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Catawba 2016-301 Exam Final Items 2B - Delay Release 2 Yrs
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Catawba Nuclear Station NRC Exam May 201 6 Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 1 of 67

NRC INITIAL LICENSE EXAM SCENARIO #

1 Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 2 of 67 Facility: Catawba NRC Exam 201 6 Scenario No.:

1 Op Test No.:

2016301 Examiners:

Operators:

SRO RO BOP Initial Conditions:

Unit 1 is at 75% power at the MOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 75% power at the MOL.

Unit 2 is at 100% power. 1A CA Pump has been removed from service for PMs. 1A CA Pump has been inoperable for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and is expected to be returned to service in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Direction for the crew is to continue a power decrease to 13% (at 10% / hour) for turbine offline work. The Unit 1 RMWST is NOT aligned to supply Unit 2 per OP/2/A/6200/012 (Reactor Makeup Water).

Event No. Malf. No. Event Type* Event Description 1 R - RO N - BOP N - SRO Decrease power to ~

13% 2 AD19F04 NC009F C - RO C - SRO TS - SRO PZR PORV fails open (Isolated by block valve

) 3 RN002B C - BOP C - SRO TS - SRO RN (Nuclear Service Water) Strainer Hi D/P 4 WL01 8 D C - BOP C - SRO 1B NCDT Pump Trip 5 CF012F C - RO C - SRO 1CF-51 (S/G 1C CF CONT ISOL) fails closed

/ Auto Reactor Trip Failure 6 SM009 M - ALL Rupture on equalization header upon Rx trip 7 ISE006A ISE006B C - RO Failure of Automatic Main Steam Isolation 8 VE001A C - BOP Failure of Automatic 1A VE Fan start

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

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 3 of 67 Scenario 1 - Summary Initial Condition Unit 1 is at 75% power at the MOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 75% power at the MOL. Unit 2 is at 100% power.

1A CA Pump has been removed from service for PMs. 1A CA Pump has been inoperable for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and is expected to be returned to service in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Direction for the crew is to continue a power decrease to 13% (at 10% / hour) for turbine offline work. The Unit 1 RMWST is NOT aligned to supply Unit 2 per OP/2/A/6200/012 (Reactor Makeup Water).

Event 1 Crew will use the provided reactivity plan to begin a power decrease to ~

13%. BOP will perform a boration per the reactivity plan. RO will input a target and load rate into the turbine control panel and place the turbine in GO to commence power decrease. RO will also insert control rods as required to maintain RCS temperature.

Event 2 1NC-36B (PZR PORV) fails open while BOP is responding to a rear board annunciator. Manual closure of the associated block valve will be successful. AP/11 (Pressurizer Pressure Anomalies) entry. TS evaluation required.

Verifiable Action

- RO will isolate PZR PORV by manually closing the associated PORV Isolation valve.

Event 3 1B RN (Nuclear Service Water) strainer Hi D/P. AP/20 (Loss of Nuclear Service Water) entry. TS evaluation required.

Verifiable Action

- BOP will start an alternate RN Pump and secure 1B RN Pump.

Event 4 1 B NCDT (Reactor Coolant Drain T ank) Pump trips. Required actions contained in Annunciator Response Procedure.

Verifiable Action

- The BOP will start the 1 A NCDT Pump per the ARP. Event 5 1CF-51 (S/G 1C CF CONT ISOL) valve fails closed. Both CFPTs will trip on Hi Discharge Pressure resulting in an AMSAC Turbine Trip. The Automatic Reactor Trip on Turbine Trip greater than 69% (P9) will fail. AP/06 (Loss of S/G Feedwater) Immediate Actions

, and the failed Automatic Trip

, will require the RO to manually trip the reactor.

Verifiable Action

- RO will manually trip the reactor.

Event 6 Following unit trip, a rupture at the steam equalization header occurs

. Verifiable Action

- Crew will terminate Safety Injection following manual initiation of Main Steam Isolation.

Event 7 Automatic Main Steam Isolation trains 'A' and 'B' fail to actuate on low S/G pressure. Manual initiation will be required.

Verifiable Action

- R O will manually initiate Main Steam Isolation on both trains.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 4 of 67 Scenario 1 - Summary Event 8 1A VE (Annulus Ventilation) Fan fails to start on Safety Injection signal. Manual start will be required

. Verifiable Action

- BOP will manually start the fan. Critical Task 1

- Manually isolate failed open Pressurizer PORV prior to reactor trip or ESF actuation.

Critical Task 2 - Manually trip the reactor from the control room before 1C S/G dryout occurs (W/R S/G level < 12%). Critical Task 3 - Manually actuate Main Steam Isolation before a severe (orange path) challenge develops to either the subcriticality or the integrity CSF or before transition to ECA

-2.1, whichever happens first.

Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5

-8) 8 2. Malfunctions after EOP entry (1

-2) 2 3. Abnormal events (2-4) 4 4. Major transients (1

-2) 1 5. EOPs entered/requiring substantive actions (1

-2) 1 6. EOP contingencies requiring substantive actions (0

-2) 0 7. EOP based Critical tasks (2

-3) 2 Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 5 of 67 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC #

1 70 START TIME:__________

Trigger Instructor Action Final Delay Ramp Delete In Event 2 ANN-AD19-F04 (YN CRITICAL TROUBLE) ON 2 11 VLV-NC009F (NC36B PZR PORV FAIL TO POSITION) 1 2 3 MAL-RN002B (RN STRAINER 1B HI D/P) 100 3 4 OVR-WL01 8D (NCDT PMP 1 B OFF PB) ON 4 4 OVR-WL-018A (NCDT PMP 1B OFF LT)

OFF 4 5 VLV-CF012F (CF51 CF CONT ISOL VLV 1CF051 FAIL TO POSITION) 0 4SEC 5 6 MAL-SM009 (SM HEADER BREAK) 1.27 e 7 6 N/A MAL-ISE006B (AUTO SM ISOL SIGNAL TRN B)

BLOCK 7 N/A MAL-ISE006A (AUTO SM ISOL SIGNAL TRNA)

BLOCK 7 N/A MAL-VE001A (FAN VE

-1A DISABLE AUTOSTART RELAY) ACTIVE 8 10 LOA-VC03 9 (MNL RST LATCH FOR CHILLER B HI COND PRESS TRP DUE TO LOSS RN) RESET 10:00 N/A LOA-CA017 (RACKOUT CA PUMP 1A) RACK-OUT N/A MAL-IPX001A (AUTO REACTOR TRIP FAILURE TRN A) ACTIVE N/A MAL-IPX001B (AUTO REACTOR TRIP FAILURE TRN B) ACTIVE Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 6 of 67 12 VLV-NC008C (NC35B PORV ISOL VLV FAIL PWR)

ACTIVE Ensure TRIGGER 11 = x5ri017a (1AD-19 Acknowledge)

Ensure TRIGGER 6 = ipplp4(1) ipplp4(2)

(Reactor Trip either train)

Ensure 1B RN Pump is in service Ensure 1 B NCDT Pump is in service Ensure Control Rods in manual

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 7 of 67 2. SIMULATOR BRIEFING 2.1 Control Room Assignments:

Position Name CRS RO BOP 2.2 Give a copy of Attachment 2 (Shift Turnover Information) to the CRS.

3. EXERCISE PRESENTATION 3.1 Familiarization Period A. Allow examinees time to familiarize themselves with the Control Board alignments.

3.2 Scenario EVENT 1 , Power decrease to 13% BOOTH INSTRUCTOR ACTION IF contacted as SOC by the crew to inform of commencing power decrease, REPEAT the information.

3.3 Scenario EVENT 2 , 1NC-36B (PZR PORV) fails open.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 2 to cause 1AD-13, F/5 (HVAC PANEL TROUBLE) to alarm.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR for 1NC-36B, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF the Unit Supervisor is contacted to remove power from 1NC-35B , THEN INSERT SIMULATOR Trigger 1 2. BOOTH INSTRUCTOR ACTION IF Station Management is contacted for power decrease guidance, ask for CRS recommendation and agree.

BOOTH INSTRUCTOR ACTION IF an AO is contacted to investigate YN Critical Trouble, REPEAT back the information.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 8 of 67 3.4 Scenario EVENT 3 , 1B RN Strainer Hi D/P BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause 1B RN Strainer Hi D/P. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to investigate the problem with 1B RN Strainer and/or breaker, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF an Operator and/or Maintenance are dispatched to investigate the 1B RN Strainer and/or breaker, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF an Operator is dispatched to reset VC/YC, THEN INSERT SIMULATOR Trigger 10

. After 10 minutes has elapsed, REPORT VC/YC has been reset.

BOOTH INSTRUCTOR ACTION WHEN contacted concerning Unit 2 RN valve position, REPORT 2RN-67A and 69B are Open. BOOTH INSTRUCTOR ACTION IF an Operator is dispatched to perform post start check of RN Pump, REPEAT back the information

. After 5 minutes has elapsed, REPORT RN Pump ____ is good for continued operation

. BOOTH INSTRUCTOR ACTION IF Environmental Chemistry is contacted, REPEAT back the information

. BOOTH INSTRUCTOR ACTION IF indication of 2AD

-12 C/2 and C/5 are requested, REPORT that both annunciators are dark. 3.5 Scenario EVENT 4 , 1 B NCDT Pump Trip BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 4 to trip 1 B NCDT pump.

BOOTH INSTRUCTOR ACTION IF Operator and/or Maintenance are dispatched to investigate the 1 B NCDT Pump and/or breaker, REPEAT back the information.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 9 of 67 BOOTH INSTRUCTOR ACTION IF SWM is called to initiate an NCR on the 1 B NCDT pump, REPEAT back the information.

3.6 Scenario EVENT 5 , 1CF-51 (S/G 1C CF CONT ISOL) fails closed.

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to fail 1CF-51 (S/G 1C CF CONT ISOL) closed.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 1 Page 10 of 67 Event

Description:

Power Reduction Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 10 of 67 EVENT 1 NOTE TO EVALUATOR: Crew will begin by performing a boration per the reactivity plan provided by reactor engineering. They will also set up the turbine controls for proper load rate and target load. Crew may also decide to insert control rods to provide a temperature error prior to placing the turbine in 'GO'.

These steps may be performed in any order that the crew chooses.

NOTE TO EVALUATOR: All needed materials have been provided to the crew to perform any needed pre job briefs prior to being brought into the simulator for their control board walk down prior to assuming the watch.

NOTE TO EVALUATOR: The following steps are taken from OP/1/A/6150/009 (Boron Concentration Control) Enclosure 4.

2 (Boration).

NOTE TO EVALUATOR: The Turbine Load Changing procedure begins on page 13.

ALL NOTE: This enclosure will affect reactivity of the core and is therefore designated important to Reactivity Management per the guidelines of AD-OP-ALL-0203 (Reactivity Management). (R.M.)

BOP 3.1 Ensure valves are aligned per Enclosure 4.8 (Valve Checklist).

BOP 3.2 Ensure the following valve control switches in "AUTO":

1NV-238A (B/A To Blender Ctrl Vlv) 1NV-186A (B/A Blender Otlt To VCT Otlt)

BOP 3.3 Ensure 1NV

-238A (B/A To Blender Ctrl Vlv) controller in auto.

BOP 3.4 Ensure at least one boric acid transfer pump is in "AUTO" or "ON".

NOTE TO EVALUATOR: The supplied Reactivity Management plan will specify an initial boric acid addition of 130 gallons.

BOP 3.5 Record the desired volume of boric acid to be added. ______ gallons BOP 3.6 Adjust the boric acid counter to the desired volume of boric acid to be added. (R.M.)

BOP 3.7 IF the blender is set up for automatic makeup per Enclosure 4.1 (Automatic Makeup), record the setpoint of the controller for 1NV

-238A (B/A To Blender Ctrl Vlv). __________ gpm

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 1 Page 11 of 67 Event

Description:

Power Reduction Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 11 of 67 BOP 3.8 Place the "NC MAKEUP MODE SELECT" switch in "BORATE".

BOP NOTE: Boric Acid flow rates > 32 gpm may result in a boric acid flow deviation annunciator.

BOP 3.9 IF required, adjust the controller for 1NV

-238A (B/A To Blender Ctrl Vlv) to the desired flow.

BOP 3.10 IF NC System boron concentration will be changed by

> 50 ppm, initiate PZR spray to equalize the boron concentration throughout the system by operating backup heaters per OP/0/A/6200/005 (Miscellaneous Component Operation).

NOTE TO EVALUATOR: Step 3.11, 3.12, and 3.13 are conditional steps and should not need to be performed during this scenario.

BOP 3.11 IF AT ANY TIME it is desired to divert letdown to the RHT manually operate 1NV

-172A (3-Way Divert to VCT

-RHT) as follows:

3.11.1 Place the control switch for 1NV

-172A (3-Way Divert to VCT

-RHT) to the "RHT" position.

3.11.2 Ensure VCT level is monitored continuously while diverting to the RHT. NOTE: Procedure may continue while performing the next step.

3.11.3 WHEN desired VCT level is reached return 1NV

-172A (3-Way Divert to VCT

-RHT) to auto as follows:

3.11.3.1 Place the control switch for 1NV

-172A (3-Way Divert to VCT-RHT) in the "VCT" position.

3.11.3.2 Place the control switch for 1NV

-172A (3-Way Divert to VC T-RHT) in the "AUTO" position.

BOP 3.12 IF AT ANY TIME during the makeup it becomes necessary to change the makeup flow rate, adjust the setpoint for 1NV

-238A (B/A Xfer Pmp To Blender Ctrl) as necessary to achieve the desired flow.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 1 Page 12 of 67 Event

Description:

Power Reduction Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 12 of 67 BOP 3.13 IF AT ANY TIME while boration is in progress it becomes necessary OR it is desired to stop the boration, perform the following:

3.13.1 Place the "NC MAKEUP CONTROL" switch to the "STOP" position. 3.13.2 Ensure the following valves close: (R.M.)

1NV-238A (B/A To Blender Ctrl Vlv) 1NV-186A (B/A To Blender Otlt To VCT Otlt) 3.13.3 Record boric acid volume added as indicated on the Boric Acid counter. __________ gallons 3.13.4 WHEN conditions allow resuming the boration, perform the following:

3.13.4.1 Determine remaining volume to be added by subtracting the amount previously added (Step 3.13.3) from the desired volume to be added (Step 3.5)

__________

- __________ = __________ gallons (Step 3.5) (Step 3.13.3) 3.13.4.2 Adjust boric acid counter to the volume of boric acid determined in Step 3.13.4.1. (R.M.)

3.13.4.3 Place "NC MAKEUP CONTROL" switch in the "START" position. (R.M.)

3.13.4.4 Verify the following:

1NV-238A (B/A To Blender Ctrl Vlv) modulates to establish desired flow 1NV-186A (B/A To Blender Otlt To VCT Otlt) opens 3.13.4.5 IF in "AUTO", verify the boric acid pump starts.

RO 3.14 WHILE makeup is in progress, monitor the following for expected results: Control rod motion NC System Tavg Reactor Power BOP NOTE: If a small makeup is being performed, placekeeping for Steps 3.15 through 3.18 may be performed after Step 3.19 is performed.

BOP 3.15 Place the "NC MAKEUP CONTROL" switch to the "START" position. (R.M.)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 1 Page 13 of 67 Event

Description:

Power Reduction Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 13 of 67 BOP 3.16 Verify the following:

1NV-238A (B/A To Blender Ctrl Vlv) modulates to establish desired flow 1NV-186A (B/A Blender Otlt To VCT Otlt) opens BOP 3.17 IF in "AUTO", verify the boric acid transfer pump starts.

BOP 3.18 Verify proper flow by observing the Boric Acid Counter. {PIP 96

-0137} BOP NOTE: The boric acid counter may count up 1

- 5 gallons after termination.

BOP 3.19 WHEN the desired volume of boric acid is reached on the boric acid counter, ensure the following valves close: (R.M.)

1NV-238A (B/A To Blender Ctrl Vlv) 1NV-186A (B/A Blender Otlt To VCT Otlt)

NOTE TO EVALUATOR: Step 3.20 may not be performed. See note below.

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

BOP 3.20 IF desired, flush the makeup line as follows:

3.20.1 Record the setpoint on 1NV

-242A (RMWST To B/A Blender Ctrl): ________ gpm 3.20.2 Place controller for 1NV

-242A (RMWST To B/A Blender Ctrl) in manual. 3.20.3 Increase demand on controller for 1NV

-242A (RMWST To B/A Blender Ctrl) to full open.

3.20.4 Open the following valves:

1NV-242A (RMWST To B/A Blender Ctrl) 1NV-186A (B/A Blender Otlt To VCT Otlt) 3.20.5 Ensure one reactor makeup water pump is in "ON".

3.20.5.1 IF Unit 1 RMWST is NOT aligned to supply Unit 2 per OP/2/A/6200/012 (Reactor Makeup Water), ensure at least one reactor makeup water pump is "ON". 3.20.5.2 IF Unit 1 RMWST is aligned to supply Unit 2 per OP/2/A/6200/012 (Reactor Makeup Water) AND a Unit 1 RMW Pump is NOT running to support Unit 2 activities, ensure at least one reactor makeup water pump is "ON".

3.20.5.3 IF Unit 1 RMWST is aligned to supply Unit 2 per

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 1 Page 14 of 67 Event

Description:

Power Reduction Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 14 of 67 OP/2/A/6200/012 (Reactor Makeup Water) AND a Unit 1 RMW Pump is running to support Unit 2 activities, ensure the second Unit 1 reactor makeup water pump is "ON".

3.20.6 WHEN ~ 20 gallons of makeup water have been flushed through the makeup line, close the following valves:

1NV-242A (RMWST To B/A Blender Ctrl) 1NV-186A (B/A Blender Otlt To VCT Otlt) 3.20.7 Place the following valve control switches in "AUTO":

1NV-242A (RMWST To B/A Blender Ctrl) 1NV-186A (B/A Blender Otlt To VCT Otlt) 3.20.8 Ensure controller for 1NV

-242A (RMWST To B/A Blender Ctrl) is set to the value recorded in Step 3.20.1. (R.M.)

3.20.9 Place controller for 1NV

-242A (RMWST To B/A Blender Ctrl) in auto. 3.20.10 IF NOT required for current plant operation, place the reactor makeup water pump started in Step 3.20.5 in "AUTO

". BOP 3.21 IF automatic makeup is desired, perform the following:

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

OR 3.21.2 IF makeup at the previous concentration is acceptable AND the system was previously aligned per Enclosure 4.1 (Automatic Makeup), perform the following:

3.21.2.1 Ensure the controller for 1NV

-238A (B/A Xfer Pmp To Blender Ctrl) is set to the value recorded in Step 3.7. (R.M.) 3.21.2.2 Place the "NC MAKEUP MODE SELECT" switch in "AUTO". 3.21.2.3 Place the "NC MAKEUP CONTROL" switch to the "START" position. (R.M.)

BOP 3.22 IF initiated in Step 3.10, terminate PZR spray by securing backup heaters per OP/0/A/6200/055 (Miscellaneous Component Operation).

END OF OP/1/A/6150/009

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 1 Page 15 of 67 Event

Description:

Power Reduction Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 15 of 67 NOTE TO EVALUATOR: The following steps are taken from OP/1/B/6300/001 (Turbine Generator) Enclosure 4.2 (Load Changing).

NOTE TO EVALUATOR: The expected load rate input to the turbine controls will be 2 MW/min.

RO CAUTION: 1. Normal steady

-state load change shall be made without exceeding limits shown on Enclosure 4.7 (Generator Operating Limits) and in the Unit One OAC Databook "Recommended Starting and Loading Curves".

2. Unit One Reactor Operating Data, Section 2.4 shall be referred to for allowable ramp rates.

RO 3.2.3 Decrease turbine generator load by performing the following:

3.2.3.1 Select "LOAD RATE" and verify it illuminates.

3.2.3.2 Input the desired load rate.

3.2.3.3 Select "ENTER" and verify "LOAD RATE" goes dark.

3.2.3.4 Select "TARGET" and verify it illuminates.

3.2.3.5 Input the desired load target.

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

3.2.3.7 Verify new load target appears on Target Display.

3.2.3.8 Select "GO" and verify it illuminates to start load decrease.

3.2.3.9 Coordinate with Secondary Chemistry to adjust S/G blowdown flowrates to obtain maximum blowdown for the appropriate load. END OF EVENT OP/1/B/6300/001

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 1 Page 16 of 67 Event

Description:

Power Reduction Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 16 of 67 NOTE TO EVALUATOR: The following steps are from OP/1/A/6150/008 (Rod Control) Enclosure 4.16 (Control Bank Manual Operation At Power). This procedure was given to the crew as part of the turnover package with initial conditions and steps 3.1 - 3.3 signed off.

Crew may decide not to perform these steps at this time.

RO NOTE: Steps 3.1 through 3.6 may be signed off as time allows ensuring operator maintains proper focus on reactivity management.

ALL 3.1 Monitor the following:

Tavg/Tref Demand Counter positions DRPI rod positions ROD MOTION RODS

-IN/RODS-OUT Light ROD MOTION DEMAND SIGNALS - TEMP ERROR/POWER MISMATCH Power Range instruments IR SUR (Startup Rate)

NOTE TO EVALUATOR:

Step 3.4 should be N/A at this time.

RO 3.4 IF withdrawing Control Banks, pull and hold the "ROD MOTION" lever "OUT" as required until control rods are in the desired position. (R.M.)

RO 3.5 IF inserting Control Banks, push and hold the "ROD MOTION" lever "IN" as required until control rods are in the desired position. (R.M.)

Booth Operator will insert Trigger 2 for EVENT 2 at the discretion of the lead evaluator.

END OF EVENT 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 2 Page 17 of 67 Event

Description:

PZR PORV Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 17 of 67 EVENT 2 NOTE TO EVALUATOR: The next event will begin with 1AD

-13, F/5 "HVAC PANEL TROUBLE" annunciator. The BOP will respond to the rear of the control boards to address this alarm. When the rear board alarm is acknowledged, 1NC

-36B (PZR PORV) will fail open requiring action by the RO.

Indications:

1AD-6 , E/10 'PZR PORV DISCH HI TEMP

' 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' OAC PT C1Q0756 'VLV NC36B PZR POWER OPERATED RELIEF' - OPEN RO Attempt to close 1NC-36B (PZR PORV)

RO Close 1NC-35B (Pzr PORV Isol)

NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/011, Pressurizer Pressure Anomalies.

NOTE TO EVALUATOR:

The following steps are from AP/1/A/5500/011, Pressurizer Pressure Anomalies, Case I (Pressurizer Pressure Decreasing).

RO 1. Verify all Pzr PORVs

- CLOSED. Critical Task #1 RO 1. RNO Perform the following:

a. CLOSE Pzr PORV(s).

b. IF any Pzr PORV cannot be closed, THEN: 1) CLOSE affected PORV(s) isolation valve.

NOTE TO EVALUATOR: Step 1.b.

2) of RNO does not apply.

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

a) IF in Mode 3 with CLAs isolated OR in Mode 4, THEN GO TO AP/1/A/5500/027 (Shutdown LOCA).

b) Trip Unit 1 reactor.

c) WHEN reactor tripped OR S/I setpoint reached, THEN ensure S/I initiated.

d) GO TO EP/1/A/5000/E

-0 (Reactor Trip or Safety Injection).

RO/BOP NOTE: Control rods may withdraw on decreasing NC pressure.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 2 Page 18 of 67 Event

Description:

PZR PORV Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 18 of 67 BOP 2. Verify Pzr spray valve(s)

- CLOSED. BOP 3. Verify all Pzr heaters

- ENERGIZED.

NOTE TO EVALUATOR: Depending on how fast the RO responded to the PORV failure, the Pzr heaters may not be energized, however, the crew will determine that the step 3 RNO will not apply.

BOP 3.RNO Perform the following:

a. IF Pzr pressure less than 2220 PSIG AND stable or decreasing, THEN ensure all Pzr heaters energized.

b. IF Pzr pressure less than 2220 PSIG AND increasing, THEN operate Pzr heaters as required to stabilize Pzr pressure at 2235 PSIG. c. WHEN Pzr pressure returns to normal AND automatic Pzr pressure control desired, THEN place Pzr heaters in auto.

BOP 4. Ensure 1NV

-37A (NV Supply To Pzr Aux Spray)

- CLOSED. RO/BOP NOTE Positive reactivity is inserted during an increase in NC pressure which may cause auto rod insertion.

BOP 5. Verify NC pressure

- STABLE OR INCREASING.

RO 6. 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: Turbine load Control rods Boron concentration.

NOTE TO EVALUATOR: Step 7 does not apply.

BOP 7. IF Pzr pressure channel failed, THEN perform following:

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 2 Page 19 of 67 Event

Description:

PZR PORV Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 19 of 67 SRO 8. 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

) 3.4.13 (RCS Operational Leakage).

NOTE TO EVALUATOR: TS 3.4.11 (Pressurizer Power Operated Relief Valves (PORVs)), Condition B (Close associated block valve and remove power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and restore PORV to operable within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) should be entered.

Tech Spec 3.4.1 (RCS Pressure, Temperature, and Flow Departure From Nucleate Boiling (DNB) Limits) Condition A (restore to within limits in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) should be entered.

NOTE: This LCO may not apply based on the speed at which the operator isolates the failed PORV. Additionally, this condition will most likely be cleared prior to CRS review of TS.

SRO 9. Determine long term plant status. RETURN TO procedure in effect.

NOTE TO EVALUATOR: The SRO will conduct a "Crew Brief" or a "Focus Brief" to summarize the event. END OF EVENT 2 Booth Operator will insert Trigger 3 for EVENT 3 at the discretion of the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 3 Page 20 of 67 Event

Description:

RN Strainer Hi D/P Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 20 of 67 EVENT 3 Indications:

1AD-12, A/2 'RN ESSENTIAL HDR A PRESSURE LO' 1AD-12, A/4 'RN PUMP B FLOW

-HI/LO' 1AD-12, A/5 'RN ESSENTIAL HDR B PRESSURE LO' 1AD-12, C/5 'RN PMP B STRAINER HI D/P' 1AD-13, F/5 'HVAC PANEL TROUBLE' 1RNP7510 1B RN Flow indication indicates 0 gpm.

BOP Recognize 1B RN Pump Strainer Hi D/P

. ALL Enter AP/0/A/5500/020, Loss of Nuclear Service Water NOTE TO EVALUATOR:

The crew will make a plant page announcing the entry into AP/0/A/5500/020, Loss of Nuclear Service Water NOTE TO EVALUATOR:

The crew may initially choose to take actions of the annunciator response per OP/1/A/6100/010 M, C/5 (RN PMP B STRAINER HI D/P). See Attachment 4 NOTE TO EVALUATOR:

The following steps are from AP/0/A/5500/020, Loss of Nuclear Service Water, Case I (Loss of RN Train).

BOP 1. Start idle RN pump(s) as required.

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

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 3 in the back of this guide.

BOP 3. Verify RN System in normal alignment as follows: Both RN Supply headers

- ALIGNED AND Both RN Discharge headers

- ALIGNED BOP 4. Verify each operating RN pump discharge flow

- GREATER THAN 8,600 GPM.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 3 Page 21 of 67 Event

Description:

RN Strainer Hi D/P Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 21 of 67 BOP 4. RNO Perform the following:

a. Stop any RN pump(s) not required to support system operation.

b. Ensure the following suction valves to lake - OPEN: 1RN-1A (RN P/H Pit A Isol From Lake) 1RN-2B (RN P/H Pit A Isol From Lake) 1RN-5A (RN P/H Pit B Isol From Lake) 1RN-6B (RN P/H Pit B Isol From Lake) c. Ensure the following essential header isolation valves for required trains - OPEN: 1RN-67A (RN Hdr 1A Supply Isol) 1RN-69B (RN Hdr 1B Supply Isol) 2RN-67A (RN Hdr 2A Supply Isol) 2RN-69B (RN Hdr 2B Supply Isol)

d. Ensure the following RN to RL discharge valves

- OPEN: 1RN-57A (Station RN Disch To RL Sys) 1RN-843B (Station RN Disch To RL Sys)

e. Ensure one of the following RL discharge valves

- OPEN: 1RL-54 (RN System Disch To A RL Header)

OR 1RL-62 (RN System Disch To B RL Header)

f. Ensure the following station RN discharge header crossover valves - OPEN: 1RN-54A (Station RN Disch Hdr X

-Over) 1RN-53B (Station RN Disch Hdr X

-Over) NOTE TO EVALUATOR: Step 4 RNO 4.g. will not apply

. BOP g. IF either of the following conditions is met:

RN cannot be aligned to lake OR No flow indicated on operating RN pump(s).

THEN align RN to SNSWP as follows:

BOP 4. RNO h. Verify the following alarms

- DARK: 1AD-12, C/2 "RN PMP A STRAINER HI D/P" 1AD-12, C/5 "RN PMP B STRAINER HI D/P" 2AD-12, C/2 "RN PMP A STRAINER HI D/P" 2AD-12, C/5 "RN PMP B STRAINER HI D/P".

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 3 Page 22 of 67 Event

Description:

RN Strainer Hi D/P Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 22 of 67 NOTE TO EVALUATOR: It is anticipated that the CRS will read step 4 RNO 4.i., but the action will not be taken at this time. This procedure is included a s Attachment 5.

BOP 4. RNO i. IF any of the previous alarms lit, THEN backflush affected strainer. REFER TO OP/0/A/6400/006C (Nuclear Service Water System). BOP 5. Verify each operating RN pump discharge flow

- LESS THAN 23,000 GPM. BOP 6. Ensure RN pumps

- IN OPERATION AS NEEDED. NOTE TO EVALUATOR:

The KC heat exchanger outlet mode switches will be in the "KC Temp" position if the corresponding train of KC is in service. Otherwise, it will be in the "Miniflow" position.

BOP 7. 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 8. Verify each operating RN pump discharge flow

- GREATER THAN 8,600 GPM. BOP 9. Verify RN

- AVAILABLE TO ALL UNIT 1 AND UNIT 2 D/G(S).

NOTE TO EVALUATOR:

The low RN flow will probably result in a trip of the operating VC/YC (Control Room Ventilation and Chilled Water System) chiller. The BOP will call the booth to dispatch an operator to perform a local reset.

BOP 10. Determine VC/YC status as follows:

Verify VC/YC

- ALIGNED TO OPERATING RN TRAIN.

Verify YC Chiller

- RUNNING. BOP 10. RNO Align VC/YC to operating RN train. REFER TO OP/0/A/6450/011 (Control Room Area Ventilation/Chilled Water System).

SRO 11. Determine and correct cause of loss of RN train.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 3 Page 23 of 67 Event

Description:

RN Strainer Hi D/P Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 23 of 67 SRO 12. 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).

NOTE TO EVALUATOR: T.S. 3.7.8 Condition A (Restore train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) should be entered.

NOTE TO EVALUATOR: The CRS may direct completion of OP/0/A/6400/006C (Nuclear Service Water System), Enclosure 4.11 (Operability Actions With ONE RN Pump and/or Its Associated D/G Inoperable With Both Units Entering An Action Statement)

. SRO 13 Determine required notifications:

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

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

BOP 14 Notify Environmental Chemistry of any RN pump shifts that have occurred. SRO 15 Determine long term plant status.

RETURN TO procedure in effect.

NOTE TO EVALUATOR: The SRO will conduct a "Crew Update" to inform the crew of any Tech Spec conditions that have been entered.

Booth Operator will insert Trigger 4 for EVENT 4 at the discretion of the lead evaluator.

END OF EVENT 3

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 4 Page 24 of 67 Event

Description:

1B NCDT Pump Trip Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 24 of 67 EVENT 4 Indications:

1AD-13, B/2 'NCDT RECIRC LO FLOW' 1WLP5730 NCDT Recirc Flow on 1MC9 indicating < 30 gpm.

BOP Recognizes 1 B NCDT Pump is OFF NOTE TO EVALUATOR:

The crew will most likely use the alarm response (listed below) to guide the required actions, and may also use OP/1/A/6500/014, Enclosure 4.1 8 (Shifting NCDT Pumps).

BOP 1. Verify low recirc. flow on 1WLP5730 on 1MC9.

BOP 2. IF due to pump malfunction, start alternate NCDT pump.

NOTE TO EVALUATOR:

The following steps are from OP/1/A/6500/014, Enclosure 4.1 8 (Shifting NCDT Pumps).

BOP 3.2. IF 1 B NCDT Pump is in service AND it is desired to place 1 A NCDT Pump in service, perform the following:

3.2.1 Stop "NCDT PUMP 1B

". 3.2.2 Start "NCDT PUMP 1A

." 3.2.3 Verify discharge flow is > 85 gpm as indicated on 1WLP5670 (NCDT Pmp Disch Flow) on 1MC9.

Booth Operator will insert Trigger 5 for EVENT 5 at the discretion of the lead evaluator.

END OF EVENT 4

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 5 Page 25 of 67 Event

Description:

Main Feed Containment Isolation Valve Fails Closed Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 25 of 67 EVENT 5 Indications:

1AD-4, A-3 'S/G C FLOW MISMATCH LO CF FLOW' 1AD-4, B/3 'S/G C LEVEL DEVIATION' 1AD-4, C/3 'S/G C FLOW MISMATCH LO CF FLOW RO Recognizes loss of all feed flow to the 1C S/G at greater than 5% reactor power. RO Manually trips the reactor per the immediate actions of AP/1/A/5500/06 (Loss of S/G Feedwater), Case l (Loss of CF Supply To S/Gs).

NOTE TO EVALUATOR: Automatic Reactor Trip is failed. Therefore, failure to manually trip the reactor will lead to S/G dryout within a few minutes. ALL Enter EP/1/A/5000/E

-0 (Reactor Trip or Safety Injection)

NOTE TO EVALUATOR:

Due to the immediate action nature of the event, it is not anticipated that the crew will have time to make a plant page announcing the entry into AP/1/A/5500/06, Loss of S/G Feedwater.

NOTE TO EVALUATOR:

The following steps are from AP/1/A/5500/06, Loss of S/G Feedwater, Case l (loss of CF Supply To S/Gs).

RO 1. Verify reactor power

- LESS THAN 5%.

Critical Task #2 RO 1. RNO IF AT ANY TIME all CF supply to S/G(s) lost, THEN perform the following:

a. Manually trip reactor.

ALL b. GO TO EP/1/A/5000/E

-0 (Reactor Trip Or Safety Injection).

END OF EVENT 5

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 6, 7, 8 Page 26 of 67 Event

Description:

Equalization header rupture, Main Steam Isolation failure, Annulus Ventilation fan 1A Auto start failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 26 of 67 EVENTS 6, 7, &

8 NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/E

-0 (Reactor Trip or Safety Injection).

RO/BOP 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 7 in the back of this guide.

RO 2. Verify Reactor Trip:

All rod bottom lights

- LIT All reactor trip and bypass breakers

- OPEN I/R power

- DECREASING.

RO 3. Verify Turbine Trip:

All turbine stop valves

- CLOSED BOP 4. Verify 1ETA and 1ETB

- ENERGIZED.

BOP 5. Verify S/I 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".

SRO 7. Determine required notifications:

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

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

RO 8. Verify all Feedwater Isolation status lights (1SI

-5) - LIT. BOP 9. Verify Phase A Containment Isolation status as follows:

a. Phase A "RESET" lights

- DARK. b. Monitor Light Panel Group 5 St lights on energized train(s)

- LIT.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 6, 7, 8 Page 27 of 67 Event

Description:

Equalization header rupture, Main Steam Isolation failure, Annulus Ventilation fan 1A Auto start failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 27 of 67 BOP 10. Verify proper Phase B actuation as follows:

a. Verify 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.

RO 11. Verify proper CA pump status as follows:

a. Motor driven CA pumps

- ON. b. 3 S/G N/R levels

- GREATER THAN 11%.

NOTE TO EVALUATOR: 1A CA Pump will not be on. However, the SRO should determine that steps contained in the RNO associated with this step will not be effective.

RO 11.a RNO Perform the following for affected train(s):

1) Reset ECCS.

2) Reset D/G load sequencer(s)

3) Start affected pump(s)

4) IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on.

11.b RNO Perform the following:

1) Place CA PMP #1 control switch to ON.

2) Ensure CA Pump #1

- RUNNING. BOP 12. Verify all of the following S/I pumps

- ON: NV pumps ND pumps NI pumps BOP 13. Verify all KC pumps

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

- ON. NOTE TO EVALUATOR: The CRS may elect to reset "B" train ECCS and D/G load sequencer and secure 1B RN pump due to previously identified clogged strainer.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 6, 7, 8 Page 28 of 67 Event

Description:

Equalization header rupture, Main Steam Isolation failure, Annulus Ventilation fan 1A Auto start failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 28 of 67 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).

NOTE TO EVALUATOR: BOP will address the failure of 1A VE Fan during performance of Enclosure 2.

NOTE TO EVALUATOR: Enclosure 2 can be found as Attachment 8 in the back of this guide.

RO 16. Verify all S/G pressures

- GREATER THAN 775 PSIG. Critical Task #3 RO 16. RNO a Verify Main Steam Isolation as follows:

All MSIVs

- CLOSED All MSIV bypass valves

- CLOSED All S/G PORVs

- CLOSED b. IF any valve open, THEN perform the following:

1) Initiate Main Steam Isolation.

2) IF any valve still open, THEN CLOSE valve.

BOP 17. Verify proper S/I flow as follows:

a. "NV S/I FLOW"

- INDICATING FLOW.

b. NC pressure

- LESS THAN 1620 PSIG.

BOP 17.b RNO 1) Ensure ND pump miniflow valve on operating ND pump(s)

- OPEN. NOTE TO EVALUATOR: Step 17.b.RNO 2) will not be applicable.

BOP 2) IF ND pump miniflow valve(s) cannot be opened, THEN perform the following for affected train(s):

3) GO TO Step 18. BOP 18. WHEN time and manpower permit (within two hours of event), THEN monitor Spent Fuel Pool level and temperature. REFER TO EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring).

NOTE TO EVALUATOR: G

-1 Enclosure 1 can be found as Attachment 9 in the back of this guide.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 6, 7, 8 Page 29 of 67 Event

Description:

Equalization header rupture, Main Steam Isolation failure, Annulus Ventilation fan 1A Auto start failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 29 of 67 RO 19. Control S/G levels as follows:

a. Verify total CA flow

- GREATER THAN 450 GPM.

b. WHEN each S/G N/R level greater than 11% (29% ACC), THEN control feed flow to maintain that S/G N/R level between 11% (29% ACC) and 50%.

RO 20. Verify all CA isolation valves

- OPEN. BOP 21. Verify S/I equipment status based on monitor light panel

- IN PROPER ALIGNMENT.

BOP 21.RNO. Align equipment.

RO NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until subsequent procedures provide alternative NC temperature control guidance. RO 22. Control NC Temperature. REFER TO Enclosure 4 (NC Temperature Control). NOTE TO EVALUATOR: Enclosure 4 can be found as Attachment 10 in the back of this guide.

BOP 23. 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. NOTE TO EVALUATOR: The CRS may elect to transition to RNO step for failed Pzr PORV BOP 23.RNO.a. IF Pzr pressure less than 2315 PSIG, THEN perform the

following:

1) CLOSE Pzr PORV(s).

2) IF any Pzr PORV cannot be closed, THEN CLOSE its isolation valve. NOTE TO EVALUATOR: Step 23 RNO 3) and 4) will not apply

. BOP 3) IF 1NC-32B OR 1NC-34A cannot be closed OR isolated, THEN perform the following:

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 6, 7, 8 Page 30 of 67 Event

Description:

Equalization header rupture, Main Steam Isolation failure, Annulus Ventilation fan 1A Auto start failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 30 of 67 BOP 23. b. Normal Pzr spray valves

- CLOSED. c. At least one Pzr PORV isolation valve

- OPEN. RO 24. Verify NC subcooling based on core exit T/Cs

- GREATER THAN 0°F.

RO 25. Verify main steamlines intact:

All S/G pressures

- STABLE OR INCREASING ALL S/Gs - PRESSURIZED.

RO/BOP 26. Verify S/G tubes 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 27. Verify NC System intact as follows:

Containment pressure

- LESS THAN 1 PSIG.

IF normal off

-site power available, THEN verify containment pressure less than 0.3 PSIG.

Containment high range EMFs

- LESS THAN 3 R/HR:

1EMF-53A (Containment Trn A) 1EMF-53B (Containment Trn B).

Containment EMF trip 1 lights

- DARK: 1EMF-38 (Containment Particulate) 1EMF-39 (L) (Containment Gas (Lo Range)).

Containment sump level

- STABLE. RO/BOP 28. Verify S/I termination criteria:

a. NC subcooling based on core exit T/Cs

- GREATER THAN 0°F.

b. Verify secondary heat sink as follows:

N/R level in any S/G - GREATER THAN 11%

OR Total feed flow to S/Gs

- GREATHER THAN 450 GPM

c. NC pressure

- STABLE OR INCREASING

d. Pzr level

- GREATER THAN 11%

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 6, 7, 8 Page 31 of 67 Event

Description:

Equalization header rupture, Main Steam Isolation failure, Annulus Ventilation fan 1A Auto start failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 31 of 67 NOTE TO EVALUATOR:

Dependent upon the speed at which the crew initiates a manual Main Steam Isolation, the Pzr level requirement may not be met at this time. In this case, the crew will initiate Pzr Spray (per step 28 RNO.d.) and loop in step 28 until S/I termination criteria is met.

ALL 28.RNO.d. Perform the following:

1) IF NC pressure increasing AND normal Pzr spray available, THEN attempt to stabilize NC pressure using normal Pzr spray.

2) RETURN TO Step 28.a BOP 29. Reset the following:

a. ECCS. b. D/G load sequencers

. c. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on.

BOP 30. Ensure only one NV pump

- ON. RO/BOP 31. Verify NC pressure

- STABLE OR INCREASING.

BOP 32. Verify VI pressure

- GREATER THAN 50 PSIG.

BOP 33. Isolate NV S/I flowpath as follows:

a. Verify the following valves

- OPEN: 1NV-203A (NV Pumps A&B Recirc Isol) 1NV-202B (NV Pumps A&B Recirc Isol)

BOP 33. a RNO Perform the following:

1) OPEN affected valve(s)

. 2) IF 1NV-203A AND 1NV

-202B open, THEN GO TO Step 33.b BOP b. CLOSE the following valves:

1NI-9A (NV Pmp C/L Inj Isol) 1NI-10B (NV Pmp C/L Inj Isol)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 6, 7, 8 Page 32 of 67 Event

Description:

Equalization header rupture, Main Steam Isolation failure, Annulus Ventilation fan 1A Auto start failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 32 of 67 BOP 34. Establish charging as follows:

a. THROTTLE 1NV

-294 (NV Pmps A&B Disch Flow Ctrl) for 32 GPM charging line flow.

b. CLOSE 1NV-309 (Seal Water Injection Flow).

c. Ensure one of the following valves

- OPEN: 1NV-32B (NV Supply To Loop A Isol) 1NV-39A (NV Supply To Loop D Isol)

d. Ensure 1NV

-37A (NV Supply To Pzr Aux Spray)

- CLOSED. e. OPEN the following valves:

1NV-312A (Chrg Line Cont Isol) 1NV-314B (Chrg Line Cont Isol)

f. Verify 1NV

-309 - ABLE TO BE OPERATED FROM THE CONTROL ROOM.

g. Place 1NV-309 in auto.

h. Perform the following:

Maintain charging flow less than 180 GPM.

Maintain 32 GPM seal water flow.

BOP 35. Control charging as follows: a. Control charging flow to maintain Pzr level stable.

b. Verify Pzr level

- STABLE OR INCREASING.

BOP 36. Ensure the following containment isolation signals

- RESET: Phase A Phase B BOP 37. Establish VI to containment as follows:

Ensure 1VI-77B (VI Cont Isol)

- OPEN. Verify VI pressure

- GREATER THAN 85 PSIG.

ALL 38. Transition to EP/1/A/5000/ES

-1.1 (Safety Injection Termination) as follows: a. Implement EP/1/A/5000/F

-0 (Critical Safety Function Status Trees). b. Monitor EP/1/A/5000/ES

-1.1 (Safety Injection Termination), Enclosure 1 (Foldout Page).

c. GO TO EP/1/A/5000/ES

-1.1 (Safety Injection Termination), Step

10.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 6, 7, 8 Page 33 of 67 Event

Description:

Equalization header rupture, Main Steam Isolation failure, Annulus Ventilation fan 1A Auto start failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 33 of 67 NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/ES

-1.1 (Safety Injection Termination).

BOP 10. Determine if NI pumps should be stopped:

a. Verify the following:

NC pressure

- STABLE OR INCREASING NC pressure

- GREATER THAN 1620 PSIG.

b. Stop NI pumps.

c. GO TO Step 11. d. Verify Pzr spray valves

- CLOSED. e. Verify main steamlines intact as follows:

ALL S/G pressures

- STABLE OR INCREASING ALL S/Gs - PRESSURIZED.

NOTE If Pzr heaters are off, NC pressure may decrease slowly due to Pzr spray bypass flow. This may be considered "stable" pressure.

BOP f. Verify NC pressure

- STABLE OR INCREASING.

g. Verify NC pressure

- GREATER THAN 1620 PSIG.

h. Stop NI pumps.

BOP 11. Ensure all ND pump(s) with suction aligned to FWST

- STOPPED. BOP 12. Verify S/I flow not required:

a. NC subcooling based on core exit T/Cs

- GREATER THAN 0°F. b. Pzr level - GREATER THAN 11% (30% ACC).

RO 13. Transfer condenser steam dump to pressure control mode as follows: a. Verify condenser

- AVAILABLE:

"C-9 COND AVAILABLE FOR STM DUMP" status light (1SI

-18) - LIT MSIVs on intact S/G(s)

- OPEN. RO/BOP CAUTION If Pzr is solid, lowering intact S/G pressures and NC T-Hots too rapidly can cause a loss of subcooling.

RO/BOP NOTE Quickly stabilizing NC temperature will help prevent Pzr overfill.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

1 Event # 6, 7, 8 Page 34 of 67 Event

Description:

Equalization header rupture, Main Steam Isolation failure, Annulus Ventilation fan 1A Auto start failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 34 of 67 RO/BOP 13. RNO a. Perform the following:

1) Dump steam using intact S/G PORV(s) in subsequent steps to stabilize NC T

-Hots. 2) IF Pzr is solid, THEN perform the following in subsequent steps while operating S/G PORVs:

a) IF NC pressure starts decreasing, THEN perform the following:

(1) IF Pzr level greater than 17%, THEN operate Pzr heaters as required to stabilize pressure.

(2) Increase charging flow as required to maintain NC subcooling based on core exit T/Cs greater than 0°F.

b) Closely monitor T

-Hots until Pzr bubble establishe

d. 3) Perform the following to place steam dumps to pressure mode:

a) Reset C-7A and C-7B by momentarily placing "STEAM DUMP SELECT" switch to "RESET".

b) Place "STM DUMP CTRL" in manual.

c) Adjust "STM DUMP CTRL" to 0% demand.

d) Place steam dumps in pressure mode.

4) GO TO Step 14. NOTE TO EVALUATOR: Step 13.RNO a. 2) will not be applicable.

RO 14. Verify all NC T

-Hots - STABLE. RO 14.RNO THROTTLE steam flow and total feed flow as required to maintain NC System temperatures stable.

END OF SCENARIO 1

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 35 of 67 Attachment List Scenario 1 ATTACHMENT 1

- Crew Critical Task Summary ATTACHMENT 2

- Shift Turnover Information ATTACHMENT 3

- AP/0/A/5500/020 Enclosure 1 (Foldout Page)

ATTACHMENT 4 - 1AD-12, C/5 "RN PMP B STRAINER HI D/P" Annunciator Response ATTACHMENT 5 - OP/0/A/6400/006C (Nuclear Service Water System), Enclosure 4.8 ATTACHMENT 6

- OP/1/A/6500/014, Enclosure 4.18 (Shifting NCDT Pumps)

ATTACHMENT 7 - EP/1/A/5000/E

-0 Enclosure 1 (Foldout Page)

ATTACHMENT 8 - EP/1/A/5000/E

-0 Enclosure 2 (Ventilation System Verification)

ATTACHMENT 9 - EP/1/A/5000/G

-1 Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring)

ATTACHMENT 10 - EP/1/A/5000/E

-0 Enclosure 4 (NC Temperature Control

)

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 36 of 67 ATTACHMENT 1

CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK 1 Manually isolate failed open Pressurizer PORV prior to reactor trip or ESF actuation.

2 Manually trip the reactor from the control room before 1C S/G dryout occurs (W/R S/G level < 12%)

. 3 Manually actuate Main Steam Isolation before a severe (orange path) challenge develops to either the subcriticality or the integrity CSF or before transition to ECA

-2.1, whichever happens first.

Comments:

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 1 NUREG 1021 Revision 10 Page 37 of 67 ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 75 % M OL 1 055 PPM per OAC Controlling Procedure OP/1/A/6100/00 3 (Controlling Procedure for Unit Operation), Enclosure 4.2 (Power Decrease). The steps up to step 3.

15 are complete.

Other Information Needed to Assume the Shift Unit 1 is at 75% power at the MOL. Unit 2 is at 100% power. 1A CA Pump has been removed from service for PMs. 1A CA Pump has been inoperable for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and is expected to be returned to service in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Direction for the crew is to continue a power decrease to 13% (at 10% / hour) for turbine offline work. The Unit 1 RMWST is NOT aligned to supply Unit 2 per OP/2/A/6200/012 (Reactor Makeup Water).

AOs Available Seven AOs are available as listed on the status board METEOROLOGICAL CONDITIONS Upper wind direction = 315 degrees, speed =

3 mph Lower wind direction = 315 degrees, speed =

4.5 mph Forecast calls for clear skies over the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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NRC INITIAL LICENSE EXAM SCENARIO #

2 Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 2 of 63 Facility: Catawba NRC Exam 201 6 Scenario No.:

2 Op Test No.:

2016301 Examiners:

Operators:

SRO RO BOP Initial Conditions:

Unit 1 is at 100% power at EOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 100% power at the EOL. Unit 2 is at 100% power. 1A CA Pump has been removed from service for PMs. 1A CA Pump has been inoperable for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and is expected to be returned to service in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Direction for the crew is to shift operating NV (Centrifugal Charging) Pumps by starting 1B NV Pump and securing 1 A NV Pump. 1B NV Pump pre

-start check has been successfully completed.

Event No. Malf. No. Event Type* Event Description 1 N - BOP N - SRO Shift Centrifugal Charging Pumps 2 IDE005F C - RO C - SRO Atmospheric Dump valve (SV

-40) fails open 3 CM004F C - BOP C - SRO 1B CFPT (Main Feed Pump) suction valve fails closed / CFPT fails to auto trip 4 FWP015C R - RO C - SRO TS - SRO Turbine runback following CFPT trip / Control rods fail to automatically insert 5 KC027F C - BOP C - SRO TS - SRO KC (Component Cooling Water) Mini-Flow fails open 6 MAL-CF001A MAL-IPX003A MAL-IPX003B C - RO C - SRO 1A CFPT (Main Feed Pump) trip / ATWS 7 CA04B CA005 C - RO 1B CA (Aux Feed) Pump fails to start 8 M - ALL CAPT#1 over speed trip / Loss of Heat Sink 9 NV014F C - BOP 1NV-37A (Aux Pzr Spray) Fails to open

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

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 3 of 63 Scenario 2 - Summary Initial Condition Unit 1 is operating at 100% power at the EOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 100% power at the EOL. Unit 2 is at 100% power. 1A CA Pump has been removed from service for PMs. 1A CA Pump has been inoperable for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and is expected to be returned to service in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Direction for the crew is to shift operating NV (Centrifugal Charging) Pumps by starting 1B NV Pump and securing 1A NV Pump. 1B NV Pump pre

-start check has been successfully completed.

Event 1 Shift NV Pumps by starting 1 B NV pump and securing 1 A NV Pump. Event 2 Atmospheric dump valve 1SV

-40 fails open. Crew must take action to isolate this steam leak. This can be accomplished using AP/28 (Steam Leak), or crew can decide to use OMP 1-7 guidance to isolate a known leak. Verifiable Action

- RO will close associated isolation valve (1SV

-50). Event 3 1B CFPT suction valve will fail closed. The automatic CFPT trip (low flow) will not occur, requiring manual action to trip. Following the CFPT trip, the annunciator for Rod Insertion Lo/Lo limit will illuminate requiring TS evaluation.

Verifiable Action

- BOP will manually trip 1B CFPT.

Event 4 Following the CFPT 1B trip, a turbine runback will occur and AP/03 (Load Rejection) will be entered. Due to the runback rods should auto insert, but this feature will be failed, requiring the RO to manually insert rods. Verifiable Action

- RO will manually insert control rods as necessary to maintain Tavg/Tref within 1°F.

Event 5 KC miniflow valve 1KC

-C37A will fail open. Crew will enter AP/21 (Loss of Component Cooling) to address the miniflow valve issue. Attempts to manually close 1KC

-C37A will not be successful. TS 3.7.7 Action A will be entered for 'A' train KC being inoperable

. Verifiable Action

- BOP will start additional KC pump in order to provide adequate flow to in service loads. Event 6 1A CFPT will spuriously trip. AP/06 immediate actions require the RO to trip Unit 1 reactor on loss of all CF flow to any S/G

. The reactor will fail to trip from the control room requiring entry into FR

-S.1. Once emergency boration flowpath is aligned (1NV

-236B open), the reactor will trip.

Verifiable Action

- RO will manually insert control rods and BOP will initiate emergency boration.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 4 of 63 Scenario 2

- Summary Event 7 1B CA pump will fail to start (and cannot be manually started) following the reactor trip.

Verifiable Action

- RO will manually start the #1 CAPT.

Event 8 Twelve minutes following initiation of emergency boration the CAPT will experience an overspeed trip. With S/G N/R levels < 11% and no CA flow possible, a transition to FR

-H.1 (Response to Loss of Secondary Heat Sink) will be required. Following transition to FR

-H.1, steam generator depressurization will be required to establish feed flow from the CM system.

Verifiable Action

- Align feed flow to establish increasing S/G levels.

Event 9 During performance of FR-H.1, an attempt to depressurize the RCS using Aux Pressurizer Spray will not be effective due to failure of 1NV

-37A (NV Supply to Pzr Aux Spray) to open. RCS depressurization using a Pressurizer PORV will be required.

Verifiable Action

- BOP will depressurize RCS using a Pzr PORV. Critical Task 1

- Insert negative reactivity into the core by at least one of the following methods before completing the immediate action steps of FR

-S.1: De-energize the control rod drive MG sets Insert RCCAs Establish emergency boration flow to the RCS Critical Task 2 - Establish required feedwater (450 gpm) flow into at least one S/G before RCS bleed and feed is required.

Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5

-8) 8 2. Malfunctions after EOP entry (1

-2) 2 3. Abnormal events (2

-4) 4 4. Major transients (1

-2) 1 5. EOPs entered/requiring substantive actions (1

-2) 2 6. EOP contingencies requiring substantive actions (0

-2) 2 7. EOP based Critical tasks (2

-3) 2

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 5 of 63 EXERCISE GUIDE WORKSHEET 1. INITIAL CONDITIONS:

1.1 Reset to IC #

21 START TIME:__________

NOTES:

Trigger Instructor Action Final Delay Ramp Delete In Event 2 MAL-IDE005F ATM STEAM DUMP SV40 UNCONDITIONAL FAILURE 100 :05 2 3 VLV-CM004F CM140 COND CF PMP 1B SUCTION ISOL FAIL TO POSITION 0 :10 3 N/A BST-JFB5943B (2/3 SUCT FLOW CFPT B TRIP)

AS-IS 3 N/A BST-JFB5944B (2/3 SUCT FLOW CFPT B TRIP)

AS-IS 3 N/A BST-JPB5972 (2/3 SUCT PRESS CFPT B TRIP

- PS) AS-IS 3 N/A BST-JPB5973 (2/3 SUCT PRESS CFPT B TRIP

- PS) AS-IS 3 N/A MAL-IRX009 (RODS FAIL TO MOVE) AUTO 4 5 VLV-KC027F (KCC37A TRAIN A RECIRC LINE ISOL VLV FAIL TO POSITION) 1 :02 5 6 OVR-FWP012C (CFPT 1A TRIP & RESET TRIP PB)

ON 6 N/A MAL-IPX003A REACTOR TRIP BKR A FAILURE ACTIVE 6 N/A MAL-IPX003B REACTOR TRIP BKR B FAILURE ACTIVE 6 10 MAL-IPX003A REACTOR TRIP BKR A FAILURE ACTIVE :01 6 10 MAL-IPX003B REACTOR TRIP BKR B FAILURE ACTIVE :02 6 N/A MAL-CA004B FAILURE OF CA PUMP B TO START BOTH 7 10 MAL-CA005 CA PUMP OVERSPEED TRIP MECH- ANICAL 1 2:00 7 Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 6 of 63 N/A LOA-CA017 (RACKOUT CA PMP 1A) RACK-OUT N/A VLV-NV014F (NV37A PRZR SPRAY LINE ISOL VLV FAIL TO POSITION) 0 11 LOA-NV078 (SEAL WATER LOW FLOW LCL REFLASH ACK (AD7,C4)) ACK 2 MIN 12 LOA-CF020 (CFPT A COMMON TROUBLE LCL REFLASH ACK )AD5/C4))

ACK 2 MIN Ensure Event 10 = x10i247o (1NV

-236B Open)

Place a collar on 1A CA Pump.

Ensure A Train KC in service.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 7 of 63 2. SIMULATOR BRIEFING

2.1 Control

Room Assignments:

Position Name CRS RO BOP 2.2 Give a copy of Attachment 2 (Shift Turnover Information) to the CRS.

3. EXERCISE PRESENTATION 3.1 Familiarization Period A. Allow examinees time to familiarize themselves with the Control Board alignments.

3.2 Scenario EVENT 1, Centrifugal Charging (NV) Pump swap BOOTH INSTRUCTOR ACTION Following start of 1B NV pump, wait one minute and REPORT "1B NV Pumps is good for continued operation".

3.3 Scenario EVENT 2 , 1 SV-40 failure BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 2 to cause 1 SV-40 to fail open.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR for 1SV-40 , REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF an AO is dispatched to investigate 1SV

-40, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF the Unit Supervisor is contacted to develop a clearance for isolation of 1SV

-40, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF RP is notified of steam leak, REPEAT back the information.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 8 of 63 3.4 Scenario EVENT 3 , 1CM-140 failure BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause 1CM-140 (1B CFPT Suction Valve) to close

. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF the SOC is notified of current unit status, REPEAT back the information

. BOOTH INSTRUCTOR ACTION IF the Reactor Group Engineer is notified of the occurrence, REPEAT back the information

. BOOTH INSTRUCTOR ACTION IF RP is notified to sample and analyze gaseous effluents, REPEAT back the information

. BOOTH INSTRUCTOR ACTION IF Chemistry is notified to sample for isotopic analysis of iodine, REPEAT back the information

. BOOTH INSTRUCTOR ACTION IF AO is dispatched to acknowledge Low Seal Water Flow Annunciator, THEN INSERT SIMULATOR Trigger 11 to acknowledge annunciator.

BOOTH INSTRUCTOR ACTION IF AO is dispatched to acknowledge MFP common trouble, THEN INSERT SIMULATOR Trigger 12 to acknowledge annunciator.

3.5 Scenario EVENT 4 , Auto Control Rod failure BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR, REPEAT back the information.

3.6 Scenario EVENT 5 , KC miniflow valve 1KC

-C37A fails open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to fail 1 KC-C37A Open.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR, REPEAT back the information.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 9 of 63 BOOTH INSTRUCTOR ACTION IF an AO is dispatched to verify EKPI

-29 is ON, REPEAT back the information.

3.7 Scenario EVENT 6 , 1A CFPT Trip

/ ATWS BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 6 to trip 1A CFPT BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF AO is contacted to locally open RX Trip Breakers and MG Set Output Breakers, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF Primary Chemistry is contacted to obtain current NC boron concentration, REPEAT back the information.

3.8 Scenario EVENT 7, 1B CA Pump failure BOOTH INSTRUCTOR ACTION IF AO is contacted to investigate the 1B CA Pump & breaker, REPEAT back the information. Wait 10 Min and inform that no obvious problems found, Maintenance investigation continuing.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to expedite return of 1A CA Pump, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR for 1B CA Pump, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF contacted as primary chemistry to periodically perform NC boron samples, REPEAT the information

.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 10 of 63 3.9 Scenario EVENT 8, Loss of Heat Sink BOOTH INSTRUCTOR ACTION IF AO is contacted to reset CAPT T&TV, repeat back the information. Wait 10 minutes and inform that T&TV is mechanically bound and cannot be reset.

BOOTH INSTRUCTOR ACTION IF maintenance is contacted to perform troubleshooting procedure EM/1/A/5200/007, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF an AO is dispatched to verify CA Valve alignment per Enclosure 2, REPEAT the information.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 1 Page 11 of 63 Event

Description:

Shift Centrifugal Charging Pumps Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 11 of 63 EVENT 1 NOTE TO EVALUATOR:

Crew begins by shifting the operating charging pump per OP/1/A/6200/001 (Chemical and Volume Control System

), Enclosure 4.13 (Shifting Of the Operating Charging Pump). The initial conditions are complete.

ALL NOTE: This enclosure affect s reactivity and is designated important to Reactivity Management per AD-OP-ALL-0203 (Reactivity Management). (R.M.)

BOP 3.1 IF shifting from 1 A NV Pump in service to 1 B NV Pump in service, perform the following:

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 1 A NV Pump and associated piping is 103 gallons; the magnitude of the transient will be minimal.

Shifting charging pumps at low NC System pressures (< 1000 psig) with NC Pump(s) in service will result in hydraulic transients being placed on the NC Pump seal packages. Operating experience shows that these transients will affect seal return flow. (PIP 09

-2596) NOTE TO EVALUATOR:

Step 3.1.1 and the preceding note will not be applicable.

NOTE: A loss of 1EPD with only the 1B NV Pump running will isolate normal letdown due to an indicated loss of both charging pumps; the loss of 1EPD will also disable the LTOP function of 1NC

-32B (PZR PORV) creating a challenge to LTOP. This challenge does NOT occur if either the 1A NV Pump is in service or ND Letdown is in service. (PIP C 1241) BOP 3.1.1 IF Unit 1 is in Mode 4 with any RCS cold leg

< 210°F, or Mode 5, or Mode 6 when the reactor vessel head on, make log entry for 1NC

-32B (PZR PORV) per the applicable:

BOP 3.1.2 Ensure VCT pressure is between 18

-40 psig as read on 1NVP5500 (VCT Vent Press) (1MC5).

NOTE: If in an emergency situation, the 30 second delay after starting the Aux Oil Pump is NOT required before starting the NV pump.

BOP 3.1.3 30 seconds prior to starting 1 B NV pump, place "NV PUMP 1B AUX OIL PUMP" in the "ON" position.

NOTE TO EVALUATOR:

The crew will make a plant page to notify personnel of the start of the 1B Charging Pump BOP 3.1.4 Start "NV PUMP 1 B". (R.M.) BOP 3.1.5 Place "NV PUMP 1 B AUX OIL PUMP" in "AUTO".

BOP 3.1.6 Stop "NV PUMP 1 A".

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 1 Page 12 of 63 Event

Description:

Shift Centrifugal Charging Pumps Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 12 of 63 BOP 3.1.7 Verify proper charging flow rate.

Booth Operator will insert Trigger 2 for EVENT 2 at the discretion of the lead evaluator.

END OF EVENT 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 2 Page 13 of 63 Event

Description:

Atmospheric Steam Dump Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 13 of 63 EVENT 2 Indications:

1SV-40 red OPEN indicating light is lit, green CLSD light is dark Steam pressure decreasing Reactor power increasing OAC PT C1Q0986 '1SV

-40 OPEN' NOTE TO EVALUATOR: The crew may take action

, per OMP 1-7 , to isolate a known leak, and close 1SV-50 instead of entering AP

-28 to perform the isolation, or use the OAC alarm response as guidance to isolate 1SV

-40. The OAC alarm response is included as Attachment 11.

NOTE TO EVALUATOR: The following steps are from AP/1/A/5500/028, Secondary Steam Leak.

NOTE TO EVALUATOR:

If crew decides to enter AP/1/A/5500/028, then a plant page announcing the entry into this AP will be made.

RO/BOP 1. Monitor Enclosure 1 (Foldout Page)

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 3 in the back of this guide.

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. RO 3. RNO Perform the following:

a. Select "MANUAL" on turbine control panel.

b. Depress "CONTROL VALVES LOWER" pushbutton and reduce turbine 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 4. RNO IF T-Avg greater than 1.5°F higher than T

-Ref, THEN insert control rods as required to maintain T

-Avg within 1°F of T

-Ref.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 2 Page 14 of 63 Event

Description:

Atmospheric Steam Dump Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 14 of 63 ALL 5. IF AT ANY TIME reactor power greater than 100%, THEN perform Step 3 RNO. BOP 6. Verify Pzr level

- STABLE OR INCREASING

. ALL 7. IF AT ANY TIME while in this procedure Pzr level decreasing in an uncontrolled manner, THEN RETURN TO Step 6. ALL 8. IF AT ANY TIME VCT level goes below 23%, THEN align NV pump suction to FWST as follows:

BOP 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 BOP 9b. Dispatch operators to locate and identify source of steam leak.

RO 9c. Verify S/G PORVs

- CLOSED RO 9d. Verify condenser dump valves

- CLOSED RO 9e. Verify atmospheric dump valves

- CLOSED NOTE TO EVALUATOR: The CRS may elect not to perform step 9.e RNO due to the failure being identified and isolated.

RO 9e.RNO IF steam dump valves required to be closed, THEN perform the following:

1) Select "OFF RESET" on the following switches:

"STEAM DUMP INTLK BYP TRN A" "STEAM DUMP INTLK BYP TRN B"

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 2 Page 15 of 63 Event

Description:

Atmospheric Steam Dump Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 15 of 63 RO 9e.RNO 2)

IF valve will not close, THEN CLOSE affected atmospheric dump valve isolation valve.

RO 9e.RNO 3)

IF isolation valve will not close, THEN dispatch operator to fail air to affected atmospheric dump valve.

RO 9e.RNO 4) WHEN leaking atmospheric dump valve isolated OR repaired, THEN return the following switches to "ON":

"STEAM DUMP INTLK BYP TRN A" "STEAM DUMP INTLK BYP TRN B" BOP 9f. Verify CA PMP #1

- OFF NOTE TO EVALUATOR: Step 9.g will not be applicable.

RO 9g. IF leak suspected to be in a doghouse, THEN CLOSE the following valves: SRO 10. Determine required notifications:

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

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

BOP 11. Notify RP of leak.

ALL 12. Verify - LEAK ISOLATED.

ALL 13. Determine long term plant status. RETURN TO procedure and step in effect.

NOTE TO EVALUATOR: SRO may have a crew or focus brief at this time.

Booth Operator will insert Trigger 3 for EVENT S 3 & 4 at the discretion of the lead examiner.

END OF EVENT 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 3 & 4 Page 16 of 63 Event

Description:

1B CFPT Suction Valve Fails Closed. Automatic Control Rod Insertion Failure on Runback Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 16 of 63 EVENT S 3 & 4 Indications:

1AD-5, C/4 CFPT B COMMON TROUBLE 1AD-5, D/4 CFPT B LO SUCT FLOW 1AD-5, F/5 CFPT B LO SUCT PRESS 1B CFPT suction flow decreasing BOP Recognize 1B CFPT (Main Feed Pump) Flow decreasing BOP Trip 1B CFPT NOTE TO EVALUATOR:

CFPT suction flow <

3000 GPM for > 20 seconds will cause a CFPT trip. The crew may elect to not wait the full 20 seconds and may decide to trip 1B CFPT. Following trip of the CFPT a turbine runback will initiate. During the runback, control rods will fail to automatically insert. This will require the RO to manually insert control rods.

NOTE TO EVALUATOR:

The crew may make a plant page announcing entry into AP/1/A/5500/003 (Load Rejection). The following steps are taken from AP/1/A/5500/003 Case I (Switchyard Available).

RO 1. Verify turbine load

- DECREASING IN AUTOMATIC.

RO 2. Verify proper reactor response:

Control rods

- IN "AUTO" AND STEPPING IN P/R neutron flux

- DECREASING.

RO 2.RNO. IF T-Avg is greater than 1.5°F higher than T

-Ref, THEN insert control rods as required to maintain T

-Avg within 1°F of T

-Ref. 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.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 3 & 4 Page 17 of 63 Event

Description:

1B CFPT Suction Valve Fails Closed. Automatic Control Rod Insertion Failure on Runback Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 17 of 63 BOP 4. Verify Pzr PORV and Pzr spray valve status as follows: a. All Pzr PORVs

- CLOSED. BOP 4.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. d. Verify standby condensate booster pump(s)

- ON. 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 power

- GREATER THAN 20%.

ALL 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 10. RNO Adjust 1AS

-2 (Main Stm To Aux Steam) as required to maintain AS header pressure between 140 PSIG and 150 PSIG

. RO 11. Adjust 1TL

-4 (Stm Seal Reg Byp) as necessary to maintain steam seal pressure between 4 PSIG

- 6 PSIG.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 3 & 4 Page 18 of 63 Event

Description:

1B CFPT Suction Valve Fails Closed. Automatic Control Rod Insertion Failure on Runback Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 18 of 63 BOP 12. Monitor Enclosure 3 (Rod Insertion Limit Boration).

NOTE TO EVALUATOR:

Restoration of Rod Insertion Limits will require a total of approximately 365 gallons of boric acid. This acid addition will be accomplished in either two or three separate borations.

NOTE TO EVALUATOR: Enclosure 3 can be found as Attachment 4 in the back of this guide.

RO 13. Verify reactor power

- LESS THAN 30%.

RO 13.RNO. 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 appropriate 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.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 3 & 4 Page 19 of 63 Event

Description:

1B CFPT Suction Valve Fails Closed. Automatic Control Rod Insertion Failure on Runback Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 19 of 63 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: Turbine load Control rods Boron concentration.

RO 18. Notify System Operations Center (SOC) using the red dispatcher telephone of current unit status.

RO/BOP 19. Determine and correct cause of load rejection.

BOP 20. Shutdown unnecessary plant equipment as follows:

a. Restore CM and CF as follows:

1) Verify C

-htr drain pumps

- ON. 2) Verify both CF Pumps

- IN SERVICE.

BOP 20.a.2)RNO.

GO TO Step 20.b.

BOP 20.b. RC pump(s) and cooling tower fans. REFER TO OP/1/B/6400/001A (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 (1SI

-18) - DARK: "C-7A LOSS OF LOAD INTLK 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 AUTO.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 3 & 4 Page 20 of 63 Event

Description:

1B CFPT Suction Valve Fails Closed. Automatic Control Rod Insertion Failure on Runback Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 20 of 63 RO 22. Verify reactor power

- GREATER THAN 15%. RO/BOP 23. Verify CA pumps

- OFF. RO 24. Verify reactor power change

- GREATER THAN OR EQUAL TO 15% IN A 1 HOUR PERIOD.

RO/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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months an d 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following last power change greater than or equal to 15% rated thermal power within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period).

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)

SLC 16.8-2 (230 KV Switchyard Systems).

NOTE TO EVALUATOR:

Tech Spec 3.1.6 Condition A should must be entered requiring the crew to initiate a boration within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restore the control rods to above the insertion limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . The BOP should be initiating a boration per Enclosure 3 direction to comply with this required action.

Tech Spec 3.4.1 Condition A may be referenced, but will not be applicable due to an applicability note stating this limit does not apply during a Thermal Power Ramp of 5% per minute.

RO/BOP 27. Notify Reactor Group Engineer of occurrence.

SRO 28. Determine long term plant status. RETURN TO OP/1/A/6100/003 (Controlling Procedure For Unit Operation).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 3 & 4 Page 21 of 63 Event

Description:

1B CFPT Suction Valve Fails Closed. Automatic Control Rod Insertion Failure on Runback Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 21 of 63 NOTE TO EVALUATOR: The crew may or may not decide to address the failure of Automatic control rods insertion at this time. If so, the following steps are taken from AP/1/A/5500/015. If not the scenario may continue by having the booth operator insert Trigger 5 for EVENT 5.

RO 1. Verify plant conditions

- STABLE. RO 2. Ensure "CRD BANK SELECT" switch

- IN MANUAL.

RO 3. Adjust the following as necessary to maintain T

-Avg within 1°F of T

-Ref: Turbine load NC System boron concentration.

RO 4. Verify Rod Control system failure:

a. 1AD-2, A/10 "ROD CONTROL URGENT FAILURE"

- LIT. RO 4.a.RNO. Verify controlling rod bank(s) operate in manual mode as follows:

1) Record the initial control bank positions:

A B C D

___ ___ ___ ___

2) Reposition the affected rods 6 to10 steps.

3) Verify proper rod movement as follows:

Controlling bank repositions on demand.

Proper bank overlap is maintained.

4) Return the affected rod bank(s) to initial position.

5) IF required, THE N rods may be moved in manual.

6) GO TO Step 6. RO/BOP 6. Notify IAE to investigate problem.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 3 & 4 Page 22 of 63 Event

Description:

1B CFPT Suction Valve Fails Closed. Automatic Control Rod Insertion Failure on Runback Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 22 of 63 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).

SRO 8. Determine required notifications:

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

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

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

a. IF rods were operated in "BANK SELECT", THEN request reactor engineer guidance prior to returning rods to "AUTO".

b. Ensure T

-Avg - WITHIN 1°F OF T

-REF. c. WHEN desired, THEN place control rods in "AUTO".

d. Ensure steam dumps

- IN DESIRED MODE FOR EXISTING PLANT CONDITIONS.

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

NOTE TO EVALUATOR: The SRO will conduct a "Crew Update" to inform the crew of any Tech Spec conditions that have been entered.

Booth Operator will insert Trigger 5 for EVENT 5 at the discretion of the lead evaluator.

END OF EVENTS 3 & 4

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 5 Page 23 of 63 Event

Description:

Component Cooling Water Mini

-flow Valve Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 23 of 63 EVENT 5 Indications:

1AD-9, F/5 KC TRAIN A SINGLE PUMP RUNOUT 1KC-C37A RED OPEN indicating light

- LIT Various other KC flow annunciators BOP Recognizes 1 KC-C37A has failed open NOTE TO EVALUATOR: The crew may start an additional KC using 1AD

-9 F/5 ARP as guidance. The ARP is included as Attachment 12.

NOTE TO EVALUATOR: The following steps are taken from AP/1/A/5500/021 (Loss of Component Cooling). 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.

ALL 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 5 in the back of this guide.

BOP 2. Verify the following:

At least one KC pump

- ON. AND Flow to KC loads presently in service ALL 3. IF AT ANY TIME all KC pumps are lost, THEN RETURN TO STEP 2. ALL NOTE Uncooled letdown may result in loss of NV pumps within a matter of minutes. BOP 4. Verify the following:

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

- DARK. AND At least one KC pump

- ON.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 5 Page 24 of 63 Event

Description:

Component Cooling Water Mini

-flow Valve Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 24 of 63 ALL 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.

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

ALL 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.

BOP 8. Verify KC flow to NC pumps as follows:

1AD-20, A/1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK. 1AD-21, A/1 "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 (Aux Bldg Non

-Ess Hdr Isol) 1KC-1A (Aux 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 (Aux Bldg Non

-Ess Ret Hdr Isol).

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 5 Page 25 of 63 Event

Description:

Component Cooling Water Mini

-flow Valve Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 25 of 63 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. NOTE TO EVALUATOR: Step 14 may or may not be performed depending upon which pump was started. BOP 14. Ensure KC heat exchanger outlet mode switches

- PROPERLY ALIGNED. RO/BOP 15. Determine and correct cause of loss of KC.

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).

NOTE TO EVALUATOR: Tech Spec 3.7.7 Condition A is applicable and the CCW train must be restored to OPERABLE status in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

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).

NOTE TO EVALUATOR: Step 18 will not apply.

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 5 Page 26 of 63 Event

Description:

Component Cooling Water Mini

-flow Valve Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 26 of 63 BOP 19. Verify KC surge tanks level as follows:

Greater than 50%

Stable or increasing BOP 20. WHEN plant conditions permit, THEN perform the following:

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 2 (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 "VCT" position and return to "AUTO". c. IF desired to restore letdown flow through NV demineralizers, THEN momentarily place 1NV

-153A (Letdn Hx Otlt 3-Way Valve) to "DEMIN" position and return to "AUTO".

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 5 Page 27 of 63 Event

Description:

Component Cooling Water Mini

-flow Valve Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 27 of 63 NOTE TO EVALUATOR: Prior to proceeding to Event 6, ensure sufficient time has passed

, following runback

, to allow the plant to stabilize (i.e. Steam Dumps closed) in order to provide desired procedure flowpath for upcoming loss of heat sink.

Booth Operator will insert Trigger 6 for EVENT 6 at the discretion of the lead evaluator.

END OF EVENT 5

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario #

2 Event # 6 Page 28 of 63 Event

Description:

1A CFPT Trip / ATWS Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 28 of 63 EVENT 6 Indications:

1AD-5, A/1 CFPT A TRIPPED 1AD-5, A/4 CFPT A COMMON TROUBLE RO Recognizes loss of all feed flow to all S/G s at greater than 5% reactor power.

RO Attempts to manually trip the reactor per the immediate actions of AP/1/A/5500/06 (Loss of S/G Feedwater), Case l (Loss of CF Supply To S/Gs). NOTE TO EVALUATOR: The following steps are taken from AP/1/A/5500/006 (Loss of S/G Feedwater).

RO 1. Verify reactor power

- LESS THAN 5%.

RO 1.RNO. IF AT ANY TIME all CF supply to S/G(s) lost, THEN perform the following:

a. Manually trip reactor.

b. GO TO EP/1/A/5000/E

-0 (Reactor Trip or Safety Injection).

NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/E

-0 (Reactor Trip or Safety Injection).

RO/BOP 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 6 in the back of this guide.

RO 2. Verify Reactor Trip:

All rod bottom lights

- LIT All reactor trip and bypass breakers

- OPEN I/R power

- DECREASING.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario #

2 Event # 6 Page 29 of 63 Event

Description:

1A CFPT Trip / ATWS Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 29 of 63 RO 2.RNO. Perform the following:

a. Trip reactor.

b. IF reactor will not trip, THEN concurrently:

Implement EP/1/A/5000/F

-0 (Critical Safety Function Status Trees). GO TO EP/1/A/5000/FR

-S.1 (Response to Nuclear Power Generation/ATWS).

NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/FR

-S.1 (Response to Nuclear Power Generation/ATWS).

ALL CAUTION NC pumps should NOT be tripped with reactor power greater than 5% to prevent fuel damage.

RO 1. Verify Reactor Trip:

All rod bottom lights

- LIT All reactor trip and bypass breakers

- OPEN I/R power

- DECREASING.

Critical Task #1 RO 1.RNO. Perform the following:

a. Trip reactor.

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

RO 2. Verify Turbine Trip:

All turbine stop valves

- CLOSED RO 3. Verify CA pumps running as follows:

a. Motor driven CA pumps

- ON. NOTE TO EVALUATOR: 1A CA Pump is tagged out. Crew will attempt to start 1B CA pump. However, this pump will not start.

RO 3.a.RNO. Start motor driven CA pump(s).

RO 3.b. 3 S/G N/R levels

- GREATER THAN 11%.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario #

2 Event # 6 Page 30 of 63 Event

Description:

1A CFPT Trip / ATWS Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 30 of 63 RO 3.b.RNO. Ensure CA Pump #1

- RUNNING. NOTE TO EVALUATOR: The reactor will trip when the BOP depresses the red OPEN pushbutton on 1NV-236B. This will also start a timer for the eventual trip of CA Pump

1. 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: I/2 I/3 I/10 H/11 BOP 6. Verify S/I status as follows:

a. "SAFETY INJECTION ACTUATED" status light (1SI

-13) - LIT. RO/BOP 6.a.RNO. Perform the following:

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

2) GO TO Step 7. RO 7. Verify the following trips have occurred:

a. Reactor Trip.

b. Turbine Trip.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario #

2 Event # 6 Page 31 of 63 Event

Description:

1A CFPT Trip / ATWS Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 31 of 63 RO 8. Verify reactor is subcritical as follows:

a. All of the following conditions exist:

P/R channels

- LESS THAN 5%

I/R channels

- LESS THAN 5%

W/R NEUTRON POWER channels

- LESS THAN 5%

I/R SUR - NEGATIVE. b. GO TO Step 16. BOP 16. Ensure all malfunctioning NC pumps

- STOPPED. BOP 17. 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/0/A/6100/006 (Reactivity Balance Calculation).

d. WHEN following conditions are satisfied, THEN stop NC System boration: Adequate shutdown margin is obtained Uncontrolled cooldown has been stopped.

SRO 18. Determine required notifications:

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

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

ALL 19. RETURN TO procedure and step in effect.

NOTE TO EVALUATOR: SRO should return to EP/1/A/5000/E

-0 step 3. END OF EVENT 6

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 7, 8, 9 Page 32 of 63 Event

Description:

1B CA Pump failure, Loss of Heat Sink, 1NV

-37A failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 32 of 63 EVENTS 7 , 8 , &9 NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/E

-0. RO 3. Verify Turbine Trip:

All turbine stop valves

- CLOSED BOP 4. Verify 1ETA and 1ETB

- ENERGIZED.

BOP 5. Verify S/I actuated:

a. "SAFETY INJECTION ACTUATED" status light (1SI-13) - LIT. b. Both E/S load sequencer actuated status lights (1SI

-14) - LIT. ALL 5.a.RNO. Perform the following:

1) Verify conditions requiring S/I:

Pzr pressure

- LESS THAN 1845 PSIG OR Containment pressure

- GREATER THAN 1.2 PSIG.

2) IF S/I required, THEN initiate S/I.

3) IF S/I not required, THEN concurrently:

Implement EP/1/A/5000/F

-0 (Critical Safety Function Status Trees) GO TO EP/1/A/5000/ES

-0.1 (Reactor Trip Response).

NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/ES

-0.1. RO/BOP 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 7 in the back of this guide.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 7, 8, 9 Page 33 of 63 Event

Description:

1B CA Pump failure, Loss of Heat Sink, 1NV

-37A failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 33 of 63 RO 2. Verify the following:

All 6.9 KV busses

- ENERGIZED.

VI pressure

- GREATER THAN 85 PSIG. RO 3. Announce "Unit 1 Reactor Trip, non

-essential personnel stay out of Unit 1 Turbine bldg".

RO NOTE Enclosure 2 (NC Temperature Control) shall remain in effect until subsequent steps provide alternative NC temperature control guidance. RO 4. Control NC temperature. REFER TO Enclosure 2 (NC Temperature Control). NOTE TO EVALUATOR: Enclosure 2 can be found as Attachment 8 in the back of this guide.

SRO 5. Determine required notifications:

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

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

BOP 6. Verify Main Generator as follows:

a. Verify turbine generator megawatt output

- LESS THAN OR EQUAL TO ZERO MW.

b. Ensure the following breakers and MODs

- OPEN: MOD 1BG and 1BT MOD 1AG and 1AT Generator Breakers 1A and 1B.

c. Ensure main generator "EXCITATION"

- OFF. d. Verify "MAN/AUTO REG" select switch "MAN" mode light

- LIT. RO 7. Verify feedwater status as follows:

a. T-Avg - LESS THAN 564°F.

b. All Feedwater Isolation status lights (1SI

-5) - LIT. c. Total feed flow to S/G(s)

- GREATER THAN 450 GPM.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 7, 8, 9 Page 34 of 63 Event

Description:

1B CA Pump failure, Loss of Heat Sink, 1NV

-37A failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 34 of 63 RO 8. Verify adequate shutdown margin as follows:

a. DRPI indication

- AVAILABLE.

b. All control and shutdown rods

- FULLY INSERTED.

c. Stop any boron dilutions in progress.

d. All NC T-Colds - GREATER THAN 545°F.

e. IF AT ANY TIME NC T-Colds decrease to less than or equal to 545°F, THEN perform Step 8.d.

BOP 9. Verify proper Pzr level control as follows:

a. Verify VI pressure

- GREATER THAN 50 PSIG.

b. Verify Pzr level

- GREATER THAN 17%.

c. Verify charging and letdown - IN SERVICE.

d. Verify Pzr level

- TRENDING TO "PZR REF LEVEL".

BOP 10. Verify Pzr pressure

- GREATER THAN 1845 PSIG.

BOP 11. Verify 1A and 1B NC pumps

- ON. BOP 12. Verify Pzr pressure

- STABLE AT OR TRENDING TO 2235 PSIG.

RO 13. Control S/G levels as follows:

a. Verify N/R level in any S/G

- GREATER THAN 11%.

b. THROTTLE feed flow to maintain S/G N/R levels between 11%

and 50%. NOTE TO EVALUATOR: When the CAPT trips (with S/G Narrow range levels < 11%

), the heat sink critical safety function will turn RED. The crew should validate this RED path and transition to EP/1/A/5000/FR

-H.1 (Response To Loss of Secondary Heat Sink).

NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/FR

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 7, 8, 9 Page 35 of 63 Event

Description:

1B CA Pump failure, Loss of Heat Sink, 1NV

-37A failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 35 of 63 RO/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.

RO/BOP 2. Verify secondary 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.

RO/BOP 3. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 9 in the back of this guide.

BOP 4. Verify at least one NV pump

- AVAILABLE.

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

a. W/R level in at least 3 S/Gs

- LESS THAN 24% (36% ACC). RO/BOP 5.a.RNO. 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 19. 3) GO TO Step 6. BOP 6. Ensure S/G BB and NM valves closed. REFER TO Enclosure 8 (S/G BB and NM Valve Checklist).

NOTE TO EVALUATOR: Enclosure 8 can be found as Attachment 10 in the back of this guide.

RO 7. Attempt to establish CA flow to at least one S/G as follows:

a. Verify 1AD

-8, B/1 "UST LO LEVEL"

- DARK. b. Verify 1CA

-4 (CA Pmps Suct From UST)

- OPEN. c. Proper CA pump status as follows:

1) Power to both motor driven CA pumps

- AVAILABLE.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 7, 8, 9 Page 36 of 63 Event

Description:

1B CA Pump failure, Loss of Heat Sink, 1NV

-37A failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 36 of 63 RO 7.c.1)RNO. Perform the following:

IF essential bus is de

-energized, THEN restore power to affected essential bus. REFER TO AP/1/A/5500/007 (Loss of Normal Power).

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

RO 7.c.2) 1AD

-5, F/3 "CAPT MECH OS TRIP"

- DARK. RO/BOP 7.c.2)RNO. Perform the following:

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

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

c) GO TO Step 7.d. RO 7.d. 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.

RO/BOP 7.g.RNO. Perform the following:

1) IF any CA pump is on, AND Step 33 has been implemented, THEN GO TO Enclosure 6 (S/G CA Flow Restoration).

2) IF any feed flow to at least one S/G verified, THEN perform the following:

3) IF no CA flow indicated, THEN perform the following:

a) IF no CA pump can be started, THEN dispatch operator and maintenance to CA pumps to attempt to restore one CA pump to service. REFER TO EM/1/A/5200/007 (Troubleshooting Cause For CA Pump(s) Failing to Start).

b) Dispatch operator to verify proper CA valve alignment. REFER TO Enclosure 2 (Local CA Flowpath Restoration).

c) IF AT ANY TIME CA flow restored prior to meeting bleed and feed initiation criteria, THEN perform Step 7.

4) GO TO Step 8.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 7, 8, 9 Page 37 of 63 Event

Description:

1B CA Pump failure, Loss of Heat Sink, 1NV

-37A failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 37 of 63 RO 8. Transfer condenser steam dump to pressure control mode as follows:

a. Verify condenser

- AVAILABLE:

"C-9 COND AVAILABLE FOR STM DUMP" status light (1SI

-18) - LIT. Any MSIV - OPEN. b. Verify Steam Dumps in

- T-AVG MODE. c. Place steam dumps in pressure mode as follows:

1) Ensure "STM DUMP CTRL"

- SET AT 1090 PSIG STEAM HEADER PRESSURE. 2) Place "STM DUMP CTRL" slim station in manual.

3) Adjust "STM DUMP CTRL" slim station output to match "% STM DUMP DEMAND" (1SMP5211).

4) WHEN output on "STM DUMP CTRL" slim station is equal to "% STM DUMP DEMAND" (1SMP5211), THEN place steam dumps in

- PRESSURE MODE

. d. Place "STM DUMP CTRL" slim station in auto.

BOP 9. Stop all NC pumps.

BOP 10. Verify CM System is in service as follows:

Hotwell pump(s)

- ON Condensate Booster pump(s)

- ON. RO 11. Reset Feedwater Isolation as follows:

a. Verify the following annunciators

- DARK: 1AD-8, D/7 "INNER DOGHOUSE TRAIN A LEVEL HI" 1AD-8, E/7 "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 S/I

- HAS PREVIOUSLY ACTUATED.

Critical Task #2 RO 11.b.RNO. 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/5200/009 (Bypassing Feedwater Isolation).

3) GO TO Step 11.e.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 7, 8, 9 Page 38 of 63 Event

Description:

1B CA Pump failure, Loss of Heat Sink, 1NV

-37A failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 38 of 63 RO/BOP 11.e. IF AT ANY TIME a subsequent Feedwater Isolation occurs, THEN RETURN TO Step 11. RO 12. Attempt to establish CF flow to at least one S/G as follows:

a. Verify CM System - 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-10 (1A CF Pump Disch Isol) (TB1

-579, 1E-21) 1CF-17 (1B CF Pump Disch Isol) (TB1

-579, 1E-20). d. Verify at least one CF pump

- AVAILABLE TO BE STARTED.

RO/BOP 12.d.RNO.

IF both CF pumps are known to be incapable of starting, THEN GO TO Step 14. BOP 14. 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.

NOTE TO EVALUATOR: 1NV

-37A operation is failed requiring transition to RNO.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 7, 8, 9 Page 39 of 63 Event

Description:

1B CA Pump failure, Loss of Heat Sink, 1NV

-37A failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 39 of 63 BOP 14.c RNO Depressurize NC System to less than 1905 PSIG using one Pzr PORV. BOP d. Maintain NC pressure less than 1905 PSIG.

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

BOP 15. Block S/I as follows:

a. Verify "P

-11 PZR S/I BLOCK PERMISSIVE" status light (1SI

-18) - LIT. b. Depress "BLOCK" pushbuttons for the following signals:

ECCS steam pressure ECCS Pzr pressure.

c. Verify the following status lights (1SI

-13) - LIT: Main Steam Isol Pzr low pressure S/I

d. IF AT ANY TIME conditions degrade while in this procedure, THEN initiate S/I.

RO 16. Attempt to establish feed flow from CM as follows:

a. Verify condenser

- AVAILABLE "C-9 COND AVAILABLE FOR STM DUMP" status light (1SI

-18) - LIT. MSIV on S/Gs to be depressurized

- OPEN RO 16.b Place "STM DUMP CTRL" slim station in manual.

RO 16.c Verify steam dumps in

- PRESSURE MODE RO 16.d WHEN "P-12 LO-LO TAVG" status light (1SI

-18) is lit, THEN place steam dump interlock bypass switches in "BYP INTLK".

RO/BOP 16.e. Verify Bleed and Feed

- PREVIOUSLY ESTABLISHED (Steps 20 through 24 Completed).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 7, 8, 9 Page 40 of 63 Event

Description:

1B CA Pump failure, Loss of Heat Sink, 1NV

-37A failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 40 of 63 RO 16.e.RNO. Perform the following:

1) CLOSE MSIV on two S/Gs not to be depressurized.

2) Ensure S/G PORV closed or in "AUTO" on two S/Gs not to be depressurized.

3) GO TO Step 16.h.

RO NOTE After low steamline pressure main steam isolation signal is blocked, maintaining steam pressure negative rate less than 2 PSIG per second will prevent a Main Steam Isolation.

OAC graphic SMRATES to monitor S/G pressure rates can be accessed via a hot button in center of SM graphic. Critical Task #2 RO 16.h. Depressurize at least one S/G to less than 500 PSIG as follows:

1) Dump steam to condenser at maximum rate while attempting to avoid a Main Steam Isolation

. NOTE TO EVALUATOR: Main Feed Isolation will occur during depressurization. Crew will return to step 11 for reset.

The next step is only applicable if the operators depressurize too quickly and a Main Steam Isolation Signal occurs.

Critical Task #2 RO 16.h.1)RNO. Perform the following:

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

b) IF no S/G PORV can be operated from the control room, THEN perform the following:

c) IF no S/G PORV can be opened, THEN GO TO Step 18. RO 16.i. WHEN S/G pressure is less than 500 PSIG, THEN stabilize S/G pressure less than 500 PSIG.

j. Verify Bleed and Feed

- PREVIOUSLY ESTABLISHED (Steps 20 through 24 Completed).

RO 16.j.RNO.

GO TO Step 16.l.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

2 Event # 7, 8, 9 Page 41 of 63 Event

Description:

1B CA Pump failure, Loss of Heat Sink, 1NV

-37A failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 41 of 63 Critical Task #2 RO 16.l. Verify CF Isolation signal - RESET OR BYPASSED.

m. OPEN CF to CA valve on 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)

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

o. Verify feedwater flow to depressurized S/G(s)

- INDICATING FLOW.

RO/BOP 16.o.RNO. Perform the following:

1) IF depressurized S/G pressure is less than 500 PSIG, THEN GO TO Step 18. 2) RETURN TO Step 16.h.

NOTE TO EVALUATOR: The crew will continue in this procedure loop until feedwater flow is indicated to depressurized S/Gs. When flow is observed to these S/Gs, then the scenario is complete.

END OF EVENTS 7, 8, 9, & 10 END OF Scenario 2

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 42 of 63 Attachment List Scenario 2 ATTACHMENT 1

- Crew Critical Task Summary ATTACHMENT 2

- Shift Turnover Information ATTACHMENT 3

- AP/1/A/5500/02 8 Enclosure 1 (Foldout Page)

ATTACHMENT 4

- AP/1/A/5500/003 Enclosure 3 (Rod Insertion Limit Boration)

ATTACHMENT 5 - AP/1/A/5500/021 Enclosure 1 (Foldout Page)

ATTACHMENT 6 - EP/1/A/5000/E

-0 Enclosure 1 (Foldout Page)

ATTACHMENT 7 - EP/1/A/5000/E S-0.1 Enclosure 1 (Foldout Page)

ATTACHMENT 8 - EP/1/A/5000/E S-0.1 Enclosure 2 (NC Temperature Control) ATTACHMENT 9 - EP/1/A/5000/FR-H.1 Enclosure 1 (Foldout Page

) ATTACHMENT 10 - EP/1/A/5000/FR

-H.1 Enclosure 8 (S/G BB and NM Valve Checklist)

ATTACHMENT 11

- OAC PT C1Q0986 '1SV

-40 OPEN' Alarm Response Procedure ATTACHMENT 12

- 1AD-9 F/5 Annunciator Response Procedure

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 43 of 63 ATTACHMENT 1

CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK 1 Insert negative reactivity into the core by at least one of the following methods before completing the immediate action steps of FR

-S.1: De-energize the control rod drive MG sets Insert RCCAs Establish emergency boration flow to the RCS 2 Establish required feedwater (450 gpm) flow into at least one S/G before RCS bleed and feed is required. Comments:

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 44 of 63 ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 10 0 % E OL 90 PPM per OAC Controlling Procedure OP/1/A/6100/003 (Controlling Procedure for Unit Operation), Enclosure 4.3 (Unit Operation Between 85% and 100% Power). The steps up to step 3.16 are complete.

Other Information Needed to Assume the Shift Unit 1 is at 100% power at the EOL. Unit 2 is at 100% power.

1A CA Pump has been removed from service for PMs. 1A CA Pump has been inoperable for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and is expected to be returned to service in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Direction for the crew is to shift operating NV (Centrifugal Charging) Pumps by starting 1B NV Pump and securing 1A NV Pump. 1B NV Pump pre

-start check has been successfully completed. AOs Available Seven AOs are available as listed on the status board METEOROLOGICAL CONDITIONS Upper wind direction = 315 degrees, speed =

3 mph Lower wind direction = 315 degrees, speed =

4.5 mph Forecast calls for clear skies over the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 2 NUREG 1021 Revision 10 Page 46 of 63 ATTACHMENT 3

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Catawba Nuclear Station NRC Exam May 201 6 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 1 of 87

NRC INITIAL LICENSE EXAM SCENARIO #

3 Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 2 of 87 Facility: Catawba NRC Exam 201 6 Scenario No.:

3 Op Test No.:

2016301 Examiners:

Operators:

SRO RO BOP Initial Conditions:

Unit 1 is at 100% power at the EOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 100% power at the EOL. Unit 2 is at 100% power. Direction for the crew is to maintain current power.

Event No. Malf. No. Event Type* Event Description 1 IRX003A C - RO C - SRO Continuous rod motion 2 KC045 C - BOP C - SRO TS - SRO KC Surge Tank level transmitter failure. First pump fails to start 3 SG001D VLV-BB004 C - BOP C - SRO TS - SRO Tube leak on 1D S/G / 1D S/G Blowdown isolation failure upon 1EMF

-33 actuation 4 R - RO N - BOP N - SRO AP/09 downpower 5 MAL-MT005B C - RO C - SRO Turbine Hi Vibration /

Reactor and Turbine trip required 6 SG001D M-ALL Tube Rupture 7 CF015A C - RO 1C F-60 fails to close on Feedwater Isolation 8 ISE011B C - BOP VA Unfiltered Exhaust Fans fail to secure on SI

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

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 3 of 87 Scenario 3 - Summary Initial Condition Unit 1 is at 100% power at the EOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 100% power at the EOL. Unit 2 is at 100% power.

Direction for the crew is to maintain current power. Event 1 Continuous rod motion (insertion). AP/15 (Rod Control Malfunction) will be entered.

Verifiable Action

- RO will place control rods in manual and ensure rod motion stops.

Event 2 The level transmitter for the KC Surge Tank (Component Cooling) fails LOW. Requires BOP manual action to restore KC cooling (system realignment). AP/21 (Loss of Component Cooling) entry. The first KC pump start attempt FAILS. TS evaluation required.

Verifiable Action

- BOP will start additional KC pump to ensure cooling to both trains.

Event 3 A tube leak on 1D S/G begins ramping in at 15 gpm. AP/10 (Reactor Coolant Leak) will be entered. Radiation monitor 1EMF

-33 (Condenser Air Ejector Monitor) will fail to auto isolate the 1D S/G blowdown flow control valve. The crew will determine a plant shutdown is required and enter AP/09 (Rapid Downpower). TS evaluation required.

Verifiable Action

- BOP will manually isolate 1D S/G blowdown.

Event 4 The crew will begin a plant shutdown per AP/09. BOP will perform a boration. RO will input a target and load rate into the turbine control panel and place the turbine in GO to commence power decrease. RO will also insert control rods as required to maintain RCS temperature.

Event 5 The turbine will experience HI bearing vibration requiring a reactor and turbine trip.

Verifiable Action

- The RO will trip the reactor and then the turbine.

Event 6 Following the reactor trip, a S/G tube rupture will occur. The crew will initiate Safety Injection.

Verifiable Action - The crew will cooldown, depressurize, and terminate Safety Injection.

Event 7 1C F-60 (S/G 1D CF Cont Isol) fails to close on the feedwater isolation.

Verifiable Action

- RO will manually close 1CF-60. Event 8 VA Unfiltered Exhaust Fans will fail to auto secure following Safety Injection.

Verifiable Action

- BOP will secure VA Unfiltered Exhaust Fans.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 4 of 87 Critical Task 1 - Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA

-3.1 occurs.

Critical Task 2 - Establish/maintain an RCS temperature so that transition from E

-3 does not occur because the RCS temperature is in either of the following conditions Too high to maintain the minimum required subcooling Below the RCS temperature that causes and extreme (red path) or a severe (orange path) challenge to the subcriticality and/or integrity status tree.

Critical Task 3 - Depressurize RCS to meet SI termination criteria before water release occurs from the ruptured S/G PORV or safety (prior to S/G NR level reaching 100% and an associated S/G PORV or Safety Valve open).

Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5

-8) 7 2. Malfunctions after EOP entry (1

-2) 2 3. Abnormal events (2

-4) 4 4. Major transients (1

-2) 1 5. EOPs entered/requiring substantive actions (1

-2) 1 6. EOP contingencies requiring substantive actions (0

-2) 0 7. EOP based Critical tasks (2

-3) 3 Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 5 of 87 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC #

1 68 START TIME:__________

NOTES: Trigger Instructor Action Final Delay Ramp Delete In Event 1 MAL-OV0797B (IREDJ5040 RODS IN DEMAND fail to FALSE/TRUE)

TRUE 1 N/A MAL-IRX003A (UNCONTROLLED ROD INSERTION)

AUTO 1 2 XMT-KC045 (LKC_5631 KC SURGE TANK KCLS5630 TO VALVES) 0 2 N/A MAL-KC001B (KC PUMP 1A2 FAILURE) BOTH 2 10 MAL-KC001B (KC PUMP 1A2 FAILURE) BOTH 1 SEC 2 N/A MAL-KC001A (KC PUMP 1A1 FAILURE) BOTH 2 11 MAL-KC001A (KC PUMP 1A1 FAILURE) BOTH 1 SEC 2 3 MAL-SG001D (S/G D TUBE LEAK) 15 3 5 MAL-MT005B (TURBINE VIBRATION 6) 13 1:00 5 6 MAL-SG001D (S/G D TUBE LEAK) 400 :05 6 N/A VLV-CF015A (CF60 CF CONT ISOL VLV 1CF060 FAIL AUTO ACTIONS) ACTIVE 7 N/A MAL-ISE011B (AUX BLDG FANS FAIL TO AUTO STOP)

ACTIVE 8 N/A VLV-BB004 (BB65

-S/G D BLOWDOWN CTRL VLV FAIL AUTO ACTIONS)

ACTIVE 3 Ensure Event 10 = x11i119n (1A1 KC Pump ON Pushbutton)

Ensure Event 11 = x11i122n (1A2 KC Pump ON Pushbutton)

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 6 of 87 Ensure "B" KC is in service Ensure 1A NV Pump is in service

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 7 of 87 2. SIMULATOR BRIEFING 2.1 Control Room Assignments:

Position Name CRS RO BOP 2.2 Give a copy of Attachment 2 (Shift Turnover Information) to the CRS.

3. EXERCISE PRESENTATION 3.1 Familiarization Period A. Allow examinees time to familiarize themselves with the Control Board alignments.

3.2 Scenario EVENT 1 , Continuous Rod Motion BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 1 to cause Control Rod Insertion.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR for Control Rod malfunction, REPEAT back the information.

3.3 Scenario EVENT 2 , KC Surge Tank Level Transmitter Failure BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 2 to cause the B train KC Surge Tank level transmitter failure

. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR for the transmitter failure

, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF an AO is dispatched to investigate leaks at the KC Surge Tanks, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR for the KC Pump, REPEAT back the information.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 8 of 87 BOOTH INSTRUCTOR ACTION IF Operator dispatched to check out the KC pump that was started, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF Unit 2 Operator is contacted for Unit 2 RN miniflow status, RESPOND "Unit 2 RN is in normal miniflow alignment."

3.4 Scenario EVENT S 3 & 4 , 1D S/G Tube Leak and rapid downpower BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to initiate 1D S/G Tube leak.

BOOTH INSTRUCTOR ACTION IF Chemistry is contacted to ensure valves are closed per the annunciator response, STATE that the valves are closed.

BOOTH INSTRUCTOR ACTION IF RP is contacted to frisk the cation columns REPEAT back the information

. BOOTH INSTRUCTOR ACTION IF Chemistry is notified to determine affected S/G by sampling REPEAT back the information

. BOOTH INSTRUCTOR ACTION IF Chemistry is notified that CM polishing demineralizers have been bypassed, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF RP is notified to sample the Turbine Building sump, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF an AO is dispatched to re

-align Aux Electric Boiler feedwater supply, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF RP is notified of current leakage, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF RP is notified to perform HP/0/B/1009/003, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF an AO is dispatched to perform G

-1, Encl. 2, REPEAT back the information.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 9 of 87 BOOTH INSTRUCTOR ACTION IF an AO is dispatched to perform G

-1, Encl. 3, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF Engineering is notified of leak, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF AO is dispatched to secure CHDT Pumps, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF an AO is dispatched to close 1SP

-3, REPEAT back the information.

3.5 Scenario EVENT S 5, 6, 7, &

8 Turbine High Vibration and Tube Rupture (following Reactor Trip)

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to cause a turbine bearing 5, 6, & 7 high vibration.

BOOTH INSTRUCTOR ACTION WHEN step 7 of ES

-0.1 has been read, THEN INSERT SIMULATOR Trigger 6 to cause the 1D S/G tube leak to increase.

BOOTH INSTRUCTOR ACTION IF Secondary Chemistry is notified to sample all S/Gs for activity, REPEAT back the information

. BOOTH INSTRUCTOR ACTION IF RP is notified to frisk all cation columns for activity, REPEAT back the information

.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 1 Page 10 of 87 Event

Description:

Continuous Rod Motion Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 10 of 87 EVENT 1 Indications:

An audible clicking noise will be heard as the control rods begin to insert without a demand signal present.

RO Recognize rod motion without demand and place the "CRD BANK SELECT" switch in MAN.

NOTE TO EVALUATOR:

The following steps are from AP/1/A/5500/015, Rod Control Malfunctions, Case II (Continuous Rod Movement).

RO 1. Ensure "CRD BANK SELECT" switch

- IN MANUAL. RO 2. Verify all rod motion

- STOPS. NOTE: For T-Ref failures, T

-Ref will need to be determined for current power level.

RO 3. Manually adjust control rods as necessary to maintain T

-Avg within 1°F of T-Ref RO/BOP 4. 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 RO/BOP 5. Determine and correct cause of continuous rod movement.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 1 Page 11 of 87 Event

Description:

Continuous Rod Motion Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 11 of 87 SRO 6. 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).

NOTE TO EVALUATOR: The SRO will determine that no Tech Spec entries are required. Booth Operator will insert Trigger 2 for EVENT 2 at discretion of lead examiner.

END OF EVENT 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 2 Page 12 of 87 Event

Description:

KC Surge Tank Level Transmitter Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 12 of 87 EVENT 2 Indications:

OAC pt. C1D221 5 'KC TRAIN A LOW-LOW LEVEL SURGE TANK ISOL

- ACTUATED BOP Recognize the following valves close:

1KC-230A (RX BLDG NON

-ESS HDR ISOL) 1KC-3A (RX BLDG NON

-ESS RET HDR ISOL) 1KC-5 0A (AUX BLDG NON

-ESS HDR ISOL) 1KC-1A (AUX BLDG NON

-ESS RET HDR ISOL)

SRO Crew enters AP/1/A/5500/021 NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/021, Loss or Component Cooling.

NOTE TO EVALUATOR:

The following steps are from AP/1/A/5500/021, Loss of Component Cooling. 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. RO/BOP 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 3 in the back of this guide.

BOP 2. Verify the following:

At least one KC pump

- ON. AND Flow to KC loads presently in service.

BOP 2. RNO Perform the following:

a. Start additional KC pump(s) as necessary.

NOTE TO EVALUATOR: The first pump start attempt will fail.

NOTE TO EVALUATOR: Step 2 RNO b. will not apply BOP b. IF no KC pump can be started, THEN perform the following:

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 2 Page 13 of 87 Event

Description:

KC Surge Tank Level Transmitter Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 13 of 87 SRO 3. IF AT ANY TIME all KC pumps are lost, THEN RETURN TO STEP 2. NOTE Uncooled letdown may result in loss of NV pumps within a matter of minutes.

BOP 4. Verify the following:

1AD-7, F/3 "LETDN HX OUTLET HI TEMP" - DARK AND At least one KC pump

- ON. SRO 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

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

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

BOP 8. Verify KC flow to NC pumps as follows:

1AD-20, A/1 "KC SUPPLY HDR FLOW TO NCP BRGS LOW" - DARK 1AD-21, A/1 "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 (Aux Bldg Non

-Ess Hdr Isol) 1KC-1A (Aux Bldg Non

-Ess Ret Hdr Isol).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 2 Page 14 of 87 Event

Description:

KC Surge Tank Level Transmitter Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 14 of 87 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 48% KC surge tank level.

BOP 9.a. RNO a.

WHEN OAC alarm C1D2215 (KC Train A Low

-Low Level Surge Tank Isol) is "NOT ACTUATED" AND cause of valve closure known, THEN ensure the affected valve(s) are open.

BOP 9. 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 (Aux Bldg Non

-Ess Ret Hdr Isol).

BOP 9. c. 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.

ALL 10. b. GO TO Step 14. NOTE TO EVALUATOR: The KC heat exchanger outlet mode switches will be in the "KC Temp" position if the corresponding train of KC is in service. Otherwise, it will be in the "Miniflow" position.

BOP 14. Ensure KC heat exchanger outlet mode switches

- PROPERLY ALIGNED. ALL 15. Determine and correct cause of loss of KC.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 2 Page 15 of 87 Event

Description:

KC Surge Tank Level Transmitter Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 15 of 87 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).

NOTE TO EVALUATOR:

T.S 3.7.7 (Component Cooling Water (CCW) System) Condition A (Restore CCW train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) should be entered.

NOTE TO EVALUATOR: The SRO will conduct a "Crew Update" to inform the crew of any Tech Spec conditions that have been entered.

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).

NOTE TO EVALUATOR: Step 18 will not apply.

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 perform the following:

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 2 (Alternate Cooling To NV Pump 1A).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 2 Page 16 of 87 Event

Description:

KC Surge Tank Level Transmitter Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 16 of 87 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 "VCT" position and return to "AUTO". c. IF desired to restore letdown flow through NV demineralizers, THEN momentarily place 1NV

-153A (Letdn Hx Otlt 3

-Way Valve) to "DEMIN" position and return to "AUTO".

SRO 23. Determine long term plant status. RETURN TO procedure in affect. NOTE TO EVALUATOR: The SRO will conduct a "Crew Brief" or a "Focus Brief" to summarize the event. Booth Operator will insert Trigger 3 for EVENT 3 at the discretion of the lead examiner.

END OF EVENT 2

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 3 Page 17 of 87 Event

Description:

1D S/G Tube Leak Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 17 of 87 EVENT 3 Indications:

1RAD-1, B-1 1EMF 33 CSAE EXHAUST HI RAD 1RAD-1, B-4 1EMF 71 S/G A LEAKAGE HI RAD 1RAD-1, E-5 1EMF 74 S/G D LEAKAGE HI RAD CREW Recognizes symptoms of a S/G tube leak BOP Selects "AUTO" on Unit 1 CSAE EXH switch on panel 1MC

-13 per the annunciator response for 1RAD

-1, B/1 (1EMF 33 CSAE EXHAUST HI RAD).

BOP Closes the S/G Blowdown flow control valves per the ARP.

CREW Enter AP/1/A/5500/010, Reactor Coolant Leak, Case I (Steam Generator Tube Leak) NOTE TO EVALUATOR: S/G leakrate is 15 gpm

. NOTE TO EVALUATOR: 1RAD

-1, B/1 Annunciator Response Procedure can be found as Attachment 4 in the back of this guide.

NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/010, Reactor Coolant Leak.

NOTE TO EVALUATOR:

The following steps are from AP/1/A/5500/010, Reactor Coolant Leak, Case I (Steam Generator Tube Leak)

RO/BOP 1. Monitor Enclosure 1 (Case I Steam Generator Tube Leak Foldout Page). NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 5 in the back of this guide.

BOP 2. Verify Pzr level

- STABLE OR INCREASING.

BOP 2. RNO: Perform the following:

a. Maintain charging flow less than 180 GPM.

b. THROTTLE 1NV

-294 (NV Pmps A&B Disch Flow Ctrl) to stabilize Pzr level.

BOP c. IF Pzr level stable OR increasing, THEN GO TO Step 3. RO/BOP 3.. IF AT ANY TIME Pzr level decreases in an uncontrolled manner or cannot be maintained greater than 4%, THEN perform Step 2.

NOTE In subsequent steps the term "affected S/G is a S/G with primary to secondary leakage.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 3 Page 18 of 87 Event

Description:

1D S/G Tube Leak Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 18 of 87 RO/BOP 4. Identify 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 S/G Leakage EMFs are highly sensitive which may cause EMFs located on adjacent steamline to be increasing or in alarm.

Verify any of the following S/G leakage EMF indication(s)

- INCREASING OR IN ALARM:

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

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

- INCREASING OR IN ALARM:

o EMF-26 (Steamline 1A) o EMF-27 (Steamline 1B) o EMF-28 (Steamline 1C) o EMF-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 exits:

1AD-7, I/1 "VCT LO LVL" alarm

- LIT AND Reactor trip breakers are closed. THEN perform Step 5.a RNO.

NOTE OAC calculated leak rate may be invalid during mode changes and/or transient conditions unless there is current, coordinated sampling data available.

Tritium sampling may be the most effective method for determining leak rate for small tube leaks when in Mode 2 or 3.

OAC Primary to Secondary Leakage points may be accessed by turn on code "GD EROSLEAK" Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 3 Page 19 of 87 Event

Description:

1D S/G Tube Leak Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 19 of 87 BOP 6. Determine S/G leak rate by any of the following methods:

Monitor the following computer points:

o EROSLEAK (Primary To Secondary Leakage).

o C1P0187 (Estimated Total Pri To Sec Leakrate) o C1P0189 (Pri To Sec Leakrate 15 Min Running Avg)

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

S/G leakage EMF indication(s):

1EMF-71 (S/G A Leakage) 1EMF-72 (S/G B Leakage) 1EMF-73 (S/G C Leakage) 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 C1P0976 (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).

BOP 7. Minimize Secondary contamination as follows:

a. Remove CM polishing demineralizers from service as follows:

1) Ensure "POLSH DEMIN BYP CTRL" - 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. REFER TO EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 2 (Minimizing Secondary Side Contamination).

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 3 Page 20 of 87 Event

Description:

1D S/G Tube Leak Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 20 of 87 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).

NOTE TO EVALUATOR: Tech Spec 3.4.13 (RCS Operational Leakage) Condition B should be entered. Also, SLC 16.7

-9 (Standby Shutdown System) Condition A and B should be entered for the total accumulated leakage being greater than 20 gpm. RO/BOP 9. Verify Unit in Mode 1.

NOTE The following leak rates are based on leakage in one S/G.

In the event of an oscillating leak, leak rate shall be determined based on peak value of the spike.

RO/BOP 10. Verify leak rate

- GREATER THAN OR EQUAL TO 5 GPD.

RO/BOP 11. Verify leak rate

- GREATER THAN OR EQUAL TO 30 GPD.

RO/BOP 12. Verify at least one of the following:

Leak rate is greater than or equal to 100 gpd.

OR Leak rate greater than or equal to 75 gpd has been sustained for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

OR All of the following:

o Leak Rate is greater than or equal to 75 gpd o C1P0187 (Estimated Total Pri To Sec Leakrate)

- INVALID o Any main steam line N

-16 radiation monitor

- INOPERABLE.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 3 Page 21 of 87 Event

Description:

1D S/G Tube Leak Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 21 of 87 BOP 13. Perform the following:

NOTE Leakage indications are validated by EMFs trending in the same direction. Precise duplication of leakage values is not required. a. Verify at least one of the following EMFs validate leakage indication:

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

NOTE Unit shutdown should not be postponed while waiting for chemistry calculation results.

b. IF AT ANY TIME Chemistry calculations contradict leakage indications, THEN perform the following:

Unit shutdown may be suspended RETURN TO Step 8. NOTE EMFs should be monitored every 15 minutes.

c. Monitor the following EMFs:

1EMF-33 (Condenser Air Ejector Exhaust) 1EMF-71 (S/G A Leakage) 1EMF-72 (S/G B Leakage) 1EMF-73 (S/G C Leakage) 1EMF-74 (S/G D Leakage).

d. Notify RP of the following:

1) Current value of leakage.

2) Perform HP/0/B/1009/003 (Radiation Protection Response Following A Primary To Secondary Leak).

e. Evaluate secondary contamination potential. REFER TO EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 3 (Turbine Building Sump Isolation).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 3 Page 22 of 87 Event

Description:

1D S/G Tube Leak Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 22 of 87 SRO 14. Determine unit shutdown requirements as follows:

a. IF AT ANY TIME leak rate is greater than or equal to 100 gpd, THEN perform the following:

1) Ensure reactor power less than 50% within 1 hr.

2) Ensure unit in Mode 3 within the following 2 hrs.

3) IF leak rate is greater than or equal to 150 gpd, THEN ensure unit in Mode 5 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

4) Observe Note prior to Step 15 and GO TO Step 15. NOTE EMF indications may decrease during unit shutdown. Unit shutdown should not be suspended based solely on decreasing radiation monitor indications.

SRO 15. Shutdown Unit as follows:

a. Notify Engineering of occurrence.

b. Verify reactor power

- GREATER THAN 15%.

c. Initiate unit shutdown. REFER TO: o OP/1/A/6100/003 (Controlling Procedure For Unit Operation)

OR o AP/1/A/5500/009 (Rapid Downpower).

d. Ensure adequate shutdown margin is maintained. REFER TO ROD Book, Section 5.11. NOTE TO EVALUATOR: The SRO may conduct a "Focus Brief" to give the crew direction.

TRANSITION TO AP/1/A/5500/009 (Rapid Downpower)

END OF EVENT 3

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 4 Page 23 of 87 Event

Description:

Rapid Downpower Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 23 of 87 EVENT 4 NOTE TO EVALUATOR: The crew will make a plant page announcing the entry into AP/1/A/5500/009, Rapid Downpower.

NOTE TO EVALUATOR:

The following steps are from AP/1/A/5500/009, Rapid Downpower RO/BOP 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 6 in the back of this guide.

SRO 2. Determine required notifications:

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

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

ALL 3. IF AT ANY TIME prompt separation from the grid is required, THEN GO TO Step 26.

NOTE TO EVALUATOR: Step 4 will not apply.

RO 4. IF load reduction is due to grid instability, THEN perform the following:

NOTE In manual mode, the control valves are capable of full travel within 3 minutes. a. Select "MANUAL" and "CONTROL VALVE LOWER" to reduce turbine load as required.

b. GO TO Step 12. RO 5. Verify Turbine Control

- IN AUTO. RO/BOP 6. Verify the following load reduction criteria

- KNOWN: Time required to reduce load Target load power level.

RO 7 Verify time required to reduce load

- GREATER THAN OR EQUAL TO 15 MINUTES.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 4 Page 24 of 87 Event

Description:

Rapid Downpower Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 24 of 87 NOTE The following tables are estimates only and can be used for rapid entry into the turbine control panel.

SRO/BOP 8. Determine the required power reduction rate (MW/Min) from the table below: NOTE TO EVALUATOR: Step 8 Table can be found as Attachment 7 in the back of this guide.

SRO/BOP 9. Determine the target load from the table below:

NOTE TO EVALUATOR: The crew should determine target load to be 40 MW.

NOTE TO EVALUATOR: Step 9 Table can be found as Attachment 8 in the back of this guide.

RO 10. Initiate turbine load reduction as follows:

NOTE Any load reduction rate of greater than 25 MW/Min must be performed in the manual mode.

Unloading rates greater than 60 MW/Min (5%/minute) will meet C-7A interlock and may result in steam dump actuation.

a. Verify automatic turbine load reduction

- DESIRED. b. Enter the desired "LOAD RATE" on the turbine control panel

. c. Enter the desired "TARGET" on the turbine control panel

. d. Depress the "GO" pushbutton on the turbine control panel

. e. Verify turbine load

- DECREASING AS REQUIRED.

f. IF AT ANY TIME the turbine controls fail to respond properly, THEN perform Step 10.e.

RO 11. IF AT ANY TIME the turbine load reduction rate OR the target load must be changed, THEN RETURN TO Step 5.

RO 12. Adjust power factor as necessary. REFER TO Unit 1 Revised Data Book Figure 43.

RO 13. Attempt to control T

-Avg as follows:

a. Verify T-Ref instrumentation

- AVAILABLE.

b. Verify control rods

- IN AUTO AND STEPPING IN.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 4 Page 25 of 87 Event

Description:

Rapid Downpower Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 25 of 87 NOTE TO EVALUATOR: OATC will insert control rods in manual due to previous automatic failure.

RO 13.RNO.3.b IF T-Avg is greater than 1.5°F higher than T

-Ref, THEN manually insert control rods as required to maintain T

-Avg within 1°F of T

-Ref. RO 13. c. Maintain T

-Avg greater than or equal to 551°F.

d. Verify Reactor Engineering Power Maneuvering Guidance has been provided by Duty Reactor Engineer.

BOP 13.RNO.3.d. Perform the following:

NOTE The boric acid added to the NC System should be added in several increments.

The boric acid added to the NC System should be added only during the first hour of the downpower event. 1) Borate NC System as required. REFER TO R.O.D. book (section 4.8).

2) GO TO Step 13.f.

BOP 13. f. Ensure operator monitors Enclosure 2 (Rod Insertion Limit Boration).

NOTE TO EVALUATOR:

Down power will require approximately 760 gallons of boric acid additions (7.6 gallons/% power).

BOP 14. Verify Pzr PORV and Pzr spray valve status as follows:

a. All Pzr PORVs

- CLOSED. b. Normal Pzr spray valves

- CLOSED. NOTE TO EVALUATOR: After step 14 of AP

-09 (and completion of boration), the booth instructor can insert Event 5 at the lead examiner's discretion.

BOP 15. Operate RC pumps and fans as necessary to maintain RC temperature greater than 60°F. REFER TO OP/1/B/6400/001A (Condenser Circulating Water System).

RO 16. Verify reactor power

- LESS THAN 85%.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 4 Page 26 of 87 Event

Description:

Rapid Downpower Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 26 of 87 RO 16.RNO Perform the following:

a. IF the target load is less than 85%, THEN: 1) WHEN time and personnel permit, THEN perform applicable steps of OP/1/A/6100/003 (Controlling Procedure for Unit Operation).

2) Do not continue in this procedure until reactor power is less than 85%. 3) WHEN reactor power is less than 85%, THEN GO TO Step 17. b. WHEN the 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 41. BOP 17. Dispatch operator to secure both C

-Htr drain pumps. REFER TO OP/1/B/6250/004 (Feedwater Heater Vents, Drains and Bleed System)

BOP 18. Align AS supply to the CF pumps as follows:

a. Adjust 1AS

-2 (Main Stm To Aux Steam) as necessary to maintain AS header pressure 165 PSIG.

b. Ensure 1AS

-12 (AS To CFPT Isol)

- OPEN. c. Dispatch operator to close 1SP

-3 (SC To CFPT 1A & 1B) (TB1

-640, 1G-24). RO 19. Adjust 1TL

-4 (Stm Seal Reg Byp) as necessary to maintain steam seal pressure between 4 PSIG

- 6 PSIG. RO 20. Verify reactor power

- LESS THAN 69%.

RO 20.RNO Perform the following:

a. IF the target load is less than 69%, THEN: 1) WHEN time and personnel permit, THEN perform applicable steps of OP/1/A/6100/003 (Controlling Procedure for Unit Operation).

2) Do not continue in this procedure until reactor power is less than 69%. 3) WHEN reactor power is less than 69%, THEN GO TO Step 21.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 4 Page 27 of 87 Event

Description:

Rapid Downpower Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 27 of 87 b. WHEN the 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 41. RO 21. Verify "P9

-REACTOR-REACTOR-TRIP ON TURBINE TRIP BLOCKED" status light (1SI

-18) - LIT. NOTE TO EVALUATOR: The following steps are taken from OP/1/A/6150/009 (Boron Concentration Control) Enclosure 4.2 (Boration).

ALL NOTE: This enclosure will affect reactivity of the core and is therefore designated important to Reactivity Management per the guidelines of AD-OP-ALL-0203 (Reactivity Management). (R.M.)

BOP 3.1 Ensure valves are aligned per Enclosure 4.8 (Valve Checklist).

BOP 3.2 Ensure the following valve control switches in "AUTO":

1NV-238A (B/A To Blender Ctrl Vlv) 1NV-186A (B/A Blender Otlt To VCT Otlt)

BOP 3.3 Ensure 1NV

-238A (B/A To Blender Ctrl Vlv) controller in auto.

BOP 3.4 Ensure at least one boric acid transfer pump is in "AUTO" or "ON".

BOP 3.5 Record the desired volume of boric acid to be added. ______ gallons BOP 3.6 Adjust the boric acid counter to the desired volume of boric acid to be added. (R.M.)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 4 Page 28 of 87 Event

Description:

Rapid Downpower Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 28 of 87 BOP 3.7 IF the blender is set up for automatic makeup per Enclosure 4.1 (Automatic Makeup), record the setpoint of the controller for 1NV

-238A (B/A To Blender Ctrl Vlv). __________ gpm BOP 3.8 Place the "NC MAKEUP MODE SELECT" switch in "BORATE".

ALL NOTE: Boric Acid flow rates > 32 gpm may result in a boric acid flow deviation annunciator.

BOP 3.9 IF required, adjust the controller for 1NV

-238A (B/A To Blender Ctrl Vlv) to the desired flow.

BOP 3.10 IF NC System boron concentration will be changed by

> 50 ppm, initiate PZR spray to equalize the boron concentration throughout the system by operating backup heaters per OP/0/A/6200/005 (Miscellaneous Component Operation).

NOTE TO EVALUATOR: Step 3.11, 3.12, and 3.13 are conditional steps and should not need to be performed during this scenario.

BOP 3.11 IF AT ANY TIME it is desired to divert letdown to the RHT manually operate 1NV

-172A (3-Way Divert to VCT

-RHT) as follows:

3.11.1 Place the control switch for 1NV

-172A (3-Way Divert to VCT

-RHT) to the "RHT" position.

3.11.2 Ensure VCT level is monitored continuously while diverting to the RHT. NOTE: Procedure may continue while performing the next step.

3.11.3 WHEN desired VCT level is reached return 1NV-172A (3-Way Divert to VCT

-RHT) to auto as follows:

3.11.3.1 Place the control switch for 1NV

-172A (3-Way Divert to VCT-RHT) in the "VCT" position.

3.11.3.2 Place the control switch for 1NV

-172A (3-Way Divert to VCT-RHT) in the "AUTO" position.

BOP 3.12 IF AT ANY TIME during the makeup it becomes necessary to change the makeup flow rate, adjust the setpoint for 1NV

-238A (B/A Xfer Pmp To Blender Ctrl) as necessary to achieve the desired flow.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 4 Page 29 of 87 Event

Description:

Rapid Downpower Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 29 of 87 BOP 3.13 IF AT ANY TIME while boration is in progress it becomes necessary OR it is desired to stop the boration, perform the following:

3.13.1 Place the "NC MAKEUP CONTROL" switch to the "STOP" position. 3.13.2 Ensure the following valves close: (R.M.)

1NV-238A (B/A To Blender Ctrl Vlv) 1NV-186A (B/A To Blender Otlt To VCT Otlt) 3.13.3 Record boric acid volume added as indicated on the Boric Acid counter. __________ gallons 3.13.4 WHEN conditions allow resuming the boration, perform the following:

3.13.4.1 Determine remaining volume to be added by subtracting the amount previously added (Step 3.13.3) from the desired volume to be added (Step 3.5)

__________

- __________ = __________ gallons (Step 3.5) (Step 3.13.3) 3.13.4.2 Adjust boric acid counter to the volume of boric acid determined in Step 3.13.4.1. (R.M.)

3.13.4.3 Place "NC MAKEUP CONTROL" switch in the "START" position. (R.M.)

3.13.4.4 Verify the following:

1NV-238A (B/A To Blender Ctrl Vlv) modulates to establish desired flow 1NV-186A (B/A To Blender Otlt To VCT Otlt) opens 3.13.4.5 IF in "AUTO", verify the boric acid pump starts.

RO/BOP 3.14 WHILE makeup is in progress, monitor the following for expected results: Control rod motion NC System Tavg Reactor Power BOP NOTE: If a small makeup is being performed, placekeeping for Steps 3.15 through 3.18 may be performed after Step 3.19 is performed.

BOP 3.15 Place the "NC MAKEUP CONTROL" switch to the "START" position. (R.M.)

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 4 Page 30 of 87 Event

Description:

Rapid Downpower Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 30 of 87 BOP 3.16 Verify the following:

1NV-238A (B/A To Blender Ctrl Vlv) modulates to establish desired flow 1NV-186A (B/A Blender Otlt To VCT Otlt) opens BOP 3.17 IF in "AUTO", verify the boric acid transfer pump starts.

BOP 3.18 Verify proper flow by observing the Boric Acid Counter. {PIP 96

-0137} BOP NOTE: The boric acid counter may count up 1

- 5 gallons after termination.

BOP 3.19 WHEN the desired volume of boric acid is reached on the boric acid counter, ensure the following valves close: (R.M.)

1NV-238A (B/A To Blender Ctrl Vlv) 1NV-186A (B/A 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.

BOP 3.20 IF desired, flush the makeup line as follows:

3.20.1 Record the setpoint on 1NV

-242A (RMWST To B/A Blender Ctrl): ________ gpm 3.20.2 Place controller for 1NV

-242A (RMWST To B/A Blender Ctrl) in manual. 3.20.3 Increase demand on controller for 1NV

-242A (RMWST To B/A Blender Ctrl) to full open.

3.20.4 Open the following valves:

1NV-242A (RMWST To B/A Blender Ctrl) 1NV-186A (B/A Blender Otlt To VCT Otlt) 3.20.5 Ensure one reactor makeup water pump is in "ON".

3.20.5.1 IF Unit 1 RMWST is NOT aligned to supply Unit 2 per OP/2/A/6200/012 (Reactor Makeup Water), ensure at least one reactor makeup water pump is "ON". 3.20.5.2 IF Unit 1 RMWST is aligned to supply Unit 2 per OP/2/A/6200/012 (Reactor Makeup Water) AND a Unit 1 RMW Pump is NOT running to support Unit 2 activities, ensure at least one reactor makeup water pump is "ON".

3.20.5.3 IF Unit 1 RMWST is aligned to supply Unit 2 per

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 4 Page 31 of 87 Event

Description:

Rapid Downpower Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 31 of 87 OP/2/A/6200/012 (Reactor Makeup Water) AND a Unit 1 RMW Pump is running to support Unit 2 activities, ensure the second Unit 1 reactor makeup water pump is "ON".

3.20.6 WHEN ~ 20 gallons of makeup water have been flushed through the makeup line, close the following valves:

1NV-242A (RMWST To B/A Blender Ctrl) 1NV-186A (B/A Blender Otlt To VCT Otlt) 3.20.7 Place the following valve control switches in "AUTO":

1NV-242A (RMWST To B/A Blender Ctrl) 1NV-186A (B/A Blender Otlt To VCT Otlt) 3.20.8 Ensure controller for 1NV

-242A (RMWST To B/A Blender Ctrl) is set to the value recorded in Step 3.20.1. (R.M.)

3.20.9 Place controller for 1NV

-242A (RMWST To B/A Blender Ctrl) in auto. 3.20.10 IF NOT required for current plant operation, place the reactor makeup water pump started in Step 3.20.5 in "AUTO".

BOP 3.21 IF automatic makeup is desired, perform the following:

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

OR 3.21.2 IF makeup at the previous concentration is acceptable AND the system was previously aligned per Enclosure 4.1 (Automatic Makeup), perform the following:

3.21.2.1 Ensure the controller for 1NV

-238A (B/A Xfer Pmp To Blender Ctrl) is set to the value recorded in Step 3.7. (R.M.) 3.21.2.2 Place the "NC MAKEUP MODE SELECT" switch in "AUTO". 3.21.2.3 Place the "NC MAKEUP CONTROL" switch to the "START" position. (R.M.)

BOP 3.22 IF initiated in Step 3.10, terminate PZR spray by securing backup heaters per OP/0/A/6200/055 (Miscellaneous Component Operation).

END OF OP/1/A/6150/009 Booth Operator will insert Trigger 5 for EVENT 5 at the discretion of the lead evaluator.

END OF EVENT 4

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 32 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 32 of 87 EVENT S 5, 6, 7, & 8 Indications:

1AD-1, E/8 TURBINE GEN HI VIBRATION OAC alarms for Turbine Bearing Vibration High on bearings 5, 6, and 7.

NOTE TO EVALUATOR: Per the annunciator response procedure for 1AD

-1, E/8, the crew should decide to trip the Unit 1 Main Turbine following validation of vibration levels exceeding 12 Mils.

With reactor power being > 69% (P

-9), the annunciator response procedure will direct a reactor trip.

This annunciator response is Attachment 9 in the back of this guide.

RO Trip Unit 1 Reactor due to high turbine vibration.

NOTE TO EVALUATOR: The following actions are from EP/1/A/5000/E

-0 (Reactor Trip or Safety Injection).

RO/BOP 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 10 in the back of this guide.

RO 2. Verify Reactor Trip:

All rod bottom lights

- LIT All reactor trip and bypass breakers

- OPEN I/R power

- DECREASING.

RO 3. Verify Turbine Trip:

All turbine stop valves

- CLOSED BOP 4. Verify 1ETA and 1ETB

- ENERGIZED.

BOP 5. Verify S/I is actuated:

a. "SAFETY INJECTION ACTUATED" status light (1SI

-13) - LIT.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 33 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 33 of 87 BOP 5.a. RNO Perform the following:

1) Verify conditions requiring S/I Pzr pressure

- LESS THAN 1845 PSIG OR Containment pressure

- GREATER THAN 1.2 PSIG.

2) IF S/I required, THEN initiate S/I.

3) IF S/I not required, THEN concurrently:

Implement EP/1/A/5000/F

-0 (Critical Safety Function Status Trees). GO TO EP/1/A/5000/ES

-0.1 (Reactor Trip Response)

NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/ES

-0.1 (Reactor Trip Response).

ALL 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 15 in the back of this guide.

BOP 2. Verify the following:

All 6.9 KV busses

- ENERGIZED.

VI pressure

- GREATER THAN 85 PSIG.

RO 3. Announce "Unit 1 Reactor Trip, non

-essential personnel stay out of Unit 1 Turbine bldg".

NOTE Enclosure 2 (NC Temperature Control) shall remain in effect until subsequent steps provide alternative NC temperature control guidance.

RO 4. Control NC temperature. REFER TO Enclosure 2 (NC Temperature Control). NOTE TO EVALUATOR: Enclosure 2 of ES

-0.1 is the same as E

-0 Enclosure 4 for NC Temperature Control, which can be found as Attachment 13 in the back of this guide. SRO 5. Determine required notifications:

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

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 34 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 34 of 87 RO 6. Verify Main Generator as follows:

a. Verify turbine generator megawatt output

- LESS THAN OR EQUAL TO ZERO MW.

b. Ensure the following breakers and MODs

- OPEN: MOD 1BG and 1BT MOD 1AG and 1AT Generator Breakers 1A and 1B.

c. Ensure main generator "EXCITATION"

- OFF. d. Verify "MAN/AUTO REG" select switch "MAN" mode light

- LIT. RO 7. Verify feedwater status as follows:

a. T-Avg - LESS THAN 564°F.

b. All Feedwater Isolation status lights (1SI

-5) - LIT. RO 7.b. RNO Perform the following:

1) Initiate Feedwater Isolation.

2) IF any status light remains dark, THEN perform Enclosure 3 (Closure of Feedwater Isolation Valves).

NOTE TO EVALUATOR: Enclosure 3 can be found as Attachment 16 in the back of this guide.

RO c. Total feed flow to S/G(s)

- GREATER THAN 450 GPM. NOTE TO EVALUATOR: Following the reading of Step 7 of ES

-0.1 , the booth operator will insert Event 6 which will cause the S/G tube leak on 1D S/G to increase to a SGTR and will require the crew to take ES

-0.1 Enclosure 1 actions for not being able to maintain Pressurizer level > 4%. This will require manual initiation of S/I and a return to E

-0. RO 8. Verify adequate shutdown margin as follows:

a. DRPI indication

- AVAILABLE.

b. All control and shutdown rods

- FULLY INSERTED.

c. Stop any boron dilutions in progress.

d. All NC T

-Colds - GREATER THAN 545°F.

e. IF AT ANY TIME NC T-Colds decrease to less than or equal to 545°F, THEN perform step 8.d.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 35 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 35 of 87 BOP 9. Verify proper Pzr level control as follows:

a. Verify VI pressure

- GREATER THAN 50 PSIG.

b. Verify Pzr level

- GREATER THAN 17%

c. Verify charging and letdown

- IN SERVICE.

d. Verify Pzr level

- TRENDING TO "PZR REF LEVEL".

BOP 10. Verify Pzr pressure

- GREATER THAN 1845 PSIG.

NOTE TO EVALUATOR: By this point the crew should diagnose that the SGTL has gotten bigger and that manually initiating S/I and returning to E

-0 is required. The following steps are taken from E

-0. ALL 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 10 in the back of this guide.

RO 2. Verify Reactor Trip:

All rod bottom lights

- LIT All reactor trip and bypass breakers

- OPEN I/R power

- DECREASING.

RO 3. Verify Turbine Trip:

All turbine stop valves

- CLOSED BOP 4. Verify 1ETA and 1ETB

- ENERGIZED.

BOP 5. Verify S/I 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".

SRO 7. Determine required notifications:

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

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

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 36 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 36 of 87 RO 8. Verify all Feedwater Isolation status lights (1SI

-5) - LIT. BOP 9. Verify Phase A Containment Isolation status as follows:

a. Phase A "RESET" lights

- DARK. b. Monitor Light Panel Group 5 St lights on energized trains

- LIT. BOP 10. Verify proper Phase B actuation as follows:

a. Verify 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.

RO 11. Verify proper CA pump status as follows:

a. Motor driven CA pumps

- ON. RO 11. a. RNO Perform the following for affected train(s):

1) Reset ECCS.

2) Reset D/G load sequencer(s).

3) Start affected pump(s).

4) IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on.

RO 11.b 3 S/G N/R levels

- GREATER THAN 11%.

BOP 12. Verify all of the following S/I pumps

- ON: NV pumps ND pumps NI pumps BOP 13. Verify all KC pumps

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

- ON. NOTE TO EVALUATOR: BOP will address the failure of VA Unfiltered Exhaust Fans to secure during performance of Enclosure 2.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 37 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 37 of 87 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).

NOTE TO EVALUATOR: Enclosure 2 can be found as Attachment 1 1 in the back of this guide.

RO 16. Verify all S/G pressures

- GREATER THAN 775 PSIG.

RO 17. Verify proper S/I flow as follows:

a. "NV S/I FLOW" - INDICATING FLOW.

b. NC pressure

- LESS THAN 1620 PSIG.

RO 17.b RNO 1) Ensure ND pump miniflow valve on operating ND pump(s)

- OPEN. 2) IF the ND pump miniflow valve(s) cannot be opened, THEN perform the following for affected train(s):

3) GO TO Step 18. RO/BOP 18. WHEN time and manpower permit (within two hours of event), THEN monitor Spent Fuel Pool level and temperature. REFER TO EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring).

NOTE TO EVALUATOR: G

-1 Enclosure 1 can be found as Attachment 1 2 in the back of this guide.

RO 19. Control S/G levels as follows:

a. Verify total CA flow

- GREATER THAN 450 GPM.

b. WHEN each S/G N/R level greater than 11% (29% ACC), THEN control feed flow to maintain that S/G N/R level between 11% (29%

ACC) and 50%.

RO 20. Verify all CA isolation valves - OPEN. BOP 21. Verify S/I equipment status based on monitor light panel

- IN PROPER ALIGNMENT.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 38 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 38 of 87 RO NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until subsequent procedures provide alternative NC temperature control guidance. RO 22. Control NC temperature. REFER TO Enclosure 4 (NC Temperature Control). NOTE TO EVALUATOR: Enclosure 4 can be found as Attachment 13 in the back of this guide.

BOP 23. 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. BOP 24. Verify NC subcooling based on core exit T/Cs

- GREATER THAN 0°F.

RO 25. Verify main steamlines intact:

All S/G pressures

- STABLE OR INCREASING ALL S/Gs - PRESSURIZED.

RO/BOP 26. Verify S/G tubes 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. ALL 25. RNO IF any EMF trip 1 light is lit OR any S/G level is increasing in an uncontrolled manner, THEN concurrently:

Implement EP/1/A/5000/F

-0 (Critical Safety Function Status Trees). GO TO EP/1/A/5000/E

-3 (Steam Generator Tube Rupture).

NOTE TO EVALUATOR: The following actions are from EP/1/A/5000/E

-3. RO/BOP 1. Monitor Enclosure 1 (Foldout Page).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 39 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 39 of 87 NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 14 in the back of this guide.

RO/BOP 2. Identify ruptured S/G(s) as follows:

S/G level

- INCREASING IN AN UNCONTROLLED MANNER.

OR Chemistry or RP has determined ruptured S/G

. OR Any of the following EMF trip 1 lights

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

RO 3. Verify at least one intact S/G

- AVAILABLE FOR NC SYSTEM COOLDOWN. RO 4. Isolate steam flow from ruptured S/G(s) as follows:

a. Verify all ruptured S/G(s) PORV

- CLOSED. b. Verify S/G(s) 1B and 1C

- INTACT. c. Isolate blowdown and steam drain on all ruptured S/G(s) as follows:

S/G 1D: 1) Close 1SM

-74B (S/G 1D Otlt Hdr Bldwn C/V).

2) Verify the following blowdown isolation valves

- CLOSED: a) 1BB-8A (S/G 1D Bldwn Cont Isol Insd).

b) 1BB-147B (S/G 1D Bldwn Cont Isol Byp).

c) 1BB-10B (S/G 1D Bldwn Cont Isol Otsd).

Critical Task #1 RO 5. Close the following valves on all ruptured S/G(s):

MSIV MSIV bypass valve.

Critical Task #1 RO 6. Control ruptured S/G(s) level as follows:

a. Verify ruptured S/G(s) N/R level

- GREATER THAN 11% (29% ACC).

b. Isolate feed flow to all ruptured S/G(s) as follows:

S/G 1D: 1) Close 1CA

-42B (CA Pmp B Disch To S/G 1D Isol).

2) Close 1CA

-38A (CA Pmp 1 Disch To S/G 1D Isol).

c. IF AT ANY TIME ruptured S/G(s) N/R level is less than 11% (29% ACC), THEN perform Step 6.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 40 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 40 of 87 RO 7. Verify all ruptured S/G(s) pressure

- GREATER THAN 320 PSIG.

BOP 8. Verify any NC pump

- ON. BOP 9. Verify Pzr pressure

- GREATER THAN 1955 PSIG.

NOTE NC pump trip criteria based on NC subcooling does not apply after starting a controlled cooldown. After low steamline pressure main steam isolation signal is blocked, maintaining steam pressure negative rate less than 2 PSIG per second will prevent a Main Steam Isolation. OAC graphic SMRATES to monitor S/G pressure rates can be accessed via hot button in the center of the SM graphic.

RO 10. Initiate NC System cooldown as follows:

a. Determine required core exit temperature based on lowest ruptured S/G pressure from the table below:

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 41 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 41 of 87 NOTE TO EVALUATOR: The SRO and BOP will use the table in step 10 to determine target core exit temperature.

SRO/BOP b. Ensure ruptured S/G(s) isolated as follows:

1) Verify the following valves on all ruptured S/G(s) - CLOSED: MSIV MSIV bypass valves.

2) Verify S/G PORV on ruptured S/G(s)

- CLOSED OR ISOLATED.

NOTE TO EVALUATOR: Step 10.b.3 will be N/A'd.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 42 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 42 of 87 SRO/BOP 3) IF S/G 1B OR 1C ruptured, THEN verify one of the following CAPT steam supply valves

- CLOSED: "CAPT TRIP T/V CTRL" OR Manual isolation valve on affected S/G.

RO c. Verify the condenser is available as follows:

"C-9 COND AVAILABLE FOR STM DUMP" status light (1SI

-18) - LIT MSIV on intact S/G(s)

- OPEN. d. Verify steam dumps

- IN PRESSURE MODE.

Critical Task #2 RO RNO e. Place steam dumps in pressure mode as follows:

1) Place "STM DUMP CTRL" M/A station in manual.

2) Adjust "STM DUMP CTRL" M/A station output to match "% STM DUMP DEMAND" (1SMP5211).

3) WHEN output on the "STM DUMP CTRL" M/A station is equal to the "% STM DUMP DEMAND" (1SMP5211), THEN place the steam dumps in pressure mode.

Critical Task #2 RO e. WHEN "P-12 LO-LO TAVG" status light (1SI

-18) is lit, THEN place the steam dump interlock bypass switches in "BYP INTLK." f. Dump steam to condenser from intact S/G(s) at maximum rate while attempting to avoid a Main Steam Isolation.

g. Verify main steam isolation blocked status lights (1SI

-13) - LIT. BOP RNO g. Perform the following:

1) Depressurize NC System to less than 1955 PSIG using one of the following:

Pzr spray OR Pzr PORV. 2) WHEN "P-11 PZR S/I BLOCK PERMISSIVE" status light (1SI-18) lit, THEN perform the following:

a) Depress ECCS steam pressure "BLOCK" pushbuttons

. b) Verify main steam isolation blocked status lights (1SI

-13) - LIT. 3) Maintain NC pressure less than 1955 PSIG.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 43 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 43 of 87 RO h. WHEN core exit T/Cs are less than required temperature, THEN stabilize core exit T/Cs less than required temperature.

RO 11. 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 16% (29% ACC) and 50%.

BOP 12. 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, WHEN Pzr pressure decreases to less than 2315 PSIG, ensure valve closes or is isolated.

BOP 13. Reset the following:

a. ECCS. b. D/G load sequencers.

c. Phase A

d. Phase B.

e. IF AT ANY TIME a B/O occurs, THEN restart S/I equipment previously on. BOP 14. Establish VI to containment as follows:

Ensure 1VI

-77B (VI Cont Isol)

- OPEN. Verify VI pressure

- GREATER THAN 85 PSIG.

BOP 15. Determine if ND pumps should be stopped:

a. Any ND pump

- ON. b. Any runing ND pump suction

- ALIGNED TO FWST.

c. NC pressure - GREATER THAN 285 PSIG.

d. Stop all ND pump(s) with suction aligned to FWST.

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

RO/BOP 16. Verify ruptured S/G(s)

- IDENTIFIED.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 44 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 44 of 87 RO 17. Verify if NC System cooldown should be stopped:

a. Verify core exit T/Cs

- LESS THAN REQUIRED TEMPERATURE.

NOTE TO EVALUATOR: At this point the required temperature may not have been reached. The crew will hold per the RNO for step 17.a.

ALL 17.a RNO Do not continue in this procedure until core exit T/Cs are less than required temperature.

Critical Task #2 RO b. Stop NC System cooldown.

c. Stabilize core exit T/Cs

- LESS THAN REQUIRED TEMPERATURE RO/BOP 18. Verify ruptured S/G(s) pressure is under operator control as follows:

a. All ruptured S/G(s) pressure

- STABLE OR INCREASING.

b. IF AT ANY TIME ruptured S/G(s) pressure is decreasing while in this procedure, THEN perform Step 18.

RO/BOP 19. Verify NC subcooling based on core exit T/Cs

- GREATER THAN 20°F. Critical Task #3 BOP 20. Depressurize NC System using PZR Spray as follows:

a. Verify normal Pzr spray flow

- AVAILABLE.

b. Initiate NC depressurization using maximum available spray.

c. IF AT ANY TIME during this step one of the following conditions exists, THEN GO TO Step 21: Spray valves are not effective in reducing NC pressure OR Ruptured S/G(s) NR level is approaching 83% (75% ACC).

d. Do not continue until at least one of the following conditions satisfied:

Both of the following:

NC pressure

- LESS THAN RUPTURED S/G(s) PRESSURE Pzr level

- GREATER THAN 11% (30% ACC).

OR Both of the following:

NC pressure

- WITHIN 300 PSIG OF RUPTURED S/G(s) PRESSURE Pzr level

- GREATER THAN 41%

(50% ACC).

OR Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 45 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 45 of 87 Pzr level

- GREATER THAN 68% (50% ACC)

OR NC subcooling based on core exit T/Cs

- LESS THAN 0°F

e. CLOSE normal Pzr spray valves.

f. Verify 1NV

-37A (NV Supply To Pzr Aux Spray)

- CLOSED g. Observe Caution prior to Step 23 and GO TO Step 23. EVALUATOR NOTE: Critical Task #3 states that the crew must depressurize the NC system to meet S/I termination criteria before water release occurs from the ruptured S/G PORV or Safety valve. The grading criteria for not meeting this would be if the ruptured S/G N/R level reached 100% and the S/G PORV or Safety lifted at that point. Following verification of S/I termination in Step 23 below, all critical tasks are complete and the scenario may be terminated at the discretion of the lead examiner.

CAUTION S/I must be terminated when termination criteria are satisfied to prevent overfilling ruptured S/G(s).

RO/BOP 23. Verify S/I termination criteria as follows:

a. NC subcooling based on core exit T/Cs

- GREATER THAN 0°F.

b. Verify secondary heat sink as follows:

N/R level in at least one intact S/G

- GREATER THAN 11% (29% ACC) OR Total feed flow available to S/G(s)

- GREATER THAN 450 GPM. c. NC pressure

- STABLE OR INCREASING.

d. Pzr level

- GREATER THAN 11% (30% ACC).

BOP 24. Stop S/I pumps as follows:

a. Stop NI pumps.

b. Ensure only one NV pump

- ON.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 46 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 46 of 87 BOP 25. Isolate NV S/I flowpath as follows:

a. Verify the following valves

- OPEN: 1NV-252A (NV Pumps Suct From FWST) 1NV-253B (NV Pumps Suct From FWST).

b. Ensure the following valves

- OPEN: 1NV-203A (NV Pumps A&B Recirc Isol) 1NV-202B (NV Pmps A&B Recirc Isol).

c. Close the following valves:

1NI-9A (NV Pmp C/L Inj Isol) 1NI-10B (NV Pmp C/L Inj Isol).

BOP 26. Depressurize NC System as follows:

a. Verify normal Pzr spray flow

- AVAILABLE.

b. Initiate NC System depressurization.

c. WHEN NC pressure less than 1125 PSIG, THEN perform the following:

1) Continue depressurizing until one of the following conditions are met: NC pressure

- LESS THAN RUPTURED S/G(s) PRESSURE OR Pzr level

- GREATER THAN 68% (50% ACC).

2) WHEN criteria in previous step met, THEN stop depressurization.

d. GO TO Step 27 NOTE VI pressure less than 50 PSIG will prevent operation of 1NV

-294 and 1NV

-309 from Control Room.

BOP 27. Establish charging as follows:

a. Verify VI pressure

- GREATER THAN 50 PSIG.

b. THROTTLE 1NV

-294 (NV Pmps A&B Disch Flow Ctrl) for 32 GPM charging line flow.

c. CLOSE 1NV-309 (Seal Water Injection Flow).

d. Ensure one of the following valves

- OPEN: 1N V-32B (NV Supply To Loop A Isol)

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

e. Ensure 1NV

-37A (NV Supply To Pzr Aux Spray)

- CLOSED. f. OPEN the following valves:

1NV-312A (Chrg Line Cont Isol) 1NV-314B (Chrg Line Cont Isol)

g. Verify 1NV

-309 - ABLE TO BE OPERATED FROM CONTROL ROOM.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 47 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 47 of 87 h. Place 1NV

-309 in auto.

i. WHEN controlling NV flow in subsequent steps, THEN maintain the following limits while throttling charging and seal injection control valves: Maintain charging flow less than 180 GPM.

Maintain 32 GPM seal water flow.

BOP 28. Control charging flow to maintain Pzr level

- GREATER THAN 11% (30% ACC).

SRO/BOP 29. Verify S/I flow not required:

a. NC subcooling based on core exit T/Cs

- GREATER THAN 0°F.

b. Pzr level

- GREATER THAN 11% (30% ACC). BOP 30. Ensure proper operation of VCT Makeup Control System as follows:

a. Determine required shutdown boron concentration. REFER TO ROD Book, Section 5.11.

b. WHEN required shutdown boron concentration is determined, THEN perform the following:

1) Verify Unit 1 RMWST aligned for VCT makeup.

2) Adjust VCT makeup controls for boron concentration greater than or equal to required shutdown boron concentration.

3) Ensure "NC MAKEUP MODE SELECT"

- IN "AUTO".

4) Place "NC MAKEUP CONTROL" switch momentarily to "START" position.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

3 Event # 5, 6, 7, & 8 Page 48 of 87 Event

Description:

Turbine Generator Hi Vibration, 1D S/G Tube Rupture, Incomplete CF Isolation, VA Unfiltered Exhaust Fan Failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 48 of 87 BOP 31. Establish normal letdown as follows:

a. Verify VI pressure

- GREATER THAN 35 PSIG.

b. Verify Pzr level

- GREATER THAN 25% (44% ACC).

c. Verify ND pumps

- OFF. d. Ensure the following valves

- CLOSED: 1KC-56A (KC To ND Hx 1A Sup Isol) 1KC-81B (KC To NC Hx 1B Sup Isol).

e. Verify the following valves for operating KC train(s)

- OPEN: A Train: 1KC1A (Aux Bldg Non

-Ess Ret Hdr Isol) 1KC-50A (Aux Bldg Non

-Ess Hdr Isol)

B Train: 1K C-2B (Aux Bldg Non

-Ess Ret Hdr Isol) 1KC-53B (Aux Bldg Non

-Ess Hdr Isol)

f. Verify containment high range EMFs

- LESS THAN 25 R/HR:

1EMF-53A (Containment Trn A) 1EMF-53B (Containment Trn B).

g. Establish normal letdown. REFER TO EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 21 (Establishing Normal Letdown).

END OF SCENARIO.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 49 of 87 Attachment List Scenario 3 ATTACHMENT 1

- Crew Critical Task Summary ATTACHMENT 2

- Shift Turnover Information ATTACHMENT 3

- AP/1/A/5500/02 1 Enclosure 1 (Foldout Page)

ATTACHMENT 4 - 1RAD-1, B/1 (1EMF

-33 CSAE Exhaust Hi Rad) Annunciator Response ATTACHMENT 5

- AP/1/A/5500/0 10 Enclosure 1 (Case I Steam Generator Tube Leak Foldout Page)

ATTACHMENT 6 - AP/1/A/5500/009 Enclosure 1 (Foldout Page)

ATTACHMENT 7 - AP/1/A/5500/009 Step 8 Power Reduction Rate Table ATTACHMENT 8 - AP/1/A/5500/009 Step 9 Target MW vs Reactor Power Table ATTACHMENT 9 - 1AD-1, E/8 (Turb Gen Hi Vibration) Annunciator Response ATTACHMENT 10 - EP/1/A/5000/E

-0 Enclosure 1 (Foldout Page)

ATTACHMENT 1 1 - EP/1/A/5000/E

-0 Enclosure 2 (Ventilation System Verification)

ATTACHMENT 1 2 - EP/1/A/5000/G

-1 Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring)

ATTACHMENT 1 3 - EP/1/A/5000/E

-0 Enclosure 4 (NC Temperature Control) rev 42 ATTACHMENT 1 4 - EP/1/A/5000/E

-3 Enclosure 1 (Foldout Page)

ATTACHMENT 15

- EP/1/A/5000/ES

-0.1 Enclosure 1 (Foldout Page)

ATTACHMENT 16

- EP/1/A/5000/ES

-0.1 Enclosure 3 (Closure of Feedwater Isolation Valves)

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 50 of 87 ATTACHMENT 1

CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK 1 Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA

-3.1 occurs.

2 Establish/maintain an RCS temperature so that transition from E-3 does not occur because the RCS temperature is in either of the following conditions Too high to maintain the minimum required subcooling Below the RCS temperature that causes and extreme (red path) or a severe (orange path) challenge to the subcriticality and/or integrity status tree.

3 Depressurize RCS to meet SI termination criteria before water release occurs from the ruptured S/G PORV or safety (prior to S/G NR level reaching 100% and an associated S/G PORV or Safety Valve open)

. Comments:

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 51 of 87 ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 10 0% E OL 90 PPM per OAC Controlling Procedure OP/1/A/6100/00 3 (Controlling Procedure for Unit Operation), Enclosure 4.3 (Unit Operation Between 85% and 100% Power). The steps up to step 3.

16 are complete.

Other Information Needed to Assume the Shift Unit 1 is at 100% power at the EOL. Unit 2 is at 100% power.

Direction for the crew is to maintain current power.

AOs Available Seven AOs are available as listed on the status board METEOROLOGICAL CONDITIONS Upper wind direction = 315 degrees, speed =

3 mph Lower wind direction = 315 degrees, speed =

4.5 mph Forecast calls for clear skies over the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 52 of 87 ATTACHMENT 3

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 53 of 87 ATTACHMENT 3

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 54 of 87 ATTACHMENT 4

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 55 of 87 ATTACHMENT 4

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 56 of 87 ATTACHMENT 5

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 57 of 87 ATTACHMENT 6

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 58 of 87 ATTACHMENT 6

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 59 of 87 ATTACHMENT 7

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 60 of 87 ATTACHMENT 8

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 61 of 87 ATTACHMENT 9

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 62 of 87 ATTACHMENT 10 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 63 of 87 ATTACHMENT 10 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 64 of 87 ATTACHMENT 11 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 65 of 87 ATTACHMENT 11 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 66 of 87 ATTACHMENT 11 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 67 of 87 ATTACHMENT 11 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 68 of 87 ATTACHMENT 11 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 69 of 87 ATTACHMENT 11 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 70 of 87 ATTACHMENT 11 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 71 of 87 ATTACHMENT 12 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 72 of 87 ATTACHMENT 12 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 73 of 87 ATTACHMENT 12 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 74 of 87 ATTACHMENT 12 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 75 of 87 ATTACHMENT 12 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 76 of 87 ATTACHMENT 12 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 77 of 87 ATTACHMENT 12 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 78 of 87 ATTACHMENT 12 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 79 of 87 ATTACHMENT 13 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 80 of 87 ATTACHMENT 13 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 81 of 87 ATTACHMENT 13 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 82 of 87 ATTACHMENT 13 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 83 of 87 ATTACHMENT 13 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 84 of 87 ATTACHMENT 14

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 85 of 87 ATTACHMENT 14

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 86 of 87 ATTACHMENT 15

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 3 NUREG 1021 Revision 10 Page 87 of 87 ATTACHMENT 16

Catawba Nuclear Station NRC Exam May 201 6 Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 1 of 69

NRC INITIAL LICENSE EXAM SCENARIO #

4 Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 2 of 69 Facility: Catawba NRC Exam 201 6 Scenario No.:

4 Op Test No.:

2016301 Examiners:

Operators:

SRO RO BOP Initial Conditions:

Unit 1 is at 7e % power at the BOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 7e % power at the BOL.

Unit 2 is at 100% power. Direction for the crew is to shift operating KC (Component Cooling) pumps by starting the 1 A1 KC pump and securing the 1 A2 KC pump and then increase power to 1% by withdrawing control rods. 1A1 KC Pump pre-start check has been successfully completed.

Note: For the purposes of this scenario there will be no reactivity manager. The CRS will fulfill this function.

Event No. Malf. No. Event Type* Event Description 1 N-BOP N-SRO Shift operating Component Cooling pumps 2 R-RO N-SRO Withdraw control rods to increase reactor power to 1%

3 NV066 C-BOP C-SRO TS-SRO 1A NV (Centrifugal Charging) pump trips. Requires manual start of 1B NV pump 4 NV011C2 C-BOP C-SRO Letdown isolation fails on NV Pump trip 5 XMT-SG101 XMT-SG102 C-RO C-SRO D S/G W/R signal fails low. Feed reg. bypass valve opens 6 FWP015C CA004B C-RO C-SRO TS-SRO 1A CF (Main Feed) Pump trips, 1B CA (AFW Pump

) fails to start 7 NC013D M-ALL LBLOCA 8 ISE003A NV025A C - BOP Train A Phase A isolation failure. 1NV

-91B ( NC Pumps Seal Ret Cont Isol) fails to close 9 ND001A ND001 B C - BOP Both ND (Residual Heat Removal) Pumps fail to auto start on SI

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

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 3 of 69 Scenario 4 - Summary Initial Condition Unit 1 is at 7e % power at the BOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 7e % power at the BOL. Unit 2 is at 100% power. Direction for the crew is to shift operating KC (Component Cooling) pumps by starting the 1A1 KC pump and securing the 1A2 KC pump and then increase power to 1% by withdrawing control rods. 1A1 KC Pump pre

-start check has been successfully completed. Note: For the purposes of this scenario there will be no reactivity manager. The CRS will fulfill this function.

Event 1 Shift operating Component Cooling pumps per OP/1/A/6400/005 (Component Cooling System), Enclosure 4.1 5 (Shifting KC Pumps).

Event 2 Raise reactor power to 1%. Crew will use control rods since unit is below POAH.

Event 3 1A NV Pump (Charging) trips. BOP manually starts the 1B NV pump to restore charging and letdown. AP/12 (Loss of Charging or Letdown) will be entered. TS evaluation required.

Verifiable Action

- BOP will start 1B NV pump and restore letdown per AP/12. Event 4 Letdown fails to isolate on loss of both NV Pumps.

Verifiable Action

- BOP will isolate letdown.

Event 5 1D S/G W/R level signal fails LOW; associated Feed Reg. Bypass Valve opens. RO takes manual control to stabilize and restore 1D S/G level. AP/06 (Loss of SG Feedwater) Case III entry. This failure is internal to the DCS and does not indicate on the W/R level board indication.

Verifiable Action

- RO will take manual control of FRV/Bypass valve and control S/G level.

Event 6 1A Main Feedwater Pump trips, along with the failure of the 1B AFW pump to auto start. AP/06 Case I entry.

Verifiable Action

- OATC will manually start the CAPT#1 to maintain S/G levels. SRO will evaluate T.S.

Event 7 A large break LOCA occurs. Crew will enter E-0 (Reactor Trip or Safety Injection) to diagnose and address the LOCA.

Verifiable Action

- The crew members will be required to trip the NC pumps on loss of subcooling. The OATC will control feed flows to maintain S/G levels.

Event 8 A Train Phase A fail to complete; 1NV

-91B (NC Pumps Seal Ret Cont Isol) failure to close.

Verifiable Action

- BOP will manually initiate "A" train Phase A isolation and manually close 1NV

-91B.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 4 of 69 Scenario 4 - Summary Event 9 Both ND Pumps fail to auto start on Safety Injection signal.

Verifiable Action

- BOP will reset ECCS and D/G load sequencers and manually start both ND pumps.

Critical Task 1 & 2

- Control S/G level to prevent an RPS actuation.

Critical Task 3 - Close containment isolation valves such that at least one valve is closed on each critical phase

-A penetration before transition out of E

-0. Critical Task 4 - Manually start at least one low

-head ECCS pump before transition out of E

-0. Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5

-8) 7 2. Malfunctions after EOP entry (1

-2) 2 3. Abnormal events (2-4) 4 4. Major transients (1

-2) 1 5. EOPs entered/requiring substantive actions (1

-2) 1 6. EOP contingencies requiring substantive actions (0

-2) 0 7. EOP based Critical tasks (2

-3) 2 Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 5 of 69 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC #

169 START TIME:__________

NOTES:

Trigger Instructor Action Final Delay Ramp Delete In Event 3 LOA-NV066 (RACKOUT NV PMP 1A) RACK-OUT 3 N/A NV011C2 (NV VLV NV10A PERMISSIVE OPEN FAIL TRUE) ACTIVE 4 5 XMT-SG101 [XCF_5641 S/G D W/R LVL CH 1 TO DCS/ELSEWHERE (CFAA5641)]

40 3 MIN 5 5 XMT-SG102 [XCF_5642 S/G D W/R LVL CH 2 TO DCS/ELSEWHERE (CFAA5642)]

40 3 MIN 5 6 OVR-FWP012C (CFPT 1A TRIP_RESET TRIP PB)

ON 6 N/A MAL-CA004B FAILURE OF CA PUMP B TO START)

BOTH 6 7 MAL-NC013D (NC COLD LEG D LEAK) 27.5 :30 7 10 LOA-NV078 (SEAL WATER LOW FLOW REFLASH ACK AD7,C4) ACKN N/A MAL-ISE003A (AUTO PHASE A ISOL SIGNAL TRN A)

BLOCK 8 N/A VLV-NV025A (NV

-91B SEAL RTN ISOL CONT VLV FAIL AUTO ACTIONS)

ACTIVE 8 N/A MAL-ND001A (ND PUMP 1A FAILURE) AUTO 9 Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 6 of 69 N/A MAL-ND001B (ND PUMP 1B FAILURE) AUTO 9 N/A ANN-AD 11-B03 (TRANSFORMER A TROUBLE) ON N/A ANN-AD 11-E03 (TRANSFORMER B TROUBLE) ON 11 LOA-CNT002 (H2 ANALYZERS)

BOTH 10:00 Ensure 1A CFPT is in service Ensure 1A NV Pump is in service Ensure OP/1/A/6100/001 (Rev. 239) Encl

. 4.1 is available

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 7 of 69 2. SIMULATOR BRIEFING 2.1 Control Room Assignments:

Position Name CRS RO BOP 2.2 Give a copy of Attachment 2 (Shift Turnover Information) to the CRS.

3. EXERCISE PRESENTATION 3.1 Familiarization Period A. Allow examinees time to familiarize themselves with the Control Board alignments.

3.2 Scenario EVENT 1 , Shift KC Pumps BOOTH INSTRUCTOR ACTION IF AO dispatched to perform a pre

-operational pump checkout, REPORT that the pump looks good for start.

BOOTH INSTRUCTOR ACTION WHEN one minute has elapsed from the start of the 1A1 KC Pump, CALL the control room and inform them that the 1A1 KC Pump looks good for a continuous run.

3.3 Scenario EVENT 2 , Increase reactor power to 1%

3.4 Scenario EVENT S 3 & 4 , 1A NV Charging Pump trip; Letdown Isolation failure upon loss of both NV Pumps BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause 1A NV Pump trip

. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR for 1A NV Pump

, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR for 1NV

-10A, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF an Operator and/or Maintenance are dispatched to investigate the 1A NV Pump and/or breaker, REPEAT back the information.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 8 of 69 BOOTH INSTRUCTOR ACTION I F AO dispatched to check the 1B NV Pump, after 5 minutes REPORT: The 1B NV Pump looks good for continuous run.

BOOTH INSTRUCTOR ACTION IF AO is dispatched to acknowledge the Low Seal Water Flow Annunciator, THEN INSERT SIMULATOR Trigger 10 to acknowledge.

3.5 Scenario EVENT 5 , 1D S/G WR Level Failure, 1D Feed Reg Bypass Valve fails open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to cause a failure of the 1D S/G WR Level.

BOOTH INSTRUCTOR ACTION IF SWM is called to initiate an NCR on the 1D S/G WR level channel, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF Operator is dispatched to verify S/G level indication on the Aux Shutdown Panels, REPORT 1D S/G Level is reading 40%.

3.6 Scenario EVENT 6 , 1 A CFPT trips, 1B CA Pump fails to start BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 6 to trip the 1 A CFPT. BOOTH INSTRUCTOR ACTION IF SWM is called to initiate an NCR on the 1 A CFPT, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF SWM is called to initiate an NCR on the 1B CA Pump, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF an AO and/or Maintenance are dispatched to investigate the 1B CA pump and/or breaker, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF an Operator is dispatched to perform the alarm response for the 1 A CFPT, REPEAT back the information.

Catawba Nuclear Station NRC Exam May 2016 Appendix D Scenario Outline Form ES-D-1 Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 9 of 69 3.6 Scenario EVENT S 7, 8, & 9 , LBLOCA, Train "A" Phase A failure, 1NV

-91B Auto close failure, ND Pump Auto start failure BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 7 to initiate a Large Break LOCA.

BOOTH INSTRUCTOR ACTION WHEN dispatched as an AO to secure all ice condenser air handling units per EP/1/A/5000/G

-1 Enclosure 11, REPEAT the information.

BOOTH INSTRUCTOR ACTION WHEN dispatched as an AO to place the Hydrogen Analyzers in service per OP/1/A/6450/010, REPEAT the information and INSERT SIMULATOR Trigger 11. After 10 minutes has elapsed, NOTIFY control room that all ice condenser air handling units have been secured per EP/1/A/5000/G

-1 Enclosure 11 &

the hydrogen analyzers have been placed in service per OP/1/A/6450/010.

BOOTH INSTRUCTOR ACTION IF contacted as secondary chemistry to sample all S/Gs for activity, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as RP to frisk all cation columns for activity, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF dispatched as an AO to secure 1A & 1B D/Gs and place them in standby readiness per OP/1/A/6350/002, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as primary chemistry to periodically perform NC boron samples, REPEAT the information.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 1 Page 10 of 69 Event

Description:

Shift Component Cooling Water Pumps Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 10 of 69 EVENT 1 NOTE TO EVALUATOR: Crew begins by shifting the operating Component Cooling pumps per OP/1/A/6 400/00 5 (Component Cooling System), Enclosure 4.1 5 (Shifting KC Pumps). NOTE TO EVALUATOR: The crew may have a Focus Brief and then make a plant page announcing the start of the 1 A1 KC Pump. NOTE TO EVALUATOR: The following actions are from OP/1/A/6400/005 (Component Cooling System), Enclosure 4.15 (Shifting KC Pumps).

BOP 3.1 IF shifting KC Train 1 A pumps, perform the following:

3.1.1 Start the idle KC Train 1 A pump: "KC PUMP A1" OR "KC PUMP A2" NOTE: 1KC-C37A (Train A Miniflow Isol) may open during performance of the next step.

BOP 3.1.2 Adjust the following flow controllers on 1MC11 to zero gpm flow:

1KC-149 (KF Hx 1A Cool Wtr Otlt) 1KC-156 (KF Hx 1B Cool Wtr Otlt)

BOP 3.1.3 Stop the desired KC Train 1 A pump: "KC PUMP A 1" OR "KC PUMP A2" BOP 3.1.4 IF KC Train 1 A flow approaches 5700 gpm while performing the next step, ensure 1KC

-C37A (Train A Miniflow Isol) is closed.

BOP 3.1.5 Perform the following for the KF cooling loops that are in service: IF 1A KF Cooling Loop is in service, adjust 1KC

-149 (KF Hx 1A Cool Wtr Otlt) flow controller on 1MC11 to 3000 gpm or as necessary to maintain Spent Fuel Pool temperature

< 125F. IF 1B KF Cooling Loop is in service, adjust 1KC

-156 (KF Hx 1B Cool Wtr Otlt) flow controller on 1MC11 to 3000 gpm or as necessary to maintain Spent Fuel Pool temperature <

125F. END OF EVENT 1

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 2 Page 11 of 69 Event

Description:

Withdraw Control Rods to increase Reactor Power to 1%

Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 11 of 69 EVENT 2 RO Withdraw control rods to increase reactor power.

NOTE TO EVALUATOR: The following actions are from OP/1/A/6100/001 (Controlling Procedure for Unit Startup), Enclosure 4.1 (Unit Startup).

NOTE: 1. Control rod withdrawal shall NOT exceed the temporary rod withdrawal limits specified in Unit One R.O.D. Section 2.3.

2. Refer to Unit One R.O.D. Section 2.4 for the rate at which reactor power can be changed.

3.The throttling of a S/G bypass reg valve affects the other S/G bypass reg valves.

Therefore, SM/

CF 4.If NC boron concentration is greater than 1000 ppmB, T

-AVG control may be very sensitive above the POAH due to a positive MTC. Unit One R.O.D.

Section 5.10 provides MTC at the current conditions

. 5. When approaching the beginning of the Power Range NI indication (.1% on the PR), a startup rate of < 0.2 dpm is required. The < .2 dpm rate shall NOT be exceeded, except when performing PT/0/A/4150/001 J (Zero Power Physics Testing), until the turbine is placed on line. (AD-OP-ALL-0203 (Reactivity Management)). (R.M.) 6. Per SOER 07

-01 (Reactivity Management) it is recommended that Plant Operators monitor multiple indications such as Thermal Power Best Estimate, Nuclear Instrumentation, Steam Pressure , , CF Flowrate, and Turbine Load when making at power reactivity changes. (R.M.)

RO 3.1 81 Increase reactor power to 1%.

(R.M.) END OF EVENT 2 Booth Operator will insert Trigger 3 for EVENT S 3 & 4 at the discretion of the lead examiner.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 3 & 4 Page 12 of 69 Event

Description:

Centrifugal Charging Pump trip / Letdown Isolation failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 12 of 69 EVENT S 3 & 4 Indications:

1AD-11, A/1 '4KV ESS PWR TRAIN A TROUBLE' 1AD-7, C/4 'NCP SEAL WATER LO FLOW' 1AD-7, E/1 'CHARGING LINE HI/LO FLOW' BOP Recognizes 1A NV pump tripped CREW Enters AP/1/A/5500/012, Loss of Charging or Letdown NOTE TO EVALUATOR:

The crew will make a plant page announcing the entry into AP/1/A/5500/0 12 , Loss of Charging or Letdown, Case I (Loss of Charging).

NOTE TO EVALUATOR:

The following steps are from AP/1/A/5500/012, Loss of Charging or Letdown, Case I (Loss of Charging).

RO 1. Stop any power changes.

BOP 2. Ensure the following letdown isolation valves

- CLOSED: 1NV-10A (Letdn Orif 1B Otlt Cont Isol) 1NV-11A (Letdn Orif 1C Otlt Cont Isol) 1NV-13A (Letdn Orif 1A Otlt Cont Isol).

BOP 3. Ensure any malfunctioning NV pump

- SECURED. RO/BOP 4. 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.

NOTE TO EVALUATOR: Step 5 will not apply.

BOP 5. IF excess letdown in service, THEN ensure manual loader for 1NV

-124B (Excess Letdn Press Ctrl)

- ADJUSTED TO 0%.

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.

BOP 6. Verify NV pump status as follows:

At least one NV pump

- ON.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 3 & 4 Page 13 of 69 Event

Description:

Centrifugal Charging Pump trip / Letdown Isolation failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 13 of 69 BOP 6. RNO Perform the following:

a. Ensure any 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). BOP c. Ensure only one suction source as follows: VCT 1NV-188A (VCT Otlt Isol)

- OPEN 1NV-189B (VCT Otlt Isol)

- OPEN VCT level

- GREATER THAN 23%

1NV-252A (NV Pumps Suct From FWST) - CLOSED 1NV-253B (NV Pumps Suct From FWST) - CLOSED. NOTE TO EVALUATOR:

The crew will determine that step 6 RNO d. does not apply BOP e. Start the available NV pump as follows:

1) OPEN 1NV-309 (Seal Water Injection Flow) to full open. 2) 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.

NOTE TO EVALUATOR:

The crew will determine that step 6 RNO e.6) and f. do not apply BOP 6) IF suction from FWST, THEN adjust Control Rods and Turbine load as required to maintain T

-Avg within 1°F of T

-Ref. REFER TO the following:

AP/1/A/5500/009 (Rapid Downpower)

OR OP/1/A/6100/003 (Controlling Procedure For Unit Operation).

f. IF no NV pump(s) available, THEN perform the following:

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 3 & 4 Page 14 of 69 Event

Description:

Centrifugal Charging Pump trip / Letdown Isolation failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 14 of 69 BOP 7. Verify charging header aligned to NC loop as follows:

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

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

- OPEN. c. Verify one of the following valves

- OPEN: 1NV-32B (NV Supply To Loop A Isol) OR 1NV-39A (NV Supply To Loop D Isol). d. Verify the following NC pump conditions:

1 seal outlet temperatures less than or equal to 180°F Lower bearing temperatures less than or equal to 180°F.

e. Verify 1NV

-294 (NV Pmps A&B Disch Flow Ctrl)

- OPEN. BOP 7.e. RNO e. Perform the following:

1) 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 8. Verify the following:

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

- IN AUTO. BOP 8. RNO Perform the following:

a. IF any NC pump #1 seal outlet temperature OR lower bearing temperature greater than 180°F, THEN maintain cooldown rate less than or equal to 1°F per minute.

b. Slowly THROTTLE 1NV

-309 (Seal Injection Flow) to establish 32 GPM "TOTAL SEAL WTR FLOW" c. Place 1NV-309 in auto.

BOP 9. Verify Pzr level

- GREATER THAN 17%.

BOP 10. Control charging to stabilize Pzr level greater than 17%.

BOP 11. Ensure "PZR HTR GROUP 1C" - ON.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 3 & 4 Page 15 of 69 Event

Description:

Centrifugal Charging Pump trip / Letdown Isolation failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 15 of 69 BOP 12. Control VCT level as follows

a. Verify NC system makeup

- SET FOR DESIRED BORON CONCENTRATION.

b. Verify "NC MAKEUP MODE SELECT" - IN AUTO. BOP 13. Verify normal letdown - IN SERVICE.

NOTE TO EVALUATOR

Step 13 RNO a. will not be performed and step b

. will be applicable. The SRO may wait to eva luate Tech Specs until after the restoration of letdown. SRO 13. RNO Perform the following:

a. IF excess letdown was previously in service, THEN perform the following:

SRO 13. RNO b. Restore normal letdown. REFER TO Case II (Loss of Letdown).

SRO 14. Ensure compliance with appropriate Tech Specs:

3.4.13 (RCS Operational Leakage) 3.4.14 (RCS Pressure Isolation Valve (PIV) Leakage) 3.5.2 (ECCS

- Operating) 3.5.3 (ECCS

- Shutdown) 3.5.5 (Seal Injection Flow) 3.6.3 (Containment Isolation Valves)

SLC 16.9-9 (Boration Systems Charging Pump

- Shutdown) SLC 16.9-10 (Boration Systems Charging Pump - Operating).

NOTE TO EVALUATOR

SRO should determine that Tech Spec 3.5.2 (ECCS

-Operating) Condition A (Restore train to OPERABLE status 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) continues to apply and SLC 16.9-10 (Boration Systems Charging Pump

- Operating) Condition A (Restore non

-functional pump to FUNCTIONAL status 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) should be entered.

SRO 1 5. Determine required notifications:

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

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

BOP 16. Verify at least one NV pump

- ON.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 3 & 4 Page 16 of 69 Event

Description:

Centrifugal Charging Pump trip / Letdown Isolation failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 16 of 69 NOTE TO EVALUATOR

Step 17 will not apply SRO 17. IF Standby Makeup Pump in service, and no longer required, THEN secure the pump. REFER TO OP/0/B/6100/013 (Standby Shutdown Facility Operations).

SRO 1 8. Determine long term plant status. RETURN TO procedure in effect. NOTE TO EVALUATOR:

The following steps are taken from AP/1/A/5500/012, Loss of Charging or Letdown, Case II (Loss of Letdown).

RO 1. Stop any power changes

. BOP 2. Ensure the following letdown isolation valves

- CLOSED: 1NV-10A (Letdn Orif 1B Otlt Cont Isol) 1NV-11A (Letdn Orif 1C Otlt Cont Isol) 1NV-13A (Letdn Orif 1A Otlt Cont Isol).

BOP 3. Verify Pzr level

- GREATER THAN 17%.

RO 4. Control charging to stabilize Pzr level at program level while maintaining seal injection flow.

BOP 5. Ensure "PZR HTR GROUP 1C" - ON. BOP 6. Control VCT level as follows:

a. Verify NC system makeup

- SET FOR DESIRED BORON CONCENTRATION.

b. Verify "NC MAKEUP MODE SELECT" - IN AUTO. BOP 7. Determine and correct cause of loss of letdown.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 3 & 4 Page 17 of 69 Event

Description:

Centrifugal Charging Pump trip / Letdown Isolation failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 17 of 69 BOP 8. IF AT ANY TIME excess letdown required, THEN establish excess letdown. REFER TO OP/1/A/6200/001 (Chemical and Volume Control System). BOP 9. Verify proper VC/YC system operation. REFER TO Enclosure 3 (Control Room Ventilation System Verification).

NOTE TO EVALUATOR: Enclosure 3 is Attachment 3 in the back of this guide.

NOTE TO EVALUATOR

The SRO may wait to evaluate Tech Specs until after the restoration of letdown. SRO 10. 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) 3.4.13 RCS (Operational Leakage).

3.6.3 (Containment Isolation Valves).

NOTE TO EVALUATOR

The SRO should determine that no Tech Specs apply for the loss of letdown. Tech Spec 3.6.3 may be conservatively entered. This would require further evaluation to determine if an auto isolation signal would fail to close 1NV

-10A. BOP 11. 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).

SRO 11. RNO GO TO Step 16. BOP 16. Establish letdown as follows:

a. Verify ability to establish normal letdown

- RESTORED. b. Ensure 1NV

-849 (Letdn Flow Var Orif Ctrl) valve demand position - 0%. c. Verify the following valves

- OPEN: 1NV-1A (NC Letdn To Regen Hx Isol) 1NV-2A (NC Letdn To Regen Hx Isol).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 3 & 4 Page 18 of 69 Event

Description:

Centrifugal Charging Pump trip / Letdown Isolation failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 18 of 69 BOP d. OPEN the following valves:

1NV-15B (Letdn Cont Isol) 1NV-10A (Letdn Orif 1B Otlt Cont Isol).

e. Adjust 1NV

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

f. THROTTLE 1NV

-148 (Letdn Press Control) to 45% demand.

g. THROTTLE open 1NV

-849 (Letdn Flow Var Orif Ctrl) in 1% to 5% increments until one of the following conditions met: Letdown flow and letdown pressure increases OR Valve demand position is 60% open.

SRO h. Do not continue until one of the above conditions 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. NOTE TO EVALUATOR

Time compression may be used in the following step at the discretion of the lead examiner.

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

1) Adjust 1NV

-849 (Letdn Flow Var Orif Ctrl) in 1%

to 5% increments to desired letdown flow

. 2) 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. RO/BOP 3) IF AT ANY TIME additional letdown flow desired, THEN establish letdown with the 45 or 75 GPM orifice. REFER TO OP/1/A/6200/001 (Chemical and Volume Control System).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 3 & 4 Page 19 of 69 Event

Description:

Centrifugal Charging Pump trip / Letdown Isolation failure Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 19 of 69 BOP l. WHEN Pzr level restored to programmed level, THEN perform the following:

1) Ensure 1NV

-294 (NV Pmps A&B Disch Flow Ctrl)

- IN AUTO. 2) Ensure "PZR Level Master" - IN AUTO. SRO 1 7. 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. Verify excess letdown

- ISOLATED. SRO 1 9. Determine long term plant status. RETURN TO procedure in effect. NOTE TO EVALUATOR: The SRO will conduct a "Crew Update" to inform the crew of any Tech Spec conditions that have been entered.

Booth Operator will insert Trigger 5 for EVENT 5 at the discretion of the lead evaluator.

END OF EVENT S 3 & 4 Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 5 Page 20 of 69 Event

Description:

D S/G W/R signal fails low, Feed Reg Bypass valve opens Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 20 of 69 EVENT 5 Indications:

1CF-57 (S/G 1D CF BYB CTRL) begins to open 1CAP5120 (CA FLOW TO S/G 1D) indication increases to top of scale.

S/G 1D Level begins to increase.

1AD-4, E/5 'CFCV ISOL VLVS CLSD' 1AD-2, F-10 'DCS TROUBLE' RO Recognizes 1CF

-57 (S/G 1D CF BYP CTRL) opening.

RO Take manual control of 1CF

-55 (S/G 1D CF CTRL) and 1CF

-57 (S/G 1D CF BYP CTRL) and control 1D S/G level at normal level.

SRO Crew enters AP/1/A/5500/006, CASE III.

NOTE TO EVALUATOR:

The crew will make a plant page announcing the entry into AP/1/A/5500/006, Loss of S/G Feedwater.

NOTE TO EVALUATOR:

The following steps are from AP/1/A/5500/006, Loss of S/G Feedwater, Case III (CF Control Not in Auto)

CREW 1. IF AT ANY TIME S/G levels approaching:

83% N/R level (S/G HI-HI Level Turb Trip)

OR 11% N/R level (S/G LO

-LO Level Rx Trip).

THEN: a. Manually trip reactor.

b. GO TO EP/1/A/5000/E

-0 (Reactor Trip Or Safety Injection).

RO/BOP 2. Verify the following:

At least one CF pump

- IN SERVICE 1AD-3, C/6 "CF ISOL TRN A" - DARK 1AD-3, D/6 "CF ISOL TRN B" - DARK. RO/BOP 3. IF AT ANY TIME any CF main feed reg valve in manual, THEN ensure associated feed reg bypass valve in manual.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 5 Page 21 of 69 Event

Description:

D S/G W/R signal fails low, Feed Reg Bypass valve opens Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 21 of 69 RO 4. Verify CF pump speed controller for in service CF pump(s):

IN AUTO RESPONDING ADEQUATELY RO 5. Verify all S/G CF control valves:

IN AUTO RESPONDING ADEQUATELY Critical Task #1 RO/BOP 5. RNO Perform the following for the affected S/G(s):

a. Ensure affected controller(s)

- IN MANUAL.

b. IF AT ANY TIME S/G level not on program, THEN adjust CF flow to obtain a slight trend in the appropriate direction.

c. IF AT ANY TIME control valve adjustment is required, THEN attempt to maintain CF/SM D/P constant during CF control valve adjustments.

RO/BOP 6. Verify the following:

S/G level(s)

- STABLE S/G level(s)

- APPROXIMATELY AT PROGRAM Malfunction

- CORRECTE D RO/BOP 6. RNO Perform the following:

a. Continue to control CF/SM D/P and S/G CF Flow rates to stabilize level in affected S/G(s) approximately at program level.

b. WHEN all the following conditions met:

S/G level(s)

- STABLE S/G level(s)

- APPROXIMATELY AT PROGRAM Malfunction

- CORRECTED.

THEN GO TO Step 7. c. Do not continue in this procedure until all conditions met.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 5 Page 22 of 69 Event

Description:

D S/G W/R signal fails low, Feed Reg Bypass valve opens Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 22 of 69 NOTE TO EVALUATOR:

The SRO may address Tech Spec 3.3.3 [Post Accident Monitoring (PAM) Instrumentation], but it does not apply. Tech Spec 3.3.4 (Remote Shutdown System) does not apply because Aux Feedwater Flow instrumentation is available NOTE TO EVALUATOR: The SRO will conduct a "Crew Brief" or a "Focus Brief" to summarize the event. Booth Operator will insert Trigger 6 for EVENT 6 at the discretion of the lead evaluator.

END OF EVENT 5

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 6 Page 23 of 69 Event

Description:

1A MFP trips, 1B Aux Feed Pump fails to start Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 23 of 69 EVENT 6 Indications:

1AD-1, A/6 'TURB TRIP ON LOSS OF BOTH CFPTS' 1AD-1, B/1 'AMSAC TURB TRIP' 1AD-1, C/6 'EXT TRAIN A

-B/ NON TRAIN TURB TRIP' 1AD-1, C/7 'LO ETS PRESS' 1AD-1, E/7 'TURB ETS HDR PRESS LO' 1AD-5, C/1 'CFPT B TRIPPED' 1AD/5, C/4 'CFPT B COMMON TROUBLE' RO Recognize 1B CFPT Trip and subsequent loss of feedwater.

RO Recognize failure of 1 B CA Pump to start and attempts to start it. CREW ENTERS AP/1/A/5500/006, CASE I NOTE TO EVALUATOR:

The crew will make a plant page announcing the entry into AP/1/A/5500/006

, Loss of S/G Feedwater.

NOTE TO EVALUATOR:

The following steps are from AP/1/A/5500/0 06, Loss of S/G Feedwater, Case I (Loss of CF Supply To S/Gs)

RO 1. Verify reactor power

- LESS THAN 5%.

RO 2. Verify all S/G hi-hi level alert alarms (1AD-4) - DARK. RO 3. Verify 1AD

-2, F/9 "DCS ALTERNATE ACTION" - DARK. RO 4. Verify total CA flow

- GREATER THAN 450 GPM.

RO 5. Control S/G levels as follows:

a. Verify all S/G N/R levels

- GREATER THAN 11%.

NOTE TO EVALUATOR: The crew will start CAPT #1 to be able to feed 1C and 1D steam generators due to the failure of 1B CA pump to start.

RO/BOP 5.a. RNO a. Maintain total feed flow greater than 450 GPM to intact S/Gs until at least one S/G N/R level greater than 11%.

Critical Task #2 RO/BOP b. WHEN at least one S/G N/R level is greater than 11%, THEN throttle feedflow to maintain all S/G N/R levels between 11%

- 50%. SRO 6. REFER TO Case II (Loss of Normal CA Supply).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 6 Page 24 of 69 Event

Description:

1A MFP trips, 1B Aux Feed Pump fails to start Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 24 of 69 NOTE TO EVALUATOR: The crew may initiate a makeup to the UST per step 2 of Case II. No other actions from Case II are necessary.

SRO 7. Ensure compliance with appropriate Tech Specs and SLCs:

3.3.2 (ESFAS Instrumentation) 3.7.5 (Auxiliary Feedwater System)

SLC 16-7.1 (AMSAC).

SLC 16-7.14 (Trip of All Main Feedwater Pumps Turbine Trip Instrumentation).

NOTE TO EVALUATOR:

T.S 3.7.5 Auxiliary Feedwater (AFW) System Condition B (Restore AFW train to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ) should be entered. Per T.S. 3.7.5, LCO 3.0.4.(b) does not apply and Mode change is not allowed now.

NOTE TO EVALUATOR: The SRO will conduct a "Crew Update" to inform the crew of any Tech Spec conditions that have been entered.

SRO 8. Determine required notifications:

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

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

SRO 9. Determine and correct cause of loss of CF supply. RO/BOP 10. Verify at least one CF Pump

- ON. NOTE TO EVALUATOR:

It is not intended for the next step to be performed in this scenario.

BOP 10. RNO Perform a hot restart of one CF Pump.

REFER TO OP/1/A/6250/001 (Condensate and Feedwater System). SRO 11. Determine long term plant status. RETURN TO procedure in effect.

NOTE TO EVALUATOR: Due to the likelihood that the scenario will progress to the next event prior to completing all of the steps of the AP, the SRO may not do a "Crew Brief" or "Focus Brief" to summarize the event.

Booth Operator will insert Trigger 7 for EVENTS 7, 8, & 9 at the discretion of the lead examiner.

END OF EVENT 6

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 7, 8, 9 Page 25 of 69 Event

Description:

LBLOCA, Train A Phase A Isolation failure with 1NV

-91B auto close failure, ND Pumps fail to auto start on SI Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 25 of 69 EVENTS 7, 8, 9, & 10 Indications:

1AD-13, F/5 HVAC PANEL TROUBLE 1AD-13, A/7 ICE COND LOWER INLET DOORS OPEN 1FO-1, D/5 HI CONT PRESS S/I RX TRIP "SAFETY INJECTION ACTUATED" status light (1SI

-13) - LIT E/S Load Sequencer Actuated status lights (1SI

-14) - LIT NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/E

-0 (Reactor Trip or Safety Injection).

RO 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 4 in the back of this guide.

RO 2. Verify Reactor Trip:

All rod bottom lights

- LIT All reactor trip and bypass breakers

- OPEN I/R power

- DECREASING.

RO 3. Verify Turbine Trip:

All turbine stop valves

- CLOSED BOP 4. Verify 1ETA and 1ETB

- ENERGIZED.

BOP 5. Verify S/I 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".

SRO 7. Determine required notifications:

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

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

RO 8. Verify all Feedwater Isolation status lights (1SI

-5) - LIT.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 7, 8, 9 Page 26 of 69 Event

Description:

LBLOCA, Train A Phase A Isolation failure with 1NV

-91B auto close failure, ND Pumps fail to auto start on SI Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 26 of 69 BOP 9. Verify Phase A Containment Isolation status as follows:

a. Phase A "RESET" lights

- DARK. Critical Task #3 BOP 9. RNO a. Initiate Phase A Isolation

. BOP b. Monitor Light Panel Group 5 St lights on energized train(s)

- LIT. Critical Task #3 BOP 9. RNO b. Align valves as necessary to ensure each penetration isolated by at least one isolation valve.

NOTE TO EVALUATOR:

The crew must either initiate "A" Phase A isolation or manually close 1NV-91B in order to isolate the open Containment penetration.

BOP 10. Verify proper Phase B actuation as follows:

a. Verify Containment pressure

- HAS REMAINED LESS THAN 3 PSIG.

RO/BOP 10.a.RNO. Perform the following:

1) Verify Phase B Isolation actuated as follows:

a) Phase B Isolation "RESET" lights

- DARK. b) IF Phase B Isolation "RESET" lights lit, THEN initiate Phase B Isolation.

c) Verify following monitor light panel lights

- LIT: Group 1 Sp lights Group 5 Sp lights Group 5 St light L/11.

d) IF monitor light panel not in correct alignment, THEN ensure correct alignment.

2) Stop all NC pumps.

3) Maintain seal injection flow.

4) Energize H 2 igniters. 5) Dispatch operator to perform the following:

a) Secure all ice condenser air handling units. REFER TO EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 11 (Securing All Ice Condenser Units).

b) Place containment H 2 analyzers in service. REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems).

6) WHEN 9 minutes elapsed, THEN verify proper VX system operation. REFER TO Enclosure 5 (VX System Operation).

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 7, 8, 9 Page 27 of 69 Event

Description:

LBLOCA, Train A Phase A Isolation failure with 1NV

-91B auto close failure, ND Pumps fail to auto start on SI Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 27 of 69 7) GO TO Step 11. NOTE TO EVALUATOR: Enclosure 5 can be found as Attachment 5 in the back of this guide.

RO 11. Verify proper CA pump status as follows:

a. Motor driven CA pumps

- ON. b. 3 S/G N/R levels

- GREATER THAN 11%.

RO/BOP 11. RNO a. Perform the following for affected train(s):

1) Reset ECCS.

2) Reset D/G load sequencer(s).

3) Start affected pump(s).

4) IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on.

RO b. 3 S/G N/R levels

- GREATER THAN 11%.

BOP 12. Verify all of the following S/I pumps

- ON: NV pumps ND pumps NI pumps Critical Task #4 BOP 12. RNO Perform the following for affected train(s):

a. Reset ECCS.

b. Reset D/G load sequencer(s).

c. Start affected pump(s).

d. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on.

NOTE TO EVALUATOR:

The crew must start at least one ND Pump in order to satisfy Criti cal Task #4. BOP 13. Verify all KC pumps

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

- ON.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 7, 8, 9 Page 28 of 69 Event

Description:

LBLOCA, Train A Phase A Isolation failure with 1NV

-91B auto close failure, ND Pumps fail to auto start on SI Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 28 of 69 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).

NOTE TO EVALUATOR: Enclosure 2 can be found as Attachment 6 in the back of this guide.

RO 16. Verify all S/G pressures

- GREATER THAN 775 PSIG.

RO/BOP 17. Verify proper S/I flow as follows:

a. "NV S/I FLOW"

- INDICATING FLOW.

b. NC pressure

- LESS THAN 1620 PSIG.

c. NI pumps

- INDICATING FLOW. d. NC pressure

- LESS THAN 285 PSIG.

e. ND pumps

- INDICATING FLOW TO C

-LEGS. RO/BOP 18. WHEN time and manpower permit (within two hours of event), THEN monitor Spent Fuel Pool level and temperature. REFER TO EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring).

NOTE TO EVALUATOR: G

-1 Enclosure 1 can be found as Attachment 7 in the back of this guide.

RO 19. Control S/G levels as follows:

a. Verify total CA flow

- GREATER THAN 450 GPM.

b. WHEN each S/G N/R level greater than 11% (29% ACC), THEN control feed flow to maintain that S/G N/R level between 11% (29%

ACC) and 50%.

RO 20. Verify all CA isolation valves

- OPEN. BOP 21. Verify S/I equipment status based on monitor light panel

- IN PROPER ALIGNMENT.

Critical Task #3/4 BOP 21.RNO. Align equipment.

NOTE TO EVALUATOR:

This step will be a final check and last procedural opportunity to satisfy Critical Tasks 3 and 4 (Isolate penetration and start ND Pump) prior to exiting E-0.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 7, 8, 9 Page 29 of 69 Event

Description:

LBLOCA, Train A Phase A Isolation failure with 1NV

-91B auto close failure, ND Pumps fail to auto start on SI Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 29 of 69 RO NOTE Enclosure 4 (NC Temperature Control) shall remain in effect until subsequent procedures provide alternative NC temperature control guidance. RO 22. Control NC Temperature. REFER TO Enclosure 4 (NC Temperature Control). NOTE TO EVALUATOR: Enclosure 4 can be found as Attachment 8 in the back of this guide.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 7, 8, 9 Page 30 of 69 Event

Description:

LBLOCA, Train A Phase A Isolation failure with 1NV

-91B auto close failure, ND Pumps fail to auto start on SI Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 30 of 69 BOP 23. 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/BOP 24. Verify NC subcooling based on core exit T/Cs

- GREATER THAN 0°F.

BOP 24.RNO IF any NV or NI pump on, THEN perform the following:

a. Ensure all NC pumps

- OFF. b. Maintain seal injection flow.

RO 25. Verify main steamlines intact:

All S/G pressures

- STABLE OR INCREASING ALL S/Gs - PRESSURIZED.

BOP 26. Verify S/G tubes 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 27. Verify NC System intact as follows:

Containment pressure

- LESS THAN 1 PSIG. IF normal off

-site power available, THEN verify containment pressure less than 0.3 PSIG.

Containment high range EMFs

- LESS THAN 3 R/HR:

1EMF-53A (Containment Trn A) 1EMF-53B (Containment Trn B).

Containment EMF trip 1 lights

- DARK: 1EMF-38 (Containment Particulate) 1EMF-39 (L) (Containment Gas (Lo Range)).

Containment sump level

- STABLE.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 7, 8, 9 Page 31 of 69 Event

Description:

LBLOCA, Train A Phase A Isolation failure with 1NV

-91B auto close failure, ND Pumps fail to auto start on SI Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 31 of 69 BOP 27.RNO Perform the following:

a. Energize H2 igniters.

b. Dispatch operator to perform the following:

1) Secure all ice condenser air handling units. REFER TO EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 11 (Securing All Ice Condenser Units).

2) Place containment H2 analyzers in service. REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems

). c. IF both the following conditions exist, Containment pressure

- HAS REMAINED LESS THAN 3 PSIG Containment pressure

- BETWEEN 1 PSIG AND 3 PSIG THEN start one VX fan and secure normal containment ventilation. REFER TO EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 18 (VX and Containment Ventilation Control).

d. 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). NOTE TO EVALUATOR: The NC Integrity status tree will be in an Orange condition, requiring entry into EP/1/A/5000/FR

-P.1 (Response to Imminent Pressurized Thermal Shock Condition).

TRANSITION TO EP/1/A/5000/FR

-P.1 (Response to Imminent Pressurized Thermal Shock Condition).

NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/FR

-P.1 (Response to Imminent Pressurized Thermal Shock Condition).

RO/BOP 1. Verify NC pressure

- GREATER THAN 285 PSIG.

CRS 1.RNO. IF ND flow to C

-Legs is greater than 675 GPM, THEN RETURN TO procedure and step in effect.

TRANSITION TO EP/1/A/5000/E

-1 (Loss of Reactor or Secondary Coolant)

NOTE TO EVALUATOR: The SRO may elect to perform a focus brief or a crew brief to summarize the event and solicit for any crew input.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 7, 8, 9 Page 32 of 69 Event

Description:

LBLOCA, Train A Phase A Isolation failure with 1NV

-91B auto close failure, ND Pumps fail to auto start on SI Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 32 of 69 NOTE TO EVALUATOR: The following steps are taken from EP/1/A/5000/E

-1 (Loss of Reactor or Secondary Coolant).

RO/BOP 1. Monitor Enclosure 1 (Foldout Page).

NOTE TO EVALUATOR: Enclosure 1 can be found as Attachment 9 in the back of this guide.

RO/BOP 2. Verify NC subcooling based on core exit T/Cs

- GREATER THAN 0°F.

BOP 2.RNO. IF any NV or NI pump on, THEN perform the following:

a. Ensure all NC pumps

- OFF. b. Maintain seal injection flow.

RO 3. Verify main steamlines intact:

All S/G pressures

- STABLE OR INCREASING All S/Gs - PRESSURIZED.

RO/BOP 4. Control intact S/G N/R levels as follows:

a. Verify N/R level in any 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%.

BOP 5. Reset the following:

a. ECCS. b. D/G load sequencers.

c. Phase A d. Phase B. e. IF AT ANY TIME B/O occurs, THEN restart S/I equipment previously on. BOP 6. Establish VI to Containment as follows:

Ensure 1VI

-77B (VI Cont Isol)

- OPEN. Verify VI pressure

- GREATER THAN 85 PSIG.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 7, 8, 9 Page 33 of 69 Event

Description:

LBLOCA, Train A Phase A Isolation failure with 1NV

-91B auto close failure, ND Pumps fail to auto start on SI Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 33 of 69 RO/BOP 7. Verify secondary radiation

- NORMAL: a. Ensure the following signals

- RESET: 1) CA System valve control

2) 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 (Steamline 1B) 1EMF-28 (Steamline 1C) 1EMF-29 (Steamline 1D)

e. Verify all S/Gs

- INTACT: All S/G pressures

- STABLE OR INCREASING All S/Gs - PRESSURIZED.

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

BOP 8. Verify Pzr PORV and Isolation Valves:

a. Power to all Pzr PORV isolation valves

- AVAILABLE.

b. All Pzr PORVs

- CLOSED. c. Any Pzr PORV isolation valve

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

RO/BOP 9. Verify S/I termination criteria:

a. NC subcooling based on core exit T/Cs

- GREATER THAN 0°F.

b. Secondary heat sink:

Any intact S/G N/R level

- GREATER THAN 11% (29% ACC)

OR Total feed flow to intact S/Gs

- GREATER THAN 450 GPM.

c. NC pressure

- STABLE OR INCREASING.

d. Pzr level

- GREATER THAN 11%

CRS 9.a.RNO.

GO TO Step 9.f.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 7, 8, 9 Page 34 of 69 Event

Description:

LBLOCA, Train A Phase A Isolation failure with 1NV

-91B auto close failure, ND Pumps fail to auto start on SI Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 34 of 69 BOP 9.f. Monitor S/I termination criteria. REFER TO Enclosure 2 (S/I Termination Criteria).

g. IF AT ANY TIME S/I termination criteria met while in this procedure, THEN RETURN TO Step 9. NOTE TO EVALUATOR: Enclosure 2 can be found as Attachment 1 0 in the back of this guide.

RO/BOP 10. Determine if ND pumps should be stopped:

a. NC pressure

- GREATER THAN 285 PSIG.

CRS 10.a.RNO.

GO TO Step 12. BOP 12. Verify D/Gs should be stopped:

a. Any D/G

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

"D/G 1A BKR TO ETA"

- OPEN 1ETA - ENERGIZED.

c. Dispatch operator to stop 1A D/G and place in standby readiness. REFER TO OP/1/A/6350/002 (Diesel Generator Operation).

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

"D/G 1B BKR TO ETB"

- OPEN 1ETB - ENERGIZED.

e. Dispatch operator to stop 1B D/G and place in standby readiness. REFER TO OP/1/A/6350/002 (Diesel Generator Operation).

BOP 13. Obtain containment H 2 concentration as follows:

a. Ensure operator dispatched to secure all ice condenser air handling units. REFER TO EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 11 (Securing All Ice Condenser Units).

b. Verify containment H 2 analyzers

- IN SERVICE.

c. Verify containment H 2 concentration

- LESS THAN 6%.

d. Verify H2 igniters

- ON. e. Verify containment H 2 concentration

- LESS THAN 0.5%.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 7, 8, 9 Page 35 of 69 Event

Description:

LBLOCA, Train A Phase A Isolation failure with 1NV

-91B auto close failure, ND Pumps fail to auto start on SI Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 35 of 69 BOP 14. Initiate evaluation of plant status as follows:

a. Verify Cold Leg Recirc capability from at least one train:

A Train 1A ND pump - AVAILABLE 1NI-185A (ND Pump 1A Cont Sump Suct)

- POWER AVAILABLE.

OR B Train 1B ND pump

- AVAILABLE 1NI-184B (ND Pump 1B Cont Sump Suct)

- POWER AVAILABLE.

BOP b. Determine if leak is in auxiliary building:

1) Verify auxiliary building radiation:

All area monitor EMF trip 1 lights

- DARK. EMF-41 (Aux Bldg Ventilation) trip 1 light

- DARK NOTE The following step is checking for a significant NC leak into the ND System. 2) Verify NC to ND pressure boundary intact as follows:

ND Pressure

- NORMAL ND Temperature

- NORMAL ND Flow - NORMAL c. Determine if NC is leaking into KC system:

1EMF-46A (COMPONENT COOLING TRAIN A) trip 1 light

- DARK. 1EMF-46B (COMPONENT COOLING TRAIN B) trip 1 light

- DARK. d. Ensure KC NC NI NM St signals

- RESET e. WHEN TSC is staffed, THEN notify TSC to perform Enclosure 4 (TSC Actions). RO/BOP 15. Determine if NC System cooldown and depressurization is required:

a. NC pressure

- GREATER THAN 285 PSIG CRS 15.RNOa. IF ND flow to C

-Legs greater than 675 GPM, THEN GO TO Step 16. BOP 16. Verify Containment Pressure

- GREATER THAN 3 PSIG.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.:

301 Scenario #

4 Event # 7, 8, 9 Page 36 of 69 Event

Description:

LBLOCA, Train A Phase A Isolation failure with 1NV

-91B auto close failure, ND Pumps fail to auto start on SI Time Position Applicant's Actions or Behavior Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 36 of 69 BOP 16. RNO Perform the following:

a. IF starting of any VX fan has previously been attempted, THEN GO TO Step 17. b. IF AT ANY TIME both of the following conditions exist, THEN start one VX fan and secure normal containment ventilation. REFER TO EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 18 (VX and Containment Ventilation Control):

Containment pressure

- HAS REMAINED LESS THAN 3 PSIG Containment pressure

- BETWEEN 1 PSIG AND 3 PSIG. BOP 17. Determine if transfer to Cold Leg Recirc is required:

a. FWST level

- LESS THAN 20% (1AD

-9, D/8 "FWST 2/4 LO LEVEL".

b. S/I systems

- ALIGNED FOR COLD LEG RECIRC.

RNO a. RETURN TO Step 14. b. GO TO EP/1/A/5000/ES

-1.3 (Transfer to Cold Leg Recirculation).

NOTE TO EVALUATOR: The crew will remain in a procedural loop between steps 14 and 17 until FWST level decreases to 20%. Once FWST level is < 20%, a transition to EP/1/A/5000/ES

-1.3 will be made. The scenario may be terminated at any time at the lead examiners discretion.

END OF SCENARIO 4 Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 37 of 69 Attachment List Scenario 4 ATTACHMENT 1

- Crew Critical Task Summary ATTACHMENT 2

- Shift Turnover Information ATTACHMENT 3

- AP/1/A/5500/012 Enclosure 3 (Control Room Ventilation System Verification

) ATTACHMENT 4 - EP/1/A/5000/E

-0 Enclosure 1 (Foldout Page)

ATTACHMENT 5

- EP/1/A/5000/E

-0 Enclosure 5 (VX System Operation)

ATTACHMENT 6 - EP/1/A/5000/E

-0 Enclosure 2 (Ventilation System Verification)

ATTACHMENT 7 - EP/1/A/5000/G

-1 Enclosure 1 (Unit 1 Spent Fuel Pool Monitoring)

ATTACHMENT 8 - EP/1/A/5000/E

-0 Enclosure 4 (NC Temperature Control) rev 42 ATTACHMENT 9

- EP/1/A/5000/E

-1 Enclosure 1 (Foldout Page)

ATTACHMENT 10

- EP/1/A/5000/E

-1 Enclosure 2 (S/I Termination)

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 38 of 69 ATTACHMENT 1

CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK 1 Control S/G level to avoid an RPS actuation.

2 Control S/G level to avoid an RPS actuation.

3 Close containment isolation valves such that at least one valve is closed on each critical phase

-A penetration before transition out of E

-0. 4 Manually start at least one low

-head ECCS pump before transition out of E

-0. Comments:

Catawba Nuclear Station NRC Exam May 2016 Appendix D Catawba NRC Exam May 2016 Scenario 4 NUREG 1021 Revision 10 Page 39 of 69 ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 7e % B OL 1 950 PPM per OAC Controlling Procedure OP/1/A/6100/00 1 (Controlling Procedure for Unit Operation), Enclosure 4.

1 (Unit Startup). The steps up to step 3.181 are complete.

Other Information Needed to Assume the Shift Unit 1 is at 7e % power at the BOL. Unit 2 is at 100% power. Direction for the crew is to shift operating KC (Component Cooling) pumps by starting the 1A1 KC pump and securing the 1A2 KC pump and then increase power to 1% by withdrawing control rods. 1A1 KC Pump pre

-start check has been successfully completed. Note: For the purposes of this scenario there will be no reactivity manager. The CRS will fulfill this function.

AOs Available Seven AOs are available as listed on the status board METEOROLOGICAL CONDITIONS Upper wind direction = 267 degrees, speed =

3 mph Lower wind direction = 373 degrees, speed =

4.0 mph Forecast calls for clear skies over the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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JPM A

Catawba Nuclear Station JPM A May 2016 NRC Exam PAGE 2 OF 13 EVALUATION SHEET Task: Respond to Inadvertent Dilution While Shutdown Alternate Path:

Yes Facility JPM #:

New Safety Function: 1 Title: Chemical and Volume Control System K/A 00 4 A 2.0 6 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent boration/dilution Rating(s):

4.2 / 4.3 CFR: 41.5 / 43/5 / 45/3 / 45/5 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

AP/1/A/5500/013 (Boron Dilution), Case II (Boron Dilution While Shutdown)

Task Standard:

Responding to an inadvertent dilution

, while in Mode 3, applicant trips the reactor, starts at least one Boric Acid Transfer Pump, and aligns emergency boration flow.

Validation Time:

1 2 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start:

___________ NAME______________________

Docket #_____________

Time Finish: ______

_____ Performance Rating:

SAT ____ UNSAT ____

Performance Time ______ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM A May 2016 NRC Exam PAGE 3 OF 13 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC

160 3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given

. Instructor Action Final Delay Ramp Delete In Event MAL-NV044F (NV238A BORIC ACID BLEND FLOW CNTRL FAIL TO POSITION) 0 ANN-AD11-B03 (TRANSFORMER A TROUBLE) ACTIVE ANN-AD11-E03 (TRANSFORMER B TROUBLE) ACTIVE MAL-NC001 (VARIABLE NC BORON CONCENTRATION) 1850 20 MIN Ensure BDMS is reset.

Do not go to "RUN" until the applicant is ready to begin.

REV. 0 PAGE 4 0F 13 Catawba Nuclear Station JPM A May 2016 NRC Exam PAGE 4 OF 13 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

Unit 1 is in Mode 3 at Normal Operating Temperature and Pressure. Shutdown banks have been withdrawn in preparation for unit startup. AP/1/A/5500/013 (Boron Dilution) has been entered following an unanticipated neutron flux level increase.

The Unit 1 RMWST and BAT are aligned for VCT makeup.

All boration flowpaths are available.

INITIATING CUES:

The CRS has directed you to perform AP/13, Case II (Boron Dilution While Shutdown)

. EXAMINER NOTE: After reading Initiating Cue, provide the applicant with a copy of AP/1/A/5500/013, Case II Catawba Nuclear Station JPM A May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 13 START TIME: _______

STEP 1: 1 Verify boron dilution event

- IN PROGRESS.

STANDARD: Applicant determines boron dilution event in progress from initiating cue and continues

. COMMENTS: ___ SAT ___ UNSAT STEP 2 2. Verify Reactor Trip:

All rod bottom lights

- LIT All reactor trip and bypass breakers

- OPEN. STANDARD: Applicant determines that the reactor is not tripped and transitions to the RNO. COMMENTS: ___ SAT ___UNSAT Catawba Nuclear Station JPM A May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 13 STEP 3 2 RNO Perform the following:

a. Trip reactor.

b. Perform Steps 5 through 10 to stop dilution and initiate boration.

c. IF above P-11, THEN GO TO EP/1/A/5000/E

-0 (Reactor Trip Or Safety Injection).

d. IF below P-11, THEN GO TO AP/1/A/5500/005 (Reactor Trip Or Inadvertent S/I Below P

-11). STANDARD: Applicant trips the reactor and proceeds to step 5.

Examiner Cue:

If applicant begins performance of E

-0 Immediate Actions, "Another operat or will perform required actions of E

-0." This step is critical to ensure negative reactivity is added.

COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT STEP 4 5. Evacuate personnel from reactor building using the following:

Containment evacuation alarm Plant page.

STANDARD: Applicant initiates Containment evacuation alarm and makes plant page. COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station JPM A May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 13 STEP 5 6 Stop any dilutions in progress as follows:

a. Place "NC MAKEUP CONTROL" switch to "STOP".

STANDARD: Applicant will rotate the "NC MAKEUP CONTROL " switch to STOP. COMMENTS: ___ SAT ___ UNSAT STEP 6 6.b Verify Unit 1 RMWST aligned for VCT makeup.

STANDARD: Applicant will determine RMWST is aligned per initiating cue.

COMMENTS: ___ SAT

___ UNSAT STEP 7 6.c Place both reactor makeup water pumps to "OFF".

STANDARD: Applicant will rotate the 1A and 1B Makeup Water Pump control switches to OFF.

COMMENTS: ___ SAT

___ UNSAT STEP 8 6.d Isolate the NV demineralizers as follows:

1) Place 1NV-153A (Letdn Hx Otlt 3

-Way Valve) in the "VCT" position.

STANDARD: Applicant rotates 1NV

-153A to the VCT position

. COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station JPM A May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 13 STEP 9 6.d.2) Ensure the following valves

- CLOSED: 1NV-353 & 364 (Mixed Bed Demin 1A Isol) 1NV-368 & 379 (Mixed Bed Demin 1B Isol).

STANDARD: Applicant depresses Red Close button and verifies valves closed.

COMMENTS: ___ SAT ___ UNSAT NOTE: Unit shutdown alignments may have established alternate boration flowpaths.

STEP 10 7 Ensure proper BDMS operation as follows:

a. Verify at least one of the following alarm(s)

- LIT: 1AD-2, E/2 "TRAIN A SHUTDOWN MARGIN ALARM" OR 1AD-2, F/2 "TRAIN B SHUTDOWN MARGIN ALARM". STANDARD: Applicant determines Shutdown Margin Monitor is not in alarm and transitions to RNO

. COMMENTS: ___ SAT ___ UNSAT Catawba Nuclear Station JPM A May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 13 STEP 1 1 7.RNO a. Perform the following:

1) IF AT ANY TIME any of the following alarms lit, THEN perform Step 7.

1AD-2, E/2 "TRAIN A SHUTDOWN MARGIN ALARM" OR 1AD-2, F/2 "TRAIN B SHUTDOWN MARGIN ALARM". 2) GO TO Step 8. STANDARD: Applicant will acknowledges step and proceeds to step 8

. COMMENTS: ___ SAT ___ UNSAT STEP 1 2 8 Initiate boration of the NC System as follows: a. Verify NV pump 1A or 1B is available as a boration flowpath. b. Verify normal charging is available as a boration flowpath. c. Align boration flowpath as follows:

1) Verify BAT is available as a borated water source. 2) Ensure the following valves

- OPEN: 1NV-188A (VCT Otlt Isol) 1NV-189B (VCT Otlt Isol).

1NV-312A (Chrg Line Cont Isol) 1NV-314B (Chrg Line Cont Isol).

STANDARD: Applicant determines that an NV pump, normal charging flowpath, boration flowpath, and BAT are available. Applicant also verifies listed valves are open.

COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station JPM A May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 10 0F 13 STEP 1 3 8.c 3) OPEN the following valves:

1NV-238A (B/A Xfer Pmp To Blender Ctrl) 1NV-186A (B/A Blender Otlt To VCT Otlt).

STANDARD: Applicant attempts to open 1NV

-238A by rotating switch to OPEN position. Valve will not open. Applicant proceeds and opens 1NV

-186A by rotating switch to OPEN position.

COMMENTS: ___ SAT ___ UNSAT STEP 1 4 8.c 4) Ensure one NV pump

- ON. 5) Ensure at least one boric acid transfer pump

- ON. STANDARD: Applicant verifies NV Pump in service and starts one OR both boric acid transfer pumps by rotating 1A and/or 1B Boric Acid Transfer switch to the ON position.

Starting of one boric acid transfer pump is critical to ensure negative reactivity is added.

COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT Catawba Nuclear Station JPM A May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 11 0F 13 STEP 1 5 8.c 6) Verify boration flow indicated on:

DCS Graphic 6003 (NVMU

- BORIC ACID BLENDER) OR 1NVCR5450 (Boric Acid Flow)

OR 1NV-238A (B/A Xfer Pmp To Blender Ctrl) M/A station. STANDARD: Applicant uses one or all of the above listed methods to determine no boration flow exists. Transitions to RNO COMMENTS: ___ SAT ___ UNSAT STEP 16 8.c RNO 6) Perform the following:

a) Ensure 1NV

-236B (Boric Acid To NV Pumps Suct) - OPEN. STANDARD: Applicant opens 1NV

-236B by depressing the red O PEN button. This step is critical to align a flowpath for boric acid injection.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM A May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 12 0F 13 STEP 1 7 8.c RNO 6) b) Verify emergency boration flow indicated on:

1NVP5440 (Emer Borate Flow)

OR DCS Graphic 6003 (NVMU

- BORIC ACID BLENDER).

STANDARD: Applicant uses one or both of the above listed methods to determine that boration flow has been established.

Examiner note:

Once the applicant has confirmed establishment of boric acid flow into the RCS, this JPM may be terminated

. Examiner Cue:

"Another operat or will continue the steps of AP/13. JPM complete."

COMMENTS: ___ SAT

___ UNSAT STOP TIME________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is in Mode 3 at Normal Operating Temperature and Pressure. Shutdown banks have been withdrawn in preparation for unit startup. AP/1/A/5500/013 (Boron Dilution) has been entered following an unanticipated neutron flux level increase.

The Unit 1 RMWST and BAT are aligned for VCT makeup.

All boration flowpaths are available.

INITIATING CUES:

The CRS has directed you to perform AP/13, Case II (Boron Dilution While Shutdown) .

Catawba Nuclear Station JPM B May 2016 NRC Exam PAGE 1 OF 15

JPM B

Catawba Nuclear Station JPM B May 2016 NRC Exam PAGE 2 OF 15 EVALUATION SHEET Task: Transfer Emergency Core Cooling System to Hot Leg Recirculation Alternate Path:

Yes Facility JPM #:

New Safety Function:

2 Title: Transfer Emergency Core Cooling System to Hot Leg Recirculation K/A SYS0 13 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; LOCA.

Rating(s):

4.6 / 4.8 CFR: 41.5/43.5/45.3/45.13 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

EP/1/A/5000/ES

-1.4 Task Standard:

Hot leg recirculation flow indicated from "A" Train NI and cold leg NI flowpaths isolated.

Validation Time:

10 Min Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ___________ NAME______________________

Docket #_____________

Time Finish: ______

_____ Performance Rating:

SAT ____ UNSAT ____

Performance Time ______ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM B May 2016 NRC Exam PAGE 3 OF 15 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC # 161

3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

Instructor Action Final Delay Ramp Delete In Event MAL-NC013A (NC COLD LEG A LEAK) 27.5 VLV-NI023F (NI121A NI PMP 1A HOT LEG INJ HDR FAIL TO POSITION) 0 VLV-NI023F (NI121A NI PMP 1A HOT LEG INJ HDR FAIL TO POSITION)

02 :0 1 1 MAL-NI001B (NI PUMP B FAILURE BOTH)

BOTH OVR-NI042C (1NI

-183B ND HDR AB HOT LEG INJECTION ISOL OPEN PB)

OFF Ensure Event 1 = x11i389o (1NI

-152B Open PB)

REV. 0 PAGE 4 0F 15 Catawba Nuclear Station JPM B May 2016 NRC Exam PAGE 4 OF 15 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A LOCA on the NC System has been in progress for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The Emergency Core Cooling System (ECCS) is in the Cold Leg Recirculation lineup. INITIATING CUES:

Transfer the ECCS System to Hot Leg Recirculation per EP/1/A/5000/ES

-1.4 (Transfer to Hot Leg Recirculation)

EXAMINER NOTE

After reading Initiating Cue, provide the applicant with a copy of EP/1/A/500 0/ES-1.4 Catawba Nuclear Station JPM B May 2016 NRC Exam PAGE 5 0F 15 START TIME: _______

STEP/STANDARD SAT/UNSAT STEP 1: 1 Verify NI pump(s)

- ALIGNED FOR COLD LEG RECIRC.

STANDARD: Applicant determines NI Pumps aligned for Cold Leg Recirc.

COMMENTS: ___ SAT

___ UNSAT STEP 2: 2 Align NI pumps for Hot Leg Recirc as follows:

a. Stop NI Pump 1A.

STANDARD: Applicant secures NI Pump 1A by depressing the Green "OFF" pushbutton and verifying the Green "OFF" light is lit

.

This is step is critical to prevent deadheading the pump in the following steps. COMMENTS:

CRITICAL STEP ___ SAT ___UNSAT Catawba Nuclear Station JPM B May 2016 NRC Exam PAGE 6 0F 15 STEP/STANDARD SAT/UNSAT STEP 3: 2.b. Close 1NI-118A (NI Pump 1A C

-Leg Inj Isol)

STANDARD: Applicant depresses the GREEN "CLOSE" pushbutton and verifies the GREEN "CLSD" light is LIT.

This is step is critical to isolate the Cold Leg Injection flowpath.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 4: 2.c. Verify 1NI

-118A (NI Pump 1A C

-Leg Inj Isol)

- CLOSED STANDARD: Applicant verifies 1NI-118A closed

. COMMENTS:

___ SAT

___ UNSAT STEP 5: 2.d. Place "PWR DISCON FOR 1NI

-121A" switch in "ENABLE" STANDARD: Applicant places "PWR DISCON FOR 1NI

-121A" switch to the "ENABLE" position COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM B May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 15 STEP 6: 2.e. Open 1NI-121A (NI Pump 1A To H-Legs B & C)

STANDARD: Applicant depresses the RED "OPEN" pushbutton and notes that valve position has not changed.

COMMENTS: ___ SAT

___ UNSAT STEP 7: 2.f. Verify 1NI

-121A (NI Pump 1A To H

-Legs B & C) - OPEN STANDARD: Applicant notes that 1NI

-121A is NOT OPEN and transitions to RNO COMMENTS:

___ SAT

___ UNSAT STEP 8: 2.f RNO f.1) IF 1NI-121A is in intermediate position, THEN wait up to 10 seconds for valve to complete valve movement.

STANDARD: Applicant determines that 1NI

-121A is NOT in the intermediate position and marks this step N/A.

COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station JPM B May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 15 STEP 9: 2.f RNO f.2) IF 1NI-121A is open, THEN GO TO Step 2.g. STANDARD: Applicant determines that 1NI

-121A is NOT OPEN and marks this step N/A. COMMENTS: ___ SAT

___ UNSAT STEP 10: 2.f RNO f.3) IF 1NI-121A is not open, THEN perform the following:

a) Dispatch operator to open 1NI

-121A (NI Pump 1A To H-Legs B&C) (AB

-572, FF-GG, 52, Rm 318).

STANDARD: Applicant determines that this step applies and dispatches operator to open 1NI-121A. Examiner Cue: "AO has been dispatched to open 1NI

-121A" Booth Operator: If applicant does not dispatch operator to open 1NI

- 121A, remove trigger #1.

This is step is critical to align the Hot Leg flowpath.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM B May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 15 STEP 11: 2.f RNO f.3)b WHEN 1NI-121A is open, THEN start NI Pump 1A STANDARD: Applicant determines that this is an continuous action step and proceeds. COMMENTS: ___ SAT

___ UNSAT STEP 12: 2.f RNO f.3)c GO TO Step 2.h. STANDARD: Applicant transitions to step 2.h.

COMMENTS: ___ SAT

___ UNSAT STEP 13: 2.h Stop NI Pump 1B.

STANDARD: Applicant secures NI Pump 1B by depressing the Green "OFF" pushbutton and verifying the Green "OFF" light is lit.

This is step is critical to prevent deadheading the pump in the following steps. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM B May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 10 0F 15 STEP 14: 2.i CLOSE 1NI-150B (NI Pump 1B C

-Leg Inj Isol).

STANDARD: Applicant depresses the GREEN "CLOSE" pushbutton and verifies the GREEN "CLSD" light is LIT.

COMMENTS: ___ SAT

___ UNSAT STEP 15: 2.j Verify 1NI-150B (NI Pump 1B C

-Leg Inj Isol)

- CLOSED. STANDARD: Applicant verifies 1NI

-150B closed.

COMMENTS:

___ SAT

___ UNSAT STEP 16: 2.k Place "PWR DISCON FOR 1NI

-162A" switch in "ENABLE".

STANDARD: Applicant places "PWR DISCON FOR 1NI

-162A" switch to the "ENABLE" position COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM B May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 11 0F 15 STEP 17: 2.l CLOSE 1NI-162A (NI To C

-Legs Inj Hdr Isol).

STANDARD: Applicant depresses the GREEN "CLOSE" pushbutton and verifies the GREEN "CLSD" light is LIT.

COMMENTS: ___ SAT

___ UNSAT STEP 1 8: 2.m Verify 1NI

-162A (NI To C

-Legs Inj Hdr Isol)

- CLOSED. STANDARD: Applicant verifies 1NI

-162A CLOSED.

COMMENTS:

___ SAT

___ UNSAT STEP 19: 2.n Place "PWR DISCON FOR 1NI

-152B" switch in "ENABLE".

STANDARD: Applicant places "PWR DISCON FOR 1NI

-152B" switch to the "ENABLE" position COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM B May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 12 0F 15 STEP 20: 2.o OPEN 1NI-152B (NI Pump 1B To H

-Legs A&D).

STANDARD: Applicant depresses the RED "OPEN" pushbutton and verifies the RED "OPEN" light is LIT.

Examiner Note:

1NI-121A will automatically open when the open pushbutton is depressed for 1NI

-152B. Examiner Cue: AO reports "1NI

-121A is OPEN". STANDARD: Applicant returns to step 2.f RNO f.3.b COMMENTS:

___ SAT

___ UNSAT STEP 21: 2.f RNO f.3.b WHEN 1NI-121A is open, THEN start NI Pump 1A.

STANDARD: Applicant starts NI Pump 1A by depressing the Red "ON" pushbutton and verifying the Red "ON" light is lit, and then returns to step 2.p.

This is step is critical to provide Hot Leg Injection flow.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM B May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 13 0F 15 STEP 2 2: 2.p Verify 1NI

-152B (NI Pump 1B To H

-Legs A&D)

- OPEN. STANDARD: Applicant verifies 1NI

-152B OPEN.

COMMENTS: ___ SAT

___ UNSAT STEP 2 3: 2.q WHEN 1NI-152B is open, THEN start NI Pump 1B.

STANDARD: Applicant attempts to start NI Pump 1B by depressing the Red "ON" pushbutton. Pump will not start.

COMMENTS:

___ SAT

___ UNSAT STEP 24: 3 Verify flow from at least one train of NI.

STANDARD: Applicant determines that flow has been established from A train NI, by observing flow on 1NIP5450, and continues.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM B May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 14 0F 15 STEP 25: 4 RETURN TO Procedure and step in effect.

STANDARD: Applicant determines that Hot Leg Recirc has been aligned.

Examiner Note:

The only available success path to align HLR is by performing RNO step 2.f.3.b (start NI Pump 1A) following notification that 1NI

-121A is open. The 1B NI Pump will fail to start and the ND Header Hot Leg Injection Valve (1NI

-183B) will fail to open, if RHR system alignment is attempted.

COMMENTS:

END OF TASK

___ SAT

___ UNSAT STOP TIME________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A LOCA on the NC System has been in progress for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . The Emergency Core Cooling System (ECCS) is in the Cold Leg Recirculation lineup.

INITIATING CUES:

Transfer the ECCS System to Hot Leg Recirculation per EP/1/A/5000/ES

-1.4 (Transfer to Hot Leg Recirculation)

Catawba Nuclear Station JPM C May 2016 NRC Exam PAGE 1 OF 10

JPM C

Catawba Nuclear Station JPM C May 2016 NRC Exam PAGE 2 OF 10 EVALUATION SHEET Task: Initiate RCS Bleed and Feed following loss of Secondary Heat Sink

. Alternate Path:

No Facility JPM

New Safety Function:

4P Title: Establish NC System Bleed and Feed K/A EPE E05 EA1.1 Ability to operate and/or monitor the following as they apply to the (Loss of Secondary Heat Sink); Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Rating(s):

4.1 / 4.0 CFR: 41.7 / 45.5 / 45.6 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

EP/1/A/5000/FR

-H.1 Task Standard:

Applicant aligns RCS for bleed and feed in accordance with EP/1/A/5000/FR

-H.1 (Response to Loss of Secondary Heat Sink) by actuating at least one train of Safety Injection and opening two PZR PORVs.

Validation Time:

1 0 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ___________ NAME______________________

Docket #_____________

Time Finish: ______

_____ Performance Rating:

SAT ____ UNSAT ____

Performance Time ______ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM C May 2016 NRC Exam PAGE 3 OF 10 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC

1 63 3. Enter the password. 4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given

. Instructor Action Final Delay Ramp Delete In Event MAL-CA003A, CAPT SA2 FAILS TO START Active MAL-CA003B, CAPT SA5 FAILS TO START Active MAL-CA004A, FAILURE OF CA PUMP A TO START Both MAL-CA004B, FAILURE OF CA PUMP B TO START Both REV. 0 PAGE 4 0F 10 Catawba Nuclear Station JPM C May 2016 NRC Exam PAGE 4 OF 10 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A Reactor Trip has occurred due to a loss of both main feedwater pumps. The CA System will not function. Attempts to restart the CFPT's have been unsuccessful. EP/1/A/5000/FR

-H.1 (Response to Loss of Secondary Heat Sink) has been entered following a validated Heat Sink "RED PATH" encountered while performing EP/1/A/5000/ES

-0.1 (Reactor Trip Response). Bleed and feed initiation criteria has been met.

INITIATING CUES:

The Control Room Supervisor has directed you to initiate NC System bleed and feed beginning at step 19 of EP/1/A/5000/FR

-H.1 (Response to Loss of Secondary Heat Sink). Inform the Control Room Supervisor when the bleed and feed path has been initiated and verified.

EXAMINER NOTE: After reading Initiating Cue, provide the applicant with a copy of EP/1/A/5000/FR

-H.1, Pages 28-3 6 Catawba Nuclear Station JPM C May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 10 START TIME: _______

STEP 1: 19 Perform Steps 20 through 24 quickly to establish NC heat removal by NC bleed and feed.

STANDARD: Acknowledges step and proceeds.

COMMENTS: ___ SAT

___ UNSAT STEP 2 20 Ensure all NC Pumps

- OFF STANDARD: Depresses GREEN "OFF" pushbuttons and verifies OFF indications for 1A, 1B, 1C, and 1D NC Pumps (1MC

-10).

Examiner Note: This step is critical to ensure that Feed and Bleed will be effective. NC pump operation would tend to keep NC pressure higher which would reduce S/I flow and increase inventory lost through the Pzr PORVs. COMMENTS:

CRITICAL STEP ___ SAT ___UNSAT Catawba Nuclear Station JPM C May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 10 STEP 3 21 Initiate S/I.

STANDARD: Depresses Train A and B "SAFETY INJECTION INITIATE" pushbuttons. Verifies "SAFETY INJECTION ACTUATED" status light lit (1SI-13) or "ECCS TRN A (B)" YELLOW "RESET" lights dark (1MC

-11). Examiner Note: This step is critical to ensure that high pressure S/I flow is available to the NC system and to ensure that containment is isolated to ensure that reactor coolant released from Pzr PORV operation in the following steps is confined to containment.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 4 2 2.a Verify NC System feed path as follows: Verify the following pumps

- ON At least one NV pump At least one NI pump STANDARD: Verifies RED "ON" lights lit for "NV PMP 1A", "NV PMP 1B" (1MC

-10), and "NI PMP 1A", "NI PMP 1B" (1MC

-11) COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM C May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 10 STEP 5 22.b Verify "NV S/I FLOW

- INDICATING FLOW.

STANDARD: Verifies flow on 1NVP6080, (1MC

-3). COMMENTS: ___ SAT

___ UNSAT STEP 6 23. Establish NC System bleed path as follows:

a. Ensure all Pzr PORV isolation valves

- OPEN STANDARD: Verifies the red 'OPEN' lights lit and green "CLSD" lights dark for 1NC

-31B, 1NC-33A and 1NC

-35B. COMMENTS:

___ SAT

___ UNSAT STEP 7 23.b Select "OPEN" on the following PZR PORVs:

1NC34A (PZR PORV) 1NC32B (PZR PORV)

STANDARD: Rotates the switches for 1NC-32B and 1NC

-34A to the 'OPEN' position.

Examiner Note: This step is critical to provide the bleed path needed to meet the task standard for this JPM.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM C May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 10 STEP 8 23.c Align N 2 to the Pzr PORVs by opening the following valves:

1NI-438A (Emer N2 FROM CLA A To 1NC

-34A) 1NI-439B (Emer N2 FROM CLA B To 1NC

-32B) STANDARD: Depresses the 'OPEN' pushbuttons for 1NI

-438A and 1NI

-439B. Verifies the red 'OPEN' lights lit and the green "CLSD" lights dark.

COMMENTS: ___ SAT

___ UNSAT STEP 9 23.d Verify power to all Pzr PORV isolation valves

- AVAILABLE.

STANDARD: Verifies red "OPEN' lights lit for 1NC

-31B, 1NC-33A, and 1NC

-35B on 1MC-10. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM C May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 10 STEP 10 24 Verify the following valves

- OPEN: 1NC-31B (PZR PORV Isol) 1NC-32B (PZR PORV) 1NC-33A (PZR PORV Isol) 1NC-34A (PZR PORV)

STANDARD: Verifies red 'OPEN' lights lit and green "CLSD" lights dark for 1NC

-31B, 1NC-32B, 1NC-33A, & 1NC-34A. Examiner Cue:

When told that feed and bleed has been established and verified, "This JPM is complete."

COMMENTS: ___ SAT

___ UNSAT STOP TIME________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A Reactor Trip has occurred due to a loss of both main feedwater pumps. The CA System will not function. Attempts to restart the CFPT's have been unsuccessful. EP/1/A/5000/FR

-H.1 (Response to Loss of Secondary Heat Sink) has been entered following a validated Heat Sink "RED PATH" encountered while performing EP/1/A/5000/ES

-0.1 (Reactor Trip Response). Bleed and feed initiation criteria has been met.

INITIATING CUES:

The Control Room Supervisor has directed you to initiate NC System bleed and feed beginning at step 19 of EP/1/A/5000/FR

-H.1 (Response to Loss of Secondary Heat Sink). Inform the Control Room Supervisor when the bleed and feed path has been initiated and verified.

Catawba Nuclear Station JPM D May 2016 NRC Exam PAGE 1 OF 11

JPM D

Catawba Nuclear Station JPM D May 2016 NRC Exam PAGE 2 OF 11 EVALUATION SHEET Task: Isolate Cold Leg Accumulators Following a Shutdown LOCA Alternate Path:

Yes Facility JPM #:

N/A Safety Function:

3 Title: Emergency Core Cooling System (ECCS)

K/A 006 A1.13 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: Accumulator pressure (level, boron concentration)

Rating(s):

3.5 / 3.7 CFR: 41.5 / 45.5 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

AP/1/A/5500/027 (Shutdown LOCA)

, Enclosure 14 (Isolating Cold Leg Accumulators)

Task Standard:

AP/1/A/5500/027 (Shutdown LOCA) Enclosure 14 (Isolating Cold Leg Accumulators) is performed and 1A & 1D Cold Leg Accumulators are isolated and 1B & 1C Cold Leg Accumulators are vented to containment.

Validation Time:

1 5 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM D May 2016 NRC Exam PAGE 3 OF 11 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC # 162

3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

Instructor Action Final Delay Ramp Delete In Event ANN-AD11-B03 (TRANSFORMER A TROUBLE) ON ANN-AD11-E03 (TRANSFORMER B TROUBLE) ON MAL-NC013B (NC COLD LEG B LEAK) 0.5 VLV-NI008F (NI65B ACCUM ISOL VLV FAIL TO POSITION) 1 VLV-NI011F (NI76A ACCUM ISOL VLV FAIL TO POSITION) 1 PAGE 4 0F 11 Catawba Nuclear Station JPM D May 201 6 NRC Exam PAGE 4 OF 11 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is in Mode 4.

Unit 1 shutdown was in progress for a refueling outage, when pressurizer pressure and level began to decrease uncontrollably.

The CRS has entered AP/1/A/5500/027 (Shutdown LOCA) to address the reactor coolant system leak.

Power to all CLA discharge isolation valves has been restored per EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 9 (Power Alignment for CLA Valves).

INITIATING CUES:

The CRS has directed you to isolate the Unit 1 Cold Leg Accumulators by performing AP/1/A/5500/027 (Shutdown LOCA) Enclosure 14 (Isolating Cold Leg Accumulators).

EXAMINER NOTE

After reading the cue, provide the applicant with a copy of AP/1/A/5500/027 Enclosure 14.

Catawba Nuclear Station JPM D May 201 6 NRC Exam PAGE 5 0F 11 START TIME: _______

STEP/STANDARD SAT/UNSAT STEP 1: 1. Dispatch operator to restore power to all CLA discharge isolation valves. REFER TO EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 9 (Power Alignment for CLA Valves)

STANDARD: Per initiating cue, the applicant should realize that this step is complete. Also valve indication for each of the CLA discharge isolation valves is available, due to power already being aligned by the AO.

COMMENTS: ___ SAT

___ UNSA T STEP 2: 2. Ensure S/I

- RESET a. ECCS b. D/G load sequencers

c. IF AT ANY TIME a B/O occurs, THEN restart S/I equipment previously on.

STANDARD: Applicant verifies that the yellow ECCS and D/G load sequencer RESET lights are lit. Applicant acknowledges the If at any time statement.

COMMENTS:

___ SAT ___UNSAT Catawba Nuclear Station JPM D May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 11 STEP 3: 3. WHEN power is aligned, THEN perform the following:

a. CLOSE the following valves:

1NI-54A (C-Leg Accum A Disch Isol) 1NI-65B (C-Leg Accum B Disch Isol) 1NI-76A (C-Leg Accum C Disch Isol) 1NI-88B (C-Leg Accum D Disch Isol)

STANDARD: Applicant depresses the green CLOSE pushbutton for the valves listed, and verifies the green CLSD light lit and red OPEN light dark for valves 1NI

-54A & 1NI-88B. Applicant also verifies the red OPEN light lit and green CLSD light dark for valves 1NI

-65B & 1NI-76A and transitions to the RNO.

The critical part of this step is to close isolation valves 1NI

-54A & 1NI-88B. The other 2 Cold Leg Accumulators will be vented to containment in subsequent steps in the RNO.

EXAMINER NOTE: This begins the alternate path of this JPM.

EXAMINER NOTE: The applicant should determine from the initiating cue that power has been aligned. If necessary, inform "Power has been aligned"

. COMMENTS:

CRITICAL STE P ___ SAT

___ UNSAT Catawba Nuclear Station JPM D May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 11 STEP 4: 3.RNOa. Perform the following:

1) Ensure containment isolation signals

- RESET: Phase A Phase B STANDARD: Applicant verifies that the yellow RESET lights are lit for both trains Phase A and Phase B isolations.

COMMENTS: ___ SAT

___ UNSAT STEP 5: 3.RNOa. 2) Ensure 1VI

-77B (VI Cont Isol)

- OPEN STANDARD: Applicant determines that the red OPEN light lit and green CLSD light dark for 1VI

-77B. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM D May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 11 STEP 6: 3.RNOa. 3) IF VI pressure is less than 85 PSIG, THEN dispatch operator to ensure proper VI compressor operation.

STANDARD: Applicant determines that VI pressure is ~ 90 PSIG. This step is N/A.

COMMENTS: ___ SAT

___ UNSAT STEP 7: 3.RNOa.4) Vent any CLA which cannot be isolated as follows:

a) OPEN 1NI

-47A (C-Leg Accum N2 Sup Cont Isol) STANDARD: Applicant depresses the red OPEN pushbutton for 1NI

-47A and verifies the red OPEN light lit and green CLSD light dark.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM D May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 11 STEP 8: 3.RNOa.4) b) Place breaker 1CB

-1 (behind 1MC

-6)(Key #11) to - ON STANDARD: Applicant lifts breaker 1CB

-1 fully up to the ON position.

This step is critical to place power on Cold Leg Accumulator Nitrogen supply isolation valves for 1B and 1C CLAs which will be opened in the next step to allow venting the accumulators to containment.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 9: 3.RNOa.4) c) OPEN valve for CLA(s) to be vented:

1NI-50 (C-Leg Accum A N2 Supply Isol) 1NI-61 (C-Leg Accum B N2 Supply Isol) 1NI-72 (C-Leg Accum C N2 Supply Isol) 1NI-84 (C-Leg Accum D N2 Supply Isol)

STANDARD: Applicant depresses the red OPEN pushbutton and verifies the red OPEN light lit and green CLSD light dark for 1NI

-61 and 1NI

-72.

This step is critical due to not being able to isolate these CLAs. If these CLAs are not vented to reduce the N2 overpressure, it could cause a hard bubble to form in the reactor coolant system as reactor coolant pressure continues to decrease.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM D May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 10 0F 11 STEP 10: 3.RNOa.4) d) CLOSE 1NI-47A. STANDARD: Applicant depresses the green CLOSE pushbutton and verifies the green CLSD light lit and red OPEN light dark for 1NI

-47A. This step is critical to allow venting the 1B and 1C CLAs.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 11: 3.RNOa.4) e) OPEN 1NI-83 (C-Leg Accums N2 Vent Ctrl) to depressurize affected CLA(s).

STANDARD: Applicant rotates potentiometer for 1NI

-83 clockwise to begin venting the 1B and 1C CLAs.

This step is critical to vent the 1B and 1C CLAs.

NOTE TO EVALUATOR: The time to fully vent the 1B & 1C CLAs would be approximately 30 minutes. The critical steps for this JPM have been met at this point and the JPM may be terminated at your discretion.

EVALUATOR CUE:

"Another operator will continue to vent the 1B and 1C Cold Leg Accumulators. This JPM i s complete."

COMMENTS:

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is in Mode 4.

Unit 1 shutdown was in progress for a refueling outage, when pressurizer pressure and level began to decrease uncontrollably.

The CRS has entered AP/1/A/5500/027 (Shutdown LOCA) to address the reactor coolant system leak.

Power to all CLA discharge isolation valves has been restored per EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 9 (Power Alignment for CLA Valves).

INITIATING CUES:

The CRS has directed you to isolate the Unit 1 Cold Leg Accumulators by performing AP/1/A/5500/027 (Shutdown LOCA) Enclosure 14 (Isolating Cold Leg Accumulators).

Catawba Nuclear Station JPM E May 201 6 NRC Exam PAGE 1 OF 9

JPM E

Catawba Nuclear Station JPM E May 201 6 NRC Exam PAGE 2 OF 9 EVALUATION SHEET Task: Operate Containment Cooling System Fans Alternate Path:

No Facility JPM #:

New Safety Function:

5 Title: Containment Cooling System K/A 022 A4.01 Ability to manually operate and/or monitor in the control room: CCS fans.

Rating(s):

3.6 / 3.6 CFR: 41.7 / 4 5.5 / 45.8 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

AP/1/A/5500/028 (Secondary Steam Leak)

Task Standard:

Place all Containment Cooling Fans in operation and all operating in "Max" cooling. Validation Time:

5 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM E May 201 6 NRC Exam PAGE 3 OF 9 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC

164 3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given

. Instructor Action Final Delay Ramp Delete In Event MAL-SM007B (STM LINE BRK INSIDE CONTAINMENT LOOP B) 20000 Ensure LCVU's 1A, 1B, and 1D are in service.

Ensure UCVU 1B is in service.

DO NOT PLACE SIMULATOR IN "RUN" UNTIL APPLICANT IS READY TO BEGIN.

PAGE 4 0F 9 Catawba Nuclear Station JPM E May 201 6 NRC Exam PAGE 4 OF 9 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

AP/1/A/5 500/028 (Secondary Steam Leak) has been entered due to indications of a steam leak.

INITIATING CUES:

The CRS has directed you to perform AP/1/A/5500/028, step 9.

No personnel are in Containment.

EXAMINER NOTE

After reading the cue, provide the applicant with a copy of AP/1/A/5500/028, step 9

.

Catawba Nuclear Station JPM E May 201 6 NRC Exam PAGE 5 0F 9 START TIME: _______

STEP/STANDARD SAT/UNSAT STEP 1: 9. Attempt to identify and isolate the leak as follows:

a. Verify the following conditions NORMAL:

Containment temperature Containment pressure Containment humidity Containment floor & equipment sump level.

STANDARD: Applicant determines conditions are not normal and transitions to RNO.

COMMENTS:

___ SAT

___ UNSA T STEP 2: 9.aRNO a. Perform the following:

1) Evacuate containment.

STANDARD: Applicant initiates the Containment Evacuation Alarm and may request the WCC to review the Containment Entry Logbook

. Examiner Cue:

"If asked, WCC reports no personnel are listed in Containment Entry Logbook."

COMMENTS:

___ SAT ___UNSAT Catawba Nuclear Station JPM E May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 9 STEP 3: 9.aRNOa. 2) Perform the following:

a) Start all lower containment ventilation units in low speed. STANDARD: Applicant rotates switch VV LCVU 1C from "OFF" to "LOW"

This step is critical to ensure all Lower Containment Ventilation Units are providing cooling and available to be used in Max cooling mode in order to minimize Containment pressure.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 4: 9.aRNOa.2) b) Start all upper containment ventilation units.

STANDARD: Applicant rotates the following switches from "OFF" to "NORM":

VV UCVU 1A VV UCVU 1C VV UCVU 1D This step is critical to ensure all Upper Containment Ventilation Units are providing cooling and available to be used in Max cooling mode in order to minimize Containment pressure.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM E May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 9 STEP 5: 9.aRNOa.2) c) Place all upper and lower containment ventilation units in "MAX" cooling.

STANDARD: Applicant verifies the following switches are in the "MAX" position.

VV LCVU 1A MAX VV LCVU 1B MAX VV LCVU 1C MAX VV LCVU 1D MAX Applicant rotates the following switches from "NORM" to "MAX":

VV UCVU 1A VV UCVU 1B VV UCVU 1C VV UCVU 1D This step is critical to ensure all Containment Ventilation Units are providing maximum cooling in order to minimize Containment pressure. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 6: 9.aRNOa.3)

IF AT ANY TIME containment pressure reaches 1.2 PSIG, THEN perform the following:

STANDARD: Applicant acknowledges the continuous action statement and continues to step 4.

COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station JPM E May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 9 STEP 7: 9.aRNOa.4)

GO TO Step 10. STANDARD: Examiner Cue: "Another operator will complete this procedure. JPM Complete" COMMENTS: END OF TASK

___ SAT

___ UNSAT EXAMINER NOTE

The applicant may choose to also place Lower Containment Ventilation Units in Hi Speed per the ARP associated with 1AD

-19 B/12 (LOWER CONT PRESS 0.5 PSIG INITIATE HI SPEED). This is not included in the standard of this JPM.

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

AP/1/A/5500/028 (Secondary Steam Leak) has been entered due to indications of a steam leak.

INITIATING CUES:

The CRS has directed you to perform AP/1/A/5500/028, step 9.

No personnel are in Containment.

Catawba Nuclear Station JPM F May 2016 NRC Exam PAGE 1 OF 9

JPM F

Catawba Nuclear Station JPM F May 2016 NRC Exam PAGE 2 OF 9 EVALUATION SHEET Task: Shift Operating RC (Condenser Circulating Water) Pumps by placing 1D RC Pump in service and securing 1B RC Pump. Alternate Path:

Yes Facility JPM #:

New Safety Function:

8 Title: Circulating Water System K/A 075 G2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Rating(s):

4.3 / 4.4 CFR: 41.10 / 43.5 / 45.2 / 45.6 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

OP/1/B/6400/001A (Condenser Circulating Water).

Task Standard:

The applicant will start 1D RC Pump. The associated discharge valve will not automatically open requiring the examinee to open manually. The applicant will then close the 1B RC Pump discharge valve and manually secure 1B RC Pump following failure to trip on discharge valve closure.

Validation Time:

10 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ___________ NAME______________________

Docket #_____________

Time Finish:

___________ Performance Rating:

SAT ____ UNSAT ____

Performance Time ______ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM F May 2016 NRC Exam PAGE 3 OF 9 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC

167 3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given

. Instructor Action Final Delay Ramp Delete In Event VLV-RC012F (RC24 CCW PMP 1D DISCHARGE FAIL TO POSITION) 0 VLV-RC012F (RC24 CCW PMP 1D DISCHARGE FAIL TO POSITION) 1 SEC 1 VLV-RC010F (RC22 CCW PMP 1B DISCHARGE VLV FAIL TO POSITION)

.02 :55 2 OVR-RL035B (1RC

-22 RC PMP 1B DISCH ISOL OPEN LT)

OFF :55 2 Ensure Event 1 = x13i140o (1RC

-24 Open PB)

Ensure Event 2 = x13i138c (1RC

-22 Close PB)

Ensure OAC Point C1Q1118 is removed from processing.

REV. 0 PAGE 4 0F 9 Catawba Nuclear Station JPM F May 2016 NRC Exam PAGE 4 OF 9 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is operating at 100% power.

INITIATING CUES:

You have been directed to shift operating RC Pumps, per Enclosure 4.7 of OP/1/B/6400/001A (Condenser Circulating Water), as follows:

o Start 1D RC Pump o Secure 1B RC Pump Initial conditions are complete.

1D RC Pump pre

-start inspection has been satisfactorily completed. The pump is NOT rotating in the reverse direction.

An AO is standing by for post

-start checks. Another AO is monitoring for cooling tower overflow. EXAMINER NOTE: After reading Initiating Cue, provide the applicant with a copy of OP/1/B/6400/001A, Encl. 4.7 with initial condition complete.

Catawba Nuclear Station JPM F May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 9 START TIME: _______

NOTE: If it is desired to swap which RC pumps are in service while reducing or increasing the number of RC pumps and cooling towers in service, this enclosure is used first. Enclosure 4.3 (Removing Cooling T owers from Service) is then used to remove RC pump(s) and cooling tower(s) from service OR Enclosure 4.2 (Placing Cooling Towers in Service) is then used to place RC pump(s) and cooling tower(s) in service.

STEP 1: 3.1 Start the desired RC Pump as follows:

3.1.1 Verify the RC pump to be started is NOT rotating in the reverse direction.

STANDARD: Per initiating cue the pump is NOT rotating in the reverse direction. COMMENTS:

___ SAT

___ UNSAT STEP 2 3.1.2 Ensure "RCP DISCH VALVE MODE SEL" in the "NORM" position.

STANDARD: Operator verifies switch in NORM position.

COMMENTS:

___ SAT ___UNSAT Catawba Nuclear Station JPM F May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 9 NOTE: To start a third RC pump three cooling towers are required to be in service to meet the interlock

. This is accomplished by temporarily opening the third tower inlet isolation, it will be reclosed by Step 3.3.

STEP 3 3.1.3 IF starting a third RC pump, perform the following:

STANDARD: Operator recognizes that this step does not apply and N/A's this step

. COMMENTS: ___ SAT

___ UNSAT NOTE: Wait approximately two minutes after starting an RC pump before stopping the desired RC pump to allow flow to stabilize.

Following each configuration change, sufficient time needs to be allowed for RC Cooling Tower Levels to stabilize prior to aligning additional components.

STEP 4 3.1.4 Start the desired RC pump STANDARD: Operator depresses the Red RC PUMP 1D "ON" Pushbutton and verifies the Red "ON" light is lit.

This step is critical to ensure proper condenser cooling water flow in the following steps.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

Catawba Nuclear Station JPM F May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 9 STEP 5 3.1.5 Ensure that its discharge valve fully opens. (Valve begins to open six seconds after pump start). STANDARD: Operator observes that the discharge valve has not automatically opened and manually opens 1RC

-24 by depressing the Red "OPEN" pushbutton and verifying the Red "OPEN" light lit.

This step is critical to ensure proper condenser cooling water flow.

Examiner Cue:

Following successful completion of this step, report "Operator reports 1D RC Pump is good for continued operation" COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT STEP 6 3.2 Stop the desired RC pump as follows: 3.2.1 Dispatch an operator to periodically monitor for cooling tower overflow until cooling tower levels have stabilized, which may take an hour.

STANDARD: Operator determines, from initiating cue, that an operator has been dispatched

. Examiner Cue:

"Dispatched operator reports cooling tower levels have stabilized" If asked, "2 minutes have elapsed since pump start." COMMENTS:

___ SAT

___ UNSAT

Catawba Nuclear Station JPM F May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 9 STEP 7 3.2.2 Close the discharge valve of the pump to be stopped:

1RC-21 (RC Pump 1A Disch Isol) 1RC-22 (RC Pump 1B Disch Isol) 1RC-23 (RC Pump 1C Disch Isol) 1RC-24 (RC Pump 1D Disch Isol)

STANDARD: Operator depresses the Green "CLOSE" pushbutton on 1RC

-22 and verifies that the Green "CLSD" light is lit

. This step is critical to ensure correct system alignment and prevent/minimize cooling tower overflow.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT STEP 8 3.2.3 Ensure that the pump stops when the valve closes.

STANDARD: Operator recognizes that the pump continues to operate following discharge valve closure and manually secures 1B RC Pump by depressing the Green "OFF" pushbutton and verifying the Green "OFF" light is lit. This step is critical to prevent pump damage.

Examiner Cue:

"Another operator will complete this enclosure. JPM complete.

" COMMENTS:

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT STOP TIME________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is operating at 100% power.

INITIATING CUES:

You have been directed to shift operating RC Pumps, per Enclosure 4.7 of OP/1/B/6400/001A (Condenser Circulating Water), as follows:

o Start 1D RC Pump o Secure 1B RC Pump Initial conditions are complete.

1D RC Pump pre

-start inspection has been satisfactorily completed. The pump is NOT rotating in the reverse direction.

An AO is standing by for post

-start checks. Another AO is monitoring for cooling tower overflow.

Catawba Nuclear Station JPM G May 2016 NRC Exam PAGE 1 OF 14

JPM G

Catawba Nuclear Station JPM G May 2016 NRC Exam PAGE 2 OF 14 EVALUATION SHEET Task: Initiate a VQ (Containment Air Release And Addition System) release per OP/1/A/6450/017 Enclosure 4.2 steps 3.5 through 3.12.

Alternate Path:

None Facility JPM #:

N/A Safety Function:

7 Title: Process Radiation Monitoring System K/A 073A4.02 Ability to manually operate and/or monitor in the control room: Radiation monitoring system control panel Rating(s):

3.7 / 3.7 CFR: 41.7/45.5 to 45.8 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

OP/1/A/6450/017 Encl. 4.2, OP/0/

A/6500/080 Encl. 4.3.

Task Standard:

Applicant aligns VQ valves for release and initiates a Containment Air release. Validation Time:

1 2 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: _______

___ NAME_ __ Docket #__ Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM G May 2016 NRC Exam PAGE 3 OF 14 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC # 166

3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

Instructor Action Final Delay Ramp Delete In Event Ensure 1VQ

-10 is at 350 and on setpoint

REV. 0 PAGE 4 0F 14 Catawba Nuclear Station JPM G May 2016 NRC Exam PAGE 4 OF 14 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is operating at 100% power.

INITIATING CUES:

The Unit 2 BOP has performed OP/1/A/6450/017 (Containment Air Release and Addition System) .2 (Air Release Mode) steps 2.1 through step 3.4. You have been tasked to initiate a Containment Air Release by performing steps 3.5 through 3.12 using 'A' Train equipment.

All Peer Checks have been waived.

EXAMINER NOTE: After reading Initiating Cue, provide the applicant with a copy of OP/1/A/6450/017 Enclosure 4.2. and OP/0/A/6500/080, Enclosure 4.3

.

Catawba Nuclear Station JPM G May 2016 NRC Exam PAGE 5 0F 14 START TIME: _______

STEP/STANDARD SAT/UNSAT NOTE: The person performing Step 3.5 or 3.6 shall NOT be the same individual who originally performed the associated actions in Steps 3.2.1.3, 3.2.1.4 or 3.4.3.

STEP 1: 3.5 IF 1EMF-39L is functional, perform the following:

3.5.1 Independently verify trip setpoints are set to the values as specified in "SETPOINT DATA" section on the Gaseous Waste Release Permit Report using OP/0/A/6500/080 (EMF RP86A Output Modules).

STANDARD: Applicant will verify trip setpoints on 1EMF

-39L per procedure.

Examiner NOTE:

After applicant reads the step, provide a copy of OP/0/A/6500/080 Enclosure 4.3 COMMENTS:

___ SAT

___ UNSAT

Catawba Nuclear Station JPM G May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 14 OP/0/A/6500/080 Enclosure 4.3 NOTE: 1. If any trip setpoint is >1000 cpm, the entered setpoint should be rounded down to the nearest 100 to ensure the setpoint remains conservative.

2. Necessary setpoint adjustments are made per Enclosure 4.2 (EMF RP86A Trip Setpoint Adjustment).

STEP 2 3.1 Press the function key [FUN] to bring up the "SELECT FUNCTION" screen.

STANDARD: Applicant will press the [FUN] key on 1EMF

-39L. COMMENTS:

___ SAT ___ UNSAT STEP 3 3.2 Press [4] to bring up the data screen.

STANDARD: Applicant will press the [4] key on 1EMF

-39L COMMENTS:

___ SAT ___ UNSAT Catawba Nuclear Station JPM G May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 14 STEP 4 3.3 Verify the Trip 1 and Trip 2 setpoints are the same as the desired setpoints.

STANDARD: Applicant will verify the trip setpoints are set correctly.

COMMENTS: ___ SAT

___ UNSAT STEP 5 3.4 Press the clear key [CLR] twice to return to the normal display screen.

STANDARD: Applicant will depress the [CLR] key twice on 1EMF

-39L COMMENTS:

___ SAT

___ UNSAT STEP 6 3.5 Verify that the correct EMF setpoints are documented in the Control Room EMF Setpoint Logbook.

STANDARD: Applicant will verify the correct EMF setpoints are documented in the Control Room EMF Setpoint Logbook.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM G May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 14 STEP 7 3.6. If required for IV purposes, ensure that the IV block is signed on Control Room EMF Setpoint Log.

STANDARD: Applicant will sign the IV block.

COMMENTS: ___ SAT

___ UNSAT OP/1/A/6450/017 Enclosure 4.2 STEP 8 3.5.2 Sign off the "Independent Verification (IV)" blank on the "VQ release monitored by EMF 39L" sheet of the Gaseous Waste Release (GWR)

Record STANDARD: Applicant will sign off the "EMF39L Operable and Source Checked" IV blank on the "VQ release monitored by EMF 39L" sheet of the Gaseous Waste Release (GWR) Record COMMENTS:

___ SAT

___ UNSAT STEP 9 3.6 Independently verify "1VQ

-10 VQ FANS DISCH TO UNIT VENT" controller is set to the "Recommended Release Rate (cfm)" on the Gaseous Waste Release Permit Report. STANDARD: Applicant will verify "1VQ-10 controller is set to

< the "Recommended Release Rate (cfm) on the Gaseous Waste Release Permit Report.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM G May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 14 STEP 10 3.7 Reset Totalizer on "1VQ

-10 VQ FANS DISCH TO UNIT VENT" controller (1MC5) by performing the following:

3.7.1 Depress the "D" pushbutton until "VQ0100.T" appears in the display window.

STANDARD: Applicant will depress the "D" pushbutton on 1VQ

-10 controller.

COMMENTS: ___ SAT

___ UNSAT STEP 1 1 3.7.2 Depress the "Reset Total" pushbutton and verify a "0" appears in the display window.

STANDARD: Applicant will depress the "Reset Total" pushbutton on the 1VQ

-10 controller.

This step is critical to ensure that amount of the release is properly quantified.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM G May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 10 0F 14 STEP 1 2 3.8 IF AT ANY TIME during the release using 1EMF

-39 the following conditions are met, immediately terminate the release.

STANDARD: Applicant will determine this is a continuous action step and leave it unsigned. COMMENTS:

___ SAT

___ UNSAT STEP 1 3 3.9 IF AT ANY TIME during the release using 1EMF

-36 the following conditions are met, immediately terminate the release.

STANDARD: Applicant will determine that this step does not apply.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM G May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 11 0F 14 STEP 1 4 3.10 Open the following valves (1MC5):

Record time first valve is opened ________

1VQ-2A (VQ Fan Suct From Cont Isol) 1VQ-3B (VQ Fan Suct From Cont Isol)

STANDARD: Applicant will open valves and document the time the first valve is opened. This step is critical to align a flow path for the air release.

Examiner NOTE: Recording of the time is not part of the critical step.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 1 5 3.11 IF 1EMF-39L AND 1EMF-36L are non

-functional, independently verify the following valves are open:

STANDARD: Applicant will determine that this step does not apply.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM G May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 12 0F 14 CAUTION: Operation of VQ Fans below 120 cfm will produce surge noise and vibration. Operation below 50 cfm results in heat buildup and may lead to fan failure.

STEP 1 6 3.12 Place one VQ train in service as follows (1MC5):

3.12.1 IF placing A train in service, perform the following:

3.12.1.1 Place "VQ Filt Htr A" in the "AUTO" position. STANDARD: Applicant will place "VQ Filt Htr A" in the "AUTO" position.

COMMENTS:

___ SAT

___ UNSAT STEP 1 7 3.12.1.2 Start "Cont Air Rel Fan 1A".

STANDARD: Applicant will start "Cont Air Release Fan 1A" by depressing the Red "ON" pushbutton and verifying the Red "ON" light is lit.

This step is critical to initiate the air release.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM G May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 13 0F 14 STEP 1 8 3.12.2 IF placing B train in service, perform the following

STANDARD: Applicant will determine that this step does not apply.

COMMENTS: END OF TASK

___ SAT

___ UNSAT STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS: Unit 1 is operating at 100% power.

INITIATING CUES:

The Unit 2 BOP has performed OP/1/A/6450/017 Enclosure 4.2 steps 2.1 through step 3.4. You have been tasked to initiate a Containment Air Release by performing steps 3.5 through 3.12 using 'A' Train equipment.

All Peer Checks have been waived.

Catawba Nuclear Station JPM H May 201 6 NRC Exam PAGE 1 OF 10

JPM H

Catawba Nuclear Station JPM H May 201 6 NRC Exam PAGE 2 OF 10 EVALUATION SHEET Task: Manually align Essential power to 1FTB from 1ETB per AP/1/A/5500/007 Case 1 Step 10 Alternate Path:

No Facility JPM #:

EP-0 18 Safety Function:

6 Title: A.C. Electrical Distribution K/A 062A4.01 Ability to manually operate and/or monitor in the control room: All breakers (including available switchyard)

Rating(s):

3.3 / 3.1 CFR: 41.7 / 45.5 to 45.8 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

AP/1/A/5500/007 Case I Task Standard:

Applicant manually energizes 1FTB from 1ETB.

Validation Time:

10 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: _______

___ NAME__________________________

Docket #_____________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM H May 201 6 NRC Exam PAGE 3 OF 10 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC

16 5 3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given

. Instructor Action Final Delay Ramp Delete In Event LOA-EP095 (600VLXH BKR LXH

-4B) OPEN 1 LOA-EP095 (600V LC LXH BKR LXH

-4B) CLOSE 2 MAL-EQB001B (D/G 1B LOAD SEQUENCER FAILURE) R1 REV. 0 PAGE 4 0F 10 Catawba Nuclear Station JPM H May 201 6 NRC Exam PAGE 4 OF 10 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is operating at 100% power.

INITIATING CUES:

Unit 1 has experienced a B Train blackout due to a failure of 1ATD. The 1B D/G is supplying 1ETB. The crew has implemented AP/1/A/5500/07 Case 1 (Loss of Normal Power to an Essential Train). The CRS has directed you to perform step 10.

EXAMINER NOTE

After reading Initiating Cue, provide the applicant with a copy of AP/1/A/5500/007 Case 1 step 10.

Catawba Nuclear Station JPM H May 201 6 NRC Exam PAGE 5 0F 10 START TIME: _______

STEP/STANDARD SAT/UNSAT STEP 1: 10. Verify B/O busses are energized as follows: a. 1AD-11, K/3 "4KV B/O BUS FTA VOLTAGE LO" - DARK. STANDARD: Applicant will verify 1AD

-11, K/3 is DARK COMMENTS:

___ SAT

___ UNSAT STEP 2 10.b. 1AD-11, K/4 "4KV B/O BUS FTB VOLTAGE LO" - DARK. STANDARD: Applicant will note that 1AD

-11, K/4 is LIT and will transition to the RNO column. COMMENTS:

___ SAT ___ UNSAT Catawba Nuclear Station JPM H May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 10 STEP 3 10.b. RNO b. 1) Ensure breaker "FTB B/O NORM FDR FRM ATD" - OPEN. STANDARD: Applicant will verify breaker is open COMMENTS:

___ SAT

___ UNSAT STEP 4 10.b. RNO b.

2) Dispatch operator to open 1LXH

-4B (Incoming Breaker Fed From Xfmr TXH) (SB-594, U-30). STANDARD: Applicant will contact the booth and dispatch an operator to open 1LXH-4B

Booth Operator

Insert Event 1 to open 1LXH

-4B. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM H May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 10 STEP 5 10.b. RNO b.

3) IF S/I has actuated, THEN ensure "ECCS TRN B" reset. STANDARD: Applicant will determine that this step does not apply.

COMMENTS:

___ SAT

___ UNSAT STEP 6 10.b RNO b.

4) Reset "D/G 1B LOAD SEQ RESET". STANDARD: Applicant will depress the "D/G 1B LOAD SEQ REST" pushbutton

This step is critical to gain manual control of the breakers in subsequent steps.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM H May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 10 STEP 7 10.b. RNO b.

5) WHEN notified by dispatched operator that 1LXH-4B is open, THEN perform the following:

a) Close breaker "FTB B/O ALT FDR FRM ETB". STANDARD: Once notified, applicant will close breaker

Booth Operator: Contact Control Room and inform operator that 1LXH-4B is open.

This step is critical to energize 1FTB from 1ETB.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 8 10.b. RNO b.5)

b) Close breaker "ETB ALT FDR TO FTB".

STANDARD: Applicant will close the breaker.

This step is critical to energize 1FTB from 1ETB.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM H May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 10 STEP 9 10.b. RNO b.5) c) Notify dispatched operator to close 1LXH-4B (Incoming Breaker Fed From Xfmr 1TXH)

(SB-594, U-30). STANDARD: Applicant will contact the booth and notify dispatched operator to close 1LXH-4B.

Booth Operator : Insert Event 2 to close 1LXH-4B. Examiner Cue: Following breaker closure, "Another operator will continue steps of this procedure. JPM complete

."

COMMENTS:

END OF TASK

___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS: Unit 1 is operating at 100% power.

INITIATING CUES:

Unit 1 has experienced a B Train blackout due to a failure of 1ATD. The 1B D/G is supplying 1ETB. The crew has implemented AP/1/A/5500/07 Case 1 (Loss of Normal Power to an Essential Train). The CRS has directed you to perform step 10.

Catawba Nuclear Station JPM I May 2016 NRC Exam PAGE 1 OF 8 JPM I

Catawba Nuclear Station JPM I May 2016 NRC Exam PAGE 2 OF 8 EVALUATION SHEET Task: Align 2A Hydrogen Igniters from their alternate power source and energize the igniters. Alternate Path: None Facility JPM #:

AD-014 Safety Function:

5 Title: Hydrogen Ignition System K/A 028G.2.1.30 Ability to locate and operate components, including local controls Rating(s):

4.4 / 4.0 CFR: 41.7 / 45.7 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator In-Plant X Perform Simulate X References

OP/0/B/6100/0 13 (Standby Shutdown Facility Operations)

Task Standard:

Examinee aligns 2A Hydrogen Igniters from their alternate power source and energizes the 2A Hydrogen Igniters.

Validation Time:

10 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ____

______ NAME____________________________

Docket #___________

Time Finish: ______

____ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS REV. 0 PAGE 3 0F 8 Catawba Nuclear Station JPM I May 2016 NRC Exam PAGE 3 OF 8 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIATING CUES:

Unit 2 has entered AP/0/A/5500/048 (Extensive Damage Mitigation). The Emergency Coordinator has directed you to align 2A Hydrogen Igniters to the alternate source per OP/0/B/6100/013 (Standby Shutdown Facility Operations), Enclosure 4.9 (2A Train Hydrogen Igniter Operation from SSF) and energize the Igniters. The initial conditions have been completed. Steps 3.1 and 3.2 have already been performed by the operator at the SSF. You are to start at step 3.3.

EXAMINER NOTE

After reading the cue provide examinee with a copy of OP/0/B/6100/013 Enc 4.9 signed off through step 3.2.

Catawba Nuclear Station JPM I May 2016 NRC Exam PAGE 4 0F 8 START TIME: _______

STEP/STANDARD SAT/UNSAT STEP 1: 3.3 Ensure 2EMXS F07E (Hydrogen Mitigation 2A Ignitor Xfmr (2XFMR0013) Alternate Feeder) (AB

-577, BB-65, Rm 486) is ON.

STANDARD: Applicant will determine that 2EMXS

-F07E is in the ON position.

Examiner Cue:

When correct breaker is located: 2EMXS-F07E is in the on position.

COMMENTS: ___ SAT

___ UNSAT STEP 2 3.4 Place 2MTSW0006 (Hydrogen Mitigation 2A Ignitor Manual Transfer SSF B/U Pwr)

(AB-577, BB-66, Rm 484) to the ALTERNATE SOURCE position.

STANDARD: Applicant will describe placing 2MTSW006 in the ALTERNATE SOURCE position.

Examiner Cue:

After examinee describes moving the handle downward:

"The power source is in the ALTERNATE SOURCE position."

This step is critical to align to the alternate source.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM I May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 8 NOTE: Shutdown of NF AHUs prevents ventilating the locally ignited hydrogen and a resulting larger hydrogen burn

. STEP 3 3.5 Open the following breakers to de

-energize all Unit 2 NF AHUs: 2MXM F03A (Ice Condenser Power Xfmr ICT2A Feeder) (AB

-577, BB-61, Rm 484) 2MXN F03A (Ice Condenser Power Xfmr ICT2B Feeder) (AB

-560, BB-61, Rm 360)

STANDARD: Applicant will locate and describe opening 2MXM-F03A and 2MXN

-F03A. Examiner Note:

Applicant must describe how to properly operate the breaker by pushing in the locking tab prior to rotating the breaker to the OFF position Examiner Cue: After locating and describing proper operation of the breakers:

2MXM(N)-F03A is OFF.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM I May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 8 NOTE: 2A H2 Igniters red On and green Off indications on 2MC7 will be lit when placed in operation from the alternate power source. STEP 4 3.6 IF AT ANY TIME directed to energize 2A Train Hydrogen Igniters from the alternate source by procedure or by Emergency Coordinator, depress the "ON" pushbutton of the "EHM 2A Train A H2 Igniters" switch at 2ELCP0357 (Hydrogen Mitigation 2A Ignitor Alternate Source Control Panel) (AB

-577, BB-66, Rm 484). STANDARD: Applicant will describe depressing the ON pushbutton for EHM 2A H2 Igniter. Examiner Cue:

Once located and proper description given, "Red ON light lit, Green Off light dark."

This step is critical to energize the H2 igniters.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM I May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 8 STEP 5 3.7 IF AT ANY TIME directed to de

-energize the 2A Train Hydrogen Igniters from the alternate source by procedure or by Emergency Coordinator representative, depress the "OFF" pushbutton of the "EHM 2A Train A H2 Igniters" switch at 2ELCP0357 (Hydrogen Mitigation 2A Ignitor Alternate Source Control Panel).

STANDARD: Applicant will determine that this step does not apply Examiner Cue:

Another Operator will de

-energize the Hydrogen Igniters when requested.

Terminating Cue: This JPM complete.

COMMENTS:

END OF TASK

___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIATING CUES:

Unit 2 has entered AP/0/A/5500/048 (Extensive Damage Mitigation). The Emergency Coordinator has directed you to align 2A Hydrogen Igniters to the alternate source per OP/0/B/6100/013 (Standby Shutdown Facility Operations), Enclosure 4.9 (2A Train Hydrogen Igniter Operation from SSF) and energize the Igniters. The initial conditions have been completed. Steps 3.1 and 3.2 have already been performed by the operator at the SSF. You are to start at step 3.3.

Catawba Nuclear Station JPM J May 2016 NRC Exam PAGE 1 OF 13

JPM J

Catawba Nuclear Station JPM J May 2016 NRC Exam PAGE 2 OF 13 EVALUATION SHEET Task: Energize 1SLXG Alternate Path:

Yes Facility JPM #:

EP-019 Safety Function:

6 Title: Energize 1SLXG K/A 0 62 A2.01 Ability to predict the impacts of the following malfunction or operations on the ac distribution system; and based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Types of loads that, if de

-energized, would degrade or hinder plant operation Rating(s):

3.4 / 3.9 CFR: 41.5 / 43.5 / 45.3 / 45.13 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator In-Plant X Perform Simulate X References

AP/1/A/5500/007 (Loss of Normal Power) Rev. 72, Enclosure 24 (Energize 1SLXG) Task Standard:

Operator energizes 1SLXG from the SSF D/G.

Validation Time:

10 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ________

NAME Docket # Time Finish: ________

Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM J May 2016 NRC Exam PAGE 3 OF 13 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 was at 100% power, when a Loss of Offsite Power (LOOP) occurred.

Both Unit 1 D/Gs started and loaded their respective 4160 V essential busses.

The control room has stabilized Unit 1 per EP/1/A/5000/ES

-0.1 (Reactor Trip Response).

AP/1/A/5500/007 (Loss of Normal Power) was entered to begin power restoration to Unit 1.

All Unit 1 6.9 KV busses have been de

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

INITIATING CUES:

The CRS has instructed you to energize 1SLXG by performing AP/1/A/5500/007 (Loss of Normal Power) Enclosure 24 (Energize 1SLXG). Peer checks have been waived.

Examiner Note

After reading the Initiating Cue, provide operator with a copy of AP/1/A/5500/007 (Loss of Normal Power) Enclosure 24 (Energize 1SLXG).

Catawba Nuclear Station JPM J May 2016 NRC Exam PAGE 4 OF 13 START TIME: _______

STEP/STANDARD SAT/UNSAT NOTE: Indications of 1SLXG being de

-energized are as follows:

Normal Lighting in SSF off with emergency lights on "LINE VOLTS" on 0CNSL0001 indicating zero volts Annunciator 0AD

-11, B/6 "LOAD CENTER 1SLXG TROUBLE"

- LIT "LOAD CENTER 1SLXG BUS VOLTAGE" on 1SLXG indicating zero volts Examiner Cue:

If asked by applicant , inform that the above indications are met.

STEP 1: 1. Ensure "SSF D/G MODE" switch is in "EMERG" position on SSF console.

STANDARD: Applicant places SSF D/G MODE switch to the EMERG position on SSF D/G control panel.

Examiner Cue:

"SSF D/G MODE switch is in the EMERG position."

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM J May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 OF 13 STEP 2: 2. Start D/G by placing "SSF D/G" switch in "ON" position. STANDARD: Applicant places SSF D/G switch to the ON position on SSF D/G control panel. Examiner Cue:

"SSF D/G is heard to be turning over, but did not fire." COMMENTS: ___ SAT

___ UNSAT STEP 3: 3. IF engine does not start within 30 seconds, THEN: a. Place "SSF D/G" switch in "OFF" position.

STANDARD: Applicant determines the SSF D/G did not start, and places the SSF D/G switch to the OFF position on the SSF D/G control panel.

Examiner Cue:

"30 seconds has elapsed and D/G has not started."

Examiner Cue:

"SSF D/G switch is in the OFF position."

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM J May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 OF 13 STEP 4: b. IF D/G turned over but did not fire during D/G start attempt, THEN turn manual override knob on shutdown valve clockwise to permit fuel flow through valve. STANDARD: Applicant turns manual override knob on the side of the D/G engine clockwise Examiner Cue:

"Manual override knob has been turned in the clockwise direction."

This step is critical to allow the SSF D/G to start.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT STEP 5: c. WHEN 1 to 2 minutes has elapsed, THEN RETURN TO Step 1.

Examiner Cue:

"2 minutes has elapsed."

STANDARD: Applicant returns to step 1 of Enclosure 24.

COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station JPM J May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 OF 13 STEP 6: 1. Ensure "SSF D/G MODE" switch is in "EMERG" position on SSF console.

Examiner Cue:

"SSF D/G MODE switch is in the EMERG position."

STANDARD: Applicant determines that the SSF D/G MODE switch is in the EMERG position. COMMENTS: ___ SAT

___ UNSAT STEP 7: 2. Start D/G by placing "SSF D/G" switch in "ON" position.

STANDARD: Applicant places the SSF D/G switch to the ON position on the SSF D/G control panel.

Examiner Cue:

"SSF D/G switch is in the ON position. SSF D/G starts and fires."

This step is critical to start the SSF D/G and energize 1SLXG.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM J May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 OF 13 STEP 8: 3. IF engine does not start within 30 seconds, THEN: STANDARD: Applicant determines this step does not apply.

COMMENTS:

___ SAT

___ UNSAT STEP 9: 4. Adjust "SSF D/G GOV CTRL" to bring frequency to 60 Hz (+/-1.2 Hz). STANDARD: Applicant verifies that Frequency is between 58.8 and 61.2 Hz on the SSF D/G control panel.

EXAMINER CUE:

"Frequency reads 60 Hz."

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM J May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 OF 13 STEP 10: 5. Adjust "SSF D/G VOLT ADJUST" until "VOLTS" is 600 to 660 volts.

STANDARD: Applicant verifies that VOLTS is between 600 and 660 volts on the SSF D/G control panel.

EXAMINER CUE:

"VOLTS reads 620 volts."

COMMENTS: ___ SAT

___ UNSAT STEP 11: 6. Press "TRIP" pushbutton on "1SLXG NORM FDR FRM 1TA" on SSF console.

STANDARD: Applicant presses the green TRIP pushbutton on 1SLXG NORM FDR FRM 1TA and verifies the green TRIP light is lit and red CLSD light is dark. EXAMINER CUE:

"Green TRIP light is lit & red CLSD light is dark."

This step is critical to perform proper lineup to energize 1SLXG from the SSF D/G.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM J May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 10 OF 13 STEP 12: 7. Open the following breakers:

1SLXG-4D (SSF Normal Battery Charger SDSC1 Feeder) 1SLXG-5C (SSF Normal Battery Charger SDSC2 Feeder) 1SLXG-5D (SSF Standby Battery Charger SDSCS Feeder) STANDARD: Applicant describes opening each breaker listed above by rotating the pistol grip counter

-clockwise to the TRIP position and listening for the breaker to open or depressing the manual "OPEN" pushbutton on the breaker faceplate.

EXAMINER CUE:

As each breaker is described being open, "Handle has been rotated to the TRIP position, breaker opens and the green OPEN light is lit and the red CLOSED light is dark."

This step is critical to prevent overloading the D/G when tying it to 1SLXG. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM J May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 11 OF 13 STEP 13: 8. Press "CLOSE" pushbutton for "SSF D/G BKR" on SSF panel.

STANDARD: Applicant presses the red CLOSE pushbutton on SSF D/G BKR and verifies the red CLOSE light is lit and green OPEN light is dark.

EXAMINER CUE:

"Red CLOSE pushbutton depressed, red CLOSE light is lit and green OPEN light is dark."

This step is critical to energize 1SLXG from the SSF D/G.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 1 4: 9. Close the following breakers on 1SLXG in 10 second intervals:

1SLXG-4D (SSF Normal Battery Charger SDSC1 Feeder) 1SLXG-5C (SSF Normal Battery Charger SDSC2 Feeder) 1SLXG-5D (SSF Standby Battery Charger SDSCS Feeder) STANDARD: Applicant rotates the pistol grip in the "CLOSE" direction, or depresses the manual "CLOSE" pushbutton on the breaker faceplate, for each breaker listed in 10 second intervals. Applicant verifies the red CLOSE light lit and green OPEN light dark for each breaker.

EXAMINER CUE:

"Handle rotated to the CLOSE position, red CLOSE light is lit, and green OPEN light is dark."

COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station JPM J May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 12 OF 13 STEP 15: 10. Notify Control Room Supervisor of status.

STANDARD: Applicant contacts the CRS at x5164 and notifies him of the status of 1SLXG being energized from the SSF D/G.

EXAMINER CUE:

Repeat back information given and inform the operator that "another operator will continue to monitor operation of the SSF D/G and this JPM is complete." COMMENTS: END OF TASK

___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task.

To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 was at 100% power, when a Loss of Offsite Power (LOOP) occurred.

Both Unit 1 D/Gs started and loaded their respective 4160 V essential busses.

The control room has stabilized Unit 1 per EP/1/A/5000/ES

-0.1 (Reactor Trip Response).

AP/1/A/5500/007 (Loss of Normal Power) was entered to begin power restoration to Unit 1.

All Unit 1 6.9 KV busses have been de

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

INITIATING CUES:

The CRS has instructed you to energize 1SLXG by performing AP/1/A/5500/007 (Loss of Normal Power) Enclosure 24 (Energize 1SLXG). Peer checks have been waived.

Catawba Nuclear Station JPM K May 2016 NRC Exam PAGE 1 OF 7

JPM K

Catawba Nuclear Station JPM K May 2016 NRC Exam PAGE 2 OF 7 EVALUATION SHEET Task: Makeup to the Unit 2 Spent Fuel Pool from RN Alternate Path:

No Facility JPM #:

KF-058 (Modified)

Safety Function:

8 Title: Plant Service Systems K/A 033 A2.0 3 Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal spent fuel pool water level or loss of water level.

Rating(s):

3.1 / 3.5 CFR: 41.5 / 43.5 / 45.3 / 45.

13 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator In-Plant X Perform Simulate X References

OP/2/A/6200/005 Spent Fuel Pool Cooling System rev.078 Task Standard:

Lineup completed to supply RN to the Spent Fuel Pool via 2RN

-78 and 2KF-104. Validation Time:

1 2 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS REV. 0 PAGE 3 0F 7 Catawba Nuclear Station JPM K May 2016 NRC Exam PAGE 3 OF 7 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A minor seismic event has cracked the Unit 2 Spent Fuel Pool causing an unisolable leak of Spent Fuel Pool water.

Spent Fuel Pool level is 39 feet and slowly decreasing.

INITIATING CUES:

The Control Room Supervisor directs you to initiate makeup to the Spent Fuel Pool from RN Train 2A per OP/2/A/6200/005 (Spent Fuel Cooling System) Enclosure 4.10.

All initial conditions have been satisfied for this enclosure.

Double verification and peer check of procedure steps have been waived during this JPM. EXAMINER NOTE

After reading the initiating cue, provide the applicant with a copy of OP/2/A/6200/005 Enclosure 4.10.

Catawba Nuclear Station JPM K May 2016 NRC Exam PAGE 4 0F 7 START TIME: _______

STEP/STANDARD SAT/UNSAT STEP 1: 3.1 Document Current Spent Fuel Pool Level

______________ ft STANDARD: Applicant documents Spent Fuel Pool level as 39 feet per the initiating cue. EXAMINER NOTE

The applicant is not required to locate the level indication in the control room.

EXAMINER CUE: Fuel Pool Level is 39 feet.

COMMENTS: ___ SAT

___ UNSAT STEP 2 3.2 IF desired to makeup from RN System Supply Header 2A, perform the following steps:

STANDARD: Applicant determines to makeup from RN Train 2A per the initial conditions COMMENTS: ___ SAT

___UNSAT Catawba Nuclear Station JPM K May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 7 STEP 3 3.2.1 Close 2 KF-172 (FWST Overflow To Spent Fuel Pool Isol) (AB-584, MM-6 2, Rm 400). STANDARD: Applicant locates and describes closing 2KF

-172. EXAMINER CUE

Valve is Closed

. COMMENTS: ___ SAT

___ UNSAT STEP 4 3.2.2 Open 2 RN-78 (2A RN Supply To Assured KF Makeup) (AB-58 9 , LL-60, Rm 400).

STANDARD: Applicant locates and describes opening 2RN

-78. EXAMINER CUE

Valve is Open

.

This step is critical to align RN to the Unit 2 Spent Fuel Pool.

COMMENTS:

CRITICAL STE P ___ SAT

___ UNSAT Catawba Nuclear Station JPM K May 2016 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 7 CAUTION: Maximum Spent Fuel Pool level shall be 40

.5 feet on 2KFP5120 (Fuel Pool Level) or OAC Point C 2A0061 (U2 Spent Fuel Pool Level). Centerline of the Spent Fuel Pool light receptacles is 41 feet.

STEP 5 3.2.3 Open 2 KF-104 (2A KF Assured Fuel Pool M/U Isol)

(AB-58 4, MM-62, Rm 400).

STANDARD: Applicant locates and describes opening 2KF

-104. EXAMINER CUE: Valve is Open

. This step is critical to align RN to the Unit 2 Spent Fuel Pool.

EXAMINER CUE: If monitoring of spent fuel pool level is mentioned by the applicant, provide the following cue: "Another operator will be monitoring spent fuel pool level

." This JPM is complete.

COMMENTS:

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A minor seismic event has cracked the Unit 2 Spent Fuel Pool causing an unisolable leak of Spent Fuel Pool water.

Spent Fuel Pool level is 39 feet and slowly decreasing.

INITIATING CUES:

The Control Room Supervisor directs you to initiate makeup to the Spent Fuel Pool from RN Train 2A per OP/2/A/6200/005 (Spent Fuel Cooling System) .10.

All initial conditions have been satisfied for this enclosure.

Double verification and peer check of procedure steps have been waived during this JPM.

Catawba Nuclear Station Admin. JPM A.1

-1 May 2016 NRC Exam PAGE 1 OF 10 JPM A.1-1 RO / SRO

Catawba Nuclear Station Admin. JPM A.1

-1 May 2016 NRC Exam PAGE 2 OF 10 EVALUATION SHEET Task: Determine Status of NC System Fill and Vent Alternate Path:

N/A Facility JPM #:

New Safety Function:

N/A K/A 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Importance:

3.9 / 4.2 CFR: 41.10 / 4 3.5 / 45.12 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate References

OP/1/A/6150/001 (Filling and Venting the Reactor Coolant System)

Task Standard:

Applicant determines the Reactor Coolant System has not reached "Loops Filled" condition following initial fill and vent operation.

Validation Time:

1 0 minutes Time Critical:

Yes No X Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 10 Catawba Nuclear Station Admin. JPM A.1

-1 May 2016 NRC Exam PAGE 3 OF 10 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Following refueling, initial venting of Reactor Coolant System has been completed per OP/1/A/6150/001 (Filling and Venting the Reactor Coolant System).

Steps 3.1 through 3.13.18.10 of Enclosure 4.2 (Reactor Coolant System Venting) are complete.

1A ND is in service

. The following indication s are noted following system pressurization to 300 psig:

o C1A0843 (VCT Level 1)

- 49.0% o C1A1524 (VCT Level 2)

- 50.6% o 1A ND HX Outlet Temp

- 105°F o 1B ND HX Outlet Temp

- 110°F o Total Makeup Batch Counter

- 2 79 0 o VCT Makeup was continuous throughout pressurization INITIATING CUES:

You are to determine if the Reactor Coolant System has reached "Loops Filled" status by completing step 3.13 of OP/1/A/6150/001, Enclosure 4.2 (Reactor Coolant System Venting). Round all calculations to the nearest tenth.

Record your answer below.

Concurrent Verification is waived for this task.

NC System is in a Loops Filled condition:

(yes or no)

.

EXAMINER NOTE

After reading cue, provide applicant with a copy of OP/1/A/6150/001, Enclosure 4.2, pages 32

-35 and Enclosure 4.8

.

Catawba Nuclear Station Admin. JPM A.1

-1 May 2016 NRC Exam PAGE 4 0F 10 START TIME: _______

STEP / STANDARD SAT / UNSAT STEP 1: 3.13.18.11 Record the following final values:

VCT level per one of the following OAC Points. Use the same VCT level channel that was used to obtain the initial level in Step 3.13.18.4

% C1A0843 (VCT Level 1) or C1A1524 (VCT Level 2)

Total Makeup batch counter reading In service ND Hx outlet temperature STANDARD: Candidate records the following data:

VCT level: 49.0%

Total Makeup batch counter reading: 2790 gal In service ND HX outlet temperature: 105°F COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-1 May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 0F 10 STEP 2: 3.13.18.12 Determine volume required to pressurize the NC System from 40 psig to 300 psig as follows:

A. If VCT makeup was suspended during the pressurization, perform the following:

STANDARD: Candidate determines that this step is not applicable.

COMMENTS: ___ SAT

___ UNSAT STEP 3: B. Determine change in VCT Level.

- = Initial level Final level

% (Step 3.13.18.4)

(Step 3.13.18.11)

STANDARD: Candidate records the following:

54% - 49% = 5% Initial level Final level

% (Step 3.13.18.4)

(Step 3.13.18.11)

This step is critical to ensure that the correct makeup value is calculated.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-1 May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 0F 10 STEP 4: C. Convert VCT level change to gallons as follows:

X 19.2 gallons/%

= % change gallons (Step 3.13.18.12B)

STANDARD: Candidate records the following:

5% X 19.2 gallons/%

= 96 % change gallons (Step 3.13.18.12B)

This step is critical to ensure that the correct makeup value is calculated.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-1 May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 0F 10 NOTE: A higher final VCT level will result in the change in VCT level being subtracted from total makeup totalizer change.

STEP 5: D. Determine total volume required to pressurize the NC System. + = VCT Makeup Change in VCT Total (Step 3.13.18.11 or level makeup Step 3.13.18.12A.2)

(Step 3.13.18.12C) required STANDARD: Candidate records the following:

2790 + 96 = 2886 VCT Makeup Change in VCT Total (Step 3.13.18.11 or level makeup Step 3.13.18.12A.2)

(Step 3.13.18.12C) required This step is critical to ensure that the correct makeup value is calculated.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-1 May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 0F 10 STEP 6: E. Compare the result of Step 3.13.18.12D with the graph in Enclosure 4.8 (Allowable Volume to Determine Loops Filled). STANDARD: Candidate refers to Enclosure 8 and determines that 2886 gallons at 105°F is NOT within the acceptable range. Therefore, the Reactor Coolant system is NOT in a loops filled condition. This step is critical to ensure that the correct determination is made concerning status of the Reactor Coolant system.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 7: F. If the volume used to pressurize is within the acceptable region of the graph in Enclosure 4.8 (Allowable Volume to Determine Loops filled), perform the following:

STANDARD: Candidate determines that this step is not applicable.

COMMENTS:

___ SAT ___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-1 May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 9 0F 10 STEP 8: G. If the volume used to pressurize is NOT within the acceptable region of the graph in Enclosure 4.8 (Allowable Volume to Determine Loops filled), perform the following:

1. Notify the CRS that the NC System has NOT achieved a Loops Filled condition per Technical Specification 3.4.7.

STANDARD: Candidate determines that the Reactor Coolant system in NOT in a loops filled condition and answers NO on initiating cue

. COMMENTS: END OF TASK

___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Following refueling, initial venting of Reactor Coolant System has been completed per OP/1/A/6150/001 (Filling and Venting the Reactor Coolant System), Steps 3.1 through 3.13.18.10 of Enclosure 4.2 (Reactor Coolant System Venting) are complete.

1A ND is in service The following indications are noted following system pressurization to 300 psig:

o C1A0843 (VCT Level 1)

- 49.0% o C1A1524 (VCT Level 2)

- 50.6% o 1A ND HX Outlet Temp

- 105°F o 1B ND HX Outlet Temp

- 110°F o Total Makeup Batch Counter

- 2790 o VCT Makeup was continuous throughout pressurization

INITIATING CUES:

You are to determine if the Reactor Coolant System has reached "Loops Filled" status by completing step 3.13 of OP/1/A/6150/001, Enclosure 4.2 (Reactor Coolant System Venting). Perform all calculations to one decimal place. Record your answer below.

Concurrent Verification is waived for this task.

NC System is in a Loops Filled condition:

(yes or no)

.

Catawba Nuclear Station Admin. JPM A.1

-2 R May 2016 NRC Exam PAGE 1 OF 11 JPM A.1-2R RO

Catawba Nuclear Station Admin. JPM A.1

-2 R May 2016 NRC Exam PAGE 2 OF 11 EVALUATION SHEET Task: Calculate Boric Acid and Water Addition to FWST Alternate Path:

N/A Facility JPM #:

New Safety Function:

N/A K/A 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Importance:

4.3 / 4.4 CFR: 41.10 / 4 3.5 / 45.2 / 45.6 Preferred Evaluation Location:

Preferred Evaluation Method: Simulator Classroom X Perform X Simulate References

OP/1/A/6 200/0 14 (Refueling Water System

), Enclosure 4.4 (FWST Makeup From Blender)

Task Standard:

Applicant determines required boric acid addition of 368.8 gallons and reactor makeup water addition of 3402.2 gallons to complete the required FWST makeup. Validation Time:

1 5 minutes Time Critical:

Yes No X Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 11 Catawba Nuclear Station Admin. JPM A.1

-2R May 2016 NRC Exam PAGE 3 OF 11 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

It has been discovered that an incorrect valve lineup decreased FWST level to 9 5%. Current conditions as follows:

o The valve lineup has been immediately corrected securing the level decrease.

o Current FWST level is 95

%. o Current FWST boron concentration is 2740 ppm B. o Unit 1 BAT boron concentration is 7500 ppmB

. o Unit 2 BAT boron concentration is 7300 ppmB

. o Unit 1 RMWST boron concentration is 4 ppmB

. INITIATING CUES:

Using OP/1/A/6200/014 (Refueling Water System), Enclosure 4.4 (FWST Makeup From Blender), steps 3.1

- 3.4 , determine the required amount of Boric Acid and RMWST water necessary to perform an FWST makeup as follows: Final FWST level of 9 6% at 2720 ppmB S. Jackson (Primary Chemistry) has been notified and directed use of the Unit 1 BAT. Concurrent Verification is waived for this task.

Round all calculations to the nearest tenth.

Boric Acid RMWST Water

EXAMINER NOTE

After reading cue, provide applicant with a copy of OP/1/A/6200/014, Enclosure 4.4.

Catawba Nuclear Station Admin. JPM A.1

-2 R May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 4 OF 11 START TIME: _______

STEP / STANDARD SAT / UNSAT NOTE: To prevent an inadvertent reduction in the shutdown margin during NC fill evolutions, makeup to the FWST shall be performed with a water source having a Boron concentration which is greater than or equal to the required NC system Boron concentration.

STEP 1: 3.1 Notify Chemistry that the following Boric Acid Tank will be used for Tech Spec blending calculations {PIP 91

- 0449}:

Person notified _______________________

_____________ Boric Acid Tank #1

_____________ Boric Acid Tank #2 STANDARD: From the cue, applicant records S. Jackson as Chemistry person notified and checks Boric Acid Tank #1.

COMMENTS:

___ SAT

___ UNSAT STEP 2: 3.2 Document current boron concentration in the Boric Acid Tank as specified by Chemistry in Step 3.1 {PIP 91- 0449}:

_____________ ppmB STANDARD: From the cue, applicant determines that BAT #1 will be used and records 7500 ppmB. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2 R May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 OF 11 NOTE The final boron concentration used in the next step shall comply with COLR requirements for the current mode of operation.

STEP 3: 3.3 Determine the boron concentration of the makeup water to the FWST (C f) to attain the final boron concentration, C FW. 3.3.1 Initial volume of FWST _______ = V

i. STANDARD: Using supplied information applicant enters the initial level of 37 3 ,875 gallons. COMMENTS:

___ SAT

___ UNSAT STEP 4: 3.3.2 Final volume of FWST after makeup _______ = V FW. STANDARD: Using supplied information applicant enters the final level of 37 7 ,646 gallons. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2 R May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 OF 11 STEP 5: 3.3.3 Compute the total gallons of makeup water to be added to the FWST

_________ = V f.. STANDARD: Applicant calculates, and records, makeup volume of 3,771 gallons. 377, 646 - 37 3 ,875 = 3, 771 This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 6: 3.3.4 Initial boron concentration of water in the FWST

______ = C

i. STANDARD: From the cue, applicant records initial FWST boron concentration of 2740 ppmB.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2 R May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 OF 11 STEP 7: 3.3.5 Solve for the desired makeup water boron concentration, Cf.

C f = C FW V FW - C i V i C f = __________

V f STANDARD: Applicant calculates desired concentration of makeup water to be 737.1 ppmB Cf = (2720 x 377 646) - (2740 x 373875) / 3771 = 737.1 ppmB This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 8: 3.4 Determine the amount of boric acid and reactor makeup water to add as follows:

3.4.1 Boron Concentration of water in BAT _________ = C

1. STANDARD: From the cue, applicant records Unit 1 BAT boron concentration of 7500 ppmB. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2 R May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 OF 11 STEP 9: 3.4.2 Boron concentration of water in RMWST

__________ = C 2.: STANDARD: From the cue, applicant records Unit 1 RMWST boron concentration of 4 ppmB. COMMENTS: ___ SAT ___ UNSAT STEP 10: 3.4.3 Total gallons of makeup water to be added to FWST

________ = V f from Step 3.3.3.:

STANDARD: Applicant records total makeup volume of 3,771 from step 3.3.3.

COMMENTS: ___ SAT ___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2 R May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 9 OF 11 STEP 11: 3.4.4 Solve for the amount of boric acid to be added (V

1) using C f obtained in Step 3.3.5.

V 1 = V f (C f - C 2)

V 1 = ___________

C 1 - C 2 STANDARD: Applicant calculates boric acid total of 368.8 gallons.

V 1 = 3771 (737.1 - 4) / (7500

- 4) = 368.8 (+/- 10)

This step is critical to ensure accurate result for final calculation.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT STEP 12: 3.4.5 If V 1 is negative, contact the OWPM Staff for instruction on adjusting the boron concentration in the FWST.

STANDARD: Applicant determines that this step does not apply.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2 R May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 10 OF 11 STEP 13: 3.4.6 Solve for the amount of RMWST water to be added (V 2). V 2 = V f - V 1 V 2 = _________ gal.

STANDARD: Applicant calculates required RMWST water to be 3402.2 gallons.

3771 - 368.8 = 3402.2 (+/- 10)

This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

It has been discovered that an incorrect valve lineup decreased FWST level to 95%.

Current conditions as follows:

o The valve lineup has been immediately corrected securing the level decrease.

o Current FWST level is 95%

. o Current FWST boron concentration is 2740 ppmB

. o Unit 1 BAT boron concentration is 7500 ppmB

. o Unit 2 BAT boron concentration is 7300 ppmB

. o Unit 1 RMWST boron concentration is 4 ppmB

.

INITIATING CUES:

Using OP/1

/A/6200/014 (Refueling Water System), Enclosure 4.4 (FWST Makeup From Blender), steps 3.1

- 3.4, determine the required amount of Boric Acid and RMWST water necessary to perform an FWST makeup as follows:

Final FWST level of 96% at 2720 ppmB S. Jackson (Primary Chemistry) has been notified and directed use of the Unit 1 BAT. Concurrent Verification is waived for this task.

Round all calculations to the nearest tenth.

Boric Acid RMWST Water

Catawba Nuclear Station Admin. JPM A.1

-2S May 2016 NRC Exam PAGE 1 OF 13 JPM A.1-2S S RO

Catawba Nuclear Station Admin. JPM A.1

-2S May 2016 NRC Exam PAGE 2 OF 13 EVALUATION SHEET Task: Calculate Boric Acid and Water Addition to FWST and determine Tech Spec actions.

Alternate Path: N/A Facility JPM #:

New Safety Function:

N/A K/A 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Importance:

4.3 / 4.4 CFR: 41.10 / 4 3.5 / 45.2 / 45.6 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate References

OP/1/A/6 200/0 14 (Refueling Water System

), Enclosure 4.4 (FWST Makeup From Blender)

Task Standard:

Applicant determines required boric acid addition of 368.8 gallons and reactor makeup water addition of 3402.2 gallons to complete the required FWST makeup and determines the following SLC/TS required LCO entries: 1000

- SLC 16-9.12 Condition D and TS 3.5.4 Condition B, 1100

- SLC 16-9.12 Condition D and TS 3.5.4 Condition B and Condition C.

Validation Time:

3 0 minutes Time Critical:

Yes No X Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 13 Catawba Nuclear Station Admin. JPM A.1

-2S May 2016 NRC Exam PAGE 3 OF 13 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is in Mode 3 during a refueling outage. The following events have occurred at the given times:

0945: 1AD-9 B/8 "FWST AT MAKEUP LEVEL" annunciator received. Operators are dispatched to investigate decreasing Unit 1 FWST level.

1000: Unit 1 BOP reports that FWST volume is 377,536.9 gallons.

1015: An improperly executed FW system clearance is discovered and determined to be the cause of FWST level decrease.

Current conditions are as follows:

o The valve lineup has been immediately corrected securing the level decrease

. o Current FWST level is 9 5%. o Current FWST boron concentration is 2740 ppm B. o Unit 1 BAT boron concentration is 7500 ppmB

. o Unit 2 BAT boron concentration is 7300 ppmB

. o Unit 1 RMWST boron concentration is 4 ppmB

. o Total Blender Makeup flowrate = 90 gpm INITIATING CUES:

1. Using OP/1/A/6200/014 (Refueling Water System), Enclosure 4.4 (FWST Makeup From Blender), steps 3.1

- 3.4 , determine the required amount of Boric Acid and RMWST water necessary to perform an FWST makeup as follows: Final FWST level of 9 6% at 2720 ppmB

. S. Jackson (Primary Chemistry) has been notified and directed use of the Unit 1 BAT. Concurrent Verification is waived for this task.

Round all calculation s to the nearest tenth.

Boric Acid RMWST Water

2. Assuming the required makeup begins at time 1030, determine which Active SLC and TS LCO entries (if any) will be required at 1000 and 1100

. 1000:

1100:

PAGE 4 0F 13 Catawba Nuclear Station Admin. JPM A.1

-2S May 2016 NRC Exam PAGE 4 OF 13 EXAMINER NOTE

After reading cue, provide applicant with a copy of OP/1/A/6200/014, Enclosure 4.4 and JPM A.1

-2R/S Reference Handout.

Catawba Nuclear Station Admin. JPM A.1

-2S May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 OF 13 QUESTION 1 START TIME: _______

STEP / STANDARD SAT / UNSAT NOTE: To prevent an inadvertent reduction in the shutdown margin during NC fill evolutions, makeup to the FWST shall be performed with a water source having a Boron concentration which is greater than or equal to the required NC system Boron concentration. STEP 1: 3.1 Notify Chemistry that the following Boric Acid Tank will be used for Tech Spec blending calculations {PIP 91

- 0449}:

Person notified _______________________

_____________ Boric Acid Tank #1

_____________ Boric Acid Tank #2 STANDARD: From the cue, applicant records S. Jackson as Chemistry person notified and checks Boric Acid Tank #1.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2S May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 OF 13 STEP 2: 3.2 Document current boron concentration in the Boric Acid Tank as specified by Chemistry in Step 3.1 {PIP 91

- 0449}: _____________ ppmB STANDARD: From the cue, applicant determines that BAT #1 will be used and records 7500 ppmB. COMMENTS:

___ SAT

___ UNSAT NOTE The final boron concentration used in the next step shall comply with COLR requirements for the current mode of operation.

STEP 3: 3.3 Determine the boron concentration of the makeup water to the FWST (C f) to attain the final boron concentration, C FW.

3.3.1 Initial volume of FWST _______ = V

i. STANDARD: Using supplied information applicant enters the initial level of 37 3 ,875 gallons. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2S May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 OF 13 STEP 4: 3.3.2 Final volume of FWST after makeup _______ = V FW. STANDARD: Using supplied information applicant enters the final level of 37 7 ,646 gallons. COMMENTS:

___ SAT

___ UNSAT STEP 5: 3.3.3 Compute the total gallons of makeup water to be added to the FWST

_________ = V f.. STANDARD: Applicant calculates, and records, makeup volume of 3,771 gallons. 377, 6 46 - 37 3 ,875 = 3, 771 This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2S May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 OF 13 STEP 6: 3.3.4 Initial boron concentration of water in the FWST

______ = C

i. STANDARD: From the cue, applicant records initial FWST boron concentration of 2740 ppmB.

COMMENTS:

___ SAT

___ UNSAT STEP 7: 3.3.5 Solve for the desired makeup water boron concentration, Cf.

C f = C FW V FW - C i V i C f = __________

V f STANDARD: Applicant calculates desired concentration of makeup water to be 737.1 ppmB Cf = (2720 x 377 6 46) - (2740 x 373875) / 3771 = 737.1 ppmB This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2S May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 9 OF 13 STEP 8: 3.4 Determine the amount of boric acid and reactor makeup water to add as follows:

3.4.1 Boron Concentration of water in BAT _________ = C

1. STANDARD: From the cue, applicant records Unit 1 BAT boron concentration of 7500 ppmB. COMMENTS:

___ SAT

___ UNSAT STEP 9: 3.4.2 Boron concentration of water in RMWST

__________ = C 2.: STANDARD: From the cue, applicant records Unit 1 RMWST boron concentration of 4 ppmB. COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2S May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 10 OF 13 STEP 10: 3.4.3 Total gallons of makeup water to be added to FWST

________ = V f from Step 3.3.3.

STANDARD: Applicant records total makeup volume of 3,771 from step 3.3.3.

COMMENTS: ___ SAT ___ UNSAT STEP 11: 3.4.4 Solve for the amount of boric acid to be added (V

1) using C f obtained in Step 3.3.5.

V 1 = V f (C f - C 2)

V 1 = ___________

C 1 - C 2 STANDARD: Applicant calculates boric acid total of 368.8 gallons. V 1 = 3771 (737.1 - 4) / (7500

- 4) = 368.8 This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2S May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 11 OF 13 STEP 12: 3.4.5 If V 1 is negative, contact the OWPM Staff for instruction on adjusting the boron concentration in the FWST.

STANDARD: Applicant determines that this step does not apply.

COMMENTS: ___ SAT ___ UNSAT STEP 13: 3.4.6 Solve for the amount of RMWST water to be added (V 2).

V 2 = V f - V 1 V 2 = _________ gal.

STANDARD: Applicant calculates required RMWST water to be 3402.2 gallons. 3771 - 368.8 = 3402.2 This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2S May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 12 OF 13 QUESTION 2 1000: SLC 16

-9.12 Condition D

/ LCO 3.5.4, Condition B The minimum volume requirement of SLC 16-9.12 (Boration Systems Borated Water Sources

- Operating) is not met. Therefore, Condition D (RWST non-functional) entry will be required. The Required Action associated with this condition is to declare the RWST inoperable and enter the applicable conditions of TS 3.5.4 Immediately.

The 377,537 gallons) is not met. Therefore, TS 3.5.4, Condition B (RWST inoperable for reasons other than Condition A) entry will be required. The Required Action associated with this condition is to Restore RWST to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

NOTE: The applicant may also determine SLC 16

-9.8 (Boration Systems Flow Paths

- Operating), Condition A (One required Boration System Flow Path non-functional) applies if familiar with the associated plant testing procedure. This procedure requires the FWST to be functional in order to meet the acceptance criteria. However , the surveillance requirements of this SLC do not list this particular requirement so this determination will not be critical to this task. 1100: SLC 16-9.12 Condition D

/ LCO 3.5.4, Conditions B & C With an initial volume of 37 3 , 875 gallons and an available makeup rate of 90 gpm (beginning at 1030), the total FWST volume at 1100 will be 376,575 gallons which remains below the required minimum of SR 3.5.4.2.

37 3 , 875 (initial volume) + {90 gpm x 30 min} = 376, 575 gallons Therefore, SLC 16-9.12 Condition D and TS 3.5.4 Condition B will remain in effect AND TS 3.5.4 Condition C (Required Action and associated Completion Time not met) must be entered.

Determination of SLC 16

-9.12 and TS 3.5.4 required actions (only) are critical to ensure proper actions are entered to address th is adverse condition.

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is in Mode 3 during a refueling outage. The following events have occurred at the given times:

0945: 1AD-9 B/8 "FWST AT MAKEUP LEVEL" annunciator received. Operators are dispatched to investigate decreasing Unit 1 FWST level.

1000: Unit 1 BOP reports that FWST volume is 377,536.9 gallons.

1015: An improperly executed FW system clearance is discovered and determined to be the cause of FWST level decrease.

Current conditions are as follows:

o The valve lineup has been immediately corrected securing the level decrease.

o Current FWST level is 95%.

o Current FWST boron concentration is 2740 ppmB.

o Unit 1 BAT boron concentration is 7500 ppmB.

o Unit 2 BAT boron concentration is 7300 ppmB.

o Unit 1 RMWST boron concentration is 4 ppmB.

o Total Blender Makeup flowrate = 90 gpm INITIATING CUES:

1. Using OP/1/A/6200/014 (Refueling Water System), Enclosure 4.4 (FWST Makeup From Blender), steps 3.1

- 3.4, determine the required amount of Boric Acid and RMWST water necessary to perform an FWST makeup as follows:

Final FWST level of 96% at 2720 ppmB.

S. Jackson (Primary Chemistry) has been notified and directed use of the Unit 1 BAT. Concurrent Verification is waived for this task.

Round all calculations to the nearest tenth.

Boric Acid RMWST Water

2. Assuming the required makeup begins at time 1030, determine which Active SLC and TS LCO entries (if any) will be required at 1000 and 1100.

1000:

1100:

Catawba Nuclear Station Admin. JPM A.1

-2R/S May 2016 NRC Exam REFERENCE HANDOUT

Catawba Nuclear Station Admin. JPM A.2 May 2016 NRC Exam PAGE 1 OF 7 JPM A.2 RO-SRO

Catawba Nuclear Station Admin. JPM A.2 May 2016 NRC Exam PAGE 2 OF 7 DATA SHEET Task: Classify a D/G Start and Complete a Logbook Entry Alternate Path:

N/A Facility JPM #:

DG3-010 Safety Function:

N/A K/A 2.2.12 Knowledge of surveillance procedures.

Importance:

3.7 / 4.1 CFR: 41.10 / 45.13 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate References

OMP 2-28 (Diesel Generator Logbook) rev 027 PT/2/A/4350/002 B, (Diesel Generator 2B Operability Test), Rev. 101 Task Standard:

Classify the D/G start as a VALID FAILURE and correctly enter data into the logbook. Validation Time:

20 minutes Time Critical: Yes No X Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 7 Catawba Nuclear Station Admin. JPM A.2 May 2016 NRC Exam PAGE 3 OF 7 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 2 is in Mode 1.

You were an extra operator on shift and assisting the Operation Test Group in a scheduled surveillance test of the 2B Emergency Diesel Generator.

The test was conducted using procedure PT/2/A/4350/002B (D/G Operability Test). Given the following timeline:

0830 2B D/G was started

. Time to reach required frequency was 7.0 seconds.

Time to reach required voltage was 6.7 seconds.

0845 2B D/G was fully loaded.

0905 2B D/G automatically tripped due to a malfunction of the low

-low lube oil pressure switch.

PT/2/A/4350/002B has been completed up to step 12.

7 5 for completing Diesel Generator Logbook entries per OMP 2

-28 (Diesel Generator Logbook)

. MCE Rotating Equipment supervisor is Rudulf Otto Schwensteiger.

Environmental Management supervisor is T. Reese Hugger.

Next sequential NCR number is #01668542.

INITIATING CUES:

Using the information provided in Initial Conditions, classify the test and fill in all available Diesel Generator Logbook data on Attachment 10.1 (Diesel Generator Log Sheet) and 10.2 (Index Sheet) of OMP 2-28 and submit to the CRS for review.

Perform all calculation s and/or round any decimal number s to 2 decimal places.

For the purposes of this JPM, complete both Attachment 10.1 and 10.2 before making notification(s), if any are required.

EXAMINER NOTE

Provide applicant with a copy of OMP 2

-28 (total of 11 pages). Attachment 10.2 will include one entry from the previous surveillance.

Catawba Nuclear Station Admin. JPM A.2 May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 4 0F 7 START TIME: _______

STEP 1: Based on initial conditions, applicant refers to OMP Section 6 to determine the TEST CLASSIFICATION.

STANDARD: Applicant determines that the test is a VALID FAILURE based on criteria 6.4.A.

Critical Step in order to meet the Task Standard: Determine the correct classification.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.2 May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 0F 7 STEP 2: Applicant enters appropriate information on Attachment 10.1 using information from the initial conditions.

STANDARD: Examiner NOTE:

See KEY provided with this document for required entries, including Critical Step aspects identified on the KEY.

Enters 2B D/G

. Enters start attempt as "2." Marks PT/1(2)/4350/002A(B) as procedure used

. Marks Scheduled Surveillance as Reason for D/G Operation

. Marks Turbo Prelube as Type of Diesel Start. Enters engine start time as 08 3 0. Enters engine shutdown time as 0905. Calculates and enters run time as 0.

58 hours6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months . Calculates and enters yearly run time as 2.33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months Enters Start Data:

Time for Frequency

> 57 Hz as 7.0 sec.

Time for Voltage

> 3950 volts as 6.7 sec.

Circles "YES" to indicate steady state voltage and freq Calculates and enters Time Diesel Loaded as 0.33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months Circles "NO" for loaded time >1 hour Enters classification as VALID FAILURE

. Marks "Record Classification in Index" for Item L.

Marks "For a VALID/INVALID FAILURE, inform the MCE Rotating Equipment Supervisor or Designee:

Enters MCE Rotating Equipment Supervisor as Rudulf Otto Schweinsteiger.

Marks "Document the PIP# for the D/G run on the Index Sheet:

Enters PIP# as NCR 01668542 in Section M and Attachment 10.2 Enters reason D/G start was not a valid success: (2B D/G automatically tripped due to a malfunction of the low

-low Lube Oil Pressure switch prior to being loaded > 2875 KW for > 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ).

The steps in bold are critical because all other entries are required regardless of the classification.

COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT Catawba Nuclear Station Admin. JPM A.2 May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 0F 7 STEP 3: Logs the start into the Index Sheet (Enclosure 10.2)

STANDARD: Enters Start # as "2".

Enters Date as today

's date. Enters Test Classification as "VALID FAILURE"

. Enters run time as 0.

58 hrs. Enters yearly run time as 2

.33 hrs. Enters PIP# as 01668542.

The items in bold are critical based on OMP 2

-28 section 3 criteria.

COMMENTS: END OF TASK CRITICAL STEP ___ SAT ___ UNSAT STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure y ou indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 2 is in Mode 1.

You were an extra operator on shift and assisting the Operation Test Group in a scheduled surveillance test of the 2B Emergency Diesel Generator.

The test was conducted using procedure PT/2/A/4350/002B (D/G Operability Test). Given the following timeline:

0830 2B D/G was started.

Time to reach required frequency was 7.0 seconds.

Time to reach required voltage was 6.7 seconds.

0845 2B D/G was fully loaded.

0905 2B D/G automatically tripped due to a malfunction of the low

-low lube oil pressure switch.

PT/2/A/4350/002B has been completed up to step 12.

7 5 for completing Diesel Generator Logbook entries per OMP 2

-28 (Diesel Generator Logbook).

MCE Rotating Equipment supervisor is Rudulf Otto Schwensteiger.

Environmental Management supervisor is T. Reese Hugger.

Next sequential NCR number is #01668542.

INITIATING CUES:

Using the information provided in Initial Conditions, classify the test and fill in all available Diesel Generator Logbook data on Attachment 10.1 (Diesel Generator Log Sheet) and 10.2 (Index Sheet) of OMP 2

-28 and submit to the CRS for revie

w. Perform all calculation s and/or round any decimal number s to 2 decimal places.

For the purposes of this JPM, complete both Attachment 10.1 and 10.2 before making notification(s), if any are required.

Catawba Nuclear Station Admin. JPM A.3 May 201 6 NRC Exam PAGE 1 OF 6 JPM A.3 RO / SRO

Catawba Nuclear Station Admin. JPM A.3 May 201 6 NRC Exam PAGE 2 OF 6 EVALUATION SHEET Task: Determine Radiation Protection Requirements for an activity Alternate Path:

N/A Facility JPM #: 2005 Admin JPM R03/SRO4 Modified Safety Function:

N/A K/A G 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.

Importance:

3.5 / 3.6 CFR: 41.12 / 45.10 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate References

Radiation Work Permit # 5021, Room 105 (ND Pump 1A) Survey Map Task Standard:

Correctly determine that total dose received for the job is 1 3 mR and maximum time to complete venting without exceeding RWP dose limits is 0900 hrs. Validation Time:

1 5 minutes Time Critical:

Yes No X Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE COMMENTS Catawba Nuclear Station Admin. JPM A.3 May 201 6 NRC Exam PAGE 3 OF 6 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is in AP/1/A/5500/019 (Loss of Residual Heat Removal)

The CRS has dispatched you to 1A ND pump room to vent the 1A ND pump casing when directed.

You are to stage yourself where you can minimize your dose while waiting.

The following is the timeline for the venting evolution:

0800 - You enter 1A ND Pump Room.

0830 - You are directed to vent using 1ND

-88 (1A ND Pump Seal Water Hx Inlet Vent).

0842 - Venting is complete. You immediately exit the room and report back to the Control Room.

INITIATING CUES:

Based on the above time line, RWP # 5021, and Survey Map s provided and discounting any dose received during transit

1. State the amount of dose that was received for the duration of the task.

Amount of dose received

- ________________ mR

2. Assuming you entered the room and began venting at the above stated times, determine the latest clock time that venting could complete without exceeding a limit imposed by the applicable task of RWP 5021. Latest clock time for venting without exceeding the MAXIMUM Dose listed on the applicable task of RWP 5021 - ___________ . EXAMINER NOTE

Each applicant should receive a copy of RWP # 5021 (Tasks 1 and 2) and the Room Survey for room s 105 and 110.

Catawba Nuclear Station Admin. JPM A.3 May 201 6 NRC Exam PAGE 4 0F 6 START TIME: _______

STEP / STANDARD SAT / UNSAT STEP 1 Determine dose received for the venting evolution:

Applicant is to stage themselves at the Low Exposure Waiting Area (LEWA) where they wait for 30 minutes (.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months )

LEWA dose:

10 mR/hr X .5 hr =

5 mR Venting time is 12 minutes (.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months )

Area dose: 40 mR/hr X .2 hr = 8 mR Total amount of dose received =

5 mR + 8 mR =

1 3 mR STANDARD: Applicant determines the total amount of dose received for the evolution to be 13 mR. This step is critical to meet the task requirements and standard for this JPM to determine the total amount of dose received.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.3 May 2016 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 0F 6 STEP 2 Determine the latest clock time that venting could complete without exceeding RWP dose requirements:

The RWP limits total exposure to 25 mR 25 mR - 5 mR (LEWA dose) = 20 mR left for venting 20 mR ÷ 40 mR/hr = .

5 hr (30 minutes) 0830 + 30 = 0900 STANDARD: Applicant determines the latest time that venting could complete to meet the RWP dose requirement is 0900.

This step is critical to meet the task requirements and standard for this JPM to determine the latest time that venting could complete without exceeding RWP dose requirements.

COMMENTS:

END OF TASK CRITICAL STEP ___ SAT ___UNSAT STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is in AP/1/A/5500/019 (Loss of Residual Heat Removal)

The CRS has dispatched you to 1A ND pump room to vent the 1A ND pump casing when directed.

You are to stage yourself where you can minimize your dose while waiting.

The following is the timeline for the venting evolution:

0800 - You enter 1A ND Pump Room.

0830 - You are directed to vent using 1ND

-88 (1A ND Pump Seal Water Hx Inlet Vent).

0842 - Venting is complete. You immediately exit the room and report back to the Control Room.

INITIATING CUES:

Based on the above time line, RWP # 5021, and Survey Maps provided and discounting any dose received during transit:

1. State the amount of dose that was received for the duration of the task.

Amount of dose received

- ________________

mR

2. Assuming you entered the room and began venting at the above stated times, determine the latest clock time that venting could complete without exceeding a limit imposed by the applicable task of RWP 5021.

Latest clock time for venting without exceeding the MAXIMUM Dose listed on the applicable task of RWP 5021

- ___________ .

CATAWBA NUCLEAR STATIONMONTHLY ROUTINE SURVEY SHEET

//HIGHEST GA*:HIGHEST CONTACT*:HIGHEST dpm/100cm 2:HIGHEST MASSLINN CCPM:*Radiation readings in mRem/hr unless otherwise noted.LEGEND:LEWA= LOW EXPOSURE WAITING AREA HS= HOT SPOT --x----x----x--= RCZ BOUNDARY= DIRECT= GENERAL= CONTACT= SMEAR= MASSLINN

.FRISK(dpm/100cm 2)Comments:RWP#15(initials)Instrument/#(s) Counter/#:PERFORMED BY:DATE/TIME:(print name)(initials)Reviewed By:

N FF 54 You Are Here T.Cabe 03-02 Room 105 ND Pump 1 A AREA> 10 40 1 ND-88 LEWA CATAWBA NUCLEAR STATIONMONTHLY ROUTINE SURVEY SHEET

//HIGHEST GA*:HIGHEST CONTACT*:HIGHEST dpm/100cm 2:HIGHEST MASSLINN CCPM:*Radiation readings in mRem/hr unless otherwise noted.LEGEND:LEWA= LOW EXPOSURE WAITING AREA HS= HOT SPOT --x----x----x--= RCZ BOUNDARY= DIRECT= GENERAL= CONTACT= SMEAR= MASSLINN

.FRISK(dpm/100cm 2)Comments:RWP#15(initials)Instrument/#(s)PERFORMED BY:DATE/TIME:(print name)(initials)Reviewed By:

You Are Here Counter/#:ND-8 8 INFORMATIONCatawba Nuclear StationINFORMATIONUSE ONLYRadiation Work PermitUSE ONLYAUX BUILDING ENTRY INTO PENTRATION ROOMS HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMSRWP # 5021Rev: 11Task # 1AUX BUILDING ENTRY INTO PENTRATION ROOMS, HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMS ED Alarm Set Points:Dose Alarm: 25 mremDose Rate Alarm: 50 mrem/h rRWP RequirementsDress Category/Work Description

Dress Category "F" 1. Complete protection of skin and clothing is NOT required. 2. Radioactive material is handled and/or transported ANDthe potential for loose surface contamination >1000 dpm/100cm2 exists AND durability of surgical gloves is sufficient.

E Dress Category "G" Entry into dry contaminated areas <25,000 dpm/100cm2 with NO climbing or physical / strenuous work. NO brushing,grinding, lapping, etc. is allowed.

Dress Category "H" Entry into dry contaminated areas <25,000 dpm/100cm2 with NO climbing or physical / strenuous work. NO brushing,grinding, lapping, etc. is allowed.

Dress Category "I" Work in dry contaminated areas <50,000 dpm/100cm2 with a risk of puncturing or tearing gloves or beta dose concerns to the hands. Work may involve brushing, grinding, lapping, etc. (1) (3) (4)

Dress Category "N" Wet work, hot particle controls are required or work in highly contaminated areas. Work may involve brushing, grinding,lapping, etc. (1)

Dress Category "Z" Special dress. See Additional Instructions.

Modesty garments, top & bottom, are required under protective clothing where personal outer clothing is not worn

(1) Cloth coverall are acceptable for use when allowed by RP. Gloves and booties must be secured (e.g. taped, elastic cuff) when wearingcloth coveralls

(2) IF double SOP is not used when wearing double PCs, remove the outer layers at the source

(3) Skull caps may be substituted for a hood when approved by RP and NO hands on work is to be performed.

(4) For activities requiring crawling, kneeling, etc., review need for additional barrier to prevent contamination events, e.g., additional protective clothing, knee pads, use of floor covering, etc.Protective Clothing

F - Lab coat, glove liners, rubber gloves OR surgical gloves, booties and shoe covers

G - Hood, coveralls, glove liners and rubber gloves, booties, and shoe covers over personal clothing (NO modesty clothing required).*H - Hood, coveralls, glove liners and rubber gloves, booties and shoe covers, NO personal outer clothing.

I - Hood, coveralls, glove liners, 2 pair rubber gloves, booties and shoe covers, no personal outer clothing.

N - Hood, coveralls, water resistant/water proof suit, glove liners, 2 pair rubber gloves, booties, 2 pair shoe covers, no personal outer clothing.

Z - Special dressContamination Control

Wipe down AND bag all tools and equipment prior to removal from a contaminated area as directed by RP

Utilize facial protection (e.g. face shield, hood sock, power visor) as directed by RP

Install catch containments OR drain rigs to prevent spills if draining components

If installing a drain rig, use hose clamps to secure hose OR tubing connections

If installing a drain rig, secure hose OR tubing to floor drain

Wear disposable (plastic) booties inside of orex booties for work in wet conditions

Change outer rubber gloves often when handling highly contaminated material as directed by RP Approved on 09/29/2014 by CAMPBELL, KENNETH CPrinted on 03/05/2015Activated on 09/29/2014 INFORMATIONCatawba Nuclear StationINFORMATIONUSE ONLYRadiation Work PermitUSE ONLYAUX BUILDING ENTRY INTO PENTRATION ROOMS HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMSRWP # 5021Rev: 11Task # 1AUX BUILDING ENTRY INTO PENTRATION ROOMS, HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMS ED Alarm Set Points:Dose Alarm: 25 mremDose Rate Alarm: 50 mrem/h rRWP Requirements

Use surgical gloves in lieu of rubber gloves for the manipulation of small or specialty items as directed by RP RP Job Coverage

Start of Job, Intermittent or No Coverage In Radiation Areas or Less

RP Coverage Required To Transport Material > 5 mrem/hr at 30 cm

Pre-job briefing required

Continuous RP Coverage for aggressive work in Alpha Level III areas or Alpha Level II areas with beta-gamma to alpha ratios less than 3000:

1 or where conditions could changeDosimetry Requirements

Monitor ED periodically while inside the RCA/RCZ (once or twice per hour in low dose rate areas). Monitor more frequently in higher dose rate areas, for example ever y 10 to 15 minutes.

If dress requirements prevent the monitoring of ED, and RP is not remotely monitoring (via teledose & communications), place ED external to the outmost layer of protective clothing for monitoringRespiratory Protection

If weighted DAC-Hours are expected to result in greater than or equal to 4 DAC-Hours per person, perform a TEDE/ALARA evaluation*Full Face Particulate (Additional Hood Required) IF warranted by TEDE ALARA Evaluation OR directed by RP

Personal (lapel) air samplers required for Alpha Level III areas or Alpha Level II areas with beta-gamma to alpha ratios of less than 3000:1RP Hold Points

Breaching Contaminated System

RP Survey Required Prior to Handling Debris or Foreign Material*RP survey required after removal of items from contaminated systems. Decon may be necessary (as directed by RP)

Notify RP prior to reaching OR entry into the overhead (8 feet and above)

Accumulated Dose Higher than Expected

Notify RP Prior to Start of Work

A change in Alpha Level (AL I to AL II or AL III; AL II to AL III) requires additional planning for alpha considerationsStop Work Criteria*Dose Alarm*Unexpected dose rate alarm

Airborne conditions higher than expected

Actual dose rates are higher than the expected levels written on this RWP task

Actual contamination levels are higher than the expected levels written on this RWP task Approved on 09/29/2014 by CAMPBELL, KENNETH CPrinted on 03/05/2015Activated on 09/29/2014 INFORMATIONCatawba Nuclear StationINFORMATIONUSE ONLYRadiation Work PermitUSE ONLYAUX BUILDING ENTRY INTO PENTRATION ROOMS HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMSRWP # 5021Rev: 11Task # 1AUX BUILDING ENTRY INTO PENTRATION ROOMS, HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMS ED Alarm Set Points:Dose Alarm: 25 mremDose Rate Alarm: 50 mrem/h rRWP Requirements

Unexpected wet conditions*Work scope changes

If monitoring of the ED indicates that the dose alarm set point will be exceeded prior to completing the job, leave the area and contact RP. Do not wait to receive an alarm before exiting the area

Failure of OR sweat soaked protective clothingExpected Radiological ConditionsExpected radiological conditions

General Area Dose Rates: <0.1 mrem/hr - 50 mrem/hrHigh Contact Dose Rates: <0.1 mrem/hr - 1000 mrem/hrContamination Levels: < 1000dpm/100cm2-100,000dpm/100cm2Additional InstructionsElectronic Dosimeter rate alarms are established based on general area dose rates. If personnel are positioned in close proximity to primary piping and equipment they may anticipate receiving a dose rate alarm.Z Dress - Orex Coveralls only. This is for use in clean areas only due to potential for contamination from wearing a fall harne ss.Approved on 09/29/2014 by CAMPBELL, KENNETH CPrinted on 03/05/2015Activated on 09/29/2014 INFORMATIONCatawba Nuclear StationINFORMATIONUSE ONLYRadiation Work PermitUSE ONLYAUX BUILDING ENTRY INTO PENTRATION ROOMS HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMSRWP # 5021Rev: 11 Task # HIGH RADIATION AREA AUX BUILDING ENTRY INTO PENTRATION ROOMS, HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMSED Alarm Set Points:

Dose Alarm:

mremDose Rate Alarm: 100 mrem/h rHigh Radiation Area EntryRWP RequirementsDress Category/Work Description

Dress Category "F" 1. Complete protection of skin and clothing is NOT required. 2. Radioactive material is handled and/or transported ANDthe potential for loose surface contamination >1000 dpm/100cm2 exists AND durability of surgical gloves is sufficient.

E Dress Category "G" Entry into dry contaminated areas <25,000 dpm/100cm2 with NO climbing or physical / strenuous work. NO brushing,grinding, lapping, etc. is allowed.

Dress Category "H" Entry into dry contaminated areas <25,000 dpm/100cm2 with NO climbing or physical / strenuous work. NO brushing,grinding, lapping, etc. is allowed.

Dress Category "I" Work in dry contaminated areas <50,000 dpm/100cm2 with a risk of puncturing or tearing gloves or beta dose concerns to the hands. Work may involve brushing, grinding, lapping, etc. (1) (3) (4)

Dress Category "N" Wet work, hot particle controls are required or work in highly contaminated areas. Work may involve brushing, grinding,lapping, etc. (1)

Dress Category "Z" Special dress. See Additional Instructions.*(1) Cloth coverall are acceptable for use when allowed by RP. Gloves and booties must be secured (e.g. taped, elastic cuff) when wearingcloth coveralls

(2) IF double SOP is not used when wearing double PCs, remove the outer layers at the source

(3) Skull caps may be substituted for a hood when approved by RP and NO hands on work is to be performed.*(4) For activities requiring crawling, kneeling, etc., review need for additional barrier to prevent contamination events, e.g., additional protective clothing, knee pads, use of floor covering, etc.Protective Clothing

F - Lab coat, glove liners, rubber gloves OR surgical gloves, booties and shoe covers

G - Hood, coveralls, glove liners and rubber gloves, booties, and shoe covers over personal clothing (NO modesty clothing required).*H - Hood, coveralls, glove liners and rubber gloves, booties and shoe covers, NO personal outer clothing.*I - Hood, coveralls, glove liners, 2 pair rubber gloves, booties and shoe covers, no personal outer clothing.

N - Hood, coveralls, water resistant/water proof suit, glove liners, 2 pair rubber gloves, booties, 2 pair shoe covers, no personal outer clothing.

Z - Special dressContamination Control

Wipe down AND bag all tools and equipment prior to removal from a contaminated area as directed by RP

Utilize facial protection (e.g. face shield, hood sock, power visor) as directed by RP

Install catch containments OR drain rigs to prevent spills if draining components*If installing a drain rig, use hose clamps to secure hose OR tubing connections

If installing a drain rig, secure hose OR tubing to floor drain

Wear disposable (plastic) booties inside of orex booties for work in wet conditions Approved on 09/29/2014 by CAMPBELL, KENNETH CPrinted on 03/05/2015Activated on 09/29/2014 INFORMATIONCatawba Nuclear StationINFORMATIONUSE ONLYRadiation Work PermitUSE ONLYAUX BUILDING ENTRY INTO PENTRATION ROOMS HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMSRWP # 5021Rev: 11 Task # HIGH RADIATION AREA AUX BUILDING ENTRY INTO PENTRATION ROOMS, HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMSED Alarm Set Points:

Dose Alarm:

mremDose Rate Alarm: 100 mrem/h rHigh Radiation Area EntryRWP Requirements*Change outer rubber gloves often when handling highly contaminated material as directed by RP

Use surgical gloves in lieu of rubber gloves for the manipulation of small or specialty items as directed by RPRP Job Coverage

Start of Job, Intermittent or No Coverage for work in High Radiation Areas or less

Start of Job, Intermittent or No Coverage In Radiation Areas or Less

RP Coverage Required To Transport Material > 5 mrem/hr at 30 cm

Pre-job briefing required

Continuous RP Coverage for aggressive work in Alpha Level III areas or Alpha Level II areas with beta-gamma to alpha ratios less than 3000:

1 or where conditions could changeDosimetry Requirements

An Auxiliary ED alarm is required in areas where general area dose rates are > 100 mrem/hr if any of the following conditions exis t:* 1. High noise level in the work area.* 2. Use of head phones* 3. Hearing impairment

4. Any other condition that would impair hearing an ED alarm

Monitor ED periodically while inside the RCA/RCZ (once or twice per hour in low dose rate areas). Monitor more frequently in higher dose rate areas, for example every 10 to 15 minutes.

If dress requirements prevent the monitoring of ED, and RP is not remotely monitoring (via teledose & communications), place ED external to the outmost layer of protective clothing for monitoringRespiratory Protection

If weighted DAC-Hours are expected to result in greater than or equal to 4 DAC-Hours per person, perform a TEDE/ALARA evaluation*Full Face Particulate (Additional Hood Required) IF warranted by TEDE ALARA Evaluation OR directed by RP

Personal (lapel) air samplers required for Alpha Level III areas or Alpha Level II areas with beta-gamma to alpha ratios of less than 3000:1RP Hold Points

Breaching Contaminated System

RP Survey Required Prior to Handling Debris or Foreign Material*RP survey required after removal of items from contaminated systems. Decon may be necessary (as directed by RP)*Notify RP prior to reaching OR entry into the overhead (8 feet and above)

Accumulated Dose Higher than Expected Approved on 09/29/2014 by CAMPBELL, KENNETH CPrinted on 03/05/2015Activated on 09/29/2014 INFORMATIONCatawba Nuclear StationINFORMATIONUSE ONLYRadiation Work PermitUSE ONLYAUX BUILDING ENTRY INTO PENTRATION ROOMS HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMSRWP # 5021Rev: 11 Task # HIGH RADIATION AREA AUX BUILDING ENTRY INTO PENTRATION ROOMS, HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMSED Alarm Set Points:

Dose Alarm:

mremDose Rate Alarm: 100 mrem/h rHigh Radiation Area EntryRWP Requirements*Notify RP Prior to Start of Work

RP Briefing Required Prior to Entering High Radiation Areas

A change in Alpha Level (AL I to AL II or AL III; AL II to AL III) requires additional planning for alpha considerationsStop Work Criteria*Dose Alarm*Unexpected dose rate alarm

Airborne conditions higher than expected*Actual dose rates are higher than the expected levels written on this RWP task

Actual contamination levels are higher than the expected levels written on this RWP task

Unexpected wet conditions*Work scope changes

If monitoring of the ED indicates that the dose alarm set point will be exceeded prior to completing the job, leave the area and contact RP. Do not wait to receive an alarm before exiting the area

Failure of OR sweat soaked protective clothingExpected Radiological ConditionsExpected radiological conditions: General Area Dose Rates: <0.1 mrem/hr - 500 mrem/hrHigh Contact Dose Rates: <0.1 mrem/hr - 3000 mrem/hrContamination Levels: < 1000 dpm/100cm2- 100,000 dpm/100cm2High Radiation Area ConditionsRoom 109- High Contact 1 - 2000 mrem/hr General Area 1 - 250 mrem/hr Contamination Levels: < 1000 dpm/100cm2- 100,000 dpm/100cm2Room 227 - High Contact 1 - 800 mrem/hr General Area 1 - 100 mrem/hr Contamination Levels: < 1000 dpm/100cm2- 100,000 dpm/100cm2Room 318 - High Contact 1 - 500 mrem/hr General Area 1 - 150 mrem/hr Contamination Levels: < 1000 dpm/100cm2- 100,000 dpm/100cm2Room 476/477 - High Contact 1 - 2500 mrem/hr General Area 1 - 200 mrem/hr Contamination Levels: < 1000 dpm/100cm2- 100,000 dpm/100cm2Room 467/468 - High Contact 1 - 2500 mrem/hr General Area 1 - 800 mrem/hr Contamination Levels: < 1000 dpm/100cm2- 100,000 dpm/100cm2 Approved on 09/29/2014 by CAMPBELL, KENNETH CPrinted on 03/05/2015Activated on 09/29/2014 INFORMATIONCatawba Nuclear StationINFORMATIONUSE ONLYRadiation Work PermitUSE ONLYAUX BUILDING ENTRY INTO PENTRATION ROOMS HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMSRWP # 5021Rev: 11 Task # HIGH RADIATION AREA AUX BUILDING ENTRY INTO PENTRATION ROOMS, HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMSED Alarm Set Points:

Dose Alarm:

mremDose Rate Alarm: 100 mrem/h rHigh Radiation Area EntryRWP RequirementsAdditional InstructionsElectronic Dosimeter rate alarms are established based on general area dose rates. If personnel are positioned in close proximity to primary piping and equipment they may anticipate receiving a dose rate alarm.Z Dress - Orex Coveralls only. This is for use in clean areas only due to potential for contamination from wearing a fall harne ss.Approved on 09/29/2014 by CAMPBELL, KENNETH CPrinted on 03/05/2015Activated on 09/29/2014 Catawba Nuclear Station Admin. JPM A.4 May 2016 NRC Exam PAGE 1 OF 9 JPM A.4 SRO

Catawba Nuclear Station Admin. JPM A.4 May 2016 NRC Exam PAGE 2 OF 9 EVALUATION SHEET Task: Determine Protective Action Recommendation per RP/0/A/5000/005 Alternate Path:

N/A Facility JPM #: N ew Safety Function:

N/A K/A 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.

Importance:

2.7 / 4.5 CFR: 41.10 / 43.5 / 45.11 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate References

RP/0/A/5000/001 (Classification of Emergency)

RP/0/A/5000/005 (General Emergency) Task Standard:

Applicant determines correct Protective Action Recommendation for General Emergency with Rapidly Progressing Severe Accident (RPSA) within 15 minutes by determining Zones A0, E1, and F1 must be evacuated and Zones E2, F2, and F3 must be sheltered in place.

Validation Time:

1 0 minutes Time Critical:

Yes X No Applicant:

Time Start:

__________ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 9 Catawba Nuclear Station Admin. JPM A.1

-1 May 2015 NRC Exam PAGE 3 OF 9 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 was performing a rapid downpower as a result of high Reactor Coolant activity when 1B S/G experienced a tube rupture. Current conditions are as follows:

The unit 1 Reactor was manually tripped from the Control Room 5 minutes ago.

Safety Injection was manually initiated and both trains are in service.

Following the Reactor trip, 1SV-13 (S/G 1B PORV) failed open. 1SV-28A (1B S/G PORV Isol) failed to close.

The most recent Chemistry sample results indicate Unit 1 DEI of 322 µCi/cc

. NCS Subcooling indicates (-)16°F and stable

. 1EMF-53A indicates 386 R/hr.

1EMF-53B indicates 392 R/hr.

Upper wind direction (C1P0250) indicates 493.5 degrees A General Emergency has been declared per RP/0/A/5000/001 (Classification of Emergency)

INITIATING CUES:

Determine initial Protective Action Recommendations (PARs) for this event per Step 2.3 of RP/0/A/5000/005 (General Emergency).

This JPM is time critical. Clock will begin upon acknowledgement of the task.

EXAMINER NOTE

Provide a copy of RP/0 5 complete through step 2.2.2 and a copy of RP/0/A/5000/001, Enclosure 4.1. This JPM is required to be completed within 15 minutes.

Catawba Nuclear Station Admin. JPM A.

4 May 201 6 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 4 0F 9 START TIME: _______

STEP 1: 2.3 Make Initial Protective Action Recommendations (PAR) on Line 5 of the Emergency Notification Form per .3, page 2 of 3.

STANDARD: Candidate refers to the flow chart contained on Page 2 of Enclosure 4.3 COMMENTS:

___ SAT

___ UNSAT STEP 2: STANDARD: Candidate determines that a GE has been declared from initial conditions

. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.

4 May 201 6 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 0F 9 STEP 3: STANDARD: Candidate refers to Note 2 for clarification

. COMMENTS: ___ SAT

___ UNSAT STEP 4: Note 2: RPSA criteria:

Only Applicable to First PAR after GE Declaration AND two of the following exist from RP/0/A/5000/001:

STANDARD: Candidate determines that this is the first PAR

, per provided information

, and proceeds to listed criteria.

COMMENTS:

___ SAT ___ UNSAT Catawba Nuclear Station Admin. JPM A.

4 May 201 6 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 0F 9 STEP 5: 1. LOSS of Primary Containment Barrier per RP/0/5000/001, Enclosure 4.1.

STANDARD: Candidate refers to the initiating cue and RP/01 to determine that the 1B S/G Tube Rupture combined with the failure of 1B S/G PORV and associated isolation valve results in "Release of secondary side to environment with primary to secondary leakage GREATER THAN Tec h Spec allowable" which constitutes a Loss of Containment Barrier. The applicant continues to Step 2 of the RPSA criteria.

This step is critical to ensure that the candidate correctly determines PARs. If the candidate does not recognize a loss of Containment has occurred, assuming the GE was declared based on a loss of RCS and Fuel Clad barrier combined with a potential loss of Containment, the incorrect determination will be made.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.

4 May 201 6 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 0F 9 STEP 6: 2. POTENTIAL LOSS of Containment Barrier per Containment Radiation Monitor EMF53A or EMF53B per RP/0/A/5000/001, Enclosure 4.1.

OR There is a significant radiological release projected to exceed PAGs (4.3.G.1 EAL) at the site boundary within an hour. (IF RPSA condition can NOT be confirmed, THEN answer NO)

STANDARD: Candidate refers to the initiating cue and RP/01 to determine that 1EMF-53B exceeds the criteria listed for the "associated time after shutdown" AND recognizes that only one EMF reading above this value is required to result in a Potential Loss of the Containment Barrier. The candidate determines that this is a RPSA (Yes) and proceeds in the flow chart.

This step is critical to ensure that the candidate correctly determines PARs. If the candidate does not recognize a Potential Loss of Containment has also occurred, the incorrect determination will be made. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.

4 May 201 6 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 0F 9 STEP 7: Note 1: For all PARs, affected Protective Action Zones (Zones) are defined in Enclosure 4.2, Page 3 of 3.

STANDARD: Candidate will subtract 360 degrees from the listed wind direction per Notes 2 & 3 listed on Page 2 of Enclosure 4.2.

493.5 - 360 = 133.5 degrees Candidate with then refer to Table 1 (Line 123.76

- 146.25) and determine the following PARs:

Evacuate: A0, E1, F1 Shelter: E2, F2, F3 This step is critical to ensure that the candidate correctly determines PARs. EXAMINER NOTE

Additional items contained within the flowchart will not assist with obtaining the proper PAR. Offsite dose projections are not available and proceeding would not apply for the initial recommendation.

COMMENTS:

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 was performing a rapid downpower as a result of high Reactor Coolant activity when 1B S/G experienced a tube rupture. Current conditions are as follows:

The unit 1 Reactor was manually tripped from the Control Room 5 minutes ago.

Safety Injection was manually initiated and both trains are in service.

Following the Reactor trip, 1SV-13 (S/G 1B PORV) failed open. 1SV-28A (1B S/G PORV Isol) failed to close.

The most recent Chemistry sample results indicate Unit 1 DEI of 322 µCi/cc

. NCS Subcooling indicates (-)16°F and stable

. 1EMF-53A indicates 386 R/hr.

1EMF-53B indicates 392 R/hr.

Upper wind direction (C1P0250) indicates 493.5 degrees A General Emergency has been declared per RP/0/A/5000/001 (Classification of Emergency)

INITIATING CUES:

Determine initial Protective Action Recommendations (PARs) for this event per Step 2.3 of RP/0/A/5000/005 (General Emergency). This JPM is time critical. Clock will begin upon acknowledgement of the task.

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