ML092940748

Initial Exam 2008-301 Final Simulator Scenarios

ML092940748
Person / Time
Site:	Catawba
Issue date:	10/20/2009
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
50-413/08-301, 50-414/08-301
Download: ML092940748 (93)

Text

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 2008 NRC EXAMINATION Facility: Catawba Nuclear Station Scenario No.:

2 Op-Test No.:

SNAP 162 Examiners: Operators:

Initial Conditions:

• 100% power

• EFPD =250 days

• Boron concentration is' 875 ppm

• 1A CA pump out of service for PMs - expected back in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

• 1A NI pump out of service for PMs - expected back in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

• Thunderstorms are in the area.

Turnover:

• Maintain 100%

Event Malf. No. Event Event No. Type* Description 1 RO I NC Loop A Cold Leg Temperature fails high - auto rod motion TS 2 BOP I PZR level Ch2 fails low - loss of letdown SRO TS 3 BOP C B Train KC mini-flow valve fails open TS 4 RO R Vacuum leak - manual turbine load decrease 5 BOP C Loss of running RN pump 6 RO C Loss of running LH pump 6a* RO C Rods H-8/M12 drop into the core - manual Rx trip required

• This will be used to initiate the major if the candidate starts the idle LH pump prior to the turbine trip. Otherwise event 6 will start the major event 7 ALL M ATWS, Loss of heat sink Additional failures Complete loss of vacuum Auto and manual Rx trip fail CAPT O/S, B CA fails to start NV aux spray valve fails closed

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

SIMULATOR SETUP

• Reset to any 100% MOL power snap

• Ensure 1B2 KC and 1A RN pump in service

• Roll Charts

• Place red tag covers on 1A CA pump and 1A NI pump

• OP/1/N61 001003 (Controlling Procedure for Unit Operation), Enclosure 4.3 completed through step 2.13 (revision 102)

MALFUNCTIONS, REMOTES, and OVERRIDES Malfunction # Description Value Event Ramp Delay Trigger XMT-NC057 TNC 5440 NC LOOP 1A COLD 630 1 6 LEG TEMP NARROW RANGE VLV-KC028F KCC40B TRAIN B RECIRC 1 3 LINE ISOL VLV FAIL TO POSITION MAL-IPX001A AUTO REACTOR TRIP FAILURE TRN A MAL-IPX001 B AUTO REACTOR TRIP FAILURE TRN B MAL-IPX002A MAN REACTOR TRIP FAILURE TRN A MAL-IPX002A MAN REACTOR TRIP 9 Del in 1 FAILURE TRN A MAL-IPX002B MAN REACTOR TRIP FAilURE TRN B MAL-IPX002B MAN REACTOR TRIP 9 Del in 1 FAILURE TRN B MAL-CA005 CA PUMP OVERSPEED TRIP MECHANICAL MAL-CA004B FAILURE OF CA PUMP B TO BOTH START MAL-MT003 LOSS OF CONDENSER 32 4 60 VACUUM (VLV LEAK)

MAL-MT003 LOSS OF CONDENSER 16 15 60 VACUUM (VLV LEAK)

LOA-RN002 RACKOUT RN PUMP 1A RACK-OUT 5 MAL-CF001A LOSS OF CFPT 1A VACUUM 20 8 20 45 MAL-CF001 B LOSS OF CFPT 1B VACUUM 20 8 20 45 MAL-MT003 LOSS OF CONDENSER 100 8 0 360 VACUUM (VLV LEAK)

• VLV-NV014F NV37A PRZR SPRAY LINE 0 ISOL VLV FAIL TO POSITION LOA-RN010 2RN48B U2 RN SUPPLY 0 20 15 10 XOVER LOA-RN011 2RN47A U2 RN SUPPLY 0 20 15 10 XOVER XMT-RN007 FRN_7510 RN PMP 1B DISCH 24500 10 10 FLOW METER

XMT-RN007 FRN 7510 RN PMP 1B DISCH 15500 20 5 Del in 1 FLOW METER XMT-NC013 LNC_5150 PZR LEVEL METER 0 2 LI-460C CH II OVR-CM001C COND A-B-C VAC BKR VL V ON 8 125 OPEN PB OVR-CM001A COND A-B-C VAC BKR VL V ON CLSD LT OVR-CM001B COND A-B-C VAC BKR VLV OFF OPEN LT LOA-CA017 RACKOUT CA PUMP 1A RACK-OUT LOA-NI003 RACKOUT NI PMP 1A RACK-OUT MAL-IRX006M12 DROPPED ROD M12 STATIONARY 7 MAL-IRX006H8 DROPPED ROD H8 STATIONARY 7 5 OVR-MT016C HYDR FLUID PUMP 1B AUTO OFF PB LOA-ENC014 RACKOUT EHC PMP 1A RACKOUT 6 ANN-AD11-102 600v NORM UNIT AUX PWR ON 6 TROUBLE LOA-NV078 SEAL WATER LOW FLOW ACKN 26 180 (AD7, C4) ACKNOWLEDGE

• Larger leak starts major EVENT TRIGGERS (other than manual)

Event Description Trigger 10 jrnnsw1 b 15 SMSS < 1160.0 20 (RRNH048B < 0.1) + ( RRNH047A < 0.1)

CRITICAL TASKS FR-S.1 C - Insert negative reactivity into the core by inserting control rods in manual per the immediate action steps of FR-S.1.

FR-H.1 A - Establish Feedwater flow into at least one S/G before transition to bleed and feed.

REFERENCES OP/1/A/61 00/003 (Controlling Procedure for Unit Operation), Enclosure 4.3 revision 102 AP/1/A/5500/023 (Loss of Condenser Vacuum) revision 017 AP/1/A/5500/012 (Loss of Charging or Letdown) revision 025 AP/1/A/5500/015 (Rod Control Malfunction) revision 011 AP/1/A/5500/021 (Loss of Component Cooling) revision 035 AP/0/A/5500/020 (Loss of Nuclear Service Water) revision 036 EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) revision 031 EP/1/A/5000/ES-0.1 (Reactor Trip Response) revision 030 EP/1/A/5000/FR-S.1 (Response to Nuclear Power Generation/AWTS) revision 018 EP/1/A/5000/FR-H.1 (Response to Loss of Secondary Heat Sink) revision 030

NOTES AND INSTRUCTIONS NOTE: The following steps are GUIDELINES. The NRC lead examiner will direct timing of events unless otherwise noted.

Event 1 - NC Loop A Cold Leg Temperature fails high - auto rod motion! SRO Technical Specification This event will be entered once the crew has taken turnover and evaluated plant conditions.

When AP/1/A/5500/015, Case 2 is complete and the SRO has completed consulting Technical Specifications, the next event can be inserted.

Event 2 - PZR level Ch2 fails low - loss of letdown! SRO Technical Specification When the failed channel has been removed from control functions, letdown has been restored, and the SRO has completed consulting Technical Specifications, the next event can be inserted.

Event 3 - B Train KC mini-flow valve fails open! SRO Technical Specification NOTE: The vacuum leak may take a several minutes to present itself to the crew. When the crew checks for KC mode switches properly aligned the next event should be inserted.

When an additional KC pump on the same train has been placed in service to clear 1AD-9 F/6 and the SRO has completed consulting Technical Specifications, the next event can be inserted.

Event 4 - Vacuum leak - manual turbine load decrease NOTE: The trigger to start the leak should already be in at this time. If load is not decreased below 1160 MW, Event 15 to reduce the vacuum leak will not occur. In this case, then Event 15 should be manually entered prior to 23.5" vacuum or whatever limit the crew may verbalize to prevent the crew from tripping the reactor/turbine.

When turbine load has been decreased and vacuum is recovering, the next event can be entered.

Event 5 - Loss of running RN pump NOTE: When the crew calls to close 2RN-47A and 2RN-48B, acknowledge that they will be closed. No booth action is required since they are triggered from 1RN-47A and 2RN-48B being less than 10% open. Once the valves have gone closed notify the crew that they are closed.

When another RN pump is in service, and conditions are stable, the next event can be entered.

Event 6 - Loss of running LH pump NOTE: If the crew does not start the standby LH pump in time to prevent a turbin!3/reactor trip, that will start the major event and event 6a will not be used.

When the standby LH pump has been placed in service the next event can be entered. This will begin the major event.

• Event 6a - Rods H-S!M12 drop into the core - manual Rx trip required The crew will be required to insert a manual reactor trip which fails and the major event starts.

Event 7 - ATWS, Loss of heat sink Additional failures Complete loss of vacuum, auto and manual Rx trip fail, CAPT O/S, B CA fails to start, NV aux spray valve fails closed NOTE: Proper timing of the triggers is crucial to ensuring a RED path on Heat Sink with out entering bleed and feed. These are approximate and should be adjusted as necessary to ensure a red path on heat sink while maintaining as much water as possible in the S/Gs.

If the crew calls immediately upon entering FR-S.1 to trip the reactor locally, then Event 8 should be inserted as soon as it is evident that C Control Banks are starting to insert and the reactor should be tripped when S/G N/R levels are 35-38% using Event 9.

If the crew calls when the step is reached, Event 8 should be inserted immediately and the reactor should be tripped when S/G N/R level is -20% using Event 9.

TERMINATE WHEN FEEDWATER FLOW IS ESTABLISHED TO 2S/Gs USING THE CONDENSATE SYSTEM PER FR-H.1.

Remove red tag covers from 1A CA pump and 1A NI pump.

CREW TURNOVER INFORMATION Initial Conditions:

• 100% power

• EFPD =250 days

• Boron concentration is 875 ppm

• 1A CA pump out of service for PMs - expected back in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

• 1A NI pump out of service for PMs - expected back in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

• Thunderstorms are in the area.

Turnover:

• Maintain 100%.

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 1 2 Page(s)

Event

Description:

NC Loop A Cold Leg Temperature fails high - auto rod motion SRO Technical Specification Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an INSTRUMENT event using AP/1/A15500/015 (Rod Control Malfunctions), Case 2 Continuous Rod Motion.

Pertinent Alarms 1AD-2 Al4 T-REFIT-AUCT HIILO 1AD-6 Al6 AUCT HI T-AVG 1AD-6 B/6 LOOP T-AVG DEVIATION 1AD-6 C/6 LOOP DIT DEVIATION RO 1. Ensure "CRD BANK SELECT" switch - IN MANUAL.

RO 2. Verify all rod motion - STOPS.

RO NOTE For T-Ref failures, T-Ref will need to be determined for current power level.

3. Manually adjust control rods as necessary to maintain T-Avg within 1°F of T-Ref.

RO 4. Verify the following parameters - NORMAL FOR EXISTING PLANT CONDITIONS:

• Channel 1 Turbine Impulse Pressure

• T-Ref.

BOP 5. Verify the following channels - NORMAL FOR EXISTING PLANT CONDITIONS:

• NC Loop A T-Avg

• NC Loop B T-Avg

• NC Loop C T-Avg

• NC Loop 0 T-Avg.

BOP 5RNO IF channel inoperable, THEN perform the FOR EXISTING PLANT CONDITIONS: following:

a. Place "(lTEMP DEFEAT" switch to failed loop.

b. Place "T-AVG DEFEAT" switch to failed loop.

c. WHEN T-Avg is within +/-1 OF of T-Ref AND auto rod control is desired, THEN return rod control to "AUTO".

d. Ensure P-12 interlock in required state for existing plant conditions. REFER TO Tech Spec 3.3.2.

e. Have IAE trip bistables associated with the failed loop within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. REFER TO Model WIO #91002943:

• OPDT (Tech Spec 3.3.1)

• OTDT (Tech Spec 3.3.1)

• Low T-Avg (Tech Spec 3.3.2).

ALL 6. Determine and correct cause of continuous rod movement.

EXAMINER NOTE: Tech Specs 3.3.1-1 #6 and #7 Condition E and 3.3.2 #8.c Condition 0 and #5.b.4 Condition J.

Page 1 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 1 2 Page(s)

Event

Description:

NC Loop A Cold Leg Temperature fails high - auto rod motion SRO Technical Specification Time Position Applicant's Actions or Behavior AppJicant's SRO 7. Ensure compliance with appropriate Tech Specs:

• 3.1.1 (Shutdown Margin (SDM))

• 3.1.4 (Rod Group Alignment Limits)

• 3.1.5 (Shutdown Bank Insertion Limits)

• 3.1.6 (Control Bank Insertion Limits)

• 3.3.1 (Reactor Trip Instrumentation)

• 3.3.2 (ESFAS Instrumentation)

• 3.4.2 (RCS Minimum Temperature for Criticality).

EXAMINER NOTE: No notifications at this time.

SRO 8. Determine required notifications:

• REFER TO RP/O/A/50001001 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 (NRC Notification Requirements).

RO 9. WHEN rod control problem is repaired, THEN perform the following:

a. Ensure T-Avg - WITHIN 1°F OF T-REF.

b. WHEN desired, THEN place control rods in "AUTO".

c. Ensure steam dumps - IN DESIRED MODE FOR EXISTING PLANT CONDITIONS.

SRO 10 Determine long term plant status. RETURN TO procedure in effect.

END EVENT Page 2 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 2 4 Pages Event

Description:

PZR level Ch2 fails low - loss of letdown SRO Technical Specification Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an INSTRUMENT event using AP/1/A15500/012 (Loss of Charging or Letdown), Case 2 (Loss of Letdown).

Pertinent Alarms 1AD-6 Al10 PZR HTR CONTROLLER TROUBLE 1AD-6 0/9 PZR LO LEVEL HTR OFF & LETDN SECURED BOP 1 Verify all Pzr level channels - INDICATING THE SAME.

BOP 1RNa IF a controlling channel is failed low, THEN place "PZR LEVEL CTRL SELECT" switch in any alternate operable channel position.

RO 2 Stop any power changes.

BOP 3 Ensure the following letdown isolation valves - CLOSED:

• 1NV-1 OA (Letdn Orif 1B Otlt Cont Isol)

• 1NV-11A (Letdn Orif 1C Otlt Cont Isol)

• 1NV-13A (Letdn Orif 1A Otlt Cont Isol).

BOP 4 Verify Pzr level - GREATER THAN 17%.

BOP 5 Control charging to stabilize Pzr level at program level while maintaining seal injection flow.

BOP 6 Ensure "PZR HTR GROUP 1C" - ON.

BOP 7 Control VCT level as follows:

a. Verify NC system makeup - SET FOR DESIRED BORON CONCENTRATION.

b. Verify "NC MAKEUP MODE SELECT" - IN AUTOMATIC.

BOP 8 Determine and correct cause of loss of letdown.

BOP 9 IF AT ANY TIME excess letdown is required, THEN establish excess letdown.

REFER TO OP/1/A/62001001 (Chemical and Volume Control System).

EXAMINER NOTE: Enclosure 5 actions are listed after step 21.

BOP 10 Verify proper VCIYC system operation. REFER TO Enclosure 5 (Control RoomVentilation System Verification).

BOP 11 Ensure "PZR LEVEL TO REC SEL" is selected to an operable channel.

EXAMINER NOTE: Tech Spec 3.3.1 #9 Condition L applies.

SRO 12 Ensure compliance with appropriate Tech Specs:

• 3.3.1 (Reactor Trip System (RTS) Instrumentation)

• 3.3.3 (Post Accident Monitoring (PAM) Instrumentation)

• 3.3.4 (Remote Shutdown System)

• 3.4.1 (RCS Pressure; Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits)

• 3.4.12 (Low Temperature Overpressure Protection (LTOP) System)

• 3.6.3 (Containment Isolation Valves).

Page 3 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 2 4 Pages Event

Description:

PZR level Ch2 fails low - loss of letdown SRO Technical Specification Time Position Applicant's Actions or Behavior BOP 13 Verify at least one of the following valves - CLOSED:

• 1NV-1A (NC Letdn To Regen Hx Isol)

OR

• 1NV-2A (NC Letdn To Regen Hx Isol).

BOP 14. Verify the following Letdn Orif Otlt Cont Isol valves - CLOSED:

• 1NV-1 OA (Letdn Orif 1B Otlt Cont Isol)

• 1NV-11A (Letdn Orif 1C Otlt Cont Isol)

• 1NV-13A (Letdn Orif 1A Otlt Cont Isol).

BOP NOTE

• If either NC loop letdown valve (1 NV-1A or 1NV-2A) closed before all orifice isolation valves (1 NV-1 OA, 1NV-11A and 1NV-13A), the letdown line will require local repressurization.

• If all valves closed from automatic signal(s), it can be assumed the orifice valves reached the closed position first.

15. Verify all the following valves - CLOSED BY AUTOMATIC SIGNAL(s).

• 1NV-1A (NC Letdn To Regen Hx Isol)

• 1NV-2A (NC Letdn To Regen Hx Isol)

• 1NV-1 OA (Letdn Orif 1B Otlt Cont Isol)

• 1NV-11 A (Letdn Orif 1C Otlt Cont Isol)

• 1NV-13A (Letdn Orif 1A Otlt Cont Isol).

RO 15RNO Perform the following:

a. IF all orifice isolation valves are known to have been closed prior to either NC loop letdown valve closing, THEN GO TO Step 18.

BOP 18 Establish letdown as follows:

a. Verify ability to establish normal letdown - RESTORED.

BOP b. Ensure 1NV-849 (Letdn Flow Var OrifCtrl) valve demand position - 0%.

BOP c. Verify the following valves - OPEN:

• 1NV-1A (NC Letdn To Regen Hx Isol)

• 1NV-2A (NC Letdn To Regen Hx Isol).

BOP 18cRNO

c. Perform the following:

1) Manually open the affected valve( s).

2) IF the affected valve(s) will not open, THEN ...

BOP NOTE If LTOP is in service, then 1NC-34A will be made inoperable when 1NV-10A is opened and returned operable when 1NV-11A or 1NV-13A is opened. (PIP

1. 01-545)

d. Open the following valves:

• 1NV-15B (Letdn Cont Isol)

• 1NV-10A (Letdn Orif 1B Otlt Cont Isol) .

BOP e. Adjust 1NV-294 (NV Pmps A&B Disch Flow Ctrl) as necessary to maintain letdown subcooled in following steps.

Page 4 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 2 4 Pages Event

Description:

PZR level Ch2 fails low - loss of letdown SRO Technical Specification Time Position Applicant's Actions or Behavior BOP f. Throttle 1NV-148 (Letdn Press Control) to 45% demand.

BOP g. Throttle open 1NV-849 (Letdn Flow Var Orif Ctrl) in 1% to 5% increments until one of the following conditions is met:

• Letdown flow and letdown pressure increases OR

• Valve demand position is 60% open .

BOP h. Do not continue until one of the above conditions is met.

BOP i. Verify letdown flow and letdown pressure - HAS INCREASED.

BOP j. Adjust 1NV-148 (Letdn Press Control) to maintain letdown pressure between 150 - 200 PSIG.

BOP k. WHEN 5 minutes have elapsed, THEN perform the following:

1) IF AT ANY TIME letdown flow is increased to greater than 80 GPM, THEN ...

2) Adjust 1NV-849 (Letdn Flow Var Orif Ctrl) in 1% increments to desired letdown flow.

3) WHEN letdown at desired flow, THEN perform the following:

a) Adjust 1NV-148 (Letdn Press Control) to maintain letdown pressure at 350 PSIG.

b) Ensure 1NV-148 (Letdn Press Control) -IN "AUTO".

4) IF AT ANY TIME additional letdown flow desired, THEN establish letdown with the 45 or 75 GPM orifice. REFER TO OP/1/A162001001 (Chemical and Volume Control System).

BOP I. WHEN Pzr level is restored to programmed level, THEN ensure 1NV-294 (NV Pmps A&B Disch Flow Ctrl) is in "AUTO".

EXAMINER NOTE: No notifications required.

SRO 19 Determine required notifications:

• REFER TO RP/O/A/5000/o01 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 (NRC Notification Requirements).

BOP 20 Verify excess letdown - ISOLATED.

SRO 21 Determine long term plant status. RETURN TO procedure in effect.

Enclosure 5 actions BOP 1. Verify one train of the following equipment is in operation:

• YC chiller

• CR AHU-1

• CRAAHU-1

• CRA PFT-1.

BOP 2. Verify the following annunciators - DARK:

• 1AD-18, Al8 "UNIT 1 INTAKE HI CHLORINE 1A"

• 1AD-18, B/8 "UNIT 1 INTAKE HI CHLORINE 1B"

• 1AD-18, D/8 "UNIT 2 INTAKE HI CHLORINE 2A"

• 1AD-18, E/8 "UNIT 2 INTAKE HI CHLORINE 2B".

Page 5 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 2 4 Pages Event

Description:

PZR level Ch2 fails low - loss of letdown SRO Technical Specification Time Position Applicant's Actions or Behavior BOP 3. Ensure the following VC dampers - OPEN:

• iVC-5B (CRA Filt Inlet)

• 1VC-6A (CRA Filt Inlet)

• 2VC-5B (CRA Filt Inlet)

• 2VC-6A (CRA Filt Inlet).

BOP 4. Repeat this enclosure until notified by Station Management as follows:

• At least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> OR

• Any time VC/yC related annunciators on 1AD-i8 actuate.

END EVENT Page 6 of 21

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 2 Event No. 3 3 Page(s)

Event

Description:

B Train KC mini-flow valve fails open Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an COMPONENT event using AP/1/A15500/021 (Loss of Component Cooling).

Pertinent Alarms 1AO-9 F/6 KC TRAIN B SINGLE PUMP RUNOUT Numerous KC flow alarms ALL CAUTION Failure to restore NC pump seal cooling via thermal barrier cooling or NV seal injection within 10 minutes will cause damage to the NC pump seals resulting in NC inventory loss.

1. Monitor Enclosure 1 (Foldout Page).

BOP 2. Verify at least one KC pump - ON.

ALL 3. IF AT ANY TIME all KC pumps are lost, THEN RETURN TO STEP 2.

BOP NOTE Uncooled letdown may result in loss of NV pumps within a matter of minutes.

4. Verify the following:

• iAD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK .

AND At least one KC pump - ON.

BOP 5. IF AT ANY TIME 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" LIT, THEN perform Step 4 RNa.

BOP 6. Verify both KC surge tank levels - 50% - 90% AND STABLE.

BOP 7. Start additional KC pump(s) as necessary to supply any KC loads presently in service.

BOP CAUTION A loss of KC cooling to the NC pumps results in a gradual approach to an overheated condition in approximately 10 minutes which will result in shaft seizure.

8. Verify KC flow to NC pumps as follows:

• iAD-20, Ali "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK

• iAD-21, Ali "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK .

BOP 9. Verify KC available as follows:

a. Verify the following Train A KC non-essential header isolation valves - OPEN:

• 1KC-230A (Rx Bldg Non-Ess Hdr Isol)

• 1KC-3A (Rx Bldg Non-Ess Ret Hdr Isol)

• 1KC-50A (Au x Bldg Non-Ess Hdr Isol)

• 1KC-1A (Au x Bldg Non-Ess Ret Hdr Isol).

b. Verify the following Train B KC non-essential header isolation valves - OPEN:

• 1KC-228B (Rx Bldg Non-Ess Hdr Isol)

• 1KC-18B (Rx Bldg Non-Ess Ret Hdr Isol)

• 1KC-53B (Aux Bldg Non-Ess Hdr Isol)

• 1KC-2B (Au x Bldg Non-Ess Ret Hdr Isol).

c. Start additional KC pump(s) as necessary to supply any KC loads presently in service.

Page 7 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 3 3 Page(s)

Event

Description:

B Train KC mini-flow valve fails open Time Position Applicant's Actions or Behavior BOP 10. Verify KC surge tank levels normal as follows:

a. Verify both KC surge tank levels - 50% - 90% AND STABLE.

b. GO TO Step 14.

EXAMINER NOTE: Switches in next step are properly aligned.

BOP 14 Ensure KC heat exchanger outlet mode switches - PROPERLY ALIGNED.

ALL 15 Determine and correct cause of loss of KC.

EXAMINER NOTE: Tech Spec 3.7.7. Condition A applies.

SRO 16 Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual:

• SLC 16.9-7 (Boration Systems Flow Path - Shutdown)

• SLC 16.9-8 (Boration Systems Flow Path - Operating)

• SLC 16.9-9 (Boration Systems Pumps - Shutdown)

• SLC 16.9-10 (Boration Systems Charging Pumps - Operating)

• 3.5.2 (ECCS - Operating)

• 3.5.3 (ECCS - Shutdown)

• 3.6.6 (Containment Spray System)

• 3.7.5 (Auxiliary Feedwater (AFW) System)

• 3.7.7 (Component Cooling Water (CCW) System).

EXAMINER NOTE: No notifications at this time.

SRO 17 Determine required notifications:

• REFER TO RP/0/A/5000/001 (Classification Of Emergency)

• REFER TO RP/0/B/5000/013 (NRC Notification Requirements).

BOP 18 IF KC Hx leak to RN is suspected, THEN perform the following:

• Notify Radiation Protection that a potential unmonitored release may have occurred.

• Notify Station Management to evaluate a KC Hx to RN leak.

BOP 19 Verify KC surge tanks level as follows:

• Greater than 50%

• Stable or increasing.

BOP 20 WHEN plant conditions permit, THEN:

• Return KC pumps to normal operation. REFER TO OP/1/A/6400/005 (Component Cooling Water System).

• Return NV Pump 1A to normal cooling as applicable. REFER TO Enclosure 4 4(Alternate (Alternate Cooling To NV Pump 1A).

BOP 21 Verify the following:

• 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK

• 1AD-7, H/3 "VCTHI TEMP" - DARK

• Normal letdown - IN SERVICE.

Page 8 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. . NRC Scenario No. 2 Event No. 3 3 Page(s)

Event

Description:

B Train KC mini-flow valve fails open Time Position Applicant's Actions or Behavior BOP 22 Ensure VCT and letdown path aligned as follows:

a. IF desired to align NV pump suction to VCT, then perform the following:

1) Open the following valves:

• 1NV-188A (VCT Otlt Isol)

• 1NV-189B (VCT Otlt Isol).

2) Close the following valves:

• 1NV-252A (NV Pumps Suct From FWST)

• 1NV-253B (NV Pumps Suct From FWST).

b. WHEN NV suction aligned to VCT, THEN momentarily place 1NV-172A (3-Way Divert To VCT-RHT) to the "VCT" position and return to "AUTO".

c. IF desired to restore letdown flow through the NV demineralizers, THEN momentarily place 1NV-153A (Letdn Hx Otlt 3-Way VI v) to the "DEMIN" position and return to "AUTO".

SRO 23 Determine long term plant status. RETURN TO procedure in affect.

END EVENT Page 9 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.

Event

Description:

NRC Scenario No. - - 2- Event No.

Vacuum leak - manual turbine load decrease

- 2 Page(s)

Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an REACTIVITY event using AP/1/A15500/023 (Loss of Condenser Vacuum).

EXAMINER NOTE: When Megawatts have been reduced to approximately 1160 MW, the vacuum leak will be reduced so that vacuum begins to increase. If students do not adequately reduce load to that level, the leak will be reduced to prevent the crew from tripping the reactor. This will occur at 23" vacuum unless the crew verbalizes the intent to trip at a higher value.

Pertinent Alarms OAC Pt C1A0734 Condenser C Absolute Back Pressure OAC Pt C1 P1670 ap Between Band C Condensers ALL 1. Monitor Enclosure 1 (Foldout Page).

RO 2. Decrease turbine load as required to stabilize vacuum as follows:

a. IF rapid power reduction required, THEN perform the following:

NOTE In "MANUAL" mode, the control valves are capable of full travel within 3 minutes.

1) Select "MANUAL" and "CONTROL VALVE LOWER" to reduce turbine load as required.

2) REFER TO AP/1/A/5500/009 (Rapid Downpower).

3) GO TO Step 3.

BOP 3. Verify proper RC System operation as follows:

a. Verify average condenser inlet temperature OAC point C1 P1493 (Unit 1 C1 &

C2 Average RC Inlet Temp) - LESS THAN 90°F.

b. Verify 1AD-8, B/4 "COOLING TOWER BASIN HIILO LEVEL" - DARK.

BOP 4. Verify "STM PRESS TO CSAE" - GREATER THAN 110 PSIG.

RO 5. Verify steam seal header conditions as follows:

a. Ensure at least one of the following valves - OPEN:

• 1TL-2 (Main Stm To Stm Seal Reg)

• 1TL-8 (Au x Stm To Stm Seal Reg).

b. Adjust 1TL-4 (Stm Seal Reg Byp) as required to obtain steam seal header pressure between 4 psig and 6 psig.

c. Verify OAC - AVAILABLE.

BOP NOTE Most TL valve positions can be displayed by OAC turn on code "TL-TF".

6. Verify supplemental steam flow into the steam seal header by at least one of the following:

• Verify 1TL-3 (Steam Seal Reg Valve) - NOT CLOSED OR

• Verify both the following:

o Unit 1 - ON LINE.

o 1TL-10 (E Bleed Steam Seal Reg Valve) - NOT- CLOSED.

Page 10 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 4 2 Page(s)

Event

Description:

Vacuum leak - manual turbine load decrease Time Position Applicant's Actions or Behavior BOP NOTE Starting additional air ejectors or vacuum pump will not restore vacuum when high RC temperature is the reason for loss of vacuum.

7. Verify condenser vacuum status as follows:

a. Condenser vacuum - STABLE OR INCREASING.

b. IF AT ANY TIME condenser vacuum decreases, THEN observe Note prior to Step 6 and perform Step 6.

BOP 8. Ensure proper operation of ZP System. REFER TO OP/O/B/62501011 (Vacuum Priming System).

BOP 9. Dispatch operator(s) to verify proper seal trough flows. REFER TO Enclosure 2 (Verification Of Seal Flows).

BOP 10. Dispatch operator to ensure CFPT seal system and waterboxes operating properly. REFER TO Enclosure 3 (CFPT Stm Seal And Waterbox Vent Verification ).

ALL 11. Determine and correct cause of loss of vacuum.

EXAMINER NOTE: No notifications at this time.

SRO 12. Determine required notifications:

• REFER TO RP/O/A/50001001 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 (NRC Notification Requirements) .

BOP 13. Verify Steam Seal System - IN NORMAL ALIGNMENT.

SRO 14. Determine long term plant status. RETURN TO J~rocedure in affect.

END EVENT Page 11 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 5 2 Page(s)

Event

Description:

Loss of running RN pump Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using AP/OIAl5500/020 (Loss of Nuclear Service Water), Case 1 Loss of RN Train.

Pertinent Alarms 1AD-12 A12 RN ESSENTIAL HDR A PRESSURE - LO 1AD-12 A14RN PUMP B FLOW - HI/LO 1AD-12 A15 RN ESSENTIAL HDR B PRESSURE - LO BOP 1. Start idle RN pump(s) as required.

RO Pa~el

2. Ensure Unit 1 and Unit 2 OATC monitors Enclosure 1 (Foldout Page).

BOP 3. Verify each operating RN pump discharge flow - GREATER THAN 8,600 GPM.

BOP 4. Verify each operating RN pump discharge flow - LESS THAN 23,000 GPM.

BOP 4RNO Perform the following:

CAUTION Closing of the RN supply x-over isolation valves may result in the momentary isolation of an essential header.

NOTE Isolating the Unit 1 or 2 non-essential header will result in loss of cooling supply to the following unit related equipment:

• VA Supply Vent Units

• VF Supply Vent Unit.

a. Ensure the following RN supply X-Over isolation valves - CLOSED:

• 1RN-47A (RN Supply X-Over Isol)

• 1RN-48B (RN Supply X-Over Isol)

• 2RN-47A (RN Supply X-Over Isol)

• 2RN-48B (RN Supply X-Over Isol).

b. IF flow is returning to normal, THEN GO TO Step 5.

EXAMINER NOTE: 2A RN pump will need to be started to supply cooling to A train equipment on both units since the crossovers are closed.

BOP 5. Ensure RN pumps - IN OPERATION AS NEEDED.

BOP 6. Ensure proper alignment of RN to KC Hxs as follows:

a. Verify RN - ALIGNED TO IN SERVICE KC HX(S).

b. Ensure KC Hx Otlt Mode switches - PROPERLY ALIGNED.

BOP 7. Verify each operating RN pump discharge flow - GREATER THAN 8,600 GPM.

BOP 8. Verify RN - AVAILABLE TO ALL UNIT 1 AND UNIT 2 D/G(S).

BOP 9, Determine VC/yC status as follows:

• Verify VC/yC - ALIGNED TO OPERATING RN TRAIN.

• Verify YC Chiller - RUNNING.

ALL 10. Determine and correct cause of loss of RN train.

EXAMINER NOTE: Tech Spec 3.7.8 Condition A.1 applies.

Page 12 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 5 2 Page(s)

Event

Description:

Loss of running RN pump Time Position Applicant's Actions or Behavior SRO 11. Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual:

• SLC 16.7-6 (RN Discharge Instrumentation)

• 3.6.5 (Containment Air Temperature)

• 3.6.6 (Containment Spray System)

• 3.6.17 (Containment Valve Injection Water System (CVIWS))

• 3.7.5 (Auxiliary Feedwater (AFW) System)

• 3.7.7 (Component Cooling Water (CCW) System)

• 3.7.8 (Nuclear Service Water System (NSWS))

• 3.7.10 (Control Room Area Ventilation System (CRAVS))

• 3.7.11 (Control Room Area Chilled Water System (CRACWS))

• 3.8.1 (A.C. Sources - Operating)

• 3.8.2 (A.C. Sources - Shutdown).

EXAMINER NOTE: No notifications at this time.

SRO 12. Determine required notifications:

• REFER TO RP/O/A/5000/001 (Classification Of Emergency)

• REFER TO RP/O/B/5000/013 (NRC Notification Requirementsl Requirements).

BOP 13. Notify Environmental Chemistry of any RN pump shifts that have occurred.

SRO 14. Determine long term plant status. RETURN TO procedure in effect.

END EVENT Page 13 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 6 1 Page(s)

Event

Description:

Loss of running LH pump Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using Computer Alarm response for point C1A1121 (LH Pressure).

Pertinent Alarms 1AD-11 1/2 600V NORM UNIT AUX PWR TROUBLE OAC Pt C1A1121 LH Pressure EXAMINER NOTE: Idle LH pump should automatically start at 1300 psig decreasing but is blocked. At 1100 psig, psig-, turbine/reactor will trip.

RO Manually starts LH pump 1B.

EXAMINER NOTE: If the crew does not start the idle pump in time, it will start the major. If he does start it in time to prevent a trip, then 2 control rods will drop into the core which requires a manual reactor triQ. trip.

END EVENT Page 14 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 7 7 Page(s)

Event

Description:

Rods H-8/M-12 drop, ATWS, loss of heat sink Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is the MAJOR event starting with a turbine trip on loss of LH pressure (OR per AP/1/A15500/014 (Control Rod Misalignment),

.Case 2 Dropped Control Rod if LH pump is started before the turbine trip).

1. Verify only one rod - DROPPED OR MISALIGNED.

1 RNO IF two or more rods are dropped OR misaligned by greater than 24 steps, THEN:

a. Manually trip Reactor.

b. GO TO EP/1/A/5000/E-O (Reactor TripOr Safety Injection)

T SRO Transition to EP/1/A/5000/E-O (Reactor Trip or Safety Injection).

ALL 1. Monitor Enclosure 1 (Foldout Page).

RO 2. Verify Reactor Trip:

• All rod bottom lights - LIT

• All reactor trip and bypass breakers -

• IIR amps - DECREASING.

RO 3. Perform the following:

a. Manually trip reactor.

b. IF reactor will not trip, THEN

c. OPEN concurrently:

• Implement EP/1/A/5000/F-O (Critical Safety Function Status Trees) .

• GO TO EP/1/A/5000/FR-S.1 (Response To Nuclear Power Generation/ATWS).

T SRO Transition to EP/1/A/5000/FR-S.1 (Response To Nuclear Power Generation/ATWS).

RO CAUTION NC pumps should NOT be tripped with reactor power greater than 5%

to prevent fuel damage.

1. Verify Reactor Trip:

• All rod bottom lights - LIT

• All reactor trip and bypass breakers - OPEN

• I/R amps - DECREASING.

RO 1RNO Perform the following:

a. Manually trip the reactor.

CT b. IF reactor will not trip, THEN manually insert rods.

RO 2. Verify Turbine Trip:

• All turbine stop valves - CLOSED BOP 3. Verify CA pumps are running as follows:

a. Motor driven CA pumps - ON.

b. 3 S/G N/R levels - GREATER THAN 11%.

BOP 3a RNO a. Manually start motor driven CA pump(s}.

pump(s).

BOP 3b. 3 S/G N/R levels - GREATER THAN 11%.

Page 15 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 7 7 Page(s)

Event

Description:

Rods H-8/M-12 drop, ATWS, loss of heat sink Time Position Applicant's Actions or Behavior BOP 4. Initiate emergency boration of NC System as follows:

a. Ensure at least one NV pump - ON.

b. Open 1NV-236B (Boric Acid To NV Pumps Suct).

c. Ensure both boric acid transfer pump switches - IN THE "ON" POSITION.

d. Verify emergency boration flow - GREATER THAN OR EQUAL TO 30 GPM.

e. Verify the following charging line isolation valves - OPEN:

• 1NV-312A (Chrg Line Cont Isol)

• 1NV-314B (Chrg Line Cont Isol).

f. Verify Pzr pressure - LESS THAN 2335 PSIG.

BOP 5. Verify the following Monitor Light Panel Group 5 St lights - LIT:

• 1/2

• 1/3

• 1/10

• H/11.

BOP 6. Verify SII status as follows:

a. "SAFETY INJECTION ACTUATED" status light (1SI-13) - LIT.

BOP 6a RNO Perform the following:

1) IF AT ANY TIME an SII signal exists OR occurs while in this procedure, THEN perform Step 6.b.

2) GO TO Step 7.

ALL 7. Verify the following trips have occurred:

a. Reactor Trip.

BOP a. Dispatch operator to open the following:

• Reactor trip breakers

• Reactor trip bypass breakers

• The following breakers for CRD MIG sets:

0 "MOTOR" Breaker 0 "GENERATOR" Breaker.

RO 7b. Turbine Trip.

RO 8. Verify the reactor is subcritical as follows:

a. All of the following conditions exist:

• PIR channels - LESS THAN 5%

• WIR NEUTRON POWER channels - LESS THAN 5%

• IIR SUR - NEGATIVE.

b. GO TO Step 17.

BOP 17. Ensure all malfunctioning NC pumps - STOPPED.

Page 16 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 7 7 Page(s)

Event

Description:

Rods H-8/M-12 drop, ATWS, loss of heat sink Time Position Applicant's Actions or Behavior BOP 18. Ensure adequate shutdown margin as follows:

a. Ensure the following signals - RESET:

1) Phase A Containment Isolations

2) KC NC NI NM St signals.

b. Obtain current NC boron concentration from Primary Chemistry.

c. WHEN current NC boron concentration is obtained, THEN perform shutdown margin calculation. REFER TO OP/O/A/61 00/006 (Reactivity Balance Calculation).

d. WHEN following conditions are satisfied, THEN stop NC System boration:

• Adequate shutdown margin is obtained

• Uncontrolled cooldown has been stopped.

EXAMINER NOTE: If HEAT SINK CSF is RED, then 4.4.G.1 (General Emergency) is correct, otherwise 4.4.5.1 (Site Area Emergency) is correct.

SRO 19. Determine required notifications:

REFER TO RP/O/A/5000/001 (Classification Of Emergency)

REFER TO RP/O/B/5000/013 (NRC Notification Requirements).

SRO 20. RETURN TO procedure and step in effect.

T SRO Transitions to EP/1/A/5000/E-0 and based on RED Path on Heat Sink, immediately transitions to EP/1/A/5000/FR-H.1 (Response to Loss of Secondary Heat Sink)

BOP 1. IF total feed flow is less than 450 GPM due to operator action, THEN RETURN TO procedure and step in effect.

BOP CAUTION IF a non-faulted S/G is available, THEN feed flow should only be established to non-faulted S/G(s) in subsequent steps.

2. Verify secondpry heat sink is required as follows:

a. NC pressure - GREATER THAN ANY NON-FAULTED S/G PRESSURE.

b. Any NC T-Hot - GREATER THAN 350°F.

ALL 3. Monitor Enclosure 1 (Foldout Page).

BOP 4. Verify at least one NV pump - AVAILABLE.

BOP 5. Verify bleed and feed is required as follows:

a. W/R level in at least 3 S/Gs - LESS THAN 24% (36% ACC).

ALL 5aRNO Perform the following:

1) Monitor bleed and feed initiation criteria. REFER TO Enclosure 1 (Foldout Page).

2) WHEN criteria is satisfied, THEN GO TO Step 18.

3) GO TO Step 6.

RO/BOP 6. Verify S/G inventory loss is minimized as follows:

a. Verify the following blowdown isolation valves on all S/Gs - CLOSED:

• Blowdown Containment Isolation Inside

• Blowdown Containment Isolation Outside

• Blowdown Containment Isolation Bypass.

b. All S/G sample isolation valves - CLOSED.

Page 17 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 7 7 Page(s)

Event

Description:

Rods H-8/M-12 drop, ATWS, loss of heat sink Time Position Applicant's Actions or Behavior BOP 7. Attempt to establish CA flow to at least one S/G as follows:

a. Verify the following annunciators - DARK.

• 1AD-5, H/4 "CACST LO LEVEL"

• 1AD-8, B/1 "UST LO LEVEL".

b. Verify the following CA suction valves - OPEN:

• 1CA-6 (CA Pmps Suct From CA CST)

• 1CA-4 (CA Pmps Suct From UST).

c. Verify proper CA pump status as follows:

• 1) Power to both motor driven CA pumps - AVAILABLE.

EXAMINER NOTE: Crew should acknowledge need to refer to AP/007, but continue in FR-H.1 at this time.

BOP 7c1 )RN01) Perform the following:

• IF the essential bus is de-energized, THEN restore power to the affected essential bus. REFER TO AP/1/A/55001007 (Loss of Normal Power).

• IF the essential bus is energized, THEN dispatch operator to determine cause of breaker failure.

BOP 7c 2) 1AD-5, F/3 "CAPT MECH OS TRIP" - DARK.

BOP 7c2) RNO 2) Perform the following:

a) Dispatch operator to reset the CAPT trip and throttle valve.

b) IF AT ANY TIME the CAPT trip and throttle valve is reset prior to reaching bleed and feed criteria, THEN perform Step 7.

c) GO TO Step 7.d.

BOP 7d. Ensure all CA isolation valves - OPEN.

e. Verify all CA flow control valves - OPEN

f. Start all available CA pumps.

g. Verify total CA flow - GREATER THAN 450 GPM.

BOP 7gRNO Perform the following:

1) IF any CA pump is on, THEN ...

2) IF no CA pumps can be started, THEN perform the following:

a) Dispatch operator and maintenance to CA pumps to attempt to restore one CA pump to service. REFER TO EM/1/A/52001007 (Troubleshooting Cause For CA Pump(s) Failing to Start).

b) IF AT ANY TIME a CA pump is restored prior to meeting bleed and feed initiation criteria, THEN perform Step 7.

c) GO TO Step 8.

BOP 8. Stop all NC pumps.

BOP 9. Verify CM System is in service as follows:

• Hotwell pump(s) - ON

• Condensate Booster pump(s) - ON.

Page 18 of 21

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 2 Event No. 7 7 Page(s)

Event

Description:

Rods H-8/M-12 drop, ATWS, loss of heat sink Time Position Applicant's Actions or Behavior RO 10. Reset Feedwater Isolation as follows:

a. Verify the following annunciators - DARK:

• 1AD-8, D/7 "INNER DOGHOUSE TRAIN A LEVEL HI"

• 1AD-8, El7 "INNER DOGHOUSE TRAIN B LEVEL HI"

• 1AD-8, D/8 "OUTER DOGHOUSE TRAIN A LEVEL HI"

• 1AD-8, E/8 "OUTER DOGHOUSE TRAIN B LEVEL HI".

b. Verify SII - HAS PREVIOUSLY ACTUATED.

RO 10b RNO b. Perform the following:

1) Reset Feedwater Isolation.

2) IF Feedwater Isolation will not reset, THEN notify IAE to bypass Feedwater Isolation. REFER TO EM/1/A/52001009 (Bypassing Feedwater Isolation).

3) GO TO Step 10.e.

EXAMINER NOTE: Crew may return to this step to reset CF Isolation numerous times while in this procedure.

ALL 10e. IF AT ANY TIME a subsequent Feedwater Isolation occurs, THEN RETURN TO Step 10.

RO 11. Attempt to establish CF flow to at least one SIG as follows:

a. Verify CM System is in service.

b. Place the following valves in manual and closed:

• All CF control valves

• All CF bypass control valves.

c. Ensure at least one of the following valves - OPEN:

• 1CF-1 0 (1 A CF Pump Disch Isol) (TB-579, 1E-21 )

• 1CF-17 (1 B CF Pump Disch Isol) (TB-579, 1E-20).

d. Verify at least one CF pump - AVAILABLE TO BE STARTED EXAMINER NOTE: Due to loss of vacuum, they should assume the CF pumps are not capable of starting.

BOP 11dRNO. IF both CF pumps are known to be incapable of starting, THEN GO TO Step 13.

EXAMINER NOTE: 1NV-37 A will not open and the RNO will be used to depressurize.

Page 19 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. - 7 Page(s)

Event

Description:

Rods H-8/M-12 drop, A TWS, loss of heat sink Time Position Applicant's Actions or Behavior BOP 13. Depressurize NC System as follows:

a. Verify letdown - IN SERVICE.

b. Verify power to 1NV-37A (NV Supply To Pzr Aux Spray) - AVAILABLE.

c. Depressurize NC System to less than 1905 PSIG using NV aux spray as follows:

1) Open the following valves:

• 1NV-312A (Chrg Line Cont Isol)

• 1NV-314B (Chrg Line Cont Isol).

2) Ensure the following valves - CLOSED:

• 1NC-27 (pzr Spray Ctrl Frm Loop A)

• 1NC-29 (pzr Spray' Ctrl Frm Loop B)

• 1NV-39A (NV Supply To Loop D Isol)

• 1NV-32B (NV Supply To Loop A Isol).

3) Maintain charging flow less than 180 GPM.

4) Throttle 1NV-37A (NV Supply To Pzr Aux Spray) and charging flow as required.

BOP 13cRNO Depressurize NC System to less than 1905 PSIG using one Pzr PORV.

BOP 13d. Maintain NC pressure less than 1905 PSIG.

e. IF AT ANY TIME letdown is lost AND a Pzr PORV is available, THEN:

1) Close 1NV-37A (NV Supply To Pzr Aux Spray).

2) Open one of the following valves:

• 1NV-39A (NV Supply To Loop D Isol)

OR

• 1NV-32B (NV Supply To Loop A Isol).

3) Depressurize NC System to less than 1905 PSIG using one Pzr PORV.

EXAMINER NOTE: This permissive will likely not be lit at this time, however, this step will be performed later.

BOP 14. Block SII as follows:

a. Verify "P-11 PZR SII BLOCK PERMISSIVE" status light (1SI-18) - LIT.

b. Depress the "BLOCK" push buttons for the following signals:

• ECCS steam pressure

• ECCS Pzr pressure.

c. Verify the following status lights (1 SI-13) - LIT:

• Main Steam Isol

• Pzr low pressure S/I.

d. IF AT ANY TIME conditions degrade while in this procedure, THEN manual SII actuation will be required.

BOP 14aRNO. Perform the following:

1) WHEN "P-11 PZR SII BLOCK PERMISSIVE" status light (1SI-18) is lit, THEN perform Steps 14 through 16.

2) GO TO Step 17.

BOP 15. Attempt to establish feed flow from CM as follows:

a. Verify Steps 19 through 32 - HAVE BEEN PREVIOUSLY PERFORMED.

Page 20 of 21

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 2 Event No. 7 7 Page(s)

Event

Description:

Rods H-S/M-12 drop, A TWS, loss of heat sink Time Position Applicant's Actions or Behavior RO 15aRNO. Perform the following:

1) Close MSIV on 2 S/Gs not to be depressurized.

2) GO TO Step 15.c.

RO c. Verify the condenser is available as follows:

• "C-9 COND AVAILABLE FOR STM DUMP" status light (1SI-1S) - LIT

• MSIV on S/G(s) to be depressurized - OPEN RO 15c RNO Perform the following:

1) Dump steam from S/G(s) selected to be depressurized using S/G PORVs at maximum rate.

2) IF no S/G PORV can be operated from the control room, THEN ...

3) IF no S/G PORV can be opened, THEN ...

4) GO TO Step 15.g.

RO 15 g. WHEN S/G pressure is less than 505 PSIG, THEN stabilize S/G pressure less than 505 PSIG.

BOP 15h. Verify Steps 19 through 32 - HAVE BEEN PREVIOUSLY PERFORMED.

SRO 15hRNO. GO TO Step 15.j.

eT RO 15j. Verify CF Isolation signal- RESET OR BYPASSED.

k. Open the CF to CA valve on the S/G(s) to be fed:

• 1CA-149 (S/G 1A CF Byp To CA Nozzle)

• 1CA-150 (S/G 1B CF Byp To CA Nozzle)

• 1CA-151 (S/G 1C CF Byp To CA Nozzle)

• 1CA-152 (S/G 1D CF Byp To CA Nozzle).

I. Throttle open CF control valve or CF bypass control valve for S/G(s) to be fed.

m. Verify feedwater flow to depressurized S/G(s) - INDICATING FLOW.

RO 15m RNO Perform the following:

1) IF depressurized S/G pressure is less than 505 PSIG, THEN GO TO Step 17.

2) RETURN TO Step 15.c.

EXAMINER NOTE: This is a procedure loop until pressure is low enough to get flow to the S/Gs from the condensate booster pumps. Scenario can be stopped when flow is indicated to the depressurized S/Gs via the condensate system.

END EVENT Page 21 of 21

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 2008 NRC EXAMINATION Facility: Catawba Nuclear Station Scenario No.: 3 Op-Test No.:

SNAP 163 Examiners: Operators:

Initial Conditions:

• 75% power

• EFPD =450 days

• Boron concentration is 215 ppm

• 1A CA pump out of service for PMs - expected back in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

• 1A NI pump out of service for PMs - expected back in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

• Thunderstorms are in the area.

Turnover:

• Increase power to 90% at 1O%/hr OP/1/A/61 00/003 (Controlling Procedure for Unit Operation)

Event Malf. No. Event Event No. Type* Description 1 RO R Power increase to 90% at 10%/hr 2 BOP N Dilution for power increase 3 RO C Generator breaker 1A opens, auto runback fails 4 BOP C Respond to EMF33 failed high, 1BB-24 (1 C S/G) fails to close SRO TS 5 RO I 1B S/G level program fails low 6 BOP C 1ETA normal feeder opens, restore charging SRO TS 7 ALL M NC PORV fails open - medium break LOCA Additional failures NI pump 1B fails to start in auto VA Fans not aligned as required on S/I

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

SIMULATOR SETUP Reset to any 75% snap.

Ensure Tavg is slightly hot for power increase Ensure 1A NV in service, 1B RN in service and B train KC in service Ensure VC/yC on unit 2 power and B train in service Roll charts Place red tag covers on 1A CA pump and 1A NI pump OP/1/A/61 00/003 (Controlling Procedure For Unit Operation), Enclosure 4.1 completed through step 2.51 (revision 102)

OP/1/B/6300/001 (Turbine Generator), Enclosure 4.2 completed through step 2.1.1.9 (revision 87)

MALFUNCTIONS, REMOTES, and OVERRIDES Malfunction # Description Value Event Ramp Delay Trigger MAL-EHC003D TURBINE GBKRS AUTO BLOCK RUNBACK FAILURE VLV-NC006F NC33A PZR PORV ISOL VLV 1 FAIL TO POSITION MAL-NI001B NI PUMP B FAILURE AUTO MAL-ISE011 B AUX BLDG FANS FAIL TO AUTO STOP VLV-NC007F NC34A PZR PORV FAIL TO 1 6 POSITION MAL-SGL004B S/G B PROGRAM LEVEL 0 4 340 ALLOW FAILURE TRACKING*

LOA-CA017 RACKOUT CA PUMP 1A RACK-OUT LOA-NI003 RACKOUT NI PMP 1A RACK-OUT LOA-EMF029 1 EMF33 BACKGROUND 1.0E7 3 RADIATION VLV-BB003 BB24- S/G C BLOWDOWN CTRL VLV FAIL AUTO ACTIONS OVR-EP007B GEN BKR 1A TRIP ENABLE PB ON 2 OVR-EP007C GEN BKR 1A TRIP PB ON 2 OVR-EP029D ETA NORM FDR FRM ATC ON 5 TRIP PB MAL-DG003A DIG 1A TRIPS ON TOTAL 5 70 LOSS OF LUBE OIL MAL-NC013A NC COLD LEG A LEAK 0.75 11 EVENT TRIGGERS (other than manual)

Event Trigger I Description 11 PNC 5130 > 95

CRITICAL TASKS E-O J - Establish flow from at least one intermediate-head ECCS pump before transition out of EP/1/N5000/E-0.

E-1 C - Trip all RCPs so that CET temperatures do not become superheated when forced circulation of the RCS stops.

REFERENCES OP/1/N61 001003 (Controlling Procedure for Unit Operation), Enclosure 4.1 revision 102 OP/1/B/63001001 (Turbine Generator), Enclosure 4.2 revision 087 OP/1/N61501009 (Boron Concentration Control) revision 065 AP/1/N55001003 (Load Rejection) revision 034 AP/1/N55001007 (Loss of Normal Power) revision 056 AP/1/N55001010 (Reactor Coolant Leak) revision 048 AP/1/N55001011 (Pressurizer Pressure Anomalies) revision 019 AP/1/N55001012 (Loss of Charging or Letdown) revision 025 EP/1/N5000/E-0 (Reactor Trip or Safety Injection) revision 031 EP/1/N5000/E-1 (Loss of Reactor or Secondary Coolant) revision 023 EP/1/N5000/ES-1.2 (Post LOCA Cooldown and Depressurization) revision 023 NOTES AND INSTRUCTIONS NOTE: The following steps are GUIDELINES. The NRC lead examiner will direct timing of events unless otherwise noted.

CAUTION: SIMULATOR EVENT NUMBERS DO NOT CURRENTLY CORRESPOND TO SCENARIO EVENT NUMBERS.

NOTE: Events 1 and 2 are performed simultaneously.

Event 1 - Power increase to 90% at 10%/hr This event will be entered once the crew has taken turnover and evaluated plant conditions.

When 6-8 MW have been added and dilution is complete per Event 2, the next event can be inserted.

Event 2 - Dilution for power increase This event will be entered once the crew has taken turnover and evaluated plant conditions.

When 6-8 MW have been added and dilution is complete per Event 2, the next event can be inserted.

Event 3 - Generator breaker 1A opens, auto runback fails When the runback target has been reached and the unit is approximately stable, the next event can be inserted.

Event 4 - Respond to EMF33 failed high, 188-24 (1C S/G) fails to close I SRO Technical Specification

NOTE: When candidates call about EMF-33 actions to frisk cation columns, after 5 minutes report that there is no activity on the cation columns and that you investigate with SP~C to checkout EMF-33.

NOTE: 10 minutes later, report that the detector appears to be failed in the alarm state and that cation columns continue to show no activity.

When 1BB-24 is closed and Radiation Protection has informed the crew that the EMF reading appears to be invalid per AP/1/A/5500/01 0 (assuming the crew asked for cation columns to be frisked) and the SRO has completed consulting Technical Specifications, the next event can be inserted.

Event 5 - 1 B S/G level program fails low When the crew has placed the 1B S/G control in manual and taken steps to stabilize and bring S/G 1B level back to program, the next event can be entered.

Event 6 1 ETA normal feeder opens, restore charging I SRO Technical Specification NOTE: When called by CR to load shed 1ETA, run schedule on A train 4160V simulator graphic screen.

NOTE: The next event should be inserted before letdown restoration has begun since this is part of another scenario.

When initial AP/1/A/5500/007 actions have been completed, charging restored to service, and the SRO has completed consulting Technical Specifications, the next event can be inserted.

Event 7 - NC PORV fails open - medium break LOCA Additional failures NI pump 1B fails to start in auto, VA Fans not aligned as required on S/I TERMINATE WHEN CREW TRANSITIONS TO EP/11A15000/ES*1.2 (Post LOCA Cooldown and Depressurization).

If this is the last use of this scenario for the day, remove red tag covers from 1A CA pump and 1A NI pump.

TURNOVER INFORMATION NEEDED OP/1/A/61 00/003 (Controlling Procedure for Unit Operation), revision 102 Enclosure 4.1 completed through step 2.51 OP/1/B/6300/001 (Turbine Generator), revision 087 Enclosure 4.2 completed through step 2.1.1.9 OP/1/A/6150/009 (Boron Concentration Control) revision 065 Boration /Dilution Plan ROD Book Data Book COLR Pre-job briefs as required

CREW TURNOVER INFORMATION Initial Conditions:

• 75% power

• EFPD =450 days

• Boron concentration is 215 ppm

• 1A CA pump out of service for PMs - expected back in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

• 1A NI pump out of service for PMs - expected back in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

• Thunderstorms are in the area.

Turnover:

• Increase power at 10% per hour to 90% per OP/1/A/61 001003 (Controlling Procedure for Unit Operation).

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 1 1 Page(s)

Event

Description:

Power increase to 90% at 10%/hr Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a REACTIVITY event using OP/1/B/6300/001 (Turbine Generator) and NORMAL event using OP/1/A16200/001 (Chemical and Volume Control System)

EXAMINER NOTE: Event 2 is the dilution for the power change and the crew may choose to dilute prior to starting the power increase.

RO CAUTION:

1. Until it is recognized that the first stage shell metal temperature change rate stays below the allowable limit (150°F/hr), the following loading rate shall NOT be exceeded:

• 1/2%/min - First Stage Inner Shell Temperature (1MC3 or OAC point C1A1140 (Turbine Lower Inner Shell Temp)) < 3500F

• 1%/min - First Stage Inner Shell Temperature (1 MC3 or OAC point C1A1140 (Turbine Lower Inner Shell Temp)) > 3500F

2. Normal steady-state load changes shall be made without ex~eeding the limits shown on Enclosure 4.7 (Generator Operating Limits) and in the Unit One OAe Databook "Recommended Startup and Loading Curves".

3. Unit One Reactor Operating Data, Section 2.4 shall be referred to for allowable ramp rates. A "LOAD RATE" > 6.2 MW/MIN shall NOT be used during normal load changes.

RO 2.1.2 Increase turbine generator load by performing the following:

2.1.2.1 Select "LOAD RATE" and verify it illuminates.

2.1.2.2 Input the desired load rate.

2.1.2.3 Select "ENTER" or "OK" and verify "LOAD RATE" goes dark.

2.1.2.4 Select "TARGET" and verify it illuminates.

2.1.2.5 Input the desired load target.

2.1.2.6 Select "ENTER" and verify" TARGET" goes dark.

2.1.2.7 Verify new load target appears on Target Display.

2.1.2.8 Select "GO" and verify it illuminates to start load increase.

2.1.2.9 S/G blowdown changes shall be coordinated with Secondary Chemistry.

RO CAUTION: The load, hydrogen pressure and power factor limits per the Unit One Revised Data Book Figure 43 shall NOT be exceeded.

END EVENT Page 1 of 28

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 3 Event No. 2 2 Page(s)

Event

Description:

Dilution for power increase Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a NORMAL event using OP/1/A16150/009 (Boron Concentration Control.

BOP 1. INITIAL CONDITIONS 1.1 Review the Limits and Precautions.

1.2 IF in Mode 1 or 2 AND dilution is being performed for normal temperature control, ensure R3 reactivity management controls established per SOMP 01-02 (Reactivity Management). (RM.)

1.3 IF in Mode 1 or 2 AND dilution is being performed as part of a power change, ensure R2 reactivity management controls established per SOMP 01-02 (Reactivity Management). (RM.)

1.4 Verify the NV System is in operation per OPf1fA/6200f001 (Chemical and Volume Control System).

1.5 Verify sufficient RHT volume is available to receive the reactor coolant displaced during the planned dilution operation.

1.6 Verify the NB System is in operation per OPf1fA/6200f012 (Reactor Makeup Water).

1.7 Ensure a minimum of one NC pump remains in operation throughout the evolution.

BOP NOTE: This enclosure will affect reactivity of the core and is therefore designated important to Reactivity Management per the guidelines of NSD 304 (Reactivity Management). (RM.)

2.1 Ensure valves are aligned per Enclosure 4.8 (Valve Checklist).

BOP 2.2 Ensure the following valve control switches in "AUTO":

• 1NV-242A (RMWST To BfA Blender Ctrl)

• 1NV-181A (BfA Blender Otlt To VCT)

BOP 2.3 Ensure 1NV-242A (RMWST To BfA Blender Ctrl) controller in "AUTO".

BOP 2.4 Ensure at least one reactor makeup water pump is in "AUTO" or "ON".

BOP 2.5 Adjust the total makeup batch counter to the desired volume of reactor makeup water to be added. (RM.)

BOP 2.6 Place the "NC MAKEUP MODE SELECT" switch to the "DILUTE" position.

BOP NOTE: High letdown flow rates result in increased backpressure on the letdown line. If letdown flow is;::: 90 gpm, it may be desirable to reduce the dilution flow rate to 80 gpm to avoid the Total Makeup Flow Deviation alarm and associated automatic actions.

2.7 Adjust the controller for 1NV-242A (RMWST To BfA Blender Ctrl) to the desired flow.

EXAMINER NOTE: Step 2.8 should NOT be required.

BOP 2.8 IF at any time it is desired to divert letdown to the RHT ...

Page 2 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 2 2 Page(s)

Event

Description:

Dilution for power increase Time Position Applicant's Actions or Behavior BOP NOTE: If necessary, dilution can be manually secured at any time by placing the "NC MAKEUP CONTROL" switch to the "STOP" position.

2.9 Place the "NC MAKEUP CONTROL" switch in the "START" position. (RM.)

BOP 2.10 Verify the following valves open:

• 1NV-242A (RMWST To BfA Blender Ctrl)

• 1NV-181A (BfA Blender Otlt To VCT)

BOP 2.11 IF in "AUTO", verify the reactor makeup water pump starts.

BOP 2.12 WHEN the desired volume of reactor makeup water is reached on the total makeup batch counter, ensure the following valves close. (RM.)

• 1NV-242A (RMWST To BfA Blender Ctrl)

• 1NV-181A (BfA Blender Otlt To VCT)

BOP 2.13 Ensure the controller for 1NV-242A (RMWST To BfA Blender Ctrl) is set to 5.62.

EXAMINER NOTE: 2.14.1 should be N/A.

BOP 2.14 IF automatic makeup is desired, perform one of the following:

2.14.1 IF it is desired to change the blender outlet boron concentration ...

OR 2.14.2 IF makeup at the previous concentration is acceptable AND the system was previously aligned per Enclosure 4.1 (Automatic Makeup), perform the following:

2.14.2.1 Place the "NC MAKEUP MODE SELECT" switch in "AUTO".

2.14.2.2 Place the "NC MAKEUP CONTROL" switch to the "START" position. (RM.)

END EVENT Page 3 of 28

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 3 Event No. 3 6 Page(s)

Event

Description:

Generator breaker 1A opens, auto runback fails Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using AP/1/A15500/003 (Load Rejection).

Pertinent Alarms 1AO-11 F/1 GEN BKR B OVERCURRENT AP/1/A15000/003 (Load Rejection) Case I (Switchyard Available) steps RO 1. Verify turbine load - DECREASING IN AUTOMATIC.

RO 1RNO Perform the following:

a. Select "MANUAL" on turbine control panel.

b. Depress "CONTROL VALVES LOWER" pushbutton and reduce turbine load as required.

RO 2. Verify proper reactor response:

• Control rods - IN "AUTO" AND STEPPING IN

• P/R neutron flux - DECREASING.

RO 3. Verify proper steam dump operation as follows:

a. Verify T-Ref instrumentation - AVAILABLE.

b. "C-9 COND AVAILABLE FOR STM DUMP" status light (1SI-18) - LIT.

c. Verify the following:

• "C-7A LOSS OF LOAD INTLK COND DUMP" status light (1SI-18) - LIT.

• Steam dump valves - MODULATING.

d. T-Avg - DECREASING TO T-REF.

BOP 4. Verify Pzr PORV and Pzr spray valve status as follows:

a. All Pzr PORVs - CLOSED.

b. Normal Pzr spray valves - CLOSED.

BOP 5. Verify proper CM System operation as follows:

a. WHEN reactor power is less than 75% THEN ensure both C-htr drain pumps -

OFF.

b. Verify reactor power - GREATER THAN 56% PRIOR TO THE EVENT.

EXAMINER NOTE: They may start hotwe" and condensate booster pumps but it should be optional in this case and based on judgment.

BOP 5c. Verify standby hotwell pump(s) - ON.

BOP 5cRNO. Manually start standby hotwell pump(s) as necessary.

BOP 5d. Verify standby condensate booster pump(s) - ON.

BOP 5dRNO. Manually start standby condensate booster pump(s) as necessary.

BOP 6. Verify the following generator alarms

• 1AD-11, C/1 "GEN BKR A OVERCURRENT"

• 1AD-11, F/1 "GEN BKR B OVERCURRENT".

RO 7. Verify S/G levels are adequate as follows:

• All S/G low level alert alarms (1AD-4) - DARK

• All S/G low CF flow alarms (1AD-4) - DARK.

Page 4 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 3 6 Page(s)

Event

Description:

Generator breaker 1A opens, auto runback fails Time Position Applicant's Actions or Behavior RO 7RNO Perform the following:

a. Ensure feedwater regulating valves - MODULATING TO CONTROL S/G LEVELS AT PROGRAM SETPOINT.

b. IF any S/G(s) N/R level is decreasing in an uncontrolled manner, THEN:

1) Trip reactor.

2) GO TO EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection).

RO 8. Verify reactor power - GREATER THAN 20%.

RO 9. IF AT ANY TIME reactor power is less than or equal to 20%, THEN perform Step 8 RNO.

BOP 10. Verify AS header pressure - GREATER THAN OR EQUAL TO 140 PSIG.

RO 11. Adjust 1TL-4 (Stm Seal Reg Byp) as necessary to maintain steam seal pressure between 4 PSIG - 6 PSIG.

RO 12. Monitor Enclosure 3 (Rod Insertion Limit Boration).

EXAMINER NOTE: These steps are listed after step 28 of this AP.

RO 13. Verify reactor power - LESS THAN 30%.

RO 13RNO Perform the following:

a. IF the run back target load is less than 30%, THEN: ...

b. WHEN the appropriate runback target load is reached, THEN:

1) Stabilize unit at current power level.

2) Maintain control rods above insertion limits.

3) Adjust the following as required to maintain T-Avg within 1°F of T-Ref:

• Turbine load

• Control rods

• Boron concentration.

c. GO TO Step 15.

BOP 15. Verify the following PCBs - CLOSED:

• Generator breaker 1A

• Generator breaker 1B

• PCB 14

• PCB 15

• PCB 17

• PCB 18.

BOP NOTE When separated from the grid the turbine reverts to speed control.

15 RNO Perform the following:

a. IF both generator PCBs are open, THEN ...

b. IF the turbine generator is separated from the grid, THEN ...

c. IF load rejection caused by loss of main busline 1A or 1B, THEN ...

RO 16. Adjust power factor as necessary. REFER TO Unit 1 Revised Data Book Figure 43.

EXAMINER NOTE: In the following step, the runback target referred to is approximately 48% power Page 5 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 3 6 Page(s)

Event

Description:

Generator breaker 1A opens, auto runback fails Time Position Applicant's Actions or Behavior RO 17. WHEN the appropriate runback target load is reached, THEN:

• Stabilize unit at appropriate power level.

• Maintain control rods above insertion limits.

• Adjust the following as required to maintain T-Avg within 1°F of T-Ref:

0 Turbine load 0 Control rods 0 Boron concentration RO 18. Notify System Operating Center (SOC) using the red dispatcher telephone of current unit status.

ALL 19. Determine and correct cause of load rejection.

BOP 20. Shut down unnecessary plant equipment as follows:

a. Restore CM and CF as follows:

1) Verify C-htr drain pumps - ON.

BOP 20a1)RNO 1) WHEN time and manpower permit, THEN complete the shutdown of the C-htr drain pumps. REFER TO OP/1/B/62501004 (Feedwater Heater Vents, Drains and Bleed System).

BOP 20a 2) Verify both CF Pumps - IN SERVICE.

3) Shutdown one CF pump as necessary. REFE~ TO OP/11A162501001 (Condensate and Feedwater System).

4) Shutdown excess Condensate Booster Pumps. REFER TO OP/11A162501001 (Condensate and Feedwater System).

5) Shutdown excess Hotwell Pumps. REFER TO OP/11A162501001 (Condensate and Feedwater System).

b. RC pump(s) and cooling tower fans. REFER TO OP/1/B/64001001A (Condenser Circulating Water System).

RO 21. Reset steam dump valves as follows:

a. Verify reactor power - STABLE.

b. Verify steam dump valves - IN "T-AVG" MODE.

c. Verify steam dump valves - CLOSED.

d. Reset steam dump valves.

e. Verify the following status lights (1 SI-18) - DARK:

• "C-7A LOSS OF LOADINTLK COND DUMP"

• "C-7B LOSS OF LOAD INTLK ATMOS DUMP".

f. IF "T-AVG" mode of operation is available, THEN ensure steam dump valves in "T-AVG" mode.

g. Verify "STM DUMP CTRL" - IN AUTOMATIC.

RO 22. Verify reactor power - GREATER THAN 15%.

BOP 23. Verify CA pumps - OFF.

RO 24. Verify reactor power change - GREATER THAN OR EQUAL TO 15% IN A 1 HOUR PERIOD.

Page 6 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 3 6 Page(s)

Event

Description:

Generator breaker 1A opens, auto runback fails Time Position Applicant's Actions or Behavior BOP 25. Notify the following sections to take appropriate samples:

• Radiation Protection to sample and analyze gaseous effluents. REFER TO Selected Licensee Commitments Manual, Section 16.11-6.

• Primary Chemistry to sample for isotopic analysis of iodine. REFER TO Tech Specs 3.4.16 (Sample must be taken between 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following last power change greater than or equal to 15% rated thermal power within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period).

EXAMINER NOTE: No Technical Specifications apply.

SRO 26. Ensure compliance with appropriate Tech Specs:

• 3.1.1 (Shutdown Margin (SDM))

• 3.1.6 (Control Bank Insertion Limits)

• 3.8.1 (AC Sources - Operating).

BOP 27. Notify Reactor Group Engineer of occurrence.

SRO 28. Determine long term plant status. RETURN TO OP/1/A/61 00/003 (Controlling Procedure For Unit Operation).

AP/1/A15500/003, Enclosure 3 steps BOP 1 IF the control rods cannot be maintained above the rod insertion limits, THEN:

a. Stop any dilutions in progress.

CAUTION Failure to initiate boration within one hour of exceeding rod insertion limits may violate Tech Spec 3.1.6.

NOTE OAC point C1 L4409 (Ctrl Bank Tech Spec Insertion Lmt Reached) and RO.D Book (Section 2.2) provide rod insertion limit indication.

b. Borate NC system as required, to restore rods above insertion limits.

c. Ensure compliance with Tech Spec 3.1.6 (Control Bank Insertion Limits).

EXAMINER NOTE: If rods are below 10-10 insertion limits, the following steps will be used to borate the rods back out.

OP/1/A16150/009 (Boron Concentration Control) Enclosure 4.2 (Boration) steps BOP 1.1 Review the Limits and Precautions.

BOP 1.2 IF in Mode 1 or 2 AND boration is being performed for normal temperature control, ensure R3 reactivity management controls established per SOMP 01-02 (Reactivity Management). (RM.)

BOP 1.3 IF in Mode 1 or 2 AND boration is being performed as part of a power change, ensure R2 reactivity management controls established per SOMP 01-02 Reactivity Management). (RM.)

Manag_ement}. (RMJ BOP 1.4 Verify the NV System is in operation per OP/1/A/6200/001 (Chemical and Volume Control System).

BOP 1.5 Verify sufficient RHT volume is available to receive the reactor coolant displaced during the planned boration operation.

Page 7 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 3 6 Page(s)

Event

Description:

Generator breaker 1A opens, auto run back fails Time Position Applicant's Actions or Behavior BOP NOTE: This enclosure will affect reactivity of the core and is therefore designated important to Reactivity Management per the guidelines of NSD 304 (Reactivity Management). (RM.)

BOP 2.1 Ensure valves are aligned per Enclosure 4.8 (Valve Checklist).

BOP 2.2 Ensure the following valve control switches in "AUTO":

1NV-238A (BfA Xfer Pmp To Blender Ctrl) 1NV-186A (BfA Blender Otlt To VCT Otlt)

BOP 2.3 Ensure 1NV-238A (BfA Xfer Pmp To Blender Ctrl) controller in "AUTO".

BOP 2.4 Ensure at least one boric acid transfer pump is in "AUTO" or "ON".

BOP 2.5 Adjust the boric acid batch counter to the desired volume of boric acid to be added. (RM.)

BOP 2.6 IF the blender is set up for automatic makeup per Enclosure 4.1 (Automatic Makeup), record the setting of the controller for 1NV-238A (BfA Xfer Pmp To Blender Ctrl).

BOP 2.7 Place the "NC MAKEUP MODE SELECT" switch in "BORATE".

BOP NOTE: Boric Acid flow rates> 32 gpm (controller pot setting of 8) may result in a boric acid flow deviation annunciator.

BOP 2.8 Adjust the controller for 1NV-238A (BfA Xfer Pmp To Blender Ctrl) to the desired flow.

BOP NOTE: If necessary, boration can be manually secured at any time by placing the "NC MAKEUP CONTROL" switch to the "STOP" position.

BOP 2.9 Place the "NC MAKEUP CONTROL" switch to the "START" position. (RM.)

BOP 2.10 Verify the following valves open:

1NV-238A (BfA Xfer Pmp To Blender Ctrl) 1NV-186A (BfA Blender Otlt To VCT Otlt)

BOP 2.11 IF in "AUTO", verify the boric acid transfer pump starts.

BOP NOTE: The total makeup flow totalizer is inaccurate at low flow rates.

BOP 2.12 Verify proper flow by observing the boric acid flow totalizer. {PIP 96-0137}

BOP 2.13 WHEN the desired volume of boric acid is reached on the boric acid batch counter, ensure the following valves close: (RM.)

1NV-238A (BfA Xfer Pmp To Blender Ctrl) 1NV-186A (BfA Blender Otlt To VCT Otlt)

BOP NOTE: If additional borations will be performed over the course of the shift, flushing the makeup line is NOT recommended.

2.14 IF desired, flush the makeup line as follows: ...

Page 8 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 3 6 Page(s)

Event

Description:

Generator breaker 1A opens, auto runback fails Time Position Applicant's Actions or Behavior BOP 2.15 IF automatic makeup is desired, perform one of the following:

2.15.1 IF it is desired to change the blender outlet boron concentration, refer to Enclosure 4.1 (Automatic Makeup).

OR 2.15.2 IF makeup at the previous concentration is acceptable AND the system was previously aligned per Enclosure 4.1 (Automatic Makeup), perform the following:

2.15.2.1 Ensure the controller for 1NV-238A (BfA Xfer Pmp To Blender Ctrl) is set to the value recorded in Step 2.6. (R.M.)

2.15.2.2 Place the "NC MAKEUP MODE SELECT" switch in "AUTO".

2.15.2.3 Place the "NC MAKEUP CONTROL" switch to the "START" position. (R.M.)

END EVENT Page 9 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 4 5 Page(s)

Event

Description:

Respond to EMF33 failed high, 1BB-24 (1 C S/G) fails to close SRO Technical Specification Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using OP/1/B/61 00/01 OX (Annunciator Response for Radiation Monitoring PaneI1RAD-1 (B/1) and an SRO Tech Spec event.

Pertinent Alarms 1RAD-1 B/1 1EMF-33 CSAE EXHAUST HI RAD ARP IMMEDIATE ACTIONS BOP 1. Verify that automatic actions occur by checking computer points C1A0968 through A0971 (S/G 1A through 1D Blowdown Flow)

The following valves close:

• 1NM-267 (S/G Smpl Hdr Rad Monitor Inlet Isol) (SRVOP)

• 1NM-269 (S/G A Smpl Hdr To Conv Smpl Sink) (CSP)

• 1NM-270 (S/G B Smpl Hdr To Conv Smpl Sink) (CSP)

• 1NM-271 (S/G C Smpl Hdr To Conv Smpl Sink) (CSP)

• 1NM-272 (S/G D Smpl Hdr To Conv Smpl Sink) (CSP)

• 1BB-27 (BB Tank Vent To Atmos) (1 MC4)

• 1BB-48 (BB Pumps Disch To TB Smp) (1MC4)

• 1BB-69 (S/G A Blowdown Flow Ctrl) (1 MC4)

• 1BB-73 (S/G B Blowdown Flow Ctrl) (1 MC4)

• 1BB-24(S/G C Blowdown Flow Ctrl) (1 MC4)

• 1BB-65 (S/G D Blowdown Flow Ctrl) (1 MC4 MC4 EXAMINER NOTE: All these valve controllers wil be set to zero. "S/G C BLDWN FLOW CTRL" (1 BB-24) valve is still open.

BOP 2. Ensure blowdown flow controllers are set to 0 flow:

"S/G A BLDWN FLOW CTRL" (1MC4)

"S/G B BLDWN FLOW CTRL" (1MC4)

"S/G C BLDWN FLOW CTRL" (1 MC4)

"S/G D BLDWN FLOW CTRL" (1 MC4)

BOP 3. Contact Primary Chemistry to ensure the following valves are closed:

• 1NM-267 (S/G Smpl Hdr Rad Monitor Inlet Isol) (Sample Room Valve Operating Panel, 1TBOX0132, located outside Unit 1 NM Lab)

• 1NM-269 (S/G A Smpl Hdr To Conv Smpl Sink) (CSP)

• 1NM-270 (S/G B Smpl Hdr To Conv Smpl Sink) (CSP)

• 1NM-271 (S/G C Smpl Hdr To Conv Smpl Sink) (CSP)

• 1NM-272 (S/G D Smpl Hdr To Conv Smpl Sink) (CSP)

BOP 4. Select "AUTO" on "UNIT 1 CSAE EXH" switch (1 MC13)

BOP 5. Verify "VA" indicating light is lit (1 MC13)

Page 1*0 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 4 5 Page(s)

Event

Description:

Respond to EMF33 failed high, 1BB-24 (1 C S/G) fails to close SRO Technical Specification Time Position Applicant's Actions or Behavior BOP 6. IF "VA" indicating light is dark, verify one of the following:

• ABFXF-1A on

• 1ABF-D-11 (AB-594, KK-54) open OR

• ABFXF-1 Bon

• 1ABF-D-4 (AB-594, KK-54) open ARP SUPPLEMENTAL ACTIONS SRO 1. Refer to AP/11A15500/1 0 (Reactor Coolant Leak).

BOP 2. Notify Secondary Chemistry and Radiation Protection of this alarm.

SRO 3. Refer to Tech Spec 3.4.13 for limitation on S/G tube leakage.

SRO 4. Refer to Tech Spec 3.7.17 for limits on secondary system activity levels BOP 5. Refer to OP/11A162501008 (Steam Generator Blowdown) for continued operation with high activity.

BOP NOTE: Operation with ZJ exhausting to the VA system filters should be minimized.

6. Notify RP to sample ZJ exhaust for Iodine.

BOP 7. IF Iodine is NOT detected in the ZJ exhaust, perform the following:

7.1 Return "UNIT 1 CSAE EXH" switch to "UNIT VENT".

7.2 Verify "UNIT VENT" indicating light is lit.

SRO SRO REFERS to AP/11A155001010 (Reactor Coolant Leak), Case 1 (Steam Generator Tube Leak).

EXAMINER NOTE: AP/1/A15500/010 is entered until it can be determined that EMF33 indications are false.

ALL 1. Monitor Enclosure 1 (Case I Steam Generator Tube Leak Foldout Page).

BOP 2. Verify Pzr level- STABLE OR INCREASING.

ALL 3. IF AT ANY TIME Pzr level decreases in an uncontrolled manner or cannot be maintained greater than 4%, THEN perform Step 2.

Page 11 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No.

-- 3

- Event No.

- 5 Page(s)

Event

Description:

Respond to EMF33 failed high, 1BB-24 (1 C S/G) fails to close SRO Technical Specification Time Position Applicant's Actions or Behavior ALL NOTE In subsequent steps the term "affected S/G" is a S/G with primary to secondary leakage.

4. Identify the affected S/G(s) as follows:

• Notify RP to frisk all cation columns.

OR

• Any S/G N/R level-INCREASING IN AN UNCONTROLLED MANNER..

OR NOTE The S/G Leakage EMFs are highly sensitive which may cause the EMFs located on the adjacent steamline to be increasing or in alarm.

• Verify any of the following S/G leakage EMF indication(s) - INCREASING OR IN ALARM:

o 1EMF-71 (S/G A Leakage) o 1EMF-72 (S/G B Leakage) o 1 EMF-73 (S/G C Leakage) o 1EMF-74 (S/G D Leakage).

OR

• Verify any of the following S/G steamline EMF indication(s)-

INCREASING OR IN ALARM:

o 1EMF-26 (Steamline 1A) o 1EMF-27 (Steamline 1B) o 1EMF-28 (Steamline 1C) o 1EMF-29 (Steamline 1D).

OR

• Verify CF flow - LOWER TO ANY S/G AS COMPARED TO OTHERS.

OR

• Notify Secondary Chemistry to determine affected S/G by sampling.

BOP 5. Verify VCT level able to be maintained by normal makeup as follows:

a. One of the following conditions exists:

• S/G tube leak is less than 90 gpm.

OR

• Automatic makeup stabilizes or increases VCT level.

OR

• Manual makeup stabilizes or increases VCT level.

b. IF AT ANY TIME the following conditions exist:

• 1AD-7, 1/1 "VCT LO LVL" alarm is lit AND

• Reactor trip breakers are closed.

THEN perform Step 5.a RNO.

Page 12 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. -- 3- 4-Event No. - - 5 Page(s)

Event

Description:

Respond to EMF33 failed high, 1 BB-24 (1 C S/G) fails to close SRO Technical Specification Time Position Applicant's Actions or Behavior BOP 6. Minimize Secondary contamination as follows:

a. Remove CM polishing demineralizers from service as follows:

1) Ensure "POLSH DEMIN BYP CTRL" - PLACED IN MANUAL.

2) Ensure "POLSH DEMIN BYP CTRL" - OPEN.

3) Notify Secondary Chemistry CM polishing demineralizers have been bypassed.

b. Align auxiliary systems to minimize secondary side contamination as follows:

1) Transfer turbine steam supply to AS as follows:

a) Open 1TL-8 (Aux Strh To Stm Seal Reg).

b) Close 1TL-2 (Main Stm To Stm Seal Reg).

2) Dispatch operator(s) to align auxiliary systems. REFER TO Enclosure 5 (Auxiliary System Alignment).

c. Stop any transfer of water between both Unit's CSTs.

EXAMINER NOTE: At this time RP will call back and report no activity noted on any cation columns.

ALL 7. Determine S/G leak rate by any of the following methods:

• Monitor the following computer points:

o C1P0187 (Estimated Total Pri To Sec Leakrate) o C1 P0189 (Pri To Sec Leakrate 15 Min Running Avg) o EROSLEAK (Primary To Secondary Leakage).

OR NOTE The S/G Leakage EMFs are highly sensitive which may cause the EMFs located on the adjacent steamline to be increasing or in alarm.

• S/G leakage EMF indication(s):

o 1 EMF-71 (S/G A Leakage) o 1 EMF-72 (S/G B Leakage) o 1EMF-73 (S/G C Leakage) o 1EMF-74 (S/G D Leakage).

OR

• Compare charging flow and letdown flow OR

• Monitor OAC NV Graphic OR

• Initiate OAC Program "NSNCLEAK" OR

• Monitor OAC point C1 P0976 (Gross NC System Leak Rate, Ten Min Run Avg).

OR

• Secondary Chemistry performance of PT/1/B/4600/028 (Determination of Steam Generator Tube Leak For Unit 1).

Page 13 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 4 5 Page(s)

Event

Description:

Respond to EMF33 failed high, 1BB-24 (1 C S/G) fails to close SRO Technical Specification Time Position Applicant's Actions or Behavior SRO 8. Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual:

• 3.4.13 (RCS Operational Leakage)

• 3.4.14 (RCS Pressure Isolation Valve (PIV) Leakage)

• 3.5.5 (Seal Injection Flow)

• 3.7.17 (Secondary Specific Activity)

• SLC 16.7-9 (Standby Shutdown System).

SRO Should note that SLC 16.11-7 #2 Conditions A, I, and K apply due to failed EMF33 once confirmation is received.

END EVENT Page 14 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 5 1 Page(s)

Event

Description:

1B S/G level program fails low Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an INSTRUMENT event using OP/1/B/6100/010E (Annunciator Response for Panel 1AD-4)

Pertinent Alarms 1AD-4 C/2 - S/G B FLOW MISMATCH LO CF FLOW} FLOW)

NOTE: SM flow channel 2 shares a reference tap with channel 2 of S/G narrow range level indication. SM flow channel 1 shares a reference tap with S/G wide range level indication. A failure on one of these level taps will affect the SM flow channel. Other indication of SM flow should be used to determine if it is an instrument failure.

IMMEDIATE ACTIONS RO 1. Compare all flow indication to verify condition.

RO 2. IF automatic controls are NOT correcting, take manual control.

SUPPLEMENTAL ACTIONS RO 1. WHEN malfunction is corrected OR bypassed, restore control to automatic.

EXAMINER NOTE: No technical specification conditions.

SRO 2. Refer to Tech Specs for operable channel requirements (TS 3.3.1,3.3.2, 3.3.3 and 3.3.4).

END EVENT Page 15 of 28

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 6 5 Page(s)

Event

Description:

1ETA normal feeder opens, restore charging Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using AP/1/A15500/007 (Loss of Normal Power) Case 1, Loss of All Power to an Essential Train.

ALL 1. Monitor Enclosure 1 (Foldout Page).

BOP 2. Verify affected bus - ENERGIZED.

EXAMINER NOTE: Bus will only be energized for 1 minute and then the DIG will trip resulting in a loss of all power to ETA.

SRO 2RNO GO TO Case II (Loss of All Power to an Essential Train},

SRO Transition to Case 2.

ALL 1. Monitor Enclosure 1 (Foldout Page).

BOP 2. Verify the essential loads powered from energized train as follows:

a. RN pump(s) - IN SERVICE AS NEEDED.

b. KC pump(s) - IN SERVICE AS NEEDED.

c. At least one NV pump - ON.

EXAMINER NOTE: SRO will refer to AP/1/A15500/012 (Loss of Charging or Letdown) to restore charging at some point. The following steps are for AP/07 and the steps for AP/12 follow.

BOP 2 d. CA pump - ON.

BOP 2dRNO IF CA pump is required to maintain SIG levels, THEN manually start pump.

BOP e. VCIYC chiller - ON.

BOP 3. Verify CA Pump #1 - ON.

RO 4. Maintain reactor power less than or equal to 100%.

BOP 5. Verify DIG on the affected bus - RUNNING.

SRO 5RNO GO TO Step 7.

BOP 7. Dispatch operator with a screwdriver to load shed the affected essential bus as follows:

• REFER TO Enclosure 8 (Manual* Load Shed Of 1ETA)

BOP 8. Verify operating RN pump(s) flow - LESS THAN 23,000 GPM.

BOP 9. Stop any dilutions in progress.

BOP 10. Verify SII status as follows:

a. S/I- HAS ACTUATED.

b. GO TO Step 12.

BOP 12. Ensure CA System - RESET.

Page 16 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 6 5 Page(s)

Event

Description:

1ETA normal feeder opens, restore charging Time Position Applicant's Actions or Behavior BOP 13. Control S/G levels as follows:

a. Verify CF flow - MAINTAINING STABLE S/G LEVELS.

b. IF AT ANY TIME CF flow control to S/Gs is lost, THEN perform Step 13.

CAUTION Battery depletion may occur as early as two hours. Battery depletion results in affected CA control valves failing full open. Failure to take local control of S/G level prior to battery depletion may result in S/G overfill.

c. IF AT ANY TIME any vital or auxiliary control channel battery charger has been de-energized for greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, THEN dispatch operators to locally control affected CA flow path. REFER TO Enclosure 16 (S/G Level Control).

RO 14. Verify "C-9 COND AVAILABLE FOR STM DUMP" status light (1SI-18) - LIT.

BOP 15. Control charging as follows:

a. Maintain charging flow less than 180 GPM.

b. Adjust charging flow as necessary to maintain Pzr level in program band.

BOP 16. Control letdown as follows:

a. Verify normal letdown - IN SERVICE.

BOP 16aRNO. Perform the following:

1) Attempt to restore letdown. REFER TO AP/1/A/5500/012 (Loss of Charging or Letdown).

2) WHEN normal letdown has been established, THEN place additional letdown orifice in service as necessary to control Pzr level.

3) GO TO Step 17.

BOP 17. Determine and correct cause of blackout.

BOP 18. Verify VI pressure - GREATER THAN 85 PSIG AND STABLE.

BOP 19. IF spent fuel pool instrumentation is failed low, THEN dispatch operator to monitor spent fuel pool conditions. REFER TO Enclosure 14 (Spent Fuel Pool Monitoring).

EXAMINER NOTE: Tech Spec 3.8.1 Condition A, Band D, 3.8.9 Condition A and 3.4.9 Condition B apply".

apply.

SRO 20. Ensure compliance with appropriate Tech Specs:

• 3.4.9 (Pressurizer)

• 3.8.1 (AC Sources - Operating)

• 3.8.2 (AC Sources - Shutdown)

• 3.8.4 (DC Sources - Operating)

• 3.8.5 (DC Sources - Shutdown)

• 3.8.7 (Inverters - Operating)

• 3.8.8 (Inverters - Shutdown)

• 3.8.9 (Distribution Systems - Operating)

• 3.8.10 (Distribution Systems - Shutdown).

EXAMINER NOTE: No notifications required at this time.

Page 17 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 6 5 Page(s)

Event

Description:

1ETA normal feeder opens, restore charging Time Position Applicant's Actions or Behavior SRO 21. Determine required notifications:

• REFER TO RP/O/A/50001001 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 (NRC Notification Requirements).

BOP 22. Verify 6.9KV busses - ENERGIZED.

SRO 23. Do not continue in this procedure until the following are satisfied:

• The status of all lockout targets have been determined

• Station management has approved power restoration to the affected bus.

T AP/1/A15500/012 (Loss of Charging or Letdown), Case 1 Loss of Charging actions RO 1. Stop any power changes.

BOP 2. Ensure the following letdown isolation valves - CLOSED:

• 1NV-1 OA (Letdn Orif 1B Otlt Cont Isol)

• 1NV-11A (Letdn Orif 1C Otlt Cont Isol)

• 1NV-13A (Letdn Orif 1A Otlt Cont Isol).

BOP 3. Monitor conditions for continued NC pump operation as follows:

• NC pump #1 seal outlet temperature - LESS THAN 235°F

• NC pump lower bearing temperature - LESS THAN 225°F.

BOP NOTE Gas entrainment in the NV pump suction can produce pump failure or degradation. Gas entrainment can result in a complete loss of charging, or in a reduction of charging capacity, without indication of cavitation.

4. Verify NV pump status as follows:

• At least one NV pump - ON.

• Charging flow - ADEQUATE FOR PLANT CONDITIONS.

Page 18 of 28

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 3 Event No. - 5 Page(s)

Event

Description:

1ETA normal feeder opens, restore charging Time Position Applicant's Actions or Behavior BOP 4RNO Perform the following:

a. Ensure malfunctioning NV pump - SECURED.

b. Ensure the following valves - OPEN:

• 1NV-203A (NV Pumps A&B Recirc Isol)

• 1NV-202B (NV Pmps A&B Recirc Isol).

c. Ensure only one suction source as follows:

• VCT 0 1NV-188A (VCT Otlt Isol) - OPEN 0 1NV-189B (VCT Otlt Isol) - OPEN 0 VCT level - GREATER THAN 23%

0 1NV-252A (NV Pumps Suet From FWST) - CLOSED 0 1NV-253B (NV Pumps Suct From FWST) - CLOSED OR

• FWST o Either of the following valves - OPEN:

• 1NV-252A (NV Pumps Suct From FWST)

• 1NV-253B (NV Pumps Suct From FWST).

o Either of the following valves - CLOSED:

• 1NV-188A (VCT Otlt Isol)

• 1NV-189B (VCT Otlt Isol).

d. IF operating NV pump tripped due to loss of suction, THEN ...

e. Start the available NV pump as follows:

1) Manually open 1NV-309 (Seal Water Injection Flow) to full open.

2) Manually close 1NV-294 (NV Pmps A&B Disch Flow Ctrl).

3) Start NV pump aux oil pump.

4) Start available NV pump.

5) Stop NV pump aux oil pump.

6) IF suction is from the FWST, THEN ...

f. IF no NV pump(s) available, THEN ...

BOP 5. Verify charging header is aligned to NC loop as follows:

a. 1NV-312A (Chrg Line Cont Isol) - OPEN.

b. 1NV-314B (Chrg Line Cont Isol) - OPEN.

c. Verify one of the following valves - OPEN:

o 1NV-32B (NV Supply To Loop A Isol)

OR o 1NV-39A (NV Supply To Loop D Isol).

d. Verify 1NV-294 NV-294LNV(NV Pmps A&B Disch Flow Ctrl) - OPEN.

BOP 5dRNO d. Perform the following:

1) Manually open 1NV-309 (Seal Water Injection Flow).

2) Throttle 1NV-294 (NV Pmps A&B Disch Flow Ctrl) to establish greater than 32 GPM "N/R CHRG LN FLOW".

BOP 6. Verify the following:

o "TOTAL SEAL WTR FLOW" - GREATER THAN 32 GPM o 1NV-309 (Seal Water Injection Flow) - IN "AUTO".

Page 19 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 6 5 Page(s)

Event

Description:

1ETA normal feeder opens, restore charging Time Position Applicant's Actions or Behavior BOP 6RNO Perform the following:

a. Slowly throttle 1NV-309 (Seal Water Injection Flow) to establish 32 GPM "TOTAL SEAL WTR FLOW".

b. Place 1NV-309 in "AUTO".

BOP 7. Verify Pzr level- GREATER THAN 17%.

BOP 8. Control charging to stabilize Pzr level greater than 17%.

BOP 9. Ensure "PZR HTR GROUP 1C" - ON.

BOP 1O. Control VCT level as follows:

a. Verify NC system makeup - SET DESIRED BORON CONCENTRATION.

b. Verify "NC MAKEUP MODE SELECT" - IN AUTOMATIC BOP 11. Verify normal letdown - IN SERVICE.

SRO 11 RNO Restore normal letdown. REFER TO Case II (Loss of Letdown).

EXAMINER NOTE: Restoration of letdown is part of another submitted scenario and should not be done per this scenario.

END EVENT Page 20 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 7 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is the MAJOR event starting with AP/1/A15500/011 (Pressurizer Pressure Anomalies)

BOP 1. Verify all Pzr pressure channels - INDICATING THE SAME.

BOP 2. VerifY'ali Pzr PORVs - CLOSED.

EXAMINER NOTE: The PORV block valve has no power in the next step and the leak cannot be isolated.

RO/BOP 2RNO Perform the following:

a. Manually close Pzr PORV(s).

b. IF any Pzr PORV cannot be closed, THEN:

1) Close the affected PORV(s) isolation valve.

2) IF the Pzr PORV isolation valve cannot be closed, THEN perform the following:

a) IF in Mode 3 or 4 AND CLAs isolated, THEN GO TO AP/1/A/55001027 (Shutdown LOCA).

b) Trip reactor.

c) Manually initiate S/I.

d) GO TO EP/1/A/5000/E-0 (Reactor Trip Or Safety Injection).

T SRO Transition to E-O (reactor Trip or Safety Injection)

ALL 1. Monitor Enclosure 1 (Foldout Page).

CT EXAMINER NOTE: At some point the NCPs will be secured due to subcooling being lost.

RO 2. Verify Reactor Trip:

• All rod bottom lights - LIT

• All reactor trip and bypass breakers -

• I/R amps - DECREASING.

RO 3. Verify Turbine Trip:

• All turbine stop valves - CLOSED BOP 4. Verify 1ETA and 1ETB - ENERGIZED.

BOP 4RNO Perform the following:

a. IF 1ETA AND 1ETB are de-energized,THEN GO TO EP/1/A/5000/ECA-0.0 (Loss Of All AC Power).

b. WHEN time allows, THEN attempt to restore power to de-energized switchgear while continuing with this procedure. REFER TO AP/1/A/55001007 (Loss of Normal Power).

BOP 5. Verify S/I is actuated:

a. "SAFETY INJECTION ACTUATED" status light (1SI-13) - LIT.

b. Both E/S load sequencer actuated status lights (1SI-14) - LIT.

RO 6. Announce "Unit 1 Safety Injection".

EXAMINER NOTE: This will be a 4.1.A.1 (Alert)

SRO 7. Determine required notifications:

• REFER TO RP/O/A/50001001 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 (NRC Notification Requirements).

RO 8. Verify all Feedwater Isolation status lights (1 SI-5) - LIT.

Page 21 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 7 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior BOP 9. Verify Phase A Containment Isolation status as follows:

a. Phase A "RESET" lights - DARK.

b. Monitor Light Panel Group 5 St lights - LIT.

BOP 10 Verify proper Phase B actuation as follows:

a. Containment pressure - HAS REMAINED LESS THAN 3 PSIG.

b. IF AT ANY TIME containment pressure exceeds 3 PSIG while in this procedure, THEN perform Step 10.a.

BOP 11 Verify proper CA pump status as follows:

a. Motor driven CA pumps - ON.

b. 3 SIG NIR levels - GREATER THAN 11%.

EXAMINER NOTE: Since crew is aware that there is no power on A train, they should state that when checking A train equipment, but not transition to RNO based on A train equipment alone. However they will transition for B train NI pump since it has power.

BOP 12 Verify all of the following SII pumps - ON:

• NV pumps

• ND pumps

• NI pumps.

CT BOP 12RNO Perform the following for affected train( s):

a. Reset ECCS.

b. Reset DIG load sequencer.

c. Manually start affected pump.

d. IF AT ANY TIME a BIO occurs, THEN restart SII equipment previously on.

BOP 13 Verify all KC pumps - ON.

BOP 14 Verify all Unit 1 and Unit 2 RN pumps - ON.

EXAMINER NOTE: BOP will find VA not aligned properly per Enclosure 2.

Enclosure 2 steps are after step 22 and before E-1 steps.

BOP 15 Verify proper ventilation systems operation as follows:

• REFER TO Enclosure 2 (Ventilation System Verification).

• Notify Unit 2 operator to perform Enclosure 3 (Opposite Unit Ventilation Verification ).

BOP 16 Verify all SIG pressures - GREATER THAN 775 PSIG.

BOP 17 Verify proper SII flow as follows:

a. "NV SII FLOW" - INDICATING FLOW.

b. NC pressure - LESS THAN 1620 PSIG.

c. NI pumps - INDICATING FLOW.

d. NC pressure - LESS THAN 285 PSIG.

BOP 17dRNO

d. Perform the following:

1) Ensure ND pump miniflow valve on operating ND pump(s) - OPEN.

2) IF the ND pump miniflow valve(s) cannot be opened, THEN ...

3) GO TO Step 18.

Page 22 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 7 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior BOP 18 Control S/G levels as follows:

a. Verify total CA flow - GREATER THAN 450 GPM.

b. WHEN at least one S/G N/R level is greater than 11 % (29% ACC), THEN throttle feed flow to maintain all S/G N/R levels between 11 % (29% ACC) and 50%.

BOP 19 Verify all CA isolation valves - OPEN.

EXAMINER NOTE: Some Equipment will not be in proper alignment but no action is available to place it in proper alignment due to loss of A train power.

BOP 20 Verify S/I equipment status based on monitor light panel - IN PROPER ALIGNMENT.

EXAMINER NOTE: A Train equipment will not be in proper alignment due to no power.

20RNO Manuallyalign equipment.

EXAMINER NOTE: Enclosure 4 actions are after Enclosure 2 actions.

RO NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until subsequent procedures provide alternative NC temperature control guidance.

21 Control NC temperature. REFER TO Enclosure 4 (NC Temperature Control).

BOP 22 Verify Pzr PORV and Pzr spray valve status as follows:

a. All Pzr PORVs - CLOSED.

BOP 22aRNO

a. IF Pzr pressure is less than 2315 PSIG, THEN:

1) Manually close Pzr PORV(s).

2) IF any Pzr PORV cannot be closed, THEN:

a) Close its isolation valve.

b) IF any Pzr PORV cannot be closed OR isolated, THEN perform the following:

(1) IF both the following conditions exist,

• Containment pressure - GREATER THAN 1 PSIG

• Containment pressure - HAS REMAINED LESS THAN 3 PSIG

- THEN manually start one VX fan. REFER TO Enclosure 5 (VX Fan Manual Start).

(2) Concurrently:

• Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees).

• GO TO EP/1/A/5000/E-1 (Loss Of Reactor Or Secondary Coolant).

E-O, Enclosure 2 steps Page 23 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. - - 3- Event No. - 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior BOP 1. Verify proper VCIYC operation as follows:

a. Verify one train of the following equipment is in operation:

• YC chiller

• CR AHU-1

• CRA AHU-1

• CRA PFT-1.

b. Verify the following alarms - DARK:

• 1AD-18, Al8 "UNIT 1 INTAKE HI CHLORINE 1A"

• 1AD-18, B/8 "UNIT 1 INTAKE HI CHLORINE 1B"

• 1AD-18, D/8 "UNIT 2 INTAKE HI CHLORINE 2A"

• 1AD-18, E/8 "UNIT 2 INTAKE HI CHLORINE 2B".

c. Ensure the following VC dampers - OPEN:

• 1VC-5B (CRA Filt Inlet)

• 1VC-6A (CRA Filt Inlet)

• 2VC-5B (CRA Filt Inlet)

• 2VC-6A (CRA Filt Inlet).

d. Repeat Step 1 of this enclosure until notified by station management as follows:

• At least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> OR

• Any time VCIYC related annunciators on 1AD-18 actuate.

BOP 1.a RNO a. Perform the following:

1) Shift operating VCIYC trains. REFER TO Enclosure 6 (Shifting Operating VCIYC Train).

2) IF no train can be properly aligned, THEN dispatch operator and IAE/Maintenance to restore at least one train of VCIYC. REFER TO the following:

• OP/0/Al6450/011 (Control Room Area Ventilation/Chilled Water System)

• EM/0/Al5200/001 (Troubleshooting Cause For Improper Operation of VCIYC System).

EXAMINER NOTE: ABUXF 1B will have to be secured manually.

BOP 2. Ensure proper VA System operation as follows:

• Ensure the following fans - OFF:

o ABUXF 1A o ABUXF 1B.

• Ensure VA System filter is in service as follows:

o 1ABF-D-12 (VA Filt A Bypass Damper) - CLOSED o 1ABF-D-5 (VA Filt B Bypass Damper) - CLOSED.

• Ensure the following fans - ON:

o ABFXF-1A o ABFXF 1B.

BOP 3. Verify proper VE System operation as follows:

a. VE fans - ON.

b. Annulus pressure - BETWEEN -1.4 IN. WC AND -1.8 IN. WC.

c. Repeat Step 3.b every 30 minutes until notified by station management.

Page 24 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 7 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior BOP 4. Record time ventilation systems are verified on following table:

Enclosure 4 actions RO 1. Verify at least one NC pump - ON.

RO 2. Use NC T-AvQ to determine NC temperature as required in subsequent steps.

RO 3. IF AT ANY TIME NC pumps are tripped, THEN use NC T-Colds to determine NC temperature as required in subsequent steps.

RO 4. Verify one of the following:

• NC temperature - STABLE AT LESS THAN OR EQUAL TO 55rF.

OR

• NC temperature - TRENDING TO 55rF.

RO 5. Continue to monitor NC temperature.

T SRO Transition to EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant)

ALL 1. Monitor Enclosure 1 (Foldout Page).

BOP 2. Verify main steamlines are intact as follows:

• All S/G pressures - STABLE OR INCREASING

• All S/Gs - PRESSURIZED.

BOP 3. Control intact S/G levels as follows:

a. Verify N/R level in all intact S/Gs - GREATER THAN 11% (29% ACC).

b. Throttle feed flow to maintain all intact S/G N/R levels between 11 % (29%

ACC) and 50%.

EXAMINER NOTE: Crew should be aware that the EMF33 signal is false and not transition based on this indication with absence of any confirmatory indications.

EXAMINER NOTE: To align S/Gs for sampling in the following step, 1NM-191 B, 211 B, 200B, and 220B will be opened.

BOP 4. Verify secondary radiation is normal as follows:

a. Ensure the following signals - RESET:

1) Phase A Containment Isolations

2) CA System valve control

3) KC NC NI NM St signals.

b. Align all S/Gs for Chemistry sampling.

c. Perform at least one of the following:

• Notify Chemistry to sample all S/Gs for activity.

OR

• Notify RP to frisk all cation columns for activity.

d. Verify the following EMF trip 1 lights - DARK:

• 1EMF-33 (Condenser Air Ejector Exhaust)

• 1EMF-26 (Steamline 1A)

• 1EMF-27 (Steam line 1B)

• 1EMF-28 (Steam line 1C)

• 1EMF-29 (Steam line 1D).

e. WHEN activity results are reported, THEN verify all S/Gs indicate no activity.

Page 25 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 7 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior BOP 5. Verify Pzr PORV and isolation valve status as follows:

a. Power to all Pzr PORV isolation valves AVAILABLE.

b. All Pzr PORVs - CLOSED.

BOP 5bRNO

b. IF Pzr pressure is less than 2315 PSIG, THEN:

1) Manually close Pzr PORV( s).

2) IF any Pzr PORV cannot be closed, THEN close its isolation valve.

BOP 5c. At least one Pzr PORV isolation valve - OPEN.

d. IF AT ANY TIME a Pzr PORV opens due to high pressure, THEN, after Pzr pressure decreases to less than 2315 PSIG, ensure the valve closes or is isolated.

RO 6. Verify S/I termination criteria as follows:

a. NC subcooling based on core exit TICs - GREATER THAN O°F.

SRO 6aRNO. GO TO Step 6.f.

EXAMINER NOTE: 5/1 termination criteria will likely not be met for this scenario. If termination is met, the crew will transition to EP/1/A/SOOO/E5-1.1. Those steps are at the end of this document if needed.

ALL 6f. Monitor SII termination criteria. REFER TO Enclosure 2 (S/I Termination Criteria).

g. IF AT ANY TIME SII termination criteria is met while in this procedure, THEN RETURN TO Step 6.

BOP 7. Verify proper NS pump operation as follows:

a. At least one NS pump - ON.

BOP 7aRNO

a. Perform the following:

1) IF AT ANY TIME an NS pump(s) starts while in this procedure, THEN perform Step 7.

2) GO TO Step 8.

EXAMINER NOTE: Power will already have been removed from the 1A sequencer per AP/07.

BOP 8. Verify criteria to stop operating ND pumps as follows:

a. NC pressure - GREATER THAN 285 PSIG.

b. NC pressure - STABLE OR INCREASING.

c. At least one ND pump - ON.

d. ND pumps suction - ALIGNED TO FWST.

e. Verify FWST level - GREATER THAN 45%.

f. Ensure SII - RESET:

1) ECCS.

2) DIG load sequencers.

3) IF AT ANY TIME a BIO occurs, THEN restart SII equipment previously on.

g. Stop ND pumps.

h. IF AT ANY TIME NC pressure decreases to less than 285 PSIG in an uncontrolled manner, THEN restart ND pumps.

Page 26 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 3 Event No. 7 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior RO 9. Verify NC and SIG pressures as follows:

a. All SIG pressures - STABLE OR INCREASING.

b. NC pressure - STABLE OR DECREASING.

BOP 10. Verify conditions to stop operating DIGs as follows:

a. At least one DIG - ON.

b. Verify 1ETA is energized by offsite power as follows:

• "DIG 1A BKR TO ETA" - OPEN

• 1ETA - ENERGIZED.

BOP 10bRNO

b. Perform the following:

1) Attempt to restore offsite power to affected switchgear. REFER TO AP/1/A/55001007 (Loss of Normal Power).

2) GO TO Step 10.d.

BOP d. Verify 1ETB is energized by offsite power as follows:

• "DIG 1B BKR TO ETB" - OPEN

• 1ETB - ENERGIZED.

e. WHEN SII is reset, THEN dispatch operator to stop 1B DIG and place in standby readiness. REFER TO OP/1/A/63501002 (Diesel Generator Operation).

f. Ensure SII - RESET:

1) ECCS.

2) DIG load sequencers.

3) IF AT ANY TIME a BIO occurs, THEN restart SII equipment previously on.

BOP 11. Obtain containment H2 concentration as follows:

a. Ensure operator has been dispatched to secure all ice condenser air handling units. REFER TO Enclosure 3 (Securing All Ice Condenser Air Handling Units).

b. Verify containment H2 analyzers - IN SERVICE.

BOP 11bRNO

b. Perform the following:

1) Dispatch operator to place containment H2 analyzers in service. REFER TO OP/1/A/64501010 (Containment Hydrogen Control System).

2) WHEN H2 analyzers are in service, THEN perform Steps 11.c through 11.e.

3) GO TO Step 12.

EXAMINER NOTE: Crew should determine that one train (8) is available for containment sump swapover and Cold Leg Recirc.

Page 27 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. - - 3- Event No. 7 8 Page(s)

Event

Description:

NC PORV fails open - medium break LOCA Time Position Applicant's Actions or Behavior BOP 12. Initiate evaluation of plant status as follows:

a. Verify S/I systems - ALIGNED FOR INJECTION MODE.

b. Verify Cold Leg Recirc capability as follows:

1) At least one ND pump - AVAILABLE.

2) Verify power to all of the following valves - AVAILABLE:

• 1FW-27A (ND Pump 1A Suct From FWST)

• 1NI-185A (ND Pump 1A Cont Sump Suct)

• 1ND-28A (ND Supply To NV & 1A NI Pmps)

• 1FW-55B (ND Pump 1 B Suct From FWST

• 1 NI-184B (ND Pump 1 B Cont Sump Suct)

• 1NI-332A (NI Pump Suct X-Over From ND)

• 1NI-333B (NI Pump Suct From ND)

• 1NI-334B (NI Pump Suct X-Over From ND)

• 1NI-136B (ND Supply To NI Pump 1 B).

3) Verify power to all of the following

• 1NI-115A (NI Pump 1A Miniflow Isol)

• 1NI-144A (NI Pump 1B Miniflow Isol)

• 1NI-147B (NI Pump Miniflow Hdr To FWST Isol).

4) Verify the "ENABLE" lights for the following switches - LIT:

• "C-LEG RECIR FWST TO CONT SUMP SWAP TRN A"

• "C-LEG RECIR FWST TO CONT SUMP SWAP TRN B".

c. Verify auxiliary building radiation is normal as follows:

• EMF-41 (Aux Bldg Ventilation) trip 1 light - DARK

• All area monitor EMF trip 1 lights - DARK.

d. WHEN the TSC is activated AND staffed, THEN:

1) Notify the Reactor Engineer to assess core damage. REFER TO RP/O/A/5000/015 (Core Damage Assessment).

2) Notify Chemistry to obtain current NC boron concentration.

3) WHEN ND is aligned for Cold Leg Recirc, THEN notify Chemistry to obtain current containment sump boron concentration.

4) Notify Operating Engineer of the following:

a) VA is required to be aligned to normal within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the event.

b) Evaluate aligning VA to normal mode. REFER TO OP/O/A/6450/003 (Auxiliary Building Ventilation System).

e. Notify station management to evaluate starting additional plant equipment to assist in recovery.

SRO 13. Verify NC System cooldown and depressurization is required as follows:

a. NC pressure - GREATER THAN 285 PSIG.

b. GO TO EP/1/A/5000/ES-1.2 (Post LOCA Cooldown And Depressurization).

T SRO Transition to EP/1/A/5000/ES-1.2 (Post LOCA Cooldown And Depressurization).

END EVENT Page 28 of 28

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 2008 NRC EXAMINATION Op-Test No.:

Facility: Catawba Nuclear Station Scenario No.:

SNAP 164 Examiners: Operators:

Initial Conditions:

• 100% power

• EFPD =450 days

• Boron concentration is 112 ppm

• 1A CA pump out of service for PMs - expected back in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

• 1A NI pump out of service for PMs - expected back in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

• Thunderstorms are in the area.

Turnover:

• Maintain 100%.

Event Malf. No. Event Event No. Type* Description 1 RO C Steam Dump valve 1SB-21 fails open 2 RO C Continuous rod motion in auto while reducing power 3 BOP C PZR spray valve fails open, B heaters fail SRO TS 4 BOP I KC surge tank level fails low, KC trains separate and no A train KC SRO TS can be started, requires NV pump swap 5 BOP C 1NV-148 fails to 20% open in auto/manual control available 6 RO C CFP trip/ T/G runback with rods fail to move 7 ALL M Loss of all AC power/ Large Break LOCA Additional failures 1B CA pump fails to auto start 1NI1 OB and 1NI184B failed auto actions FWST Puncture

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

SIMULATOR SETUP

• Reset to a 100% EOL power snap

• Ensure B train KC in service

• Roll charts

• Place red tag covers on 1A CA pump and 1A NI pump

• OP/1/A/61 001003 (Controlling Procedure for Unit Operation), Enclosure 4.3 completed through step 2.13 (revision 102)

MALFUNCTIONS, REMOTES, and OVERRIDES Malfunction # Description Value Event Ramp Delay Trigger MAL-IPE003C PZR SPRAY VLV NC-29 FAIL, 100 3 MAN CTRL MAL-IRX009 RODS FAIL TO MOVE AUTO 6 MAL-CF003A CF DISCHARGE VLV CF10 6 FAILS CLOSED MAL-IDE003G STEAM DUMP VLV SB21 FAIL 100 1 TO POSITION XMT-KC045 LKC_5631 KC SURGE TANK 0 4 KCLS5630 TO VALVES MAL-CA004B FAILURE OF CA PUMP B TO AUTO START MAL-NV021A NV-148 AUTO FAILURE WITH 20 5 30 MAN CNTRL MAL-EQB006A TRN B BLACKOUT SEQUENCER BLOCK MAL-EQB006B TRN B SI SEQUENCER BLOCK MAL-EQB006B TRN B SI SEQUENCER BLOCK 18 Del in 1

VLV-NI002A NI10B B.I.T. DISCHARGE ISOL VLV FAIL AUTO ACTIONS MAL-NC013A NC COLD LEG A LEAK 27.5 18 150 MAL-EP008A LOSS OF 4160V BUS ETA 10 LOA-NC026 RACKOUT PZR HTR 1B RACK-OUT 3 LOA-EP031 RACKOUT 7 KV nD FDR FROM 7 n1B OVR-EP064A 7KV BUS nD TIE BKR OPEN LT ON LOA-EP032 RACKOUT 7 KV BUS nD TIE RACK-OUT 5 BKR LOA-CA017 RACKOUT CA PUMP 1A RACK-OUT LOA-NI003 RACKOUT NI PMP 1A RACK-OUT MAL-DG004A DIG 1A OVERSPEED TRIP MAL-FW001 FWST LEAK 7500 18 360, Del in 780

OVR-DG016C DIG 1B PB (11/407) ON PB OFF LOA-IDE007 SB20 - INLET ISOL 0 25 60 240 VLV-NI037A NI184B CNMT SUMP LINE 1B ISOL (STEM) FAIL AUTO ACTIONS MAL-KC001A KC PMP 1A1 FAILURE MANUAL MAL-KC001B KC PMP 1A2 FAILURE MANUAL MAL-IRX003A UNCONTROLLED ROD AUTO 1 INSERTION ANN-AD09-A04 FWST MISSLE WALL SUMP HI AS IS 18 700 LEVEL ANN-AD09-A07 FWST PUNCTURE AS IS 18 700 EVENT TRIGGERS (other than manual)

Event Trigger Description 10 jpplp4(1) I jpplp4(2) (NOTE: Center character is a "pipe")

18 X11 i400i CRITICAL TASKS

1. E-O I - Establish flow from at least one high head ECCS pump before transition out of E-O.

2. ES-1.3 A - Transfer to cold leg recirculation and establish ECCS recirculation flow from one train equivalent of ECCS.

REFERENCES OP/1/A/61 001003 (Controlling Procedure for Unit Operation), Enclosure 4.3 revision 102 OP/1/A/62001001 (Chemical and Volume Control System), Enclosure 4.13 revision 135 AP/1/A/55001028 (Secondary Steam Leak) revision 004 AP/1/A/55001015 (Rod Control Malfunction) revision 011 AP/1/A/55001011 (Pressurizer Pressure Anomalies) revision 019 AP/1/A/55001003 (Load Rejection) revision 034 AP/1/A/55001021 (Loss of Component Cooling) revision 035 EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) revision 031 EP/1/A/5000/ECA-0.0 (Loss of All AC Power) revision 033 EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant) revision 023 EP/1/A/5000/ES-1.3 (Transfer to Cold Leg Recirculation) revision 021

NOTES AND INSTRUCTIONS NOTE: The following steps are GUIDELINES. The NRC lead examiner will direct timing of events unless otherwise noted.

Event 1/2 - Steam Dump valve 1SB-21 fails open I Continuous rod motion in auto while reducing power This event will be entered once the crew has taken turnover and evaluated plant conditions. When the dump has been closed and the plant is stable, the next event can be inserted.

NOTE: When called to isolate 1S8021, insert EVENT 25 to close the block valve. Once the valve has closed (4 minute delay), call the crew and report that 1S8-20 is closed.

Event 3 - PZR spray valve fails open, B heaters fail! SRO Technical Specification When the spray valve is closed, NC pressure is increasing, and the SRO has completed consulting Technical Specifications the next event can be inserted.

Event 4 - KC surge tank level fails low, KC trains separate and no A train KC can be started, requires NV pump swap I SRO Technical Specification When the 1B NV pump has been started, 1A NV pump is secured, and the SRO has completed consulting Technical Specifications the next event can be inserted.

Event 5 - 1 NV-148 fails to 20% open in auto I manual control available When 1NV-148 is in manual and the crew has control of letdown temperature the next event can be inserted.

Event 6 - CFP tripl T/G runback with rods fail to move in automatic When the runback has been completed and reactor power is approximately stable the next event can be inserted. This will begin the major event.

Event 7 - Loss of all AC powerl Large Break LOCA Additional failures 1B CA pump fails to auto start, 1NI10B and 1NI184B failed auto actions, FWST Puncture NOTE: If crew is delayed in getting one DIG in service, ensure SSF schedule is run. (This should not be necessary for this scenario)

TERMINATE AFTER PROPER RECIRC FLOW IS VERIFIED PER STEP 5 of ES-1.3.

Remove red tag covers from 1A CA pump and 1A NI pump.

CREW TURNOVER INFORMATION Initial Conditions:

• 100% power

• EFPD =450 days

• Boron concentration is 112 ppm

• 1A CA pump out of service for PMs - expected back in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

• 1A NI pump out of service for PMs - expected back in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

• Thunderstorms are in the area.

Turnover:

• Maintain 100%.

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 1 3 Page(s)

Event

Description:

Steam Dump valve 1SB-21 fails open Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using AP/1/AJ5500/028 (Secondary Steam Leak)

Pertinent Alarms OAC Pt C1Q0972 - VLV SB21 STM BYPASS TO COND CONTROL #21 -

OPEN ALL 1. Monitor Enclosure 1 (Foldout Page).

RO 2. Verify turbine - ONLINE.

RO 3. Verify the following:

• Reactor power - LESS THAN OR EQUAL TO 100% POWER

• T-Avg - WITHIN 1.5°F OF T-Ref.

EXAMINER NOTE: This steam dump is worth 3-4 % full load and actions will be required to maintain reactor power < 100%.

EXAMINER NOTE: Once rods start to move, they will continue to step in that direction at the same rate until rods are placed in manual. Steps for this failure are listed in EVENT 2.

RO 3. RNO Perform the following:

a. Select "MANUAL" on turbine control panel.

b. Depress "CONTROL VALVES LOWER" pushbutton and reduce load to maintain:

• Reactor power - LESS THAN OR EQUAL TO 100% POWER

• T-Avg - WITHIN 1.5°F OF T-Ref.

RO 4. Verify proper reactor response as follows:

• Control rods -IN "AUTO" AND STEPPING IN

• P/R neutron flux - DECREASING.

RO 5. IF AT ANY TIME reactor power is greater than 100%, THEN perform Step 3 RNO.

EXAMINER NOTE: The SRO may transition to RNO step due to PZR level slightly decreasing, but it is not required since it is due to NC temperature decrease shrinkage.

BOP 6. Verify Pzr level - STABLE OR INCREASING.

ALL 7. IF AT ANY TIME while in this procedure Pzr level is decreasing in an uncontrolled manner, THEN RETURN TO Step 6.

BOP 8. IF AT ANY TIME VCT level goes below 23%, THEN align NV pump suction to FWST as follows:

a. Open the following valves:

• 1NV-252A (NV Pumps Suct From FWST)

• 1NV-253B (NV Pumps Suct From FWST).

b. Close the following valves:

• 1NV-188A (VCT Otlt Isol)

• 1NV-189B (VCT Otlt Isol).

EXAMINER NOTE: Crew should diagnose the leak is OUTSIDE containment.

Page 1 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 1 3 Page(s)

Event

Description:

Steam Dump valve 1SB-21 fails open Time Position Applicant's Actions or Behavior ALL 9. Attempt to identify and isolate leak as follows:

a. Verify the following conditions - NORMAL:

• Containment temperature

• Containment pressure

• Containment humidity

• Containment floor & equipment sump level.

b. Dispatch operators to locate and identify source of steam leak.

c. Verify S/G PORVs - CLOSED.

d. Verify condenser dump valves - CLOSED.

RO 9dRNO

d. Perform the following:

1) Select "OFF RESET" on the following switches:

."STEAM DUMP INTLK BYP TRN A"

."STEAM DUMP INTLK BYP TRN B".

2) IF valve will not close, THEN dispatch operator to close affected condenser dump valve isolation valve.

RO 9. e. Verify atmospheric dump valves - CLOSED.

f. Verify CA PMP #1 - OFF.

g. IF leak is suspected to be in a doghouse, THEN ...

EXAMINER NOTE: No required notifications at this time.

SRO 10. Determine required notifications:

• REFER TO RP/O/A/50001001 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 (NRC Notification Requirements).

BOP 11. Notify RP of leak.

EXAMINER NOTE: Leak will likely NOT yet be isolated at this time so additional steps are provided. The crew will skip to step 14 per the RNa of step 12. When leak is isolated the event can be ended.

RO 12. Verify - LEAK ISOLATED.

SRO 13. Determine long term plant status. RETURN TO procedure and step in effect.

BOP 14. Verify UST level- STABLE OR INCREASING.

RO 15. Verify - REACTOR CRITICAL.

Page 2 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 1 3 Page(s)

Event

Description:

Steam Dump valve 1SB-21 fails open Time Position Applicant's Actions or Behavior RO 16. Determine approximate steam leak size as follows:

a. Verify - TURBINE ONLINE.

b. Ensure stable plant conditions:

• Stable T-Avg

• Condenser dump valves closed.

NOTE Secondary plant configuration can affect Thermal Power Best Estimate.

Diverse reactor power indications should be used to determine reactor power.

c. Determine percent turbine power as follows:

1) Divide turbine impulse pressure by 100% power value for turbine impulse pressure. REFER TO OAC Data Book for 100 % power value for turbine impulse pressure.

2) Multiply result by 100.

d. Verify difference between reactor power and turbine power - LESS THAN 5%.

e. Notify RP of leak size.

RO 17. Verify reactor power - GREATER THAN 1%.

SRO 18. Evaluate unit shutdown as follows:

a. Verify unit shutdown required based on either of the following:

• Steam leak cannot be isolated or until leak can be isolated or repaired at power OR

• OSM judgment.

b. Initiate unit shutdown. REFER TO one of the following:

• OP/1/A/61 00/003 (Controlling Procedure For Unit Operation)

OR

• OP/1 1A/61 00/002 (Controlling Procedure For Unit Shutdown)

OR

• AP/1/A/5500/009 (Rapid Downpower).

c. GO TO Step 20.

END EVENT Page 3 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 2 1 Page(s)

Event

Description:

Continuous rod motion in auto while reducing power (per event 1)

Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using AP1/A15500/015 (Control Rod Malfunction), Case 2 Continuous Rod Movement Pertinent alarms N/A - The student should recognize unwarranted rod motion (based on Tavg being with in 1.5°F of Tref)

RO 1. Ensure "CRD BANK SELECT" switch - IN MANUAL.

RO 2. Verify all rod motion - STOPS.

RO NOTE For T-Ref failures, T-Ref will need to be determined for current power level.

3. Manually adjust control rods as necessary to maintain T-Avg within 1°F of T-Ref.

RO 4. Verify the following parameters - NORMAL FOR EXISTING PLANT CONDITIONS:

• Channel 1 Turbine Impulse Pressure

• T-Ref.

BOP 5. Verify the following channels - NORMAL FOR EXISTING PLANT CONDITIONS:

• NC Loop A T-Avg

• NC Loop B T-Avg

• NC Loop C T-Avg

• NC Loop D T-Avg.

ALL 6. Determine and correct cause of continuous rod movement.

EXAMINER NOTE: SRO determines that no Technical Specification apply due to this failure.

SRO 7. Ensure compliance with appropriate Tech Specs:

• . 3.1.1 (Shutdown Margin (SDM))

• 3.1.4 (Rod Group Alignment Limits)

• 3.1.5 (Shutdown Bank Insertion Limits)

• 3.1.6 (Control Bank Insertion Limits)

• 3.3.1 (Reactor Trip Instrumentation)

• 3.3.2 (ESFAS Instrumentation)

• 3.4.2 (RCS Minimum Temperature for Criticality).

EXAMINER NOTE: No notifications are required.

SRO 8. Determine required notifications:

• REFER TO RP/O/A/50001001 (Classification Of Emergency)

• REFER TO RP/O/B/50001013 (NRC Notification Requirements).

RO 9. WHEN rod control problem is repaired, THEN perform the following:

a. Ensure T-Avg - WITHIN 1°F OF T-REF.

b. WHEN desired, THEN place control rods in "AUTO".

c. Ensure steam dumps -IN DESIRED MODE FOR EXISTING PLANT CONDITIONS.

ALL 10. Determine long term plant status. RETURN TO procedure in effect.

END EVENT Page 4 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 3 2 Page(s)

Event

Description:

PZR spray valve fails open, B heaters fail SRO Technical Specification Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using AP/1/A15500/011 (Pressurizer Pressure Anomalies).

Pertinent Alarms 1AD-6 F/8 PZR LO PRESS CONTROL 1AD-6 D/10 PZR LO PRESS PORV NC32 & 36 BLOCKED 1AD-6 D/11 PZR LO PRESS PORV NC34 BLOCKED BOP 1. Verify all Pzr pressure channels - INDICATING THE SAME.

BOP 2. Verify all Pzr PORVs - CLOSED BOP NOTE Control rods may withdraw on decreasing NC pressure.

3. Verify Pzr spray valve( s) - CLOSED BOP 3RNO Perform the following:

a. Manually close affected spray valve(s).

b. IF affected spray valve(s) will not close, THEN ...

BOP 4. Verify all Pzr heaters - ENERGIZED BOP 4RNO IF Pzr pressure is less than 2220 PSIG, THEN ensure all Pzr heaters are energized.

BOP 5. Ensure 1NV-37A (NV Supply To Pzr Aux Spray) - CLOSED BOP NOTE Positive reactivity is inserted during an increase in NC pressure which may cause auto rod insertion.

6. Verify NC pressure - STABLE OR INCREASING.

RO 7. WHEN NC pressure is stable, THEN:

• Stabilize unit at appropriate power level.

• Adjust the following as required to maintain T-Avg within 1°F of T-Ref:

0 Turbine load 0 Control rods 0 Boron concentration BOP 8. IF a Pzr pressure channel failed high, THEN ...

EXAMINER NOTE: SRO determines that 3.4.9 (Pressurizer), condition B applies and 3.4.1 (DNB), condition B applies until pressure is > COLR limit of 2219.8 psig psigJmeter)

(meter) 12215.8 psig (OAC)

Page 5 of 28

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 4 Event No. 3 2 Page(s)

Event

Description:

PZR spray valve fails open, B heaters fail SRO Technical Specification Time Position Applicant's Actions or Behavior SRO 9. Ensure compliance with appropriate Tech Specs:

• 3.3.1 (Reactor Trip System (RTS) Instrumentation)

• 3.3.2 (Engineered Safety Features Actuation System (ESFAS)

Instrumentation)

• 3.3.3 (Post Accident Monitoring (PAM) Instrumentation)

• 3.3.4 (Remote Shutdown System)

• 3.4.1 (RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits)

• 3.4.4 (RCS Loops - MODES 1 and 2)

• 3.4.5 (RCS Loops - MODE 3)

• 3.4.6 (RCS Loops - MODE 4)

• 3.4.9 (Pressurizer)

• 3.4.10 (Pressurizer Safety Valves)

• 3.4.11 (Pressurizer Power Operated Relief Valves (PORVs>>

(PORVs))

• 3.4.13 (RCS Operational Leakage)

BOP 10. Ensure "PZR PRESS TO REC SELECT" is selected to an operable channel.

SRO 11. Determine long term plant status. RETURN TO procedure in effect.

END EVENT Page 6 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 4 4 Page(s)

Event

Description:

KC surge tank level fails low, KC trains separate and no A train KC can be started, requires NV pump swap Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is an INSTRUMENT event using AP/1/A15500/021 (Loss of Component Cooling).

Pertinent alarms 1AO-70/2 NV PUMP A OIL COOLER LO FLOW ALL CAUTION Failure to restore NC pump seal cooling via thermal barrier cooling or NV seal injection within 10 minutes will cause damage to the NC pump seals resulting in NC inventory loss.

1. Monitor Enclosure 1 (Foldout Page).

BOP 2. Verify at least one KC pump - ON.

BOP 3. IF AT ANY TIME all KC pumps are lost, THEN RETURN TO STEP 2.

BOP NOTE Uncooled letdown may result in loss of NV pumps within a matter of minutes.

4. Verify the following:

• 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK.

AND

• At least one KC pump - ON .

BOP 5. IF AT ANY TIME 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" LIT, THEN perform Step 4 RNO.

BOP 6. Verify both KC surge tank levels - 50% - 90% AND STABLE.

EXAMINER NOTE: Level transmitters are working properly, however the relay that controls the valves on low level is actuated. This will separate the KC trains and another pump on the opposite train will need to be started to support opposite train equipment. Neither A train KC pump will start; this will require a swap of NV pumps.

BOP 7. Start additional KC pump(s) as necessary to supply any KC loads presently in service.

BOP CAUTION A loss of KC cooling to the NC pumps results in a gradual approach to an overheated condition in approximately 10 minutes which will result in shaft seizure.

8. Verify KC flow to NC pumps as follows:

• 1AD-20, Al1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK

• 1AD-21, Al1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK.

Page 7 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 4 4 Page(s)

Event

Description:

KC surge tank level fails low, KC trains separate and no A train KC can be started, requires NV pump swap Time Position Applicant's Actions or Behavior BOP 9a. Verify the following Train A KC non-essential header isolation valves - OPEN:

• 1KC-230A (Rx Bldg Non-Ess Hdr Isol)

• 1KC-3A (Rx Bldg Non-Ess Ret Hdr Isol)

• 1KC-50A (Aux Bldg Non-Ess Hdr Isol)

• 1KC-1A (Au x Bldg Non-Ess Ret Hdr Isol).

b. Verify the following Train B KC non-essential header isolation valves - OPEN:

• 1KC-22BB (Rx Bldg Non-Ess Hdr Isol)

• 1KC-1BB (Rx Bldg Non-Ess Ret Hdr Isol)

• 1KC-53B (Aux Bldg Non-Ess Hdr Isol)

• 1KC-2B (Au x Bldg Non-Ess Ret Hdr Isol).

BOP 9b RNO NOTE The KC non-essential header valves can be reopened when the appropriate train's level switch is reset. This should occur between 40% and 4B%

KC surge tank level.

b. WHEN OAC alarm C1 02214 (KC Train B Low-Low Level Surge Tank Isol) is "NOT ACTUATED", THEN ensure the affected valve(s) are open.

EXAMINER NOTE: The level switch will not reset so an additional KC pump (opposite train) must be started. Neither A train KC pump will start; this will require a swap of NV pumps. The OP steps to swap NV pumps is listed at the end of this section.

BOP 9c. Start additional KC pump(s) as necessary to supply any KC loads presently in service.

BOP 10 Verify KC surge tank levels normal as follows:

a. Verify both KC surge tank levels - 50% - 90% AND STABLE.

b. GO TO Step 14.

EXAMINER NOTE: Switches are currently properly aligned.

BOP 14 Ensure KC heat exchanger outlet mode switches - PROPERLY ALIGNED.

BOP 15 Determine and correct cause of loss of KC.

EXAMINER NOTE: SRO determines Tech Spec 3.7.7 (Component Cooling Water) Action A applies.

SRO 16 Ensure compliance with appropriate Tech Specs and Selected Licensee Commitments Manual:

• SLC 16.9-7 (Boration Systems Flow Path - Shutdown)

• SLC 16.9-B (Boration Systems Flow Path - Operating)

• SLC 16.9-9 (Boration Systems Pumps - Shutdown)

• SLC 16.9-10 (Boration Systems Charging Pumps - Operating)

• 3.5.2 (ECCS - Operating)

• 3.5.3 (ECCS - Shutdown)

• 3.6.6 (Containment Spray System)

• 3.7.5 (Auxiliary Feedwater (AFW) System)

• 3.7.7 (Component Cooling Water (CCW) System).

EXAMINER NOTE: No notifications required at this time.

Page 8 of 28

CNS 2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 4 Event No. 4 4 Page(s)

Event

Description:

KC surge tank level fails low, KC trains separate and no A train KC can be started, requires NV pump swap Time Position Applicant's Actions or Behavior SRO 17 Determine required notifications:

• REFER TO RP/0/A/5000/001 (Classification Of Emergency)

• REFER TO RP/0/B/5000/013 (NRC Notification Requirements).

BOP 18 IF KC Hx leak to RN is suspected, THEN ...

BOP 19 Verify KC surge tanks level as follows:

• Greater than 50%

• Stable or increasing.

BOP 20 WHEN plant conditions permit, THEN:

• Return KC pumps to normal operation. REFER TO OP/1/A/6400/005 (Component Cooling Water System).

• Return NV Pump 1A to normal cooling as applicable. REFER TO Enclosure 4 (Alternate Cooling To NV Pump 1A).

BOP 21 Verify the following:

• 1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK

• 1AD-7, H/3 "VCT HI TEMP" - DARK

• Normal letdown - IN SERVICE.

BOP 22 Ensure VCT and letdown path aligned as follows:

a. IF desired to align NV pump suction to VCT, then perform the following:

1) Open the following valves:

• 1NV-188A (VCT Otlt Isol)

• 1NV-189B (VCT Otlt Isol).

2) Close the following valves:

• 1NV-252A (NV Pumps Suct From FWST)

• 1NV-253B (NV Pumps Suct From FWST).

b. WHEN NV suction aligned to VCT, THEN momentarily place 1NV-172A (3-Way Divert To VCT-RHT) to the "VCT" position and return to "AUTO".

c. IF desired to restore letdown flow through the NV demineralizers, THEN momentarily place 1NV-153A (Letdn Hx Otlt 3-Way VI v) to the "DEMIN" position and return to "AUTO".

SRO 23 Determine long term plant status. RETURN TOprocedure in affect.

EXAMINER NOTE: The following steps swap NV pumps per Enclosure 4.13 of OP/11A16200/001 (Chemical and Volume Control System).

NV Pump information: OAC Point C1P0015 Hi - 203°F, Hi-Hi - 220°F 1.1 Review the Limits and Precautions.

1.2 IF in Mode 1 or 2, ensure R3 reactivity management controls established per SOMP 01-02 (Reactivity Management). (R.M.)

1.3 Verify the NV System is in operation per one of the following:

• Enclosure 4.1 (Establishing Charging Flow And Seal Injection Flow)

• Enclosure 4.26 (Establishing/Securing NV Charging With ND Letdown)

Page 9 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 4 4 Page(s)

Event

Description:

KC surge tank level fails low, KC trains separate and no A train KC can be started, requires NV pump swap Time Position Applicant's Actions or Behavior NOTE: This enclosure will affect reactivity of the core and is therefore designated important to Reactivity Management per the guidelines of NSD 304 (Reactivity Management). (R.M.)

2.1 Shift the operating centrifugal charging pump by completing the following steps:

EXAMINER NOTE: If the crew considers this an "emergency situation", they will NOT wait the 30 seconds per the note.

CAUTION: If an NV Pump has been idle for an extended period of time, a boron transient may be initiated when it is placed in service. The volume of 1A NV Pump and associated piping is 103 gallons, the volume of 1B NV Pump and associated piping is 65 gallons; the magnitude of the transient will be minimal.

NOTE: If in an emergency situation, the 30 second delay after starting the Aux Oil Pump isNOT required before starting the NV pump.

2.1.1 Ensure VCT pressure is between 18-40 psig as read on 1NVP5500 (VCT Vent Press) (1 MC5).

2.1.2 30 seconds prior to starting the idle NV pump, place its associated aux oil pump in the "ON" position:

• "NV PUMP 1A AUX OIL PUMP"

• "NV PUMP 1B AUX OIL PUMP" 2.1.3 Start the idle NV pump. (R.M.)

• "NV PUMP 1A"

• "NV PUMP 1B" 2.1.4 Place the NV pump aux oil pump started in Step 2.1.2 in "AUTO".

2.1.5 Stop the previously running NV pump:

• "NV PUMP 1A"

• "NV PUMP 1B" 2.1.6 Verify proper charging flow rate.

END EVENT Page 10 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 5 1 Page(s)

Event

Description:

1NV-148 fails to 20% open in auto/manual control available Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using OP/1/B/6100/010H (Annunciator Response For PaneI1AD-7).

Pertinent Alarms 1AD-7 F/1 - LETDN HX OUTLET HI PRESS IMMEDIATE ACTIONS BOP 1. Verify alarm using 1NVP5570 (Letdn Press) (1 MC5).

BOP 2. Take manual control of 1NV-148 (Letdn Press Control) and attempt to restore pressure to normal.

BOP 3. Verify proper orifice selection and letdown line valve alignment.

SUPPLEMENTAL ACTIONS BOP 1. IF necessary, place excess letdown in service per OP/1/A/62001001 (Chemical

& Volume Control System). .

BOP 2. Determine and correct cause of alarm.

END EVENT Page 11 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 6 3 Page(s)

Event

Description:

CFP trip/ T/G runback with rods fail to move Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is a COMPONENT event using AP/1/A15500/003 (Load Rejection), Case I - Switchyard Available.

Pertinent Alarms 1AD-5 A11 CFPT A TRIPPED 1AD-5 A14 CFPT A COMMON TROUBLE 1AD-5 A15 CFPT A HI DISCH PRESS EXAMINER NOTE: Runback Target for this event is approximately 65%

reactor power.

RO 1. Verify turbine load - DECREASING IN AUTOMATIC RO 2. Verify proper reactor response:

• Control rods - IN "AUTO" AND STEPPING

• P/R neutron flux - DECREASING RO 2RNO IF T-Avg is greater than 1.5°F higher than T-Ref, THEN manually insert T-Av~_ within IN 1°F of T-Ref.

control rods as required to maintain T-Avg RO 3. Verify proper steam dump operation as follows:

a. Verify T-Ref instrumentation - AVAILABLE

b. "C-9 COND AVAILABLE FOR STM DUMP" status light (1SI-18) - LIT

c. Verify the following:

• "C-7A LOSS OF LOAD INTLK COND DUMP" status light (1SI-18) - LIT

• Steam dump valves - MODULATING

d. T-Avg - DECREASING TO T-REF.

BOP 4. Verify Pzr PORV and Pzr spray valve status as follows:

a. All Pzr PORVs - CLOSED

b. Normal Pzr spray valves - CLOSED BOP 5. Verify proper CM System operation as follows:

a. WHEN reactor power is less than 75%, THEN ensure both C-htr drain pumps-OFF.

b. Verify reactor power - GREATER THAN 56% PRIOR TO THE EVENT.

c. Verify standby hotwell pump(s) - ON BOP 5cRNO c. Manually Manuallystart start standby hotwell pump(s) as necessary BOP 5d. Verify standby condensate booster pump(s) - ON BOP 5dRNO. Manually start standby condensate booster pump(s) as necessary.

BOP 6. Verify the following generator alarms - DARK

• 1AD-11, C/1 "GEN BKR A OVER CURRENT"

• 1AD-11, F/1 "GEN BKR B OVER CURRENT" RO 7. Verify S/G levels are adequate as follows:

• All S/G low level alert alarms (1AD-4) - DARK

• All S/G low CF flow alarms (1AD-4) - DARK RO 8. Verify reactor reactorpower power - GREATER THAN 20%.

RO 9. IF AT ANY TIME reactor power is less than or equal to 20%, THEN perform Step 8 RNO.

BOP 10. Verify AS header pressure - GREATER THAN OR EQUAL TO 140 PSIG BOP 11. Adjust 1TL-4 (Stm Seal Reg Byp) as necessary to maintain steam seal pressure between 4 PSIG - 6 PSIG.

Page 12 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 6 3 Page(s)

Event

Description:

CFP tripl TIG run back with rods fail to move Time Position Applicant's Actions or Behavior EXAMINER NOTE: Enclosure 3 steps are at the end of this section.

RO 12. Monitor Enclosure 3 (Rod(Rod Insertion Limit Boration)

RO power - LESS THAN 30%

13. Verify reactor power RO 13RNO Perform the following:

a. IF the runback target load is less than 30%, THEN: ...

b. WHEN the appropriate runback target load is reached, THEN:

1) Stabilize unit at current power level.

2) Maintain control rods above insertion limits.

3) Adjust the following as required to maintain T-Avg within 1°F of T-Ref:

• Turbine load

• Control rods

• Boron concentration.

c. GO TO Step 15.

BOP 15. Verify the following PCBs - CLOSED:

• Generator breaker 1A

• Generator breaker 1B

• PCB 14

• PCB 15

• PCB 17

• PCB 18 RO 16. Adjust power factor as necessary. REFER TO Unit 1 Revised Data Book Figure 43 RO 17. WHEN the appropriate runback target load is reached, THEN:

• Stabilize unit at appropriate power level.

• Maintain control rods above insertion limits.

• Adjust the following as required to maintain T-Avg within 1°F of T-Ref:

0 Turbine load 0 Control rods 0 Boron concentration RO 18. Notify System Operating Center (SOC) using the red dispatcher telephone of current unit status ALL 19. Determine and correct cause of load rejection EXAMINER NOTE: This is where the next event is scheduled to begin.

Enclosure 3 actions Page 13 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 6 3 Page(s)

Event

Description:

CFP trip/ T/G runback with rods fail to move Time Position Applicant's Actions or Behavior

1. IF the control rods cannot be maintained above the rod insertion limits, THEN:

a. Stop any dilutions in progress.

CAUTION Failure to initiate boration within one hour of exceeding rod insertion limits may violate Tech Spec 3.1.6.

NOTE OAC point C1 L4409 (Ctrl Bank Tech Spec Insertion Lmt Reached) and RO.D Book (Section 2.2) provide rod insertion limit indication.

b. Borate NC system as required, to restore rods above insertion limits.

c. Ensure compliance with Tech Spec 3.1.6 (Control Bank Insertion Limits).

END EVENT Page 14 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 7 14 Page(s)

Event

Description:

Loss of all AC power/ Large Break LOCA Additional Failures: 1B CA pump fails to autostart, 1NI-1 OB and 1NI-184B failed auto actions, FWST puncture Time Position Applicant's Actions or Behavior EXAMINER NOTE: This is the MAJOR event and starts in EP/1/A/5000/E-O (Reactor Trip or Safety Injection)

EXAMINER NOTE: The crew may go directly to ECA-O.O. If so, when they transition back to E-O it will be to Step 1.

ALL 1. Monitor Enclosure 1 (Foldout Page)

RO 2. Verify Reactor Trip:

• All rod bottom lights - LIT

• All reactor trip and bypass breakers - OPEN

• I/R amps - DECREASING RO Verify Turbine Trip:

• All turbine stop valves - CLOSED BOP 4. Verify 1ETA and 1ETB - ENERGIZED.

BOP 4RNO Perform the following:

a. IF 1ETA AND 1ETB are de-energized, THEN GO TO EP/1/A/5000/ECA-0.0 (Loss Of All AC Power).

T SRO Transition to ECA-O.O (Loss Of All AC Power).

ALL 1. CSF Status trees should be monitored for information only. Do not exit this procedure to implement any of the CSF procedures.

RO 2. Verify Reactor Trip:

• All rod bottom lights - LIT

• Reactor trip and bypass breakers - OPEN

• IIR amps - DECREASING.

RO 3. Verify Turbine Trip:

• All turbine stop valves - CLOSED BOP 4. Establish NC pump seal injection from the SSF:

• Notify Security Officer at SSF (Ext. 5251 or 5212) to perform EP/1/A/5000/ECA-0.0 (Loss Of All AC Power), Enclosure 2 (Establishing NC Makeup/Seal Injection From The SSF)

• Dispatch operator to 1ETA switchgear room to align alternate power supply to 1EMXS. REFER TO Enclosure 1 (Align Alternate Power Supply To 1EMXS)

• Dispatch operator to SSF to establish NC pump seal injection. REFER TO Enclosure 2 (Establishing NC Makeup/Seal Injection From The SSF).

Page 15 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 7 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Additional Failures: 1B CA pump fails to autostart, 1NI-1 OB and 1NI-184B failed auto actions, FWST puncture Time Position Applicant's Actions or Behavior BOP 5. Verify NC System is isolated as follows:

a. All Pzr PORVs - CLOSED.

b. All the following letdown isolation valves - CLOSED:

• 1NV-1 OA (Letdn Orif 1B Otlt Cont Isol)

• 1NV-11 A (Letdn Orif 1C Otlt Cont Isol)

• 1NV-13A (Letdn Orif 1A Otlt Cont Isol)

• 1NV-1A (NC Letdn To Regen Hx Isol)

• 1NV-2A (NC Letdn To Regen Hx Isol)

• 1NV-135 (ND Flow To Letdn Hx).

c. All the following excess letdown isolation valves - CLOSED:

• 1NV-122B (Loop C To Exs Letdn Hx Isol)

• 1NV-123B (Loop C To Exs Letdn Hx Isol)

• 1NV-124B (Excess Letdn Press Ctrl).

BOP 6. Verify total CA flow - GREATER THAN 450 GPM.

CT BOP 7. Attempt to restore power to 1ETA or 1ETB as follows:

a. Manually start DIGs from control room.

EXAMINER NOTE: 2.S minutes after the SII is initiated, a LB LOCA occurs.

BOP 7a.RNO Perform the following:

1) Manually initiate SII to emergency start D/G(s).

2) IF no DIG can be started, THEN GO TO Step 8.

T EXAMINER NOTE: Crew will transition to FR-P.1 briefly but kick back out due to flow to cold legs from NO on the LB LOCA.

BOP 7b. Verify at least one DIG load sequencer - AUTOMATICALLY LOADING BUS.

c. Verify 1ETA or 1ETB - ENERGIZED.

d. Implement EP/1/A15000/F-0 (Critical Safety Function Status Trees).

e. RETURN TO procedure and step in effect.

T SRO Transition back to E-O Step 5.

BOP 5a. "SAFETY INJECTION ACTUATED" status light (1SI-13) - LIT.

b. Both EIS load sequencer actuated status lights (1 SI-14) - LIT.

BOP 5bRNO b. Manually initiate S/I.

EXAMINER NOTE: By approximately this point a Large Break LOCA will occur.

RO 6. Announce "Unit 1 Safety Injection".

EXAMINER NOTE: Notifications are 4.S.A.2 or 4.1.A.1 (ALERTS)

SRO 7. Determine required notifications:

• REFER TO RP/0IAl50001001 (Classification Of Emergency)

• REFER TO RP/0/B/50001013 (NRC Notification Requirements).

RO 8. Verify all Feedwater Isolation status lights (1 SI-5) - LIT.

Page 16 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. - --- -4' --

Event No. - --'------

14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Additional Failures: 1B CA pump fails to autostart, 1NI-1 OB and 1NI-184B failed auto actions, FWST puncture Time Position Applicant's Actions or Behavior BOP 9. Verify Phase A Containment Isolation status as follows:

a. Phase A "RESET" lights - DARK.

b. Monitor Light Panel Group 5 St lights - LIT.

EXAMINER NOTE: Once the LB LOCA occurs the crew should go back and perform Step 10 again. Initially, depending on crew speed, they may be past Step 10 when the LOCA occurs and NOT perform the RNO at this time.

BOP 10. Verify proper Phase B actuation as follows:

a. Containment pressure - HAS REMAINED LESS THAN 3 PSIG.

BOP 10aRNO

a. Perform the following:

NOTE This time may be used later to determine when to align ND Aux spray.

1) Record approximate time of reactor trip.

2) Verify NS pumps -INDICATING FLOW.

3) IF flow is not indicated, THEN manually initiate Phase B Isolation for affected train( s).

4) Verify Phase B Isolation hasactuated as follows:

a) Phase B Isolation "RESET" lights - DARK.

b) IF Phase B Isolation "RESET" lights are lit, THEN manually initiate Phase B Isolation.

c) Verify following monitor light panel lights - LIT:

• Group 1 Sp lights

• Group 5 Sp lights

• Group 5 St lights U11 and U12.

d) IF monitor light panel not in correct alignment, THEN ensure correct alignment.

e) IF NS pump(s) did not start, THEN perform the following for the affected train( s):

(1) Reset ECCS.

(2) Reset DIG load sequencer.

(3) Manually start affected NS pump.

(4) IF AT ANY TIME a BIO occurs, THEN restart SII equipment previously on.

(5) Stop all NC pumps.

(6) Maintain seal injection flow.

(7) WHEN 9 minutes has elapsed, THEN verify proper VX system operation. REFER TO Enclosure 7 (VX System Operation).

(8) GO TO Step 11.

BOP 11 Verify proper CA pump status as follows:

a. Motor driven CA pumps - ON.

Page 17 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 7 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Additional Failures: 1B CA pump fails to autostart, 1NI-1 OB and 1NI-184B failed auto actions, FWST puncture Time Position Applicant's Actions or Behavior BOP 11aRNO

a. Perform the following for the affected train(s):

1) Reset ECCS.

2) Reset DIG load sequencer.

3) Manually start affected motor driven CA pump.

4) IF AT ANY TIME a BIO occurs, THEN restart S/I equipment previously on.

RO 11 b. 3 S/G NIR levels - GREATER THAN 11 %.

BOP 12 Verify all of the following SII pumps - ON:

• NV pumps

• NO pumps

• NI pumps.

BOP 13 Verify all KC pumps - ON.

BOP 14 Verify all Unit 1 and Unit 2 RN pumps - ON.

EXAMINER NOTE: Enclosure 2 actions are after step 26.

BOP 15 Verify proper ventilation systems operation as follows:

• REFER TO Enclosure 2 (Ventilation System Verification).

• Notify Unit 2 operator to perform Enclosure 3 (Opposite Unit Ventilation Verification ).

RO 16 Verify all S/G pressures - GREATER THAN 775 PSIG.

BOP 17 Verify proper S/I flow as follows:

a. "NV SII FLOW" - INDICATING FLOW.

b. NC pressure - LESS THAN 1620 PSIG.

c. NI pumps - INDICATING FLOW.

d. NC pressure - LESS THAN 285 PSIG.

e. NO pumps - INDICATING FLOW TO C-LEGS.

BOP 18 Control S/G levels as follows:

a. Verify total CA flow - GREATER THAN 450 GPM.

b. WHEN at least one S/G NIR level is greater than 11 % (29% ACC), THEN throttle feed flow to maintain all S/G NIR levels between 11 % (29% ACC) and 50%.

BOP 19 Verify all CA isolation valves - OPEN.

eT EXAMINER NOTE: If not already addressed, the BOP should note that 1NI*

10B is closed and open it manually. This is a critical step.

BOP 20 Verify SII equipment status based on monitor light panel - IN PROPER ALIGNMENT.

BOP 20RNO Manually align equipment.

EXAMINER NOTE: Enclosure 4 actions are listed after Enclosure 2 actions.

Page 18 of 28

CNS '2008 NRC Exam Appendix 0, Rev. 9 Required Operator Actions Form ES-O-2 Op-Test No. NRC Scenario No. 4 Event No. 7 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Additional Failures: 1B CA pump fails to autostart, 1NI-10B and 1NI-184B failed auto actions, FWST puncture Time Position Applicant's Actions or Behavior RO NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until subsequent procedures provide alternative NC temperature control guidance.

21 Control NC temperature. REFER TO Enclosure 4 (NC Temperature Control).

BOP 22 Verify Pzr PORV and Pzr spray valve status as follows:

a. All Pzr PORVs - CLOSED.

b. Normal Pzr spray valves - CLOSED.

c. At least one Pzr PORV isolation valve - OPEN.

RO 23 Verify NC subcooling based on core exit TICs - GREATER THAN OaF.

BOP 23RNO IF any NV OR NI pump is on, THEN:

a. Ensure all NC pumps" OFF.

b. Maintain seal injection flow.

RO 24 Verify main steam lines are intact as follows:

• All S/G pressures - STABLE OR INCREASING

• ALL S/Gs - PRESSURIZED.

BOP 25 Verify S/G tubes are intact as follows:

• Verify the following EMF trip 1 lights - DARK:

• 1EMF-33 (Condenser Air Ejector Exhaust)

• 1EMF-26 (Steamline 1A)

• 1EMF-27 (Steamline 1B)

• 1EMF-28 (Steamline 1C)

• 1EMF-29 (Steamline 1D).

• All S/G levels - STABLE OR INCREASING IN A CONTROLLED MANNER.

BOP 26 Verify NC System is intact as follows:

• Containment pressure - LESS THAN 1 PSIG.

• IF normal off-site power is available, THEN verify containment pressure less than 0.3 PSIG.

• Containment high range EMFs - LESS THAN 3 RlHR:

• 1EMF~53A (Containment Trn A)

• 1EMF-53B (Containment Trn B).

• Containment EMF trip 1 lights - DARK:

• 1EMF-38 (Containment Particulate)

• 1EMF-39 (Containment Gas).

• Containment sump level - STABLE.

Page 19 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. - - 4- Event No. 7 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Additional Failures: 1B CA pump fails to autostart, 1NI-1 OB and 1NI-184B failed auto actions, FWST puncture Time Position Applicant's Actions or Behavior BOP 26RNO Perform the following:

a. IF both the following conditions exist,

• Containment pressure - GREATER THAN 1 PSIG

• Containment pressure - HAS REMAINED LESS THAN 3 PSIG THEN manually start one VX fan. REFER TO Enclosure 5 (VX Fan Manual start).

b. Concurrently:

• Implement EP/1/A15000/F-0 (Critical Safety Function Status Trees).

• GO TO EP/1/A15000/E-1 (Loss Of Reactor Or Secondary Coolant).

E-O, Enclosure 2 steps BOP 1. Verify proper VCIYC operation as follows:

a. Verify one train of the following equipment is in operation:

• YC chiller

• CR AHU-1

• CRA AHU-1

• CRA PFT-1.

b. Verify the following alarms - DARK:

• 1AD-18, Al8 "UNIT 1 INTAKE HI CHLORINE 1A"

• 1AD-18, B/8 "UNIT 1 INTAKE HI CHLORINE 1B"

• 1AD-18, D/8 "UNIT 2 INTAKE HI CHLORINE 2A"

• 1AD-18, E/8 "UNIT 2 INTAKE HI CHLORINE 2B".

c. Ensure the following VC dampers - OPEN:

• 1VC-5B (CRA Filt Inlet)

• 1VC-6A (CRA Filt Inlet)

• 2VC-5B (CRA Filt Inlet)

• 2VC-6A (CRA Filt Inlet).

d. Repeat Step 1 of this enclosure until notified by station management as follows:

• At least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> OR

• Any-time VCIYC related annunciators on 1AD-18 actuate.

BOP 2. Ensure proper VA System operation as follows:

• Ensure the following fans - OFF:

o ABUXF 1A o ABUXF 1B.

• Ensure VA System filter is in service as follows:

o 1ABF-D-12 (VA Filt A Bypass Damper) - CLOSED o 1ABF-D-5 (VA Filt B Bypass Damper) - CLOSED.

• Ensure the following fans - ON:

o ABFXF-1A o ABFXF 1B.

Page 20 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 7 14 Page(s)

Event

Description:

Loss of all AC power/ Large Break LOCA Additional Failures: 1B CA pump fails to autostart, 1NI-1 OB and 1NI-184B failed auto actions, FWST puncture Time Position Applicant's Actions or Behavior BOP 3. Verify proper VE System operation as follows:

a. VE fans - ON.

b. Annulus pressure - BETWEEN -1.4 IN. WC AND -1.8 IN. WC.

c. Repeat Step 3.b every 30 minutes until notified by station management.

BOP 4. Record time ventilation systems are verified on following table:

E-O Enclosure 4 actions RO 1. Verify at least one NC pump - ON.

RO 1RNO. Perform the following:

a. Use NC T-Colds to determine NC temperature as required in subsequent steps.

b. GO TO Step 4.

RO 4. Verify one of the following:

• NC temperature - STABLE AT LESS THAN OR EQUAL TO 55rF.

OR

• NC temperature - TRENDING TO 55rF.

SRO 4RNO GO TO Step 7.

RO 7. Verify NC temperature - LESS THAN 55rF AND DECREASING.

RO 8. Attempt to stop the NC cooldown as follows:

a. Ensure all steam dumps - CLOSED.

b. Ensure all S/G PORVs - CLOSED.

c. Ensure S/G blowdown is isolated.

d. Close the following valves:

• 1SM-77A (S/G 1A Otlt Hdr Bldwn CN)

• 1SM-76B (S/G 1B Otlt Hdr Bldwn CN)

• 1SM-75A (S/G 1C Otlt Hdr Bldwn CN)

• 1SM-74B (S/G 1D Otlt Hdr Bldwn CN).

e. Depress and hold "SN BEFORE SEAT DRN" "CLOSE" pushbutton (1MC-3) to close the following valves:

• 1SM-41 (Stop Vlv #1 Before Seat Drn)

• 1SM-44 (Stop Vlv #2 Before Seat Drn)

• 1SM-43 (Stop Vlv #3 Before Seat Drn)

• 1SM-42 (Stop Vlv #4 Before Seat Drn).

f. Verify NC cooldown - STOPPED.

Page 21 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 7 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Additional Failures: 1B CA pump fails to autostart, 1NI-1 OB and 1NI-184B failed auto actions, FWST puncture Time Position Applicant's Actions or Behavior RO 8fRNO.

f. IF cooldown continues, THEN throttle feed flow as follows:

1) IF S/G N/R level is less than 11 % (29% ACC) in all S/G's, THEN throttle feed flow to achieve the following:

• Minimize cooldown

• Maintain total feed flow greater than 450 GPM.

2) WHEN N/R level is greater than 11 % (29% ACC) in at least one S/G, THEN throttle feed flow further to achieve the following:

• Minimize cooldown

• Maintain at least one S/G N/R level greater than 11 % (29% ACC).

3) IF cooldown continues, THEN close the following valves:

• All MSIVs

• All MSIV bypass valves.

RO 9. Continue to perform the actions of this enclosure as required to ensure one of the following:

• NC temperature - STABLE AT LESS THAN OR EQUAL TO 55rF.

OR

• NC temperature - TRENDING TO 55rF.

T SRO Transition to EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant).

ALL 1. Monitor Enclosure 1 (Foldout Page).

RO 2. Verify main steamlines are intact as follows:

• All S/G pressures - STABLE OR INCREASING OR

• All S/Gs - PRESSURIZED.

BOP 3. Control intact S/G levels as follows:

a. Verify N/R level in all intact S/Gs - GREATER THAN 11 % (29% ACC).

b. Throttle feed flow to maintain all intact S/G N/R levels between 11 % (29%

ACC) and 50%.

Page 22 of 28

CNS 2008 NRC Exam Append ix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 7 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Additional Failures: 1B CA pump fails to autostart, 1NI-1 OB and 1NI-184B failed auto actions, FWST puncture Time Position Applicant's Actions or Behavior BOP 4. Verify secondary radiation is normal as follows:

a. Ensure the following signals - RESET:

1) Phase A Containment Isolations

2) CA System valve control

3) KC NC NI NM St signals.

b. Align all S/Gs for Chemistry sampling.

c. Perform at least one of the following:

• Notify Chemistry to sample all S/Gs for activity.

OR

• Notify RP to frisk all cation columns for activity.

d. Verify the following EMF trip 1 lights - DARK:

• 1EMF-33 (Condenser Air Ejector Exhaust)

• 1EMF-26 (Steam line 1A)

• 1EMF-27 (Steamline 1B)

• 1EMF-28 (Steam line 1C)

• 1EMF-29 (Steam line 1D).

e. WHEN activity results are reported, THEN verify all S/Gs indicate no activity.

BOP 5. Verify Pzr PORV and isolation valve status as follows:

a. Power to all Pzr PORV isolation valves - AVAILABLE.

b. All Pzr PORVs - CLOSED.

c. At least one Pzr PORV isolation valve - OPEN.

d. IF AT ANY TIME a Pzr PORV opens due to high pressure, THEN, after Pzr pressure decreases to less than 2315 PSIG, ensure the valve closes or is isolated.

RO 6. Verify S/I termination criteria as follows:

a. NC subcooling based on core exit TICs - GREATER THAN O°F.

SRO 6aRNO GO TO Step 6.f.

ALL 6f. Monitor S/I termination criteria. REFER TO Enclosure 2 (S/I Termination Criteria).

g. IF AT ANY TIME S/I termination criteria is met while in this procedure, THEN RETURN TO Step 6.

BOP 7. Verify proper NS pump operation as follows:

a. At least one NS pump - ON.

b. Verify the following valves - OPEN:

• 1FW-27A (ND Pump 1A Suct From FWST).

• 1FW-55B (ND Pump 1B Suct From FWST).

c. Containment pressure - LESS THAN 2.4 PSIG.

EXAMINER NOTE: Pressure may be less than 2.4 psig and 7cRNO will not be required.

Page 23 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 7 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Additional Failures: 1B CA pump fails to autostart, 1NI-10B and 1NI-184B failed auto actions, FWST puncture Time Position Applicant's Actions or Behavior BOP 7cRNO Perform the following:

1) WHEN containment pressure is less than 2.4 PSIG, THEN perform Step 7.

2) GO TO Step 8.

BOP 7d. Verify operating NS pump(s) - HAVE REMAINED RUNNING SINCE INITIAL PHASE B SIGNAL.

e. Ensure SII - RESET:

1) ECCS.

2) DIG load sequencers.

3) IF AT ANY TIME a B/O occurs,THEN restart SII equipment previously on.

f. Reset NS.

g. Stop NS pumps.

h. Close the following valves:

• 1NS-29A (NS Spray Hdr 1A Cont Isol)

• 1NS-32A (NS Spray Hdr 1A Cont Isol)

• 1NS-15B (NS Spray Hdr 1B Cont Isol)

• 1NS-12B (NS Spray Hdr 1B Cont Isol).

BOP 8. Verify criteria to stop operating ND pumps as follows:

a. NC pressure - GREATER THAN 285 PSIG.

SRO 8a.RNO

a. GO TO Step 10.

BOP 10. Verify conditions to stop operating DIGs as follows:

a. At least one DIG - ON.

b. Verify 1ETA is energized by offsite power as follows:

• "DIG 1A BKR TO ETA" - OPEN

• 1ETA - ENERGIZED.

BOP 10bRNO

b. Perform the following:

1) Attempt to restore offsite power to affected switchgear. REFER TO AP/1/A/55001007 (Loss of Normal Power).

2) GO TO Step 10.d.

BOP 10d. Verify 1ETB is energized by offsite power as follows:

• "DIG 1B BKR TO ETB" - OPEN

• 1ETB - ENERGIZED.

BOP 10dRNO

d. Perform the following:

1) Attempt to restore offsite power to affected switchgear. REFER TO AP/1/A/55001007 (Loss of Normal Power).

2) IF 1ETA is energized from offsite power, THEN GO TO Step 10.f.

3) GO TO Step 11.

Page 24 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. - - 4- Event No. - 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Additional Failures: 1B CA pump fails to autostart, 1NI-1 OB and 1NI-184B failed auto actions, FWST puncture Time Position Applicant's Actions or Behavior BOP 11. Obtain containment H2 concentration as follows:

a. Ensure operator has been dispatched to secure all ice condenser air handling units. REFER TO Enclosure 3 (Securing All Ice Condenser Air Handling Units).

b. Verify containment H2 analyzers - IN SERVICE.

BOP 11bRNO

b. Perform the following:

1) Dispatch operator to place containment H2 analyzers in service. REFER TO OP/1/A/64S01010 (Containment Hydrogen Control System).

2) WHEN H2 analyzers are in service, THEN perform Steps 11.c through 11.e.

3) GO TO Step 12.

BOP 12. Initiate evaluation of plant status as follows:

a. Verify S/I systems - ALIGNED FOR INJECTION MODE.

b. Verify Cold Leg Recirc capability as follows:

1) At least one NO pump - AVAILABLE.

2) Verify power to all of the following valves - AVAILABLE:

• 1FW-27A(ND Pump 1ASuct From FWST)

• 1NI-18SA (NO Pump 1A Cont Sump Suct)

• 1ND-28A (NO Supply To NV & NI Pmps)

• 1FW-SSB (NO Pump 1B Suct

• 1NI-184B (NO Pump 1B Cont Sump Suct)

• 1NI-332A (NI Pump Suct X-Over From NO)

• 1NI-333B (NI Pump Suct From NO)

• 1NI-334B (NI Pump Suct X-Over From NO)

• 1NI-136B (NO Supply To NI Pump 1B).

BOP 12b2)RNO

2) Perform the following:

IF power cannot be verified to minimum number of valves required to perform the following:

• Transfer one train of NO to the containment sump

• Establish NO flow from containment sump to one train of NV and NI pumps.

THEN GO TO EP/1/A/SOOO/ECA-1.1 (Loss Of Emergency Coolant NO)

BOP 12b3) Verify power to all of the following valves - AVAILABLE:

• 1NI-11SA (NI Pump 1A Miniflow Isol)

• 1NI-144A (NI Pump 1B Miniflow Isol)

• 1NI-147B (NI Pump Miniflow HdrTo FWST Isol).

Page 25 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 7 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Additional Failures: 1B CA pump fails to autostart, 1NI-10B and 1NI-184B failed auto actions, FWST puncture Time Position Applicant's Actions or Behavior BOP 12b3)RNO IF power cannot be verified to valves minimum number of valves required to isolate NI pump miniflow, THEN perform the following:

• Attempt to restore power to miniflow isolation valve(s)

• Have operator standing by to locally close the required valve:

• 1NI-147B (NI Miniflow Hdr To FWST Isol) (AB-548, HH-JJ, 53-54, Rm 234)

• 1NI-115A (NI Pump 1A Miniflow Isol) (AB-549, GG-HH, 53-54, Rm 235)

• 1NI-144A (NI Pump 1B Miniflow Isol) (AB-548, HH-JJ, 53-54, Rm 234).

BOP 12b4) Verify the "ENABLE" lights for the following switches - LIT

• "C-LEG RECIR FWST TO CONT SUMP SWAP TRN A"

• "C-LEG RECIR FWST TO CONT SUMP SWAP TRN B".

BOP c. Verify auxiliary building radiation is normal as follows:

• EMF-41 (Aux Bldg Ventilation) trip 1 light - DARK

• All area monitor EMF trip 1.lights - DARK.

d. WHEN the TSC is activated AND staffed, THEN:

1) Notify the Reactor Engineer to assess core damage. REFER TO RP/O/A/50001015 (Core Damage Assessment).

2) Notify Chemistry to obtain current NC boron concentration.

3) WHEN NO is aligned for Cold Leg Recirc, THEN notify Chemistry to obtain current containment sump boron concentration.

4) Notify Operating Engineer of the following:

a) VA is required to be aligned to normal within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the event.

b) Evaluate aligning VA to normal mode. REFER TO OP/O/A/64501003 (Auxiliary Building Ventilation System).

e. Notify station management to evaluate starting additional plant equipment to assist in recovery.

BOP 13. Verify NC System cooldown and depressurization is required as follows:

a. NC pressure - GREATER THAN 285 PSIG BOP 13a.RNO IF NO flow to C-Legs is greater than 675 GPM, THEN GO TO Step 14.

BOP 14. Verify transfer to Cold Leg Recirc as follows:

a. FWST level - LESS THAN 37% (1AD-9, 0/8 "FWST 2/4 LO LEVEL" - LIT).

EXAMINER NOTE: FWST will likely not be at 37% at this time, but transition will occur at 37% based on Enclosure 1 actions. The procedure loops until that time.

SRO 14a RNO. RETURN TO Step 11.

T Transition to EP/1/A/5500/ES-1.3 ALL 1. Monitor Enclosure 1 (Foldout Page).

Page 26 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. 4 Event No. 7 14 Page(s)

Event

Description:

Loss of all AC powerl Large Break LOCA Additional Failures: 1B CA pump fails to autostart, 1NI-1 OB and 1NI-184B failed auto actions, FWST puncture Time Position Applicant's Actions or Behavior ALL CAUTION SII recirculation flow to NC System must be maintained at all times.

NOTE

• Steps 2 through 8 should be performed without delay.

• CSF should not be implemented until directed by this procedure.

BOP 2. Verify at least one of the following annunciators - LIT:

• 1AD-20, B/3 "CO NT. SUMP LEVEL >3.3 ft"

• 1AD-21, B/3 "CO NT. SUMP LEVEL >3.3 ft".

BOP 3. Verify KC flow to ND heat exchangers - GREATER THAN 5000 GPM.

BOP 3RNO Establish KC flow to affected ND Hx(s).

BOP 4. Ensure SII - RESET:

a. ECCS.

b. DIG load sequencers.

c. IF AT ANY TIME a BIO occurs, THEN restart S/I equipment previously on.

EXAMINER NOTE: Only B train valves can be aligned due to lack of A train power. The crew will evaluate the RNOs but no actions will be taken based solely on lack of power. 1NI-184B did not open in auto but will be opened manually through the RNO step.

BOP 5. Align SII system for reCirc as follows:

a. Verify following valves - OPEN:

• 1NI-185A (ND Pump 1A Cont Sump Suct)

• 1NI-184B (ND Pump 1B Cont Sump Suct).

CT BOP 5aRNOa. Perform the following:

1) Manually open affected valve(s).

2) IF valve(s) will not open, THEN:

a) Stop the ND pump(s) associated with a closed containment sump suction valve(s).

b) Close the associated ND pump(s) suction valve from the FWST:

• 1FW-27A (ND Pump 1A Suct From FWST)

• 1FW-55B (ND Pump 1B Suct From FWST) c) WHEN the ND pump(s) suction valve from the FWST is closed, THEN perform the following:

(1 ) Attempt to manually open the affected containment sump suction valve(s).

• 1NI-185A (ND Pump 1A Cont Sump Suct)

• 1NI-184B (ND Pump 1B Cont Sump Suct) .

(2) IF affected containment sump suction valve will not open, THEN ...

3) IF both containment sump suction valves are closed, THEN:

Page 27 of 28

CNS 2008 NRC Exam Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No. NRC Scenario No. - - 4- Event No. - -

7- 14 Page(s)

Event

Description:

Loss of all AC power/ Large Break LOCA Additional Failures: 1B CA pump fails to autostart, 1NI-10B and 1NI-184B failed auto actions, FWST puncture Time Position Applicant's Actions or Behavior BOP 5b. Verify following valves - CLOSED:

• 1FW-27 A (NO Pump 1A Suct From FWST)

• 1FW-55B (NO Pump 1B Suct From FWST).

c. Verify NO pumps - ON.

d. Isolate NI pump miniflow as follows:

1) Verify NC pressure - LESS THAN 1620 PSIG.

2) Close the following valves:

• 1NI-115A (NI Pump 1A Miniflow Isol)

• 1NI-144A (NI Pump 1B Miniflow Isol).

3) Place "PWR DISCON FOR 1NI-147B" switch in "ENABLE".

4) Close 1NI-147B (NI Pump Miniflow Hdr To FWST Isol).

e. Close the following valves:

• 1ND-32A (NO Train 1A Hot Leg Inj Isol)

• 1ND-65B (NO Train 1B Hot Leg Inj Isol).

f. Verify at least one of the following NV pumps miniflow valves - CLOSED:

• 1NV-203A (NV Pumps A&B Recirc Isol)

OR

• 1NV-202B (NV Pmps A&B Recirc Isol).

g. Align NO train discharges to NI and NV pump suctions as follows:

1) Open the following valves:

• 1NI-332A (NI Pump Suct X-Over From NO)

• 1NI-333B (NI Pump Suct From NO).

2) Ensure 1NI-334B (NI Pump Suct X-Over From NO) - OPEN.

3) Open the following valves:

• 1ND-28A (NO Supply To NV & 1A NI Pmps)

• 1NI-136B (NO Supply To NI Pump 1B).

h. Isolate FWST from NVand NI pumps as follows:

1) Place "PWR DISCON FOR 1NI-1 OOB" switch in "ENABLE".

2) Close 1NI-1 OOB (NI Pmps Suct From FWST).

3) Close the following valves:

• 1NV-252A (NV Pumps Suct From FWST)

• 1NV-253B (NV Pumps Suct From FWST).

i. Verify proper recirc flow as follows:

• "NV S/I FLOW" - INDICATING FLOW

• NI pumps - INDICATING FLOW

• NO pumps - INDICATING FLOW.

END EVENT Page 28 of 28