Cable Spreading Room has caused an unplanned loss of ALL Main Control Board Annunciators.

• AOP-35.0, Loss of Main Control Board Annunciators, is in progress.

At 10:16:

• IBSGFPtrips.

• The crew takes actions to stabilize the plant and a Reactor Trip does NOT occur.

Which one of the following completes the statements below?

At 10:16, a(n) (1) emergency classification is required in accordance with NMP-EP-110-GLO1, FNP EALs - ICs, Threshold Values and Basis.

Upon a loss of annunciator MH1, FIRE, AOP-35.0 requires establishing (2) within one hour.

REFERENCE PROVIDED (1) (2)

A. NOUE hourly fire watches in all affected zones B. NOUE a Pyrotronics panel firewatch C. ALERT hourly fire watches in all affected zones D. ALERT a Pyrotronics panel firewatch TLT-35 SRO NRC Exam 6128/2012 Page 97 of 100

98. The following conditions exist on Unit 1:

At 10:00:

• ECP-2.1, Uncontrofled Depressurization of All Steam Generators, is in progress.

• VOIOA, IA Main Steamline Safety valve, is open and will NOT close.

• PCV-3371B, lB MS ATMOS REL VLV, is open and will NOT close.

a HV-3369C and HV-33700, 10 SG MSIVs, are both open and will NOT close.

a All SG narrow range levels are 15% and lowering.

At 10:15:

a All RCS hot leg temperatures are slowly falling.

• All SG narrow range levels are 5%.

a The STA reports that the RCS cooldown for the previous hour is 85° F.

• ECP-2.1, step 5 Control AFW flow to minimize RCS Cooldown has just been completed.

At 10:16:

• HV-3369C is closed and 1C SG pressure is rising.

Which one of the following completes the statement below?

At 10:16 the Control Room crew is required to A. remain in ECP-2.1, Uncontrolled Depressurization of All Steam Generators, and verify total AFW flow> 395 gpm B. transition to EEP-2.O, Faulted Steam Generator Isolation, and verify total AFW flow> 395 gpm C. remain in ECP-2.1, Uncontrolled Depressurization of All Steam Generators, and verify AFW flow of 20 gpm per SG D. transition to EP-2.0, Faulted Steam Generator Isolation, and verify AFW flow of 20 gpm per SG LT-35 SRO NRC Exam 6/28/2012 Page 98 of 100

99. Unit I is performing a natural circulation cooldown in accordance with ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding. The following conditions exist:

• RCS cold leg temperatures are 525°F.

• RCS pressure is 1900 psig.

• IA and lB CRDM fans are running.

• RCPs 1A, 1B, and 1C are tripped and can NOT be restarted.

• CST level is 10.0 ft.

• AFW flow is 350 gpm

• RCS cooldown rate is 5°F/hr.

• PZR level is stable at 25%.

• All RVLIS lights are dark (not illuminated).

Which one of the following is the required response lAW ESP-0.2 and the MAXIMUM permitted cooldown rate to lower TCOLD to 500° F?

Procedure titles:

ESP-0.2, Natural Circulation Cooldown to Prevent Reactor Vessel Head Steam Voiding ESP-0.4, Natural Circulation Cooldown With Allowance For Reactor Vessel Head Steam Voiding (Without RVLIS)

REFERENCE PROVIDED A.

• Continue with ESP-0.2.

• The maximum cooldown rate is < 50°F/hr.

B.

• Continue with ESP-0.2.

• The maximum cooldown rate is < 100°F in any 60 minute period.

C.

• Transition to ESP-0.4.

• The maximum cooldown rate is < 50°F/hr.

D.

• Transition to ESP-0.4.

• The maximum cooldown rate is < 100°F in any 60 minute period.

ILT-35 SRO NRC Exam 6/28/2012 Page 99 of 100

100. Unit I was operating at 100% power with the IA RHR pump Tagged Out.

Subsequently, a Large Break LOCA occurred and Cold Leg Recirculation was established. The foHowing sequence of events occurred:

At 10:00:

• ECP-1 .3, Loss of Emergency Coolant Recirculation Caused by Sump Blockage, was entered.

At 10:30:

• ALL CETCs were 705°F and rising.

• RCS subcooling was negative (-) 328°F.

At 10:45:

• 1A RHR pump Tag Out has been cleared.

1A RHR pump has been started with stable amps and flow.

• ALL CETCs are 695° F and trending down.

Which one of the following completes the statements below?

At 10:30, FRP-C.2, Response to Degraded Core Cooling, (1) required to be performed.

AtlO:45,thecrewwill (2)

(1) (2)

A. IS remain in ECP-1.3 B. is NOT remain in ECP-1 .3 C. IS transition to LEP-1 .0, Loss of Reactor or Secondary Coolant D. is NOT transition to EEP-1 .0, Loss of Reactor or Secondary Coolant ILT-35 SRO NRC Exam 6/28/2012 Page 100 of 100

SRO References DOCUMENT ID PAGES FNP-0-AOP-29.0, v41 .0 Table 1 PARTIAL- Pg 1 of 4 &

pg3of4 2Pages FNP-1-EEP-3.0, v27 PARTIAL- Pg 39 of 54 I Page D-175009 Sheet 1 of (c 1 Page NOTE: LARGER drawing available upon request from Proctor (tablet 11X17)

FNP-1-ESP-0.2, v19 Attachment 3 PARTIAL 1 Page COLR UNIT 1 Cycle 24 Figure 1, Aug 2010 PARTIAL - Pg 9 of 12 1 Page TS 3.7.7 v186 PARTIAL I Page FNP-ODCM PARTIAL Pg 3-1 to 3-5 5 Pages FNP-0-EIP-8.0, v108 COMPLETE 35 Pages NMP-EP-1 I 0-GLOI, Figure 2 PARTIAL I Page NOTE: LARGER reference available upon request from Proctor (tablet 11X17)

FNP-O-AOP-29.O PLANT FIRE Revision 41 TABLE 1 ACTIONS REQUIRED TO MAINTAIN AT LEAST ONE TRAIN OF SAFE SHUTDOWN CAUTION: Cables/components can fail in the event of a fire causing a loss of reactor coolant inventory. The rooms containing these cables/components are designated with an asterisk (*)*

NOTE:

• This table lists various rooms/locations that contain redundant safe shutdown equipment or could potentially result in loss of reactor coolant inventory. Appendix R safe shutdown analysis documents the basis of safe shutdown for each fire area.

• For each location listed, an appropriate attachment is cross-referenced.

1 For a fire in an area listed in Table 1. implement the actions required by the associated attachment.

NOTE: A fire that is outside an area listed in Table 1 will not affect both trains of a safe shutdown function.

2 IF a fire IS NOT in an area listed in Table 1, THEN use other plant procedures for any actions that may be required.

-END-Page 1 of 4

FNP-0-AOP-29.O PLANT FIRE Revision 41 Table 1 Unit 1 Fire Areas Fire Area Location Attachment 1-001 UNIT 1 AUXILIARY BUILDING RAD SIDE 121 AND 100 4 PENETRATION ROOMS, 83 ELEVATION AND 77 ELEVATION 1-004 Zone 1 UNIT 1 AUXILIARY BUILDING 100 RAD SIDE EXCEPT 5 PENETRATION ROOM AND CHARGING PUMP AREA 1-004 Zone 2 UNIT 1 AUXILIARY BUILDING 121 AND 127 RAD SIDE 6 EXCEPT THE 121 PENETRATION ROOM 1-004 Zone 3 UNIT 1 AUXILIARY BUILDING 139 RAD SIDE EXCEPT PRF 6 1-004 Zone 4 ROOM AND THE ELECTRICAL PENETRATION ROOMS UNIT 1 AUXILIARY BUILDING 155 ELEVATION AND SFP 7 4

HVAC ROOM 1-005 CHARGING PUMP ROOMS AND HALLWAY AND STORAGE ROOMS 8 1-006 UNIT 1 NON RAD AUXILIARY BUILDING 100 ELEVATION 9 1-006 UNIT 1 MAIN STEAM AND FEEDWATER VALVE ROOM 10 1-008 UNIT 1 TRAIN A VERTICAL CABLE CHASE 11

• 1OO9 UNIT 1 TRAIN B VERTICAL CABLE CHASE 12 1-012 UNIT 1 HOT SHUTDOWN PANEL ROOM 13 1-013 UNIT I AUX BLDG VERTICAL CABLE CHASE RN 227, 300. 14 465, 466AND 500 1-014 UNIT 1 COMPUTER ROOM 20 1-015 UNIT 1 COMMUNICATIONS ROOM 20 1-016 UNIT 1 B TRAIN AUX BLDG BATTERY ROOM 16 1-017 UNIT 1 A TRAIN AUX BLDG BATTERY ROOM 15 1-018 UNIT 1 TRAIN A DC SWITCHGEAR ROOM AUX BUILDING 15 1-019 UNIT 1 TRAIN B DC SWGR ROOM 14 1-020 UNIT 1 NON-RAIJ HALLWAY 121 FT. EL. 14 1-021 UNIT 1 AUX BLDG SWGR ROOM B TRN 12 1-023 UNIT 1 AUX BLDG CRDM SWGR RN 12 1-030 UNIT I AUX BLDG B TRAIN CABLE CHASE 12 1-031 UNIT I AUX BLDG A CABLE TUNNEL 11

• ]O34 B TRAIN ELECTRICAL PENE ROOM AND PENETRATION ROOM 16 FILTRATION ROOM

• 1035 A TRAIN ELECTRICAL PENE ROOM 17 1-041 UNIT 1 139 4160V SWGR AND CRDM MG SET ROOM 11 (RM 335,343 AND 346) 1-042 UNIT I 139 HALLWAY (RN 319, 339. AND 345) 15 1-075 UNIT I AUX BLDG TO DIESEL BLDG A TRN CABLE TUNNEL 11 1-076 UNIT I AUX BLDG TO DIESEL BLDG B TRN CABLE TUNNEL 18 1-081 UNIT 1 TURBINE BUILDING BATTERY ROOM 38 1-094 COMBUSTIBLE STORAGE ROOM 167 39 1-SQl UNIT I NON RAD STAIRWELL 21 1-S1O UNIT I RAD STAIRWELL EASTSIDE TO 130 EL 37 1-SVB2 SERVICE WATER VALVE BOX 2 19 1-SVB4 SERVICE WATER VALVE BOX 4 19 1-TB UNIT 1 TURBINE BUILDING 20 Page 3 of 4

FNP1EEP3 STEAM GENERATOR TUBE RUPTURE Revision 27 Step Action/Expected Response Response NOT Obtained I I I CAUTION: To prevent release of radioactivity to the environment, RCS and ruptured SC(s) pressures must be maintained less than the ruptured SG(s) atmospheric relief valve setpoint (1035 psig) 31 [CAl Control RCS parameters to minimize RCS to secondary leakage.

31.1 Perform appropriate action(s) from table.

RUPTURED SG(s) LEVEL Rising Falling Offscale high

. Raise

• Raise

• Raise charging flow, charging flow, charging flow.

Less than 25%(50%}

• Reduce

• Maintain RCS RCS pressure. and ruptured SC(s) pressures equal.

P R Between

• Reduce

• Turn on

• Maintain RCS Z 25%{50%} RCS pressure. PRZR and ruptured R and 60%{60%} heaters. SC(s) pressures equal.

L E

• Reduce

• Turn on

• Maintain RCS V Between RCS pressure. PRZR and ruptured E 60%(60%} and heaters. SG(s) pressures L 73%(66%}

• Reduce equal.

charging flow.

Greater than

• Reduce

• Turn on

• Maintain RCS 73%{66%} charging flow. PRZR and ruptured heaters. SG(s) pressures equal.

Step 31 continued on next page.

Page 39 of 54

1LT35 NRC EXAM STUDENT REFERENCE **FOR TRAINING USE ONLY** ILT35 NRC EXAM STUDENT REFERENCE.

2 11 I 12 I 13 US 60051VU A A B S 4

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P 4 5 F 7 B I 9 I 10 I 11 I 17 1LT35 NRC EXAM STUDENT REFERENCE TRAINING USE ONLY** 1LT35 NRC EXAM STUDENT REFERENCE.

1/6/2012 13:45 NATURAL CIRCULATION COOLDOWN TO PREVENT REACTOR FNP-1-ESP-O.2 Revision 19 VESSEL HEAD STEAM VOIDING ATTACHMENT 3 CALCULATION FOR ADEQUATE AVAILABLE CST INVENTORY RCS Cooldown Rate vs Minimum Required CST Level 40 10°F/hr

/A

/*

25 /

-J I

(I)

/

0 / 25°F/hr 15 ii,

/ . 50°F/hr 75°F/hr I 00°F/hr 5 4 3ft) 375 4D 425 45) 475 fLD 525 EfO RCS Tøi 0

NOTE: These pots are based on an AFW flowrate of 350 gpm. An accurate assessment of required CST inventory can be made using the following calculation and mat result used to make a de4ermination if a transition to ESP-0,3 or 0.4 is required.

[(s Io 3.0i 1X AFW Ilowrate x6O-- (25001 + &3 = Requred CST

[k Cooldewn Rate ) J Basis:

• Current Cooldown Rate Is in Degrees F per hour.

• Current AFW flowrate is in Gallons per minute.

• 350F = Temperature required to place RH on-service.

• 12500 = Gallons per foot of CST level.

• 60 = Minutes per hour.

• 5.3 = Minimum CST level In feet before having to shut AFW suction to SW.

CORE OPERATING LIMITS REPORT, FNP UNIT 1 CYCLE 24 AUGUST 2010 Figure 1 Rod Bank Insertion Limits versus Rated Thermal Power Fully Withdrawn 225 to 231 steps, inclusive 225 200 175 Ca 150 I

0

0. 125 a)

U)

C 0

0 100 0

C Ca 75 0

50 25 0

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of RATED THERMAL POWER Fully Withdrawn shall be the condition where control rods are at a position within the interval 225 and 231 steps withdrawn.

Note: The Rod Bank Insertion Limits are based on the control bank withdrawal sequence A, B, C, D and a control bank tip-to-tip distance of 128 steps.

Page9ofl2

CCW System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CCW) System LCO 3.7.7 Two CCW trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CCW train A.1 NOTE inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.6, RCS LoopsMODE 4, for residual heat removal loops made inoperable by CCW.

Restore CCW train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not ANfl met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Farley Units 1 and 2 3.7.7-1 Amendment No. 146 (Unit 1)

AmendmentNo. 137 (Unit2)

FNP-ODCM CHAPTER 3 GASEOUS EFFLUENTS 3.1 LIMITS OF OPERATION The following Limits of Operation implement requirements established by Technical Specifications Section 5.0. Terms printed in all capital letters are defined in Chapter 10.

3.1.1 Gaseous Effluent MonitorinQ Instrumentation Control In accordance with Technical Specification 5.5.4.a, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 3-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Section 3.1 .2.a are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with Section 3.3.

3.1.1.1 Applicability These limits apply as shown in Table 3-1.

3.1.1.2 Actions With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, declare the channel inoperable, or restore the setpointto a value that will ensure that the limits of Section 3.1 .2.a are met.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3-1. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report pursuant to Section 7.2 why this inoperability was not corrected in a timely manner.

This control does not affect shutdown requirements or MODE changes.

3.1.1.3 Surveillance Requirements Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIONAL TEST (COT) operations at the frequencies shown in Table 3-2.

3-1 Version 24 01/10

FN P-ODCM 3.1.1.4 Basis The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Section 3.3 to ensure that the alarm/trip will occur prior to exceeding the limits of Section 3.1 .2.a. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3-2 Version 24 01/10

FNP-ODCM Table 3-1 Radioactive Gaseous Effluent Monitoring Instrumentation OPERABILITY Reguirements Minimum Channels Instrument OPERABLE Applicability ACTION Steam Jet Air Ejector Noble Gas Activity Monitor (RE-15) I MODES 1,2,3,4 37

2. Plant Vent Stack

a. Noble Gas Activity Monitor (RE-i 4 or RE-22) 37a 1 At all times

b. Iodine Sampler 1 At all times 39 c Particulate Sampler I At all times 39

d. Flowrate Monitor I At all times 36

3. GASEOUS RADWASTE TREATMENT SYSTEM Noble Gas Activity Monitor (RE-14), with Alarm and Automatic Termination of Release 1 At all times 35

a. For continuous releases.

b. All requirements in this table apply to each unit.

3-3 Version 24 01/10

FNP-ODCM Table 3-1 (contd) Notation for Table 3-1 ACTION Statements ACTION 35 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tanks contents are analyzed, and

b. At least two technically qualified members of the Facility Staff independently verify the discharge line valving, and (1) Verify the manual portion of the computer input for the release rate calculations performed on the computer, or (2) Verify the entire release rate calculations if such calculations are performed manually.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flowrate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 37 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 39 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 3-3.

3-4 Version 24 01/10

FNP-ODCM Table 3-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Surveillance Requirementsd CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST MODES° Steam Jet Air Ejector Noble Gas Activity Monitor(RE-15) D M Rb Q a(2) 1,2,3,4

2. Plant Vent Stack

a. Noble Gas Activity Monitor

)

2 Qa(l.

0 M R All RE-14

)

2 Qa(

RE-22 0 M R All

b. Iodine Sampler W NA NA NA All

c. Particulate Sampler W NA NA NA All

d. Flowrate Monitor D NA R Q All

a. In addition to the basic functions of a CHANNEL OPERATIONAL TEST (Section 10.2):

(1) The CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room annunciation occur if any of the following conditions exists:

(a) Instrument indicates measured levels above the alarm/trip setpoint; (b) Loss of control power; or (c) Loss of instrument power.

(2) The CHANNEL OPERATIONAL TEST shall also demonstrate that control room annunciation occurs if any of the following conditions exists:

(a) Instrument indicates a downscale failure; or (b) Instrument controls not set in the OPERATE mode.

b. The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology, or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. For any subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.

c. MODES in which surveillance is required. All means At all times.

All requirements in this table apply to each unit.

3-5 Version 24 01/10

10/10/11 12:16:08 SHARED FNP-0-EIP-8.0 June 15, 2011 Version 108 FARLEY NUCLEAR PLANT EMERGENCY PLAN IMPLEMENTING PROCEDURE F N P-a- El P-8 .0 S

A F

E T

Y NON-EMERGENCY NOTIFICATIONS R

E L

A T

E D

PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY__[ SECTIONS Continuous: NONE

Reference:

ALL Information: NONE Approved:

TODD YOUNGBLOOD Plant Manager Date Issued 06/23/2011

10/10/11 12:16:08 FNP-0-EIP-8.0 LIST OF EFFECTIVE PAGES PROCEDURE CONTAINS NUMBER OF PAGES Table of Contents 2 Body 18 Tablel I Table2 10 Figure 1 2 Page 1 of 1 Version 108

10/10/11 12:16:08 SFII\FEE FNP-0-EIP-8.0 NON-EMERGENCY NOTIFICATIONS TABLE OF CONTENTS Section Title Pacje 1.0 Purpose 1 2.0 References 1 3.0 General 1 4.0 Notification Means 2 5.0 Notifications for EIP-1 1, Handling Of Injured Personnel 3 6.0 Notification for EIP-13, Fire Emergencies 4 7.0 One-Hour Technical Specifications Deviation Reports, 10CFR5O.72(b)(1) 5 8.0 One-Hour Special Nuclear Material Control and Accountability Manual, 5 1 OCFR72.74 9.0 One-Hour Reportable Safeguards Events, 10CFR73, Appendix C 5 10.0 Four-Hour Reports, 10CFR5O.72(b)(2) 6 11.0 Four Hour Radioactive Material Reports, 1 OCFR2O.2201 or 2202 7 12.0 Four Hour Independent Storage of Spent Fuel Reports, 10CFR72.75(b)(1). 8 13.0 Eight-Hour Reports, 10CFR5O.72(b)(3) 8 14.0 Eight Hour Independent Storage of Spent Fuel Reports, 10CFR72.75(c). 9 15.0 Security Quarterly Log 9 16.0 24 HOUR Fitness-For-Duty-Events, 10CFR26.73 11 17.0 24 HOUR Independent Storage of Spent Fuel Reports, 10CFR72.75 (d)(1) 12 18.0 48-Hour Reports, 10CFR5O.9 (b) 12 19.0 Miscellaneous Notifications 13 20.0 Additional Corporate Duty Manager Notification 14 21.0 EPA Notification 15 22.0 Transportation Accidents 15 Page 1 of 2 Version 108

10/10/11 12:16:08 FNP-0-EIP-8.0 NON-EMERGENCY NOTIFICATIONS TABLE OF CONTENTS (Continued)

TABLE 1 REFERENCES TABLE 2 SECURITY REPORTABILITY MATRIX FIGURE 1 FNP EVENT NOTIFICATION FORM Page2of2 Version 108

10/10/11 12:16:08 S FII\FE E FNP-0-EIP-8.0 NON-EMERGENCY NOTIFICATIONS 1.0 Purpose This procedure delineates the 48-hour or less reporting requirements for events that occur at the plant that QQ NOT result in the Declaration of an Emergency classification.

2.0 References See Table 1.

3.0 General 3.1 For Declared Emergencies, reporting requirements are described in FNP EIP-9.0. A fire or personnel injury may require notifications from both procedures.

3.2 Pilor to using this procedure to make a non-emergency report, determine if emergency declaration is required, using FNP-0-EIP-9.0.

3.3 Farley Nuclear Plant is required to notify the NRC Operations Center (NRCOC) via the Emergency Notification System of the non-emergency events specified in paragraphs 7.0, 10.0, and 13.0 that occurred within three years of the date of discovery.

3.4 Notification Responsibility. In the event of certain occurrences at Farley Nuclear Plant, several off-site authorities must be notified. It is the responsibility of plant officials to make the notifications to the appropriate authorities. The plant officials responsible for official notifications are:

• Shift Supervisor

• Shift Manager

• Emergency Director

• FNP Duty Manager 3.5 The FNP Duty Manager will be informed by the Shift Manager of notification required by this procedure. Notification of the Corporate Duty Manager should be done by the FNP Duty Manager. the FNP Duty Manager is NOT able to notify the Corporate Duty Manager, THEN the Shift Manager should make the notification. The FNP Duty Manager will determine the EOF Manager needs to be informed of the notification immediately. IF the EOF Manager is to be notified immediately, the FNP Duty Manager will make the notification or direct the Shift Manager to do so.

Version 108

10/10/11 12:16:08 S Fl/\FE ED FNP-0-EIP-8.0 3.6 Incident Notification Form, Figure 1, will be used for transmitting Non-Emergency and Security Notifications to the NRC Operations Center (NRCOC).

3.7 Communication equipment operating instructions are located in FNP-0-EIP-8.3. Plant personnel who are familiar with the use of the equipment are NOT required to have the procedure with them when using the equipment.

3.8 Emergency phone numbers are located in FNP-0-EIP-8.1.

3.9 The plant notification roster, which contains the home addresses and phone numbers of the plant staff, is located in FNP-0-EIP-8.2.

3.10 The On-Call Memo contains the phone number and beeper number of all members of the plant staff who are caM. This memo is located at the front of the Emergency Phone Directory, FNP-0-EIP-8.1.

3.11 IF the NRCOC is being notified, notify the NRC resident in association with that notification. Notify the NRC resident at other times when it is deemed appropriate by the ED or on shift supervision. The notification of the resident has NO specific time requirement.

4.0 Notification Means 4.1 The NRCOC SHALL be contacted by use of the FTS Emergency Notification System (ENS) for notifications required in one hour, four hours, or eight hours of the occurrence or event.

4.2 Phone numbers for use on the FTS ENS are located on labels on the ENS phones OR can be found in FNP-0-EIP-8.1.

4.3 For ENS failures, ANY other FTS phone located in the TSC and the EOF can be used to contact the NRCOC by dialing the same numbers as listed on the ENS phones. Refer to FNP-0-EIP-8.1 for phone locations.

4.4 For ENS or FTS failures, ANY commercial phone line can be used to contact the NRCOC by accessing an outside line, dialing 1, and then the phone number as listed on the ENS phones.

4.5 Other agencies OR individuals can be contacted by using the commercial phones. The phone numbers are located in FNP-0-EIP-8.1.

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10/10/11 12:16:08 S FI/\FE ED FNP-0-EIP-8.0 5.0 Notifications for EIP-1 1, Handling of Inlured Personnel NOTE: DURING A DECLARED EMERGENCY THE EMERGENCY DIRECTOR WILL DIRECT ALL OF THE EIP-1 1 NOTIFICATIONS. WHEN THERE IS NO DECLARED EMERGENCY THE SHIFT MANAGER SHOULD CONTINUE WITH THE ED NOTIFICATIONS UNTIL THE ED ARRIVES ON SITE OR OTHERWISE RELIEVES THE SHIFT MANAGER OF THE RESPONSIBILITY.

5.1 Ensure all required FNP-0-EIP-1 1.0, Guideline 1, notifications are completed.

5.2 Notify the FNP Duty Manager N Corporate Duty Manager 5.3 Notify the EOF Manager if reguired by the FNP Duty Manager.

5.4 Notify office of Alabama Radiation Control IF a radiation casualty is to be transported to an off-site medical facility.

5.5 Notify the NRC, per step 13.5, if the injury reguires the transport of a radioactively contaminated person to an off-site medical facility. IF the NRCOC is being notified, THEN notify the NRC resident in conlunction with that notification.

5.6 Occupational Safety and Health Administration (OSHA) SHALL be notified within eight hours after learning of a single fatality or in-patient hospitalization of three or more employees as a result of a single work related accident. This requirement applies to any fatality or hospitalization that occurs within 30 days of the work related accident. The OSHA phone number is located in FNP-0-EIP-8.1.

• Report the establishment name, contact name and phone number, number of individuals involved, location, time, and a brief description of the incident.

5.7 Refer to the following steps IF a transportation accident is involved with an injury or fatality:

• Step 10.5

• Step 20.4

• Step 20.7

• Step 22.0 5.8 Refer to the following step IF radiation overexposure has occurred OR is suspected.

• Step 11.2 Version 108

10/10/11 12:16:08 SHARED FNP-0-EIP-8.0 5.9 IF the NRC has NOT been notified of the event for other reasons, THEN refer to Step 13.0 for possible additional notification requirements. (Al 2010203446) 6.0 Notification for EIP-13, Fire Emerciencies NOTE: 1. DURING A DECLARED EMERGENCY, THE EMERGENCY DIRECTOR WILL DIRECT ALL OF THE EIP-13 NOTIFICATIONS. WHEN THERE IS NO DECLARED EMERGENCY THE SHIFT MANAGER SHOULD CONTINUE WITH THE ED NOTIFICATIONS UNTIL THE ED ARRIVES ON SITE OR OTHERWISE RELIEVES THE SHIFT MANAGER OF THIS RESPONSIBILITY.

2. NOTIFICATIONS ARE REQUIRED FOR ALL PLANT FIRES INCLUDING SMALL FIRES AND HYDROGEN VENT STACK FIRES. EXCEPTION:

NOTIFICATIONS ARE NOT REQUIRED FOR INTENTIONALLY SET FIRES AT THE FIRE TRAINING FACILITY.

CAUTION: A PLANT FIRE MAY REQUIRE AN EMERGENCY DECLARATION, DEPENDING ON THE LOCATION OR IMPACT TO PLANT EQUIPMENT OR STRUCTURES.

6.1 The Shift Manager SHALL ensure the following are notified:

6.1.1 Plant Fire Brigade needed.

6.1.2 WHEN requesting support for Dothan Fire Department (DFD) to FNP, THEN provide the responder with the route to take to the site to avoid unnecessary radiological exposure, applicable.

6.1.3 Dothan Fire Department (DFD), IF needed. Call DFD and request that DFD return the call to verify the request for assistance. WHEN the DFD returns the call, THEN verify the need for assistance.

6.1.4 Plant Security, IF the fire involves breaches of plant security or i.E off-site agencies are to be escorted on-site.

6.1.5 The FNP Duty Manacier.

6.1.6 The Plant Fire Marshall, OR in the event the Fire Marshall CANNOT be reached, Engineering Support supervision.

6.1.7 WHEN requesting support from Air Products to FNP, THEN provide the responder with the route to take to the site to avoid unnecessary radiological exrosure, if applicable.

6.1.8 Air Products, IF the emergency involves a liquid hydrogen tank, a liquid oxygen tank, OR associated use systems.

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10/10/11 12:16:08 S [11\FE L FNP-0-EIP-8.0 6.2 The ED I FNP Duty Manager SHALL notify:

6.2.1 Appropriate portions of the Plant Emergency Organization.

6.2.2 Corporate Duty Manager. jf PCB transformers are involved in the fire-related incident, THEN provide Corporate Duty Manager with appropriate Environmental Protection Agency notification information from FNP-0-AP-60.

6.2.3 NRC (notification to be made as required by appropriate emergency classification.) IF the NRCOC is being notified, THEN notify the NRC resident in conjunction with that notification.

NOTE: SEE STEP 8.0 FOR ONE-HOUR SPECIAL NUCLEAR MATERIAL REPORTS. SEE STEP 9.0 FOR ONE-HOUR REPORTABLE SAFEGUARDS EVENTS.

7.0 One-Hour Technical Specifications Deviation Report, 1 OCFR 50.72(b)(1).

H NOT reported as a Declaration of an Emergency class per FNP EIP-9.0, THEN the NRCOC and the Corporate Duty Manager SHALL be notified by the Shift Manager or the FNP Duty Manager within one hour of the occurrence of jjy deviation from the plants Technical Specifications authorized pursuant to 10CFR5O.54(x), (i.e., a deviation from Technical Specifications dictated by emergency conditions. (Figure 1 will be used): 1 OCFR 50.72(b)(1)

• Notify the NRC resident in conjunction with this notification.

8.0 One-Hour Special Nuclear Material Control and Accountability Manual, 1 OCFR72.74

• The Shift Manager or FNP Duty Manager SHALL notify the NRCOC and Corporate Duty Manager within one hour of occurrence of any of the following:

• Notify the NRC resident in coniunction with this notification.

8.1 ANY accidental CRITICALITY, 10CFR72.74.(a).

8.2 ANY loss of licensed special nuclear material as defined in Reference 10 1 OCFR72.74.(a).

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10/10/11 12:16:08 S II/\FE E FNP-0-EIP-8.0 9.0 One-Hour Reportable Safeguards Events, 10CFR73, Appendix G 9.1 The Shift Manager, Security Supervision will determine the security event listed in EIP-8.0, Table 2 (SECURITY REPORTABILITY MATRIX) by of the following methods:

9.1.1 A face to face meeting in the Shift Managers, or Security Captains office, OR 9.1.2 A telephone call with both parties referencing Table 2 (SECURITY REPORTABILITY MATRIX).

9.2 Security Supervision will inform the Shift Manager if the compensatory measures taken were within the time allowed in the Security Plan.

9.3 The Shift Manager will determine if the security event is reportable per NMP-EP-1 lO-GLO1, FNP EALs ICs, THRESHOLD VALUES AND BASIS.

9.4 if the security event is classified as a one hour reportability event in Table 2, THEN the Shift Manager or the FNP Duty Manager will perform the following:

9.4.1 Document the report by completing the applicable portions of Figure 1.

9.4.2 Notify the NRCOC AND the Corporate Manager within one hour of the occurrence of the event.

9.4,3 Notify the NRC resident in conjunction with this notification.

9.4.4 The Principle Licensing Engineer will prepare a follow-up written report per NMP-AD-030 LICENSEE EVENT REPORT (LER).

9.5 Security Supervision will record the event in accordance with the reQuirements of FNP-0-EIP-8.0, NON-EMERGENCY NOTIFICATIONS, Section 15.0, Security Quarterly Log.

10.0 Four-Hour 50.72 Reports 10CFR5O.72(b)(2).

• IF NOT reported as a Declaration of an Emergency class or as a one hour non emergency report, THEN the NRCOC and Corporate Duty Manager SHALL be notified by the Shift Manager or the FNP Duty Manager as soon as practical and in ji cases within four hours of the occurrence of any of the following (Figure 1 will be used):

• Notify the NRC resident in coniunction with this notification.

10.1 The initiation of ANY nuclear plant SHUTDOWN required by Technical Specifications. 10CFR5O.72(b)(2)(i)

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10/10/11 12:16:08 S Fl/\FE i: FNP-0-LIP-8.0 10.2 event that results or should have resulted in Emergency Core Cooling System (ECCS) discharge into the reactor coolant system as a result of a valid signal EXCEPT when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.

1 OCFR5O.72(b)(2)(iv)(A) 10.3 ANY event or condition that results in actuation of the reactor protection system (RPS) WHEN the reactor CRITICAL EXCEPT when the actuation results from and is part of a pre-planned sequence during testing or reactor operation. I OCFR5O.72(b)(2)(iv)(B) 10.4 ANY event or discovery of any incident in which an attempt has been made or is believed to have been made to commit a theft or unlawful diversion of uranium or thorium. 10CFR4O.64(c)(2)

NOTE: 1. PARAGRAPH 10.5 ALSO SATISFIES SECTION 4.1 OF THE FNP ENVIRONMENTAL PROTECTION PLAN.

2. THE CHEMISTRY MANAGER AND/OR CORPORATE ENVIRONMENTAL AFFAIRS SHOULD BE CONSULTED FOR REPORTING APPLICABILITY CONCERNING GROUNDWATER CONTAMINATION INCIDENTS. (Al 2009206007) 10.5 ANY event or situation related to the health and safety of the public or onsite personnel or to protection of the environment, for which a news release is planned Q, notification to other government agencies has been or will be made. [IOCFR5O.72(b)(2)(xi)] and [IOCFR72.75(b)(2)]

Examples:

• An onsite fatality See section 5.0 for possible additional reporting requirements.

• Inadvertent release of radioactively contaminated materials.

• Notification of governmental agencies for issues that will cause heightened public or government concern related to protection of the environment. Minor non-radiological, on-site chemical spills or minor environmental permit deviations DO NOT need to be reported under this criterion. Contact SNC Environmental Services for assistance in determining reportability of environmental issues under IOCFR5O.72(b)(2)(xi) (Al 2010203554).

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10/10/11 12:16:08 S 1I

/

4 \FE E FNP-0-EIP-8.0 11.0 Four Hour Radioactive Material Reports 10CFR2O.2201 or 10CFR2O.2202.

• HZ NOT reported as a Declaration of an Emergency class Q as a one hour non emergency report, the NRCOC and Corporate Duty Manager SHALL be notified by the Shift Manager or the FNP Duty Manager as soon as practical and in ALL cases within four hours of the occurrence of ANY of the following (Figure 1 will be used):

• Notify the NRC resident in coniunction with this notification.

11.1 ANY loss or theft of licensed material in an aggregate quantity equal to or greater than 1000 times the quantity specified in Appendix C of 1 OCFR2O AND under such circumstances that it appears that an exposure could result to persons in unrestricted areas. Immediate notifications made under this paragraph satisfies the requirements of [10CFR2O.2201 (a) (1)].

NOTE: STEPS 11.2 AND 11.3 ARE ACTUALLY 24 HOURS NOTIFICATION REQUIREMENTS. THE FOUR HOURS NOTIFICATION REQUIREMENTS ARE APPROXIMATELY 5 TIMES THESE VALUES. FARLEY NUCLEAR PLANT HAS TAKEN THE POSITION THAT WE WILL MAKE THE FOUR HOURS NOTIFICATION IF EITHER LIMIT IS EXCEEDED.

11.2 ANY event involving licensed material that may have caused or threaten to cause an individual to receive any of the doses listed in the below table.

Immediate notifications made under this paragraph satisfy the requirements of 10CFR2O.2202 (a) (1) and (b) (1). See section 5.0 for possible additional reporting requirements.

TOTAL EYE DOSE SHALLOW DOSE HOT PARTICLES (See Information EFFECTIVE DOSE EQUIVALENT Notice 90-48)

EQUIVALENT IN CONTACT NOT IN CONTACT WITH SKIN WITH SKIN TEDE LDE SKIN OR WHOLE BODY OR EXTREMITIES EXTREMITIES 5 REM 15 REM 50 REM 75 ici-hr I 50 RAD 11 .3 The release of radioactive material, inside or outside of a restricted area, so that, had an individual been present for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the individual could have received an intake in excess of one occupational annual limit on intake, (the provisions of this paragraph DO NOT apply to locations where personnel are NOT normally stationed during routine operations, such as hot-cells or process enclosures). Immediate notifications made under this paragraph satisfy the requirements of paragraphs 1 OCFR2O.2202 (a) (2) and (b) (2).

See section 5.0 for possible additional reporting requirements.

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10/10/11 12:16:08 S I1fFE E FNP-0-EIP-8.0 12.0 Four Hour lndeendent Storage of Spent Fuel Reports 10CFR72.75(b)(1).

• IF NOT reported as a Declaration of an Emergency class or as a one hour non emergency report, THEN the NRCOC and Corporate Duty Manager SHALL be notified by the Shift Manager or the FNP Duty Manager as soon as practical and in ALL cases within four hours of the occurrence of of the following: (Figure 1 will be used):

• Notify the NRC resident in conjunction with this notification.

12.1 An action taken in an emergency that departs from a condition or a Technical Specification contained in a license or certificate of compliance issued under this part, WHEN the action is immediately needed to protect the public health and safety, NQ NO action consistent with license or certificate of compliance conditions or Technical Specifications that can provide adequate or equivalent protection is immediately ararent.

13.0 Eight-Hour Rejorts 10CFR5O.72(b)(3).

• IF not reported as a Declaration of an Emergency class or as a one hour or four hour non emergency report, THEN the NRCOC and Corporate Duty Manager SHALL be notified by the Shift Manager or the FNP Duty Manager as soon as practical and in JJ, cases within eight hours of the occurrence of of the following (Figure 1 will be used):

• Notify the NRC resident in coniunction with this notification.

13.1 ANY event or condition that results in the condition of the nuclear power plant, including its principal safety barriers being seriously degraded.

1 OCFR5O.72(b)(3)(ii)(A) 13.2 ANY event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.

1 OCFR5O.72(b)(3)(ii)(B)

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10/10/11 12:16:08 S [II\RE E 13.3 ANY event or condition that results in valid actuation of any of the systems listed below EXCEPT when the actuation results from and is part of a pre planned sequence during testing or reactor operation. (10CFR5O.72 (b)(3)(iv)(A)

(1) Reactor Protection System (RPS) including reactor trip. Actuation of the RPS when the reactor is critical is reportable under section 10 as a four hour report.

(2) General containment isolation signals affecting containment isolation valves in more than one system OR multiple main steam isolation valves (MS lVs).

(3) Emergency core cooling systems (ECCS) including: high-head and low-head injection systems.

(4) Auxiliary feedwater system.

(5) Containment heat removal and depressurization systems, including containment spray fan cooler systems.

(6) Emergency AC electrical power systems, including emergency diesel generators (EDG5).

13.4 ANY event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: IOCFR5O.72(b)(3)(v)

(1) Shut down the reactor and maintain it in a safe shutdown condition.

(2) Remove residual heat.

(3) Control the release of radioactive material.

(4) Mitigate the consequences of an accident.

• Events covered in this step may include:

1. One or more procedural errors.

2. Equipment failures.

3 Discovery of design, analysis, fabrication, construction, and/or procedural inadequacies.

• However, individual component failures need NOT be reported pursuant to this step IF redundant equipment in the same system was operable available to perform the required safety function.

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10/10/11 12:16:08 S II/\FE E FNP-0-LIP-8.0 13.5 ANY event requiring the transport of a radioactively contaminated person to an off-site medical facility for treatment, 1 OCFR5O.72(b)(3)(xii) and 10CFR72.75(c)(3). See section 5.0 for possible additional reporting requirements.

13.6 ANY event that results in a major loss of emeriency assessment capability, off-site response capability, or offsite communications capability.

1 OCFR5O.72(b)(3)(xiii)

Consider examples such as:

13.6.1 Emergency Response Facilities (one of the following inaccessible OR unusable AND the facility CANNOT be restored within 75 minutes of being reciuired. (10CFR5O.72(b)(3)(xiii).

• TSC

• EOF 13.6.2 Emergency communications facilities and equipment (one of the following inoperable for over one hour), (1 OCFR5O.72(b)(3)(xiii).

• ENS (Refer to FNP-0-EIP-8.3 to report any FTS failure to the NRC to start repairs for the failed system.)

• ENN, loss of ability to communicate with the State of Alabama (Dothan JQ Montgomery)

• ENN, loss of ability to communicate with the State of Georgia (Blakely Atlanta)

• Microwave communications via Met Tower (total loss)

• Land line communications via Ashford Phone Company JQ the Dothan Phone company (total loss)

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10/10/11 12:16:08 S I1I\FE E. FNP-0-EIP-8.0 13.6.3 Public Prompt Notification System 10CFR5U.72(b)(3)(xiii).

• Tone alert radio system inoperable for one hour.

• Siren control panel or repeater at Houston County Courthouse inoperable for one hour.

• Simultaneous loss of Gordon, Ashford, and Columbia sirens for one hour.

• Notification that the tone alert radio system or all three sirens have failed their functional test. IF it is determined that the eight-hour report was NOT necessary, THEN a corrected report is to be made to the NRC.

• Onsite and offsite equipment failures will be reported to Information Resources.

13.6.4 Emergency Assessment Capability, 1 OCFR5O.72(b)(3)(xiii). (Al 2009207243)

• Loss of multiple plant monitors necessary for accident assessment (required to use action statement E or F of Post Accident Monitor Technical Specification 3.3.3 for four or more functions listed in table 3.3.3.1).

• Loss of the SPDS system and other assessment equipment greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• Significant unplanned loss of control room indication, annunciators, or monitors for less than 15 minutes.

• Unplanned loss of all plant vent stack radiation monitors.

14.0 Eight Hour Independent Storage Of Spent Fuel Reports, 10CFR72.75(c).

• IF NOT reported as a Declaration of an Emergency class or as a one hour or four hour non emergency report, THEN the NRCOC and Corporate Duty Manager SHALL be notified by the Shift Manager or the FNP Duty Manager as pp as practical and in JJ, cases within eight hours of the occurrence of ANY of the following (Figure 1 will be used):

• Notify the NRC resident in conjunction with this notification.

14.1 A defect in ANY spent fuel, High Level Waste (HLW), or reactor-related Greater Than Class C (GTCC) waste storage structure, system, or component that is important to safety. 1 OCFR72.75(c)(1).

14.2 A significant reduction in the effectiveness of any spent fuel, HLW, or reactor-related GTCC waste storage confinement system during use.

1 OCFR72.75(c)(2).

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10/10/11 12:16:08 S F1?\FE E FNP-0-EIP-8.0 15.0 Security Quarterly Log. Security Supervision SHALL record certain events in the Reportable Safeguards Event Quarterly Log within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of occurrence.

Security Supervision will periodically have a copy of Safeguards Event Quarterly Log entries transmitted to Document Control for retention.

Events that are to be recorded in the Security Quarterly Log are described in Table 2 (SECURITY REPORTABILITY MATRIX).

16.0 24 HOUR Fitness-For-Duty Events 10CFR26.719. The Shift Manager or the FNP Duty Manager SHALL notify the NRCOC and Corporate Duty Manager within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the occurrence of of the following below. The report SHALL be documented by completion of the applicable portions of Figure 1.

• Fitness-for-duty events SHALL be reported under 10CFR26.719 rather than under 10CFR73.71 (Al 2009203644 and 2010203449).

• Notify the NRC resident in coniunction with this notification.

16.1 The use, sale, distribution, possession, or presence of illegal drugs, or the consumption or presence of alcohol within a protected area.

16.2 Commission of ANY of the following acts by a licensed operator, senior operator or supervisory employee (SNC or contractor).

16.2.1 Sale, use, or possession of a controlled substance.

16.2.2 Result of a determination that the individual has violated the FFD policy (i.e. confirmed positive drug or alcohol test, substitution, subversion, etc. as defined in section 26.5);

16.2.3 Involve the consumption of alcohol within a protected area or while performing the duties that require the individual to be subject to the FFD program 16.3 ANY intentional act that casts doubt on the integrity of the FED Program.

16.4 programmatic failure, degradation, or discovered vulnerability of the FFD Program that may permit undetected drug or alcohol use or abuse by individuals within a protected area, OR by individuals who are assigned to perform duties that require them to be subject to the FED program 16.5 IF a false positive error occurs on a blind performance test sample submitted to an HHS-certified laboratory.

16.6 jf a false negative error occurs on a quality assurance check of validity screening tests Version 108

10/10/11 12:16:08 S [1/\FE E FNP-0-EIP-8.0 17.0 24 HOUR Independent Storage Of Spent Fuel Reports 1 OCFR72.75(d)(1).

• IF NOT reported as a Declaration of an Emergency class or as a one hour, four hour or eight hour non emergency report, of the following events involving spent fuel, High Level Waste (HLW), or reactor-related Greater Than Class C (GTCC) waste event SHALL be reported to the NRCOC and Corporate Duty Manager by the Shift Manager or the FNP Duty Manager as soon as practical JjQ in J.

cases within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the occurrence of the event. (Figure 1 will be used):

• For notifications made under this paragraph, the licensee may delay the notification to the NRC if the end of the 24-hour period occurs outside of the NRCs normal working day (i.e., 7:30 am. to 5:00 p.m. Eastern time), on a weekend, or a Federal holiday. In these cases, the licensee SHALL notify the NRC before 8:00 a.m. Eastern Standard Time on the next working day.

• Notify the NRC resident in coniunction with this notification.

17.1 An event in which important safety equipment is disabled or fails to function as designed when: 10CFR72.75(d) (1).

17.1.1 The equipment is required by regulation, license condition, or certificate of compliance to be available and operable to prevent releases that could exceed regulatory limits, to prevent exposures to radiation or radioactive materials that could exceed regulatory limits, or to mitigate the consequences of an accident; and 1 OCFR72.75(d)(1 )(i).

17.1.2 jjQ redundant equipment was available and operable to perform the required SAFETY FUNCTION. 1 OCFR72.75(d)(1)(ii).

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10/10/11 12:16:08 S [1/\FE E FNP-0-EIP-8.0 18.0 48-Hour Reports 10CFR5O.9 (b), (Significant Event, Condition or Information)

• IF NOT reported under another paragraph of this procedure, the NRCOC and Corporate Duty Manager SHALL be notified by the Shift Manager or the FNP Duty Manager within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> (or within two working days) of an event, condition, or newly discovered information that has a significant implication for public health and safety (Figure 1 will be used). Such an event, condition, or new information is reportable under 10CFR5O.9 (b) if it meets i2 of the following criteria:

• Notify the NRC resident in conjunction with this notification.

18.1 It is NOT reportable under other NRC notification OR updating requirement.

18.2 It has a significant implication for public health and safety QE common defense and security. Significant means that:

18.2.1 It is relevant to the NRC in its regulatory capacity. Information relating solely to economics, labor relations or industrial safety may not be relevant to the NRCs nuclear safety role.

AND 18.2.2 It is material, in that it would have a tendency to influence the NRC on the issue of regulatory compliance.

19.0 Miscellaneous Notifications (Al 2008202381) 19.1 Overdue Nuclear Fuel Transport Vehicle 100FR73.67.

• The Shift Manager SHALL notify the On-Call Reactor Engineer when a nuclear fuel transport vehicle is greater than four hours overdue, based on its scheduled arrival time. The On-Call Reactor Engineer will initiate a trace investigation to determine if the shipment is lost, stolen or diverted.

19.2 Inadvertent Siren/Tone Alert Radio Activation

• The Shift Manager or Emergency Director SHALL notify the Houston County Emergency Management Agency (EMA) upon an inadvertent activation of the tone alert radio system, OR an inadvertent activation of the Ashford, Columbia, or Gordon alert siren. Refer to step 20.6 and FNP-0-EIP-2.O for additional reguirements.

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10/10/11 12:16:08 S IIl4L\FE E FNP-0-E(P-8.0 20.0 Additional Corporate Duty Manager Notifications

• To ensure that the appropriate company upper management positions receive timely reports concerning unusual significant events, the guidelines listed below SHALL be used.

• The Plant Manager or his alternate, who is designated at the time as the FNP Duty Manager SHALL verbally report the following events to the Corporate Duty Manager: IF the FNP Duty Manager is NOT able to notify the corporate Duty Manager, THEN the Shift Manager should make the notification.

20.1 ANY initiation of an event requiring NRC reporting per 100FR5O.72 including Declared Emergencies AND including sections 7, 8, 9, 10, 11, 12 and 16 of this procedure 20.2 The Limiting conditions of operations(LCOs) as contained in the Technical Specifications that could require unit shutdowns within the next twelve hours.

OR

• Involuntary entry into a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or less LCO.

20.3 Unscheduled shutdowns, reactor trips or power reductions to below 50%

OR

• Unplanned power reductions> 10%

OR

• Unplanned Unit de-rating OR

• FNP Unit required to change its unit generation schedule 20.4 Serious personnel iniurv or fatality. See Section 5.0 for possible additional reporting requirements.

20.5 Events that are likely to result in unusual interest by outside agencies, the public or the news media..

20.6 False siren or Tone Alert Radio activation.

20.7 Transportation incidents 49CFR171.15 involving radioactive materials or new fuel in which: (See Section 5.0 for possible additional reporting requirements.)

20.7.1 A person is killed.

20.7.2 A person receives injuries requiring medical treatment.

20.7.3 Measurable property damage occurs to the carrier Q to some other entity.

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10/10/11 12:16:08 S F1/\FE E FNP-0-EIP-8.0 20.7.4 Fire, breakage, spillage, OR suspected radioactive contamination occurs.

20.7.5 A continuinc danger to life exists at the scene of the incident.

20.7.6 The Emergency Director determines that it is in SNC or APCos best interest that off-site agencies be notified.

20.7.7 If unable to contact the Corporate Duty Manager within four hours, the Emergency Director SHALL notify the Department of Transportation (DOT) AND American-Nuclear Insurers (ANI).

20.8 The decision has been made to activate the Corporate ERO for reasons other than emergency classification of ALERT OR above 20.9 Other events which are considered at the time of their occurrence to be of possible concern to upper management including but not limited to (Al 2008204673):

• Events reguirinç entry into the EOPs or AOPs

• Unplanned releases to the environment of radioactive, potentially radioactive, OR other hazardous effluents

• Excursions in chemistry parameters which affect primary or secondary operation

• Structural damage to company property

• Work disruptions or stoppages

• Potential need to implement the SNC Business Continuity Plan 20.10 Other conditions which are likely to result in unusual interest by outside agencies Q the media including but not limited to:

• False siren or Tone Alert Radio (TAR) activation

• Radiological material OR new fuel transportation accident 20.11 Equipment failures that affect ability to implement Emergency Plan 21 .0 EPA Notifications

• The Shift Manager should notify the FNP Duty Manager the FNP Duty Manager should notify the Corporate Duty Manager if any reporting is required per FNP-0-AP-60 21 .1 Reporting of natural oil spills, synthetic oil spills and polychlorinated biphenyl (PC B) spills is addressed in FNP-0-AP-60.

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10/10/11 12:16:08 SHARED FNP-0-EIP-8.0 21 .2 Reporting of releases, fires or explosions which involve hazardous wastes is addressed in FNP-0-AP-60.

21.3 Reporting of releases of hazardous substances or extremely hazardous substances (including radionuclides) are addressed in FNP-0-AP-60.

NOTE: REFER TO STEP 20.7 OF THIS PROCEDURE FOR OTHER NOTIFICATION REQUIREMENTS.

22.0 Transportation incidents involving hazardous substances or extremely hazardous substances, (including radioactive materials) (this is driver/carrier responsibility) -

see section 5.0 for possible additional reporting requirements involving fatalities or hospitalization. (Al 2008206101) 22.1 The Shift Manager should ensure that the Department of Transportation/Coast Guard National Response Center has been notified by the driver/carrier in the event that hazardous materials cause one or more of the following:

22.1.1 A person is killed.

22.1.2 A person receives injuries requiring hospitalization.

22.1.3 Estimated carrier or other property damage exceeds $50,000.

22.1.4 Fire, breakage, spillage, or suspected radioactive contamination occurrences involving shipment of radioactive material.

22.1.5 Fire, breakage, spillage, or suspected contamination occurs involving shipment of etiologic agents (includes sewage and medical waste).

22.1 .6 Continuing danger to life exists at the scene of the incident.

22.2 The Shift Manager should notify the FNP Duty Manager.

22.3 The Shift Manager should notify the On-Call Environmental Supervisor (non-rad shipment) OR On-Call HP Supervisor (rad shipment) to prepare a follow-up report per 49CFR171 .15 NQ to assess whether APCo should provide support at the scene of the accident.

22.4 The FNP duty Manager should notify the Corporate Duty Manager Ji!2 request that the Corporate Duty Manager notify SNC Environmental Services to provide support.

Version 108

10/10/11 12:16:08 S [1?\FE ED FNP-0-EIP-8.0 TABLE I REFERENCES

1. Joseph M. Farley Nuclear Plant Emergency Plan

2. FNP-0-EIP-3.0, Duties of the Emergency Director

3. FNP-0-EIP-9.0, Emergency Classification and Actions

4. FNP-0-EIP-10.0, Evacuation and Personnel Accountability

5. FNP-0-EIP-1 1 .0, Handling of Injured Personnel

6. FNP-0-EIP-13.0, Fire Emergencies

7. FNP-0-AP-60, Oil Spill Prevention Control and Countermeasures Plan

8. 10CFR5O.72, ENS Notification Criteria

9. 10CFR73.71, Reportable Safeguards Events

10. FNP-0-SNM-0, Special Nuclear Material Control and Accountability Manual

11. 1 OCFR5O.9, Reporting Requirements (NS-88-0 145)

12. 49CFR171.15, Hazardous Materials Incidents

13. 10CFR26, Fitness for Duty

14. Reporting of Safeguards Events (USNRC Generic Letter 91-03)

15. Enforcement Policy for Hot Particle Exposure (Information Notice 90-48)

16. 29CFR part 1904 - Reporting of Fatality or Multiple Hospitalization Incidents

17. NUREG-1 022 Event Reporting Guidelines

18. Regulatory Guide 5.6.2, Nov. 1987, Reporting of Safeguards Events

19. NMP-EP-002 Corporate Duty Manager 20,0 1 OCFR72 Licensing Requirements For The Independent Storage Of Spent Fuel Page 1 of I Version 108

10/10/11 12:16:08 FNP-0-EIP-8.0 TABLE 2 SECURITY REPORTABILITY MATRIX The time constraints to implement compensatory measures and initiate NRC reports typically start at the time the event occurs. If the exact time cannot be determined, the time of event discovery by on-site security management or an equivalent level of plant management will be used for initiating compensatory measures and event reporting. Events should be properly compensated within 10 minutes of discovery or within the time prescribed in the Security Plan. However, if extenuating circumstances prevent compensation within that time, the event need not be reported promptly provided there was no malevolent intent, nothing adverse resulted from the delay, and appropriate measures were taken to ensure necessary action in the future.

Event Description SystemlComponent Status Compensatory Measures Reportability Taken Within Time Allowed In The Security Plan Step 16 A. THREATS OR ACTS 10CFR73, Appendix G

1. Any event in which a person has Theft or unlawful diversion of N/A One Hour report per step 9.0 committed or caused, or attempted to any special nuclear material at commit or cause, or has made a FNP or of nuclear fuel enroute to credible threat to commit or cause: FNP

2. Any event in which a person has Significant physical damage to N/A One Hour report per step 9.0 committed or caused, or attempted to either FNP unit, spent fuel pool commit or cause, or has made a or nuclear fuel transport vehicle credible threat to commit or cause: to the extent that it CANNOT perform its normal function Page 1 of 10 Version 108

10/10/11 12:16:08 SIII\FEE FNP-O-EIP-8.0 TABLE 2 SECURITY REPORTABILITY MATRIX Event Description SystemlComponent Status Compensatory Measures Reportability Taken Within Time Allowed In The Security Plan Step 16 B. LOSS OF VA BARRIER SYSTEM/COMPONENT 10CFR73, Appendix G

1. VA Barrier(s) (1) Physically/Forcibly Breached N/A One Hour report per step 9.0 and or Doors(s) Log per step 15.0 Design flaw or vulnerability Yes One Hour report per step 9.0 in VA barrier No

2. Keycard and Alarmed-Not Locked Yes Log per step 15.0 Alarmed Doors(s) No One Hour report per step 9.0 Log per step 15.0 Locked-Not Alarmed Yes One Hour report per step 9.0 No Log per step 15.0 Not Alarmed-Not Locked Yes(2) One Hour report per step 9.0 No

3. Card Reader Failure allows unauthorized Yes Log per step 15.0 Failure access through door. No One Hour report per step 9.0 C. LOSS OF PA BARRIER SYSTEM/COMPONENT IOCFR73, Appendix G

1. PA Barrier(s) (1) Physically/Forcibly Breached N/A One Hour report per step 9.0 or Turnstiles(s) Log per step 15.0 Design flaw or vulnerability Yes One Hour report per step 9.0 in PA barrier No

2. Turnstile(s)/PA Alarmed-Not Locked Yes Log per step 15.0 Entry Doors(s) No One Hour report per step 9.0 Log per step 15.0 Locked-Not Alarmed Yes One Hour report per step 9.0 No Log per step 15.0 One Hour report per step 9.0 Not Alarmed-Not Locked Yes No Page 2 of 10 Version 108

10/10/11 12:16:08 S

[1 A E 1) FNP-0-EIP-8.0 TABLE 2 SECURITY REPORTABILITY MATRIX Event Description SystemlComponent Status Compensatory Measures Reportability Taken Within Time Allowed In The Security Plan Step 16 D. LOSS OF INTRUSION ALARM AND/OR ASSESSMENT CAPABILITIES 10CFR73, Appendix G

1. Loss of Microwave or Infrared (one or Inoperable! Out of Service due Yes Log per step 15.0 more zones) to No One Hour report per step 9.0 Failure/Maintenance/Repair/Test ing

2. Loss of CCTV Surveillance (one or Inoperable! Out of Service due Yes Log per step 15.0 more cameras/monitors) to Failure/Maintenance/Repair! No One Hour report per step 9.0 Testing

3. Loss of Remote Control Panel (RCP), Keycard/Alarm or Zone Yes Log per step 15.0 Local Control Panel (LCP) or Node Inoperable/Out of Service due to No One Hour report per step 9.0 Panel (Total loss) Failure/Maintenance/Repair/Test ing

4. Loss of RCP, LCP, or Node Panel Keycard/Alarm or Zone Yes Log per step 15.0 (Partial) Inoperable/Out of Service due to No One Hour report per step 9.0 Failure/Maintenance/Repair!

Testing

5. Loss of both Inoperable/Out of Service due to Yes Log per step 15.0 computer processors Failure/Maintenance/Repair/Test No One Hour report per step 9.0 i ng

6. Loss of one computer processor FaW over to Backup Yes(2) Log per step 15.0 No Log perstep 15.0

7. Loss of CAS/SAS Alternate Alarm Station operable N/A Log per step 15.0 Both Stations inoperable Yes Log per step 15.0 No One Hour report per step 9.0

8. Loss of PA lighting Inoperable/Out of Service due to Yes Log per step 15.0 (Total or Partial) Failure/Maintenance/Repair/Test No One Hour report per step 9.0 ing Log per step 15.0 Momentary Loss of PA lighting N/A Page 3 of 10 Version 108

10/10/11 12:16:08 SHARED FNP-0-EIP-8.0 TABLE 2 SECURITY REPORTABILITY MATRIX Event Description System/Component Status Compensatory Measures Reportability Taken Within Time Allowed In The Security Plan Step 16 E. LOSS OF POWER IOCFR73, Appendix G

1. Loss of AC power Standby Power maintains Yes Log per step 15.0 (Total or Partial) integrity. No One Hour report per step 9.0

2. Loss of Standby Power during loss of Total power loss N/A One Hour report per step 9.0 power F. LOSS OF LLEA COMMUNICATIONS IOCFR73, Appendix G

1. Partial Loss At least one method of N/A Log per step 15.0 communicating operable

2. Total Loss All on-site communications N/A One Hour report per step 9.0 capabilities Inoperable/Out of Service due to Failure!

Maintenance/Repair/Testing G. INTERRUPTION OF NORMAL OPERATIONS IOCFR73, Appendix G

1. Fire or Explosion of suspicious or N/A N/A One Hour report per step 9.0 unknown origin within the PA, including the Isolation Zone

2. Suspicious explosive device N/A N/A One Hour report per step 9.0 discovered

3. Confirmed unauthorized use of, or N/A N/A One Hour report step 9.0 vandalism or tampering with machinery, components or controls, including the security system/components

4. Credible bomb or extortion threat N/A N/A One Hour report per step 9.0

5. Unsubstantiated bomb or extortion N/A N/A Log per step 15.0 threat

6. Mass demonstrations or civil N/A N/A One Hour report per step 9.0 disturbance near the site which may a threat to the facility G. INTERRUPTION OF NORMAL OPERATIONS (Continued Next Page)

Page 4 of 10 Version 108

10/10/1112:16:08 FNP-0-EIP-8.0 TABLE 2 SECURITY REPORTABILITY MATRIX Event Description System/Component Status Compensatory Measures Reportability Taken Within Time Allowed In The Security Plan Step 16 G. INTERRUPTION OF NORMAL OPERATIONS 10CFR73, Appendix G (Continued from previous page)

7. An assault on the facility, regardless N/A N/A One Hour report per step 9.0 of whether perimeter penetration is achieved.

8. Attempted or confirmed intrusion, N/A N/A One Hour report per step 9.0 actual entry of an unauthorized (7) individual into PAJVA

9. Discovery of/or attempted malevolent N/A N/A One Hour report per step 9.0 introduction of weapons, explosives, or incendiary devices in/into the PA.

10. Discovery of contraband inside the PA N/A N/A Log per step 15.0 that is NOT a significant threat. For example, such a condition could be the discovery of a bullets

11. Discovery of contraband in a vehicle N/A N/A Normally no report or log located in a parking lot outside the PA entry is required. IE it constitutes a threat, a report is required within One Hour per RG 5.62 AND NUREG 1304 NOTE: FFD events will be reported using step 16 of the main body of the procedure unless the requirements of Note 6 below are met.

The requirements of [10 CFR 26.73] are applicable to item 12 regarding controlled substances. See Note 6 below.

12. Reasonable suspicion of illegal use, N/A N/A One Hour report per step 9.0 sale, possession, or introduction of controlled substances(s) inside the Protected Area or other criminal acts involving personnel with unescorted access which directly affect operations

13. Suspension of Safeguards controls by N/A Yes Log per step 15.0 the Shift Superintendent during No One Hour report per step 9.0 Emergencies including a Security Emergency.

H. SECURITY FORCE PERSONNEL RELATED 10CFR73, Appendix G Page 5 of 10 Version 108

S

[.1 \FE L FNP-0-EIP-8.0 10/10/11 12:16:08 TABLE 2 SECURITY REPORTABILITY MATRIX Event Description System/Component Status Compensatory Measures Reportability Taken Within Time Allowed In The Security Plan Step 16

1. Unavailability of minimum number or N/A Yes Log per step 15.0 impending strike of Security No One Hour report per step 9.0 Personnel.

2. Loss of Security Retrieved within one hour Yes Log per step 15.0 Weapon On-site No One Hour report per step 9.0

3. Security Officer asleep Post N/A Yes Log per step 15.0 No One Hour report per step 9.0 I. PROCEDURAL RELATED FAILURE IOCFR73, Appendix G

1. Loss or Theft of Safeguards N/A Yes One Hour report per step 9.0 Information which could Not significant or would not Log per step 15.0 SIGNIFICANTLY assist radiological assist sabotage

2. Inadvertent/accidental removal of N/A Yes (4) Log/Non-Event(5) security keys from PA No

3. Discovery of intentionally falsified N/A N/A One Hour report per step 9.0 identification badges or key cards

4. Unauthorized use of, unaccounted for, N/A Yes (4) Log per step 15.0 lost, or stolen badge that could allow No One Hour report per step 9.0 unauthorized access to PAs or VAs

5. Visitor without Escort N/A Yes Log/Non-Event(5)

No Log (5)

6. Individual authorized only PA access N/A Yes Non-Event is incorrectly issued a badge granting No Log VA access (initial badge issue), but does NOT enter any VAs or does NOT enter any VAs with malevolent intent.

J. MISCELLANEOUS

1. Discovery of off-site criminal acts by N/A Yes Log per step 15.0 personnel with unescorted access No One Hour report per step 9.0 which could cause concern about their trustworthiness and reliability or a program weakness.

Page 6 of 10 Version 108

10/10/11 12:16:08 S [IJ\RE TABLE 2 ED FNP-0-EIP-8.0 SECURITY REPORTABILITY MATRIX Event Description SystemlComponent Status Compensatory Measures Reportability Taken Within Time Allowed In The Security Plan Step 16

2. ANY criminal act by a licensee N/A Yes Log per step 15.0 employee committed offsite, which No One Hour report per step 9.0 receives media attention, and has the potential for affecting the radiological safety of licensee activities.

3. other threatened attempted, or N/A Yes Log per step 15.0 committed act NQI previously defined No One Hour report per step 9.0 having potential for reducing Physical Security Effectiveness 4 Vehicle Barrier System Degradation N/A For short time period (not to Log per step 15.0 exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />)

For longer time period (not to Log per step 150 exceed 30 days)

Page 7 of 10 Version 108

10/10/11 12:16:08 FNP-0-EIP-8.0 TABLE 2 SECURITY REPORTABILITY MATRIX Event Description SystemlComponent Status Compensatory Measures Reportability Taken Within Time Allowed In The Security Plan Step 16 K. PARTIAL FAILURE OF ACCESS CONTROL PROGRAM Generic Letter 91-03 A badged person inadvertently enters N/A Yes Log per step 15.0 the PA through a vehicle gate before No One Hour report per step 9.0 being searched.

2. A badged person walks into a VA N/A N/A Log per step 15.0 behind another person without using a badge, IF the improper entry was inadvertent or without malevolent intent.

3. A person enters a VA to which he is N/A N/A Log per step 15.0 authorized unescorted access by inadvertently using a badge intended for another person who is authorized access to the area.

4. Incomplete pre-employment screening N/A N/A Log per step 15.0 records (to include falsification of a minor nature), OR inadequate administration control OR evaluation of psychological tests. Unescorted access of the individual may need to be cancelled or suspended until the anomaly is resolved.

Page 8 of 10 Version 108

10/10/11 12:16:08 RED FNP-0-EIP-8 .0 TABLE 2 SECURFY REPORTABILITY MATRIX Event Description System/Component Status Compensatory Measures Reportability Taken Within Time Allowed In The Security Plan Step 16

5. IF the licensee determines that Reportability unescorted access would have been Requirements denied based on developed information that is viewed as Discovery of significant One hour report per Step 9.0 significant as outlined in Corporate information, access is Security Department (CSD-3) denied fjj the event Procedure. will be reported to the NRC within 1-hour.

Log per Step 15.0 If less significant information, access is denied AND the event is recorded in the security safeguards log within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

L. INCOMPLETE PRE-EMPLOYMENT SCREENING RECORDS (to include falsification and willful omission from the screening application)

1. Unescorted access of the individual N/A Reportability may need to be cancelled or Requirements suspended I the identified anomaly is resolved. If the licensee Discovery of significant One Hour report per step 9.0 determines that unescorted access information, access is denied would have been denied based on JQ the event will be reported developed information that is viewed to the NRC within 1-hour.

as significant as outlined in Corporate Security Department (CSD 3) If less significant information, Log per step 15.0 Procedure, access is denied AND the event is recorded in the security safeguards log within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Page 9 of 10 Version 108

10/10/11 12:16:08 FNP-0-EIP-8.0 TABLE 2 SECURITY REPORTABILITY MATRIX Event Description SystemlComponent Status Compensatory Measures Reportability Taken Within Time Allowed In The Security Plan Step 16 M. TEMPORARY SUSPENSION OF SECURITY MEASURES

1. Temporary suspension of security N/A N/A. One Hour report per step 9.0 measures in accordance with

[10CFR5O.54 (x) or (y)] as described in_section_19.3_of the_Security_Plan.

NOTES (1) Examples include floor or wall plugs, bisco seals, barriers in HVAC ducts, etc.

(2) To be properly compensated, measures must be in place within 10 minutes of event discovery.

(3) Events reportable under 50.72 or 50.73 NOT require duplicate reports under 73.71 (4) To be properly compensated, both invalidating the badge and initiating actions to ensure no unauthorized use of the badge must occur within 10 minutes of event discovery by on-site security personnel.

(5) May be a lociciable event depending on circumstances.

(6) A significant FED event must be reported under the provisions of 10 CFR 26.73, but need .QI be reported under 10 CFR section 73.71.

FED program perlormance data must be submitted under provisions of 10 CER 26.71(d). In those rare cases where an event with safeguards significance is caused by an FED event, the FED aspects must be submitted to the NRC in accordance with 10 CFR Part 26, the safeguards aspects reported in accordance with 10 CER 73.71. When a telephone report is reciuired by both rules, only one telephone call is needed to the Operations Center. In that case, a written report of the safeguards aspects must also be submitted within 30 days, as required by 10 CFR 73.71.

(7) For cases involving the failure to report a legal action, reportability for unauthorized entries into the protected area cannot be determined until Fleet Access has evaluated and adjudicated the facts surrounding the case. Typically the individual is immediately removed from the protected area and badge placed on administrative hold until Fleet Access can complete the review of the case.

Page 10 of 10 Version 108

10/10/11 12:16:08 SHARED FNP-0-EIP-8.0 FIGURE 1 FARLEY NUCLEAR PLANT EVENT NOTIFICATION FORM A. EVENTDATEYYMMDD / /

B. PERSON MAKING NOTIFICATION:____

LISHIFT SUPERINTENDENT LIOTHER..

C. EVENT CLASSIFICATION (check appropriate block and list EIP paragraph #

Lila CFR 50.72 NON-EMERGENCY NOTIFICATION_______________

Lila CFR2O RADIOACTIVE MATERIALS______________________

Lila CFR 50.9 (B) SIGNIFICANT EVENT, CONDITION OR INFORMATION Lila CFR 73, APP. G REPORTABLE SAFEGUARDS EVENT_________

Lila CFR 26.73 FITNESS FOR DUTY EVENT____________________

Ella CFR 72 SPECIAL NUCLEAR MATERIAL CONTROL____________

LIMISCELLANEOUS NOTIFICATIONS__________________________

D. Event Date and Time Discovery Date and Time Report Time Requirement Li one hour Li four hour El eight hour Li 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Li 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Li Other Date and Time Report required (event date and time+report time requirement).

E. Complete appropriate information on the NRC form 361 portion of this figure (last page of this figure) prior to contacting the NRC Operations center. Obtain the Event Notification Number (EN #) from the NRCOC and put that number at the indicated location at the top of the next page. The last page of the form may be faxed to the NRC of they desire.

F. AGENCIES NOTIFIED PERSON NOTIFIED I TIME LIALABAMA RADIATION CONTROL I LIALABAMA EMA /

LIH0UsTON COUNTY EMA I LIGEORGIA EMA Li EARLY COUNTY EMA LiNRC OPERATIONS CENTER I LINRC RESIDENT I LIEMERGENCY DIRECTOR I EIRECOVERY MANAGER I EOPERATIONS MANAGER I LIEMERGENCY SUPPORT MANAGER I LIOTHER:____________________ I C. HAS A PRESS RELEASE BEEN MADE OR PLANNED? LYES LINO Page 1 of 2 Version 108

10/10/11 12:16:08 SHARED FNP-0-EIP-8.0 FIGURE 1 SIMILAR to NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN #

NRC OPERATION TELEPHONE NUMBER: PRIMARY-- 301-816-5100, BACKUPS -- [1st] 301-951-0550, [2nd] 301-415-0550 and [3rdl 301-415-0553 NOTIFICATION TIME FACILITYOR ORGANIZATION UNIT NAME OF CALLER CALL BACK#ENS 700-221.0807 FARLEY NUCLEAR PLANT Comercial # 334-899-5156 EVENT TIME & ZONE EVENT DATE POWER/MODE BEFORE POWER/MODE AFTER EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR5O.72(b)(1) (v)(A) SafeS/DCapability AINA GENERAL EMERGENCY GEN/MEC TS Deviation ADEV (v)(B) RHR Capability AINB SITE AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) (v)(C) Control of Pad Release AINC ALERT ALE/AAEC (i) TS Required S/D ASHU (v)(D) Accident Mitigatio AIND UNUSUAL EVENT UNU/IiAEC (iv)(A) ECCS Discharge to RCS ACCS (xf) Offsite Medical AMED 50.72 NON-EMERGENCY (see next columns) (iv)(B) RPS Actuation (scram) ARPS ijii) Loss Comm/Asmt/Resp ACOM PHYSICAL SECURITY (73.71> DODD (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1)

MATERIALJEXPOSURE B??? Invalid Specified System Actuation AINV 8-Hr. Non-Emergency 10 CFR 50.72(b)(3)

FITNESS FOR DUTY HFIT (ii)(A) Degraded Condition ADEG Other Unspecified Requirement (Identify)

OTHER UNSPECIFIED REQMT (see last column) (ii)(B) Unanalyzed Condition AUNA NONR INFORMATION ONLY NINF iv)(A) Specified System Actuation AESF NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back) y [..Jrj WILL BE ANYTHING UNUSUAL OR U YES (Explain above) U NO DID ALL SYSTEMS r YES U Li NO (Ex P lain above)

FUNCTION AS REQUIRED?

OTHER GOV AGENCIES MODE OF OPERATION ESTIMATED ADDITIONAL INFO ON BACK MEDIAIPRESS RELEASE UNTIL CORRECTED: RESTART DATE: U YES UNO Page2of2 Version 108

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