ML17241A216

301 ADAMS2B Final Exam Items Delay Release

ML17241A216
Person / Time
Site:	Catawba
Issue date:	08/29/2017
From:	NRC/RGN-II
To:	Duke Energy Corp
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Download: ML17241A216 (788)

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Catawba Nuclear Station NRC Exam June 2017 2017 INITIAL LICENSE NRC EXAM SCENARIO # 1 Scenario #1 Catawba 2017 NRC Exam Page 1 of 139

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Facility: Catawba NRC Exam 2017 Scenario No.: 1 Op Test No.: 2017301 Examiners: Operators: SRO RO BOP Initial Conditions: Unit 1 is at 75% power at the EOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 75% power at the EOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. 1A Condensate Booster Pump is tagged out for emergent motor replacement. Direction for the crew is to decrease reactor power to 50% to secure a main feedwater pump in preparation for entering a Unit 1 Refueling Outage. A reactivity plan has been provided by Reactor Engineering for a 10% per hour decrease in reactor power.

Event Event Event Malf. No.

No. Type* Description R - RO 1 N - BOP Decrease reactor power N - SRO C - BOP 2 CM004F 1B CFPT suction valve fails closed / 1B CFPT fails to auto trip C - SRO C - RO 3 NC005F C - SRO NC PORV 1NC-32B fails open TS - SRO C - BOP 4 NV020D 1A NV pump trips TS - SRO IPX001A C - RO 5 1A CFPT trips / Reactor fails to automatically trip IPX001B C - SRO CA005 6 M - ALL Loss of Secondary Heat Sink EP008B EP008B 7 C - RO 1ETB Blackout / CAPT #1 fails to autostart CA005 C - BOP 8 NI001A 1A NI pump fails to auto start on initiation of Feed and Bleed C - SRO

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario #1 Catawba 2017 NRC Exam Page 2 of 139

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Scenario 1 - Summary Initial Condition Unit 1 is at 75% power at the EOL. Unit 2 is at 100% power.

Turnover:

Unit 1 is at 75% power at the EOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. 1A Condensate Booster Pump is tagged out for emergent motor replacement. Direction for the crew is to decrease reactor power to 50% to secure a main feedwater pump in preparation for entering a Unit 1 Refueling Outage. A reactivity plan has been provided by Reactor Engineering for a 10% per hour decrease in reactor power.

Event 1 BOP will perform an initial boration and RO will input desired load rate and target load into the main turbine. RO may also insert control rods prior to placing the main turbine in GO to initiate the power decrease at 10%/hour.

Event 2 The 1B CFPT suction valve (1CM-140) will fail closed. 1B CFPT will not trip on low suction pressure or low suction flow. Following manual trip of the 1B CFPT, the crew will enter AP/1/A/5500/003 (Load Rejection) Case 1 (Switchyard Available) to address the turbine runback.

Verifiable Action - BOP will manually trip 1B CFPT.

Event 3 NC PORV 1NC-32B will fail open. Crew will enter AP/1/A/5500/011 (Pressurizer Pressure Anomalies) to address this failure.

Verifiable Action - The RO will attempt to manually close 1NC-32B. This valve will not close and the RO will be required to close the PORV isolation valve, 1NC-31B, to isolate the failed open PORV.

Event 4 1A NV pump will trip. The crew will enter AP/1/A/5500/012 (Loss of Charging or Letdown) to address this failure.

Verifiable Action - BOP will start the 1B NV pump and restore normal letdown to service per AP/1/A/5500/012.

Event 5 A trip of the running Condensate Booster Pumps will cause 1A CFPT to trip on low suction pressure after 20 seconds. The RO will take the immediate actions of AP/1/A/5500/006 (Loss of S/G Feedwater) to manually trip Unit 1 reactor.

Verifiable Action - RO trips Unit 1 reactor.

Event 6 A loss of secondary heat sink will occur following loss of all power to 1ETB (1A CA pump tagged out & 1B CA pump loss of power) and subsequent overspeed trip of CAPT #1.

Verifiable Action - RO will start CAPT #1 following failure of it to autostart. Crew will eventually enter EP/1/A/5000/FR-H.1 (Loss of Secondary Heat Sink), and establish NC system feed and bleed.

Event 7 1ETB will lose all power and CAPT #1 will fail to autostart on the blackout.

Verifiable Action - RO will manually start CAPT #1.

Scenario #1 Catawba 2017 NRC Exam Page 3 of 139

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Event 8 NI pumps will fail to autostart upon initiation of S/I for establishing NC system feed and bleed.

Verifiable Action - BOP initiates S/I, will reset ECCS and D/G load sequencer for A train and manually start 1A NI pump, and then open 2 Pressurizer PORVs.

Critical Task 1 - Manually isolate failed open Pressurizer PORV (1NC-32B) prior to any RPS actuation.

Critical Task 2 - Manually trip the reactor from the control room prior to S/G dryout conditions

(<12% W/R level) occurs on any S/G.

Critical Task 3 - Initiate Reactor Coolant System Bleed and Feed before Pressurizer PORVs 1NC-34A and 1NC-36B open automatically (NC system pressure of 2335 PSIG) due to heat up of the NC system.

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

1. Total malfunctions (5-8) 6

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) 1

7. Critical tasks (2-3) 3 Scenario #1 Catawba 2017 NRC Exam Page 4 of 139

Catawba Nuclear Station NRC Exam June 2017 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC # 170 and load schedule file for NRC Scenario 1 START TIME:__________

Trigger Instructor Action Delete Final Delay Ramp Event In VLV-CM004F (CM140 COND CF 2 PMP 1B SUCTION ISOL FAIL TO 0 :20 2 POSITION)

BST-JFB5940B (2/3 LO SUCT 2 AS_IS 2 FLOW CFPT B TRIP)

BST-JFB5943B (2/3 LO SUCT 2 AS_IS 2 FLOW CFPT B TRIP)

BST-JPB5972 (2/3 LO SUCT 2 AS_IS 2 PRESS CFPT B TRIP) - PS BST-JPB5973 (2/3 LO SUCT 2 AS_IS 2 PRESS CFPT B TRIP) - PS ANN-AD19-F04 (YN CRITICAL 3 ON 3 TROUBLE)

VLV-NC005F (NC32B PZR PORV 10 1 3 FAIL TO POSITION) 4 OVR-NV020D (NV PMP 1A OFF PB) ON 4 RACK-5 LOA-CM040 (RACKOUT CBP 1B) 5 OUT RACK-5 LOA-CM041 (RACKOUT CBP 1C) 5 OUT RACK-LOA-CM039 (RACKOUT CBP 1A) 5 OUT MAL-IPX001A (AUTO REACTOR ACTIVE 5 TRIP FAILURE TRN A)

MAL-IPX001B (AUTO REACTOR ACTIVE 5 TRIP FAILURE TRN B)

MAL-CA005 (CA PUMP MECH-6 OVERSPEED TRIP) ANICAL MAL-EP008B (LOSS OF 4160V 7 ACTIVE :10 7 BUS ETB)

MAL-NI001A (NI PUMP A AUTO 8 FAILURE)

LOA-CA017 (RACKOUT CA PUMP RACK-1A) OUT Scenario #1 Catawba 2017 NRC Exam Page 5 of 139

Catawba Nuclear Station NRC Exam June 2017 11 OVR-NV020D (NV PMP 1A OFF PB) OFF :01 13 LOA-CNT002 (H2 ANALYZERS) BOTH 10:00 VLV-NC004C (NC31B PZR PORV 15 ACTIVE 10:00 ISOL VLV FAIL PWR)

LOA-NV078 (SEAL WATER LOW 17 FLOW LCL REFLASH ACK ACKN 5:00 (AD7,C4))

Ensure EVENT 7 = jpplp4(1) jpplp4(2) (Reactor Trip Either Train)

Ensure EVENT 10 = x5ri017a (1AD-19 Acknowledge)

Ensure EVENT 11 = x11i197i Ensure control rods are placed in MANUAL Ensure Red Collar is placed on 1A Condensate Booster Pump Ensure Red Collar is placed on 1A CA Pump Ensure all Pressurizer heaters are on for mixing Scenario #1 Catawba 2017 NRC Exam Page 6 of 139

Catawba Nuclear Station NRC Exam June 2017

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 50%

BOOTH INSTRUCTOR ACTION IF contacted as SOC by the crew to inform of commencing power decrease, REPEAT the information.

3.3 Scenario EVENT 2, 1B CFPT suction valve 1CM-140 fails closed with failure of 1B CFPT to trip automatically BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 2 to cause 1B CFPT suction valve 1CM-140 to fail closed.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1CM-140, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF an AO is contacted to complete shutdown of the CHDPs, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as the SOC reporting on runback of Unit 1, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection to sample and analyze gaseous effluents referring to SLC 16.11-6, REPEAT the information.

Scenario #1 Catawba 2017 NRC Exam Page 7 of 139

Catawba Nuclear Station NRC Exam June 2017 BOOTH INSTRUCTOR ACTION IF contacted as Primary Chemistry to sample for isotopic analysis of iodine between 2-6 hours following a power change of > 15% in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period referring to Tech Spec 3.4.16, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF contacted as Reactor Engineering to report on Unit 1 runback, REPEAT the information.

3.4 Scenario EVENT 3, NC PORV 1NC-32B Fails Open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause an HVAC Panel Trouble Alarm. Once this alarm is acknowledged on 1AD-19, NC PORV 1NC-32B will fail open.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1NC-32B, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF an AO or the Unit Supervisor is contacted to create a clearance to remove power from 1NC-31B, REPEAT the information and INSERT Trigger 15.

After 10 minutes, contact the control room and REPORT Power has been removed from 1NC-31B.

3.5 Scenario EVENT 4, 1A NV Pump Trip BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 4 to cause 1A NV Pump Trip.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1A NV Pump, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as an AO to perform a post start check of 1B NV pump, REPEAT the information.

After 5 minutes, contact the crew and REPORT 1B NV pump looks good for continued operation.

BOOTH INSTRUCTOR ACTION When AP-12 Case 2 Step 16.k (WHEN 5 minutes has elapsed)is read, call the control room and REPORT Using time compression, 5 minutes has elapsed.

Scenario #1 Catawba 2017 NRC Exam Page 8 of 139

Catawba Nuclear Station NRC Exam June 2017 BOOTH INSTRUCTOR ACTION IF contacted as an AO to acknowledge seal water low flow alarm on reflash panel 1, REPEAT the information and INSERT Trigger 17.

After 5 minutes, contact the crew and REPORT Seal Water Low Flow alarm has been acknowledged.

3.6 Scenario EVENT 5, Trip of Running Condensate Booster Pumps BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to cause a trip of the running condensate booster pumps.

3.7 Scenario EVENTS 6, 7, 8, Loss of Heat Sink, 1ETB Blackout, and NI Pumps Fail to Autostart On Initiation of Bleed and Feed BOOTH INSTRUCTOR ACTION IF the SWM is contacted to expedite the return of 1A CA pump, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF an AO is contacted to locally reset the Trip and Throttle valve, REPEAT the information.

After 10 minutes, REPORT The trip and throttle valve is mechanically bound and cannot be reset.

BOOTH INSTRUCTOR ACTION IF AO is dispatched to place the containment H2 Analyzers in service per OP/1/A/6450/010, REPEAT the information and INSERT Trigger 13.

After 10 minutes contact the crew and REPORT Ice Condenser Air Handling Units have been secured per G-1 Enclosure 11, and the H2 Analyzers have been placed in service per OP/1/A/6450/010.

BOOTH INSTRUCTOR ACTION IF an AO is contacted to restore power to 1NC-31B (1EMXD-F02C), REPEAT the information.

Scenario #1 Catawba 2017 NRC Exam Page 9 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 10 of 139 Event

Description:

Power Reduction To 50%

Note To Evaluator:

The scenario begins with a power decrease to 50% by the crew. This will involve several procedures to accomplish. The following procedures are included in this guide:

OP/1/A/6150/009 Enclosure 4.2 (Boration)

OP/1/A/6150/008 Enclosure 4.16 (Control Bank Manual Operation At Power)

OP/0/B/6300/001 Enclosure 4.2 (Load Changing)

These procedures may be performed in any order by the crew. Instructions for continuing to the next Event are included at the end of OP/0/B/6300/001 Enclosure 4.2.

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Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 11 of 139 Event

Description:

Power Reduction To 50%

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Description:

Power Reduction To 50%

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Description:

Power Reduction To 50%

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Description:

Power Reduction To 50%

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Description:

Power Reduction To 50%

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Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 16 of 139 Event

Description:

Power Reduction To 50%

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Description:

Power Reduction To 50%

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Description:

Power Reduction To 50%

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Description:

Power Reduction To 50%

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Description:

Power Reduction To 50%

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Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 21 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Control Room Indications 1AD-5, D/4 CFP B LOW SUCT FLOW - LIT 1AD-5, F/5 CFP B LOW SUCT PRESS - LIT CF PUMP 1B Suction pressure on 1CMP5970 decreasing CF PUMP 1B Suction flow on 1CMP5940 decreasing GREEN CLSD light LIT and RED OPEN light DARK on 1CM-140 Note To Evaluator:

Normally 20 seconds after receiving a low suction pressure or flow on a CFPT, that CFPT will trip. Both of these trips are blocked for 1B CFPT for this scenario, so the crew will be required to manually trip 1B CFPT. Once this occurs the crew will transition to AP/1/A/5500/003 (Load Rejection) Case 1 (Switchyard Available). This procedure begins on the following page.

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Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 22 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Scenario #1 Catawba 2017 NRC Exam Page 22 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 23 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Scenario #1 Catawba 2017 NRC Exam Page 23 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 24 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Scenario #1 Catawba 2017 NRC Exam Page 24 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 25 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Scenario #1 Catawba 2017 NRC Exam Page 25 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 26 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Scenario #1 Catawba 2017 NRC Exam Page 26 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 27 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Scenario #1 Catawba 2017 NRC Exam Page 27 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 28 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Scenario #1 Catawba 2017 NRC Exam Page 28 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 29 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Scenario #1 Catawba 2017 NRC Exam Page 29 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 30 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Scenario #1 Catawba 2017 NRC Exam Page 30 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 31 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Scenario #1 Catawba 2017 NRC Exam Page 31 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 32 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Scenario #1 Catawba 2017 NRC Exam Page 32 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 33 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Scenario #1 Catawba 2017 NRC Exam Page 33 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 34 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Scenario #1 Catawba 2017 NRC Exam Page 34 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 35 of 139 Event

Description:

1B CFPT Suction Valve Fails Closed With Failure of 1B CFPT To Trip Automatically Scenario #1 Catawba 2017 NRC Exam Page 35 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 36 of 139 Event

Description:

NC PORV 1NC-32B Fails Open Control Room Indications 1AD-13, F/5 HVAC PANEL TROUBLE - LIT (This is the only initial alarm until the alarm panel is acknowledged on 1AD Then the following alarms and indications are noted) 1AD-6, D/10 PZR LO PRESS PORV NC32 & 36 BLOCKED - LIT 1AD-6, D/11 PZR LO PRESS PORV NC34 BLOCKED - LIT 1AD-6, E/10 PZR PORV DISCH HI TEMP - LIT 1AD-6, F/8 PZR LO PRESS CONTROL - LIT Pressurizer Pressure Channels on 1MC-10 decreasing Scenario #1 Catawba 2017 NRC Exam Page 36 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 37 of 139 Event

Description:

NC PORV 1NC-32B Fails Open Scenario #1 Catawba 2017 NRC Exam Page 37 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 38 of 139 Event

Description:

NC PORV 1NC-32B Fails Open Scenario #1 Catawba 2017 NRC Exam Page 38 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 39 of 139 Event

Description:

NC PORV 1NC-32B Fails Open Scenario #1 Catawba 2017 NRC Exam Page 39 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 40 of 139 Event

Description:

NC PORV 1NC-32B Fails Open Scenario #1 Catawba 2017 NRC Exam Page 40 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 41 of 139 Event

Description:

NC PORV 1NC-32B Fails Open Scenario #1 Catawba 2017 NRC Exam Page 41 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 42 of 139 Event

Description:

1A NV Pump Trip Control Room Indications 1AD-7, C/4 NCP SEAL WATER LO FLOW - LIT 1AD-7, E/1 CHARGING LINE HI/LO FLOW - LIT GREEN OFF light for 1A NV Pump - LIT Scenario #1 Catawba 2017 NRC Exam Page 42 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 43 of 139 Event

Description:

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Description:

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Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 5 Page 66 of 139 Event

Description:

Trip of Condensate Booster Pumps / 1A CFPT Trip On Low Suction Pressure Control Room Indications 1AD-5, B/4 CFPT A LO SUCT FLOW - LIT 1AD-5, E/5 CFP A LOW SUCT PRESS - LIT 1AD-5, A/1 CFPT A TRIPPED - LIT (After 20 second delay) 1AD-4, C/1-4 S/G A/B/C/D FLOW MISMATCH LO CF FLOW - LIT Scenario #1 Catawba 2017 NRC Exam Page 66 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 5 Page 67 of 139 Event

Description:

Trip of Condensate Booster Pumps / 1A CFPT Trip On Low Suction Pressure Scenario #1 Catawba 2017 NRC Exam Page 67 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 68 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Note To Evaluator:

Once the reactor is tripped, a blackout of 1ETB will occur. CAPT#1 will fail to start automatically, requiring the crew to manually start it to feed the S/Gs. Once started, it will experience a mechanical overspeed trip. Once S/G levels all decrease to below 11% N/R, a transition to FR-H.1 will occur. Crew will immediately transition to steps to initiate NC system Feed and Bleed due to no NV pumps being available. Once S/I is initiated, the 1A NI pump will fail to start requiring the crew to reset S/I and the D/G load sequencer and manually starting the 1A NI pump. The 1A NV pump will also start when S/I is initiated.

Scenario #1 Catawba 2017 NRC Exam Page 68 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 69 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 69 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 70 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 70 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 71 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 71 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 72 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 72 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 73 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 73 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 74 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 74 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 75 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 75 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 76 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 76 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 77 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 77 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 78 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 78 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 79 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 79 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 80 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 80 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 81 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 81 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 82 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 82 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 83 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 83 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 84 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 84 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 85 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 85 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 86 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 86 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 87 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 87 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 88 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 88 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 89 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 89 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 90 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 90 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 91 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 91 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 92 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 92 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 93 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 93 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 94 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 94 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 95 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 95 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 96 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 96 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 97 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 97 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 98 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 98 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 99 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 99 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 100 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 100 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 101 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 101 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 102 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 102 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 103 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 103 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 104 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 104 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 105 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 105 of 139

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6, 7, 8 Page 106 of 139 Event

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 106 of 139

Attachment List Scenario 1 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - AP/1/A/5500/003 Enclosure 3 (Rod Insertion Limit Boration)

ATTACHMENT 4 - AP/1/A/5500/012 Enclosure 3 (Control Room Ventilation System Verification)

ATTACHMENT 5 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page)

ATTACHMENT 6 - EP/1/A/5000/ES-0.1 Enclosure 1 (Foldout Page)

ATTACHMENT 7 - EP/1/A/5000/ES-0.1 Enclosure 2 (NC Temperature Control)

ATTACHMENT 8 - EP/1/A/5000/G-1 Enclosure 16 (Control Room Ventilation Verification)

ATTACHMENT 9 - EP/1/A/5000/FR-H.1 Enclosure 1 (Foldout Page)

ATTACHMENT 10 - EP/1/A/5000/FR-H.1 Enclosure 4 (System Verification Following S/I Actuation)

ATTACHMENT 11 - EP/1/A/5000/FR-H.1 Enclosure 9 (System Verification Following S/I Actuation)

Scenario #1 Catawba 2017 NRC Exam Page 107 of 139

ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK Manually isolate failed open Pressurizer PORV (1NC-32B) 1 prior to any RPS actuation.

Manually trip the reactor from the control room prior to S/G 2

dryout conditions (W/R S/G level < 12%) occurs on any S/G.

Initiate Reactor Coolant System Bleed and Feed before 3 Pressurizer PORVs open automatically (NC system pressure of 2235 PSIG) due to heat up of the NC system.

Comments:

Scenario #1 Catawba 2017 NRC Exam Page 108 of 139

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 75 % EOL 177 PPM per OAC Controlling Procedure OP/1/A/6100/003 (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 EOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. 1A Condensate Booster Pump is tagged out for emergent motor replacement.

Direction for the crew is to decrease reactor power to 50% to secure a main feedwater pump in preparation for entering a Unit 1 Refueling Outage. A reactivity plan has been provided by Reactor Engineering for a 10% per hour decrease in reactor 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Scenario #1 Catawba 2017 NRC Exam Page 109 of 139

ATTACHMENT 3 Scenario #1 Catawba 2017 NRC Exam Page 110 of 139

ATTACHMENT 4 Scenario #1 Catawba 2017 NRC Exam Page 111 of 139

ATTACHMENT 4 Scenario #1 Catawba 2017 NRC Exam Page 112 of 139

ATTACHMENT 4 Scenario #1 Catawba 2017 NRC Exam Page 113 of 139

ATTACHMENT 5 Scenario #1 Catawba 2017 NRC Exam Page 114 of 139

ATTACHMENT 5 Scenario #1 Catawba 2017 NRC Exam Page 115 of 139

ATTACHMENT 6 Scenario #1 Catawba 2017 NRC Exam Page 116 of 139

ATTACHMENT 7 Scenario #1 Catawba 2017 NRC Exam Page 117 of 139

ATTACHMENT 7 Scenario #1 Catawba 2017 NRC Exam Page 118 of 139

ATTACHMENT 7 Scenario #1 Catawba 2017 NRC Exam Page 119 of 139

ATTACHMENT 7 Scenario #1 Catawba 2017 NRC Exam Page 120 of 139

ATTACHMENT 7 Scenario #1 Catawba 2017 NRC Exam Page 121 of 139

ATTACHMENT 7 Scenario #1 Catawba 2017 NRC Exam Page 122 of 139

ATTACHMENT 8 Scenario #1 Catawba 2017 NRC Exam Page 123 of 139

ATTACHMENT 8 Scenario #1 Catawba 2017 NRC Exam Page 124 of 139

ATTACHMENT 8 Scenario #1 Catawba 2017 NRC Exam Page 125 of 139

ATTACHMENT 9 Scenario #1 Catawba 2017 NRC Exam Page 126 of 139

ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 127 of 139

ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 128 of 139

ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 129 of 139

ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 130 of 139

ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 131 of 139

ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 132 of 139

ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 133 of 139

ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 134 of 139

ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 135 of 139

ATTACHMENT 11 Scenario #1 Catawba 2017 NRC Exam Page 136 of 139

ATTACHMENT 11 Scenario #1 Catawba 2017 NRC Exam Page 137 of 139

ATTACHMENT 11 Scenario #1 Catawba 2017 NRC Exam Page 138 of 139

ATTACHMENT 11 Scenario #1 Catawba 2017 NRC Exam Page 139 of 139

Catawba Nuclear Station NRC Exam June 2017 2017 INITIAL LICENSE NRC EXAM SCENARIO # 2 Scenario #2 Catawba 2017 NRC Exam Page 1 of 136

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Facility: Catawba NRC Exam 2017 Scenario No.: 2 Op Test No.: 2017301 Examiners: Operators: SRO RO BOP Initial Conditions: Unit 1 is at 100% power at the MOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 100% power at the MOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Direction for the crew is to initiate a VQ release from A train by completing the in-progress OP/1/A/6450/017 (Containment Air Release and Addition System) Enclosure 4.2 (Air Release Mode).

Event Event Event Malf. No.

No. Type* Description N - BOP 1 VQ Release N - SRO C - BOP 2 SLIM05_02 Letdown Heat Exchanger Temperature Control Valve (1KC-132) Failure C - SRO C - RO 3 SM002B S/G PORV (1SV-13) Fails Open C - SRO TS-SRO R - RO EP006C 4 N - BOP 1B GPCB Trip / No Auto Rods IRX009 TS - SRO NC013D C - BOP 5 ISE008A C - SRO NC System Leak (SH Failure - Secure VQ)

ISE008B TS -SRO 6 NC013D M - ALL LBLOCA ISE002A 7 C - BOP SI Fails to Automatically Actuate ISE002B 8 CF006A C - RO 1CF-33 (S/G 1A CF Cont Isol) Fails to Close on Feedwater Isolation ND001A 9 C - BOP ND Pumps Fail to Auto Start ND001B

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario #2 Catawba 2017 NRC Exam Page 2 of 136

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Scenario 2 - Summary Initial Condition Unit 1 is at 100% power at the MOL. Unit 2 is at 100% power.

Turnover:

Unit 1 is at 100% power at the MOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Direction for the crew is to initiate a VQ release from A train by completing the in-progress OP/1/A/6450/017 (Containment Air Release and Addition System) Enclosure 4.2 (Air Release Mode).

Event 1 Initiate VQ Release.

Event 2 Letdown Heat Exchanger Temperature Control Valve (1KC-132) setpoint increases causing 1KC-132 to close and causing a letdown heat exchanger outlet high temperature alarm.

Verifiable Action - BOP will take 1KC-132 to manual and throttle it open to decrease letdown temperature. If letdown temperature exceeds 136F, then letdown heat exchanger outlet three way valve (1NV-153A) will fail to go to the VCT position (will continue flow to NV demineralizers) and the BOP will be required to manually align to the VCT.

Event 3 1B S/G PORV (1SV-13) will fail open. Crew may enter AP/1/A/5500/028 (Secondary Steam Leak) for guidance to isolate the leak. Alternatively, the crew may use OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines) guidance to address failure.

Verifiable Action - The RO will close 1SV-28A (S/G 1B PORV Isol) to isolate the leak. RO may decrease turbine generator load to maintain reactor power < 100%.

Event 4 1B Main Generator Breaker (GEN BKR 1B) will spuriously open resulting in a turbine runback. Control Rods will fail to automatically insert. Crew will enter AP/1/A/5500/003 (Load Rejection), Case I (Switchyard Available).

Verifiable Action - OATC will manually insert Control Rods as required. BOP will borate to restore Control Rod Insertion limits. SRO will address Tech Specs.

Event 5 A Primary Coolant system leak will develop inside containment. Crew will enter AP/1/A/5500/010 (Reactor Coolant Leak), Case II (NC System Leak). Containment Ventilation Isolation Signal (SH) will fail to actuate on high containment radiation level (EMF-38, 39).

Verifiable Action - BOP will adjust charging to maintain Pressurizer level. BOP will secure Containment Air Release (VQ). SRO will address Tech Specs.

Event 6 A Large Break LOCA will occur. Crew will enter EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) and transition to EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant).

Verifiable Action - RO will manually trip the reactor. BOP will manually initiate Safety Injection.

Event 7 Safety Injection will fail to automatically actuate on High Containment Pressure or Low Pressurizer Pressure.

Scenario #2 Catawba 2017 NRC Exam Page 3 of 136

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Verifiable Action - BOP will manually actuate both trains of Safety Injection Event 8 1CF-33 (S/G 1A CF Cont Isol) fails to automatically close on Feedwater Isolation Signal.

Verifiable Action - RO will manually close valve.

Event 9 Both ND Pumps will fail to automatically start on Safety Injection initiation.

Verifiable Action -SRO will direct reset of D/G sequencer and ECCS. BOP will manually start 1A and 1B ND Pumps.

Critical Task 1 - Manually actuate at least one train of SIS-actuated safeguards before transition to E-1 occurs (E-0 Step 27 RNO d).

Critical Task 2 - Manually start at least one low-head ECCS pump before transition out of E-0 (E-0 Step 27 RNO d).

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) 3

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. Critical tasks (2-3) 2 Scenario #2 Catawba 2017 NRC Exam Page 4 of 136

Catawba Nuclear Station NRC Exam June 2017 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC # 158 and load Schedule file for Scenario 2.

START TIME:__________

Trigger Instructor Action Delete Final Delay Ramp Event In MAL-SLIM05_02 (1NVSS5590 KC- Button 2 132 Raise Setpoint Pushbutton fail Depress- :10 2 to position) ed VLV-NV035A (NV153A L/D HX ACTIVE 2 DIVERSION FAIL AUTO ACTIONS)

MAL-SM002B (S/G PORV SV13 3 100 3 FAILURE)

OVR-EP006B (GEN BKR 1B TRIP 4 ON 4 ENABLE PB)

OVR-EP006C (GEN BKR 1B TRIP 4 ON 4 PB)

MAL-IRX009 (RODS FAIL TO AUTO 4 MOVE)

MAL-NC013D (NC COLD LEG D 5 0.2 5 LEAK)

MAL-ISE008A (AUTO CNT VENT BLOCK 5 SIGNAL TRN A)

MAL-ISE008B (AUTO CNT VENT BLOCK 5 SIGNAL TRN B)

MAL-NC013D (NC COLD LEG D 6 27.5 6 LEAK)

MAL-ISE002A (AUTO SI TRN A ACTIVE 7 FAILS TO ACTUATE)

MAL-ISE002B (AUTO SI TRN B ACTIVE 7 FAILS TO ACTUATE)

VLV-CF006A (CF33 CF CONT ISOL ACTIVE 8 VLV 1CF033 FAIL AUTO ACTIONS)

MAL-ND001A (ND PUMP A AUTO 9 FAILURE)

MAL-ND001B (ND PUMP B AUTO 9 FAILURE)

LOA-CA017 (RACKOUT CA PUMP RACK-1A) OUT 10 LOA-CNT002 H2 ANALYZERS BOTH 10:00 Scenario #2 Catawba 2017 NRC Exam Page 5 of 136

Catawba Nuclear Station NRC Exam June 2017 Ensure Red Collar is placed on 1A CA Pump

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, Initiate VQ Release 3.3 Scenario EVENT 2, Letdown Heat Exchanger temperature control valve (1KC-132) failure BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 2 to cause 1KC-132 to slowly close.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1KC-132 or 1NV-153A, REPEAT the information.

3.4 Scenario EVENT 3, 1B S/G PORV (1SV-13) Fails Open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause 1B S/G PORV (1SV-13) to fail open.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1SV-13, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection notifying of steam leak from 1SV-13 failing open, REPEAT the information.

3.5 Scenario EVENT 4, Generator Breaker 1B Trip Scenario #2 Catawba 2017 NRC Exam Page 6 of 136

Catawba Nuclear Station NRC Exam June 2017 BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 4 to cause Generator Breaker 1B to trip open.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for Generator Breaker 1B or control rods failing to insert, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as an AO to complete shutdown of the CHDPs, REPEAT the information..

BOOTH INSTRUCTOR ACTION IF contacted as the SOC reporting on runback of Unit 1, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection to sample and analyze gaseous effluents referring to SLC 16.11-6, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as Primary Chemistry to sample for isotopic analysis of iodine between 2-6 hours following a power change of > 15% in a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period referring to Tech Spec 3.4.16, REPEAT back the information.

BOOTH INSTRUCTOR ACTION IF contacted as Reactor Engineering reporting on runback of Unit 1, REPEAT the information.

3.6 Scenario EVENT 5, NC System Leak BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to cause an NC System Leak on loop 1D.

BOOTH INSTRUCTOR ACTION IF contacted as Reactor Engineering reporting on need for shutdown of Unit 1, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as Station Management for further actions, REPORT Once further actions are required, station management will contact the control room.

3.7 Scenario EVENT 6, Large Break LOCA Scenario #2 Catawba 2017 NRC Exam Page 7 of 136

Catawba Nuclear Station NRC Exam June 2017 BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 6 to cause a Large Break LOCA on loop 1D.

BOOTH INSTRUCTOR ACTION IF contacted as an AO to secure all ice condenser AHUs per G-1 Enclosure 11 and to place the H2 Analyzers in service per OP/1/A/6450/010, REPEAT the information and INSERT Trigger 10.

After 10 minutes, contact the control room and REPORT All ice condenser AHUs have been secured per G-1 Enclosure 11 and the H2 Analyzers have been placed in service per OP/1/A/6450/010.

BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection to frisk all Unit 1 S/G cation columns for activity, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as Secondary Chemistry to sample all Unit 1 S/Gs for activity, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as an AO to secure both D/Gs and place them in standby readiness per the OP, REPEAT the information.

Scenario #2 Catawba 2017 NRC Exam Page 8 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 9 of 136 Event

Description:

Initiate a VQ Release Scenario #2 Catawba 2017 NRC Exam Page 9 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 10 of 136 Event

Description:

Initiate a VQ Release Scenario #2 Catawba 2017 NRC Exam Page 10 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 11 of 136 Event

Description:

Initiate a VQ Release Scenario #2 Catawba 2017 NRC Exam Page 11 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 12 of 136 Event

Description:

Initiate a VQ Release Scenario #2 Catawba 2017 NRC Exam Page 12 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 13 of 136 Event

Description:

Initiate a VQ Release Scenario #2 Catawba 2017 NRC Exam Page 13 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 14 of 136 Event

Description:

Initiate a VQ Release Scenario #2 Catawba 2017 NRC Exam Page 14 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 15 of 136 Event

Description:

Initiate a VQ Release Scenario #2 Catawba 2017 NRC Exam Page 15 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 16 of 136 Event

Description:

Initiate a VQ Release Scenario #2 Catawba 2017 NRC Exam Page 16 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 17 of 136 Event

Description:

Initiate a VQ Release Scenario #2 Catawba 2017 NRC Exam Page 17 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 18 of 136 Event

Description:

Initiate a VQ Release Scenario #2 Catawba 2017 NRC Exam Page 18 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 19 of 136 Event

Description:

Letdown Heat Exchanger Temperature Control Valve (1KC-132) Failure Control Room Indications 1AD-7, F/3 LETDN HX OUTLET HI TEMP - LIT 1KC-132 (Letdn Hx Otlt Temp Ctrl) closing Letdown temperature on 1NVPT5590 increasing Note To Evaluator:

The crew response for this failure can be found in the annunciator response for 1AD-7, F/3 on the following page. The failure is on the setpoint increase button on the controller for 1KC-132 and will delete after 10 seconds. The crew may either take manual control of 1KC-132 or may decrease the setpoint on the controller for 1KC-132 to increase cooling flow to the Letdown Heat Exchanger. If letdown temperature exceeds 136F, then letdown 3-way valve 1NV-153A should bypass the mixed bed demineralizers.

This is also failed, so crew may need to take 1NV-153A to the VCT position to manually bypass the demineralizers.

Scenario #2 Catawba 2017 NRC Exam Page 19 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 20 of 136 Event

Description:

Letdown Heat Exchanger Temperature Control Valve (1KC-132) Failure Scenario #2 Catawba 2017 NRC Exam Page 20 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 21 of 136 Event

Description:

1B S/G PORV (1SV-13) Fails Open Control Room Indications OAC Alarm for 1SV OPEN Main Steam Header Pressure - DECREASING Turbine Generator Electrical Load - DECREASING Reactor Power - INCREASING RED OPEN light for 1SV LIT Note To Evaluator:

Crew may decide to invoke OMP 1-7 guidance to isolate a known leak and not enter AP/28 (Secondary Steam Leak). AP/28 is included in this guide beginning on the following page.

Scenario #2 Catawba 2017 NRC Exam Page 21 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 22 of 136 Event

Description:

1B S/G PORV (1SV-13) Fails Open Scenario #2 Catawba 2017 NRC Exam Page 22 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 23 of 136 Event

Description:

1B S/G PORV (1SV-13) Fails Open Scenario #2 Catawba 2017 NRC Exam Page 23 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 24 of 136 Event

Description:

1B S/G PORV (1SV-13) Fails Open Scenario #2 Catawba 2017 NRC Exam Page 24 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 25 of 136 Event

Description:

1B S/G PORV (1SV-13) Fails Open Scenario #2 Catawba 2017 NRC Exam Page 25 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 26 of 136 Event

Description:

1B S/G PORV (1SV-13) Fails Open Scenario #2 Catawba 2017 NRC Exam Page 26 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 27 of 136 Event

Description:

1B S/G PORV (1SV-13) Fails Open Scenario #2 Catawba 2017 NRC Exam Page 27 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 28 of 136 Event

Description:

1B S/G PORV (1SV-13) Fails Open Scenario #2 Catawba 2017 NRC Exam Page 28 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 29 of 136 Event

Description:

1B S/G PORV (1SV-13) Fails Open Scenario #2 Catawba 2017 NRC Exam Page 29 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 30 of 136 Event

Description:

1B S/G PORV (1SV-13) Fails Open Technical Specification 3.4.7, Condition A, was added to form ES-D-2 for this event.

Scenario #2 Catawba 2017 NRC Exam Page 30 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 31 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Control Room Indications 1AD-11, C/1 GEN BKR A OVER CURRENT - LIT 1AD-1, D/6 EHC SYSTEM FAULT - LIT 1AD-1, F/4 TURB RUNBACK INITIATED - LIT Turbine Generator MW output - RAPIDLY DECREASING Reactor Power - DECREASING Scenario #2 Catawba 2017 NRC Exam Page 31 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 32 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 32 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 33 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 33 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 34 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 34 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 35 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 35 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 36 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 36 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 37 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 37 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 38 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 38 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 39 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 39 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 40 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 40 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 41 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 41 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 42 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 42 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 43 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 43 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 44 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 44 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4 Page 45 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 45 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 46 of 136 Event

Description:

NC System Leak Control Room Indications 1RAD-1, A/1 1EMF-38 CONTAINMENT PART HI RAD - LIT 1RAD-1, B/1 1 EMF 39 CONTAINMENT GAS HI RAD - LIT Pressurizer Level - DECREASING Pressurizer Pressure - DECREASING Containment Floor and Equipment Sump Levels - INCREASING Scenario #2 Catawba 2017 NRC Exam Page 46 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 47 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 47 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 48 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 48 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 49 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 49 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 50 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 50 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 51 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 51 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 52 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 52 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 53 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 53 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 54 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 54 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 55 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 55 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 56 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 56 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 57 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 57 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 58 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 58 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 59 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 59 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 60 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 60 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 61 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 61 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 62 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 62 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 63 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 63 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 5 Page 64 of 136 Event

Description:

NC System Leak Scenario #2 Catawba 2017 NRC Exam Page 64 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 65 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Control Room Indications 1FO-1, D/5 HI CONT PRESS S/I RX TRIP - LIT DRPI Rod Bottom Lights - LIT Pressurizer Level - DECREASING RAPIDLY Pressurizer Pressure - DECREASING RAPIDLY Neutron Flux Level - DECREASING RAPIDLY Scenario #2 Catawba 2017 NRC Exam Page 65 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 66 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 66 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 67 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 67 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 68 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 68 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 69 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 69 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 70 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 70 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 71 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 71 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 72 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 72 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 73 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 73 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 74 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 74 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 75 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 75 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 76 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 76 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 77 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 77 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 78 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 78 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 79 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 79 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 80 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 80 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 81 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 81 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 82 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 82 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 83 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 83 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 84 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 84 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 85 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 85 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 86 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 86 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 87 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 87 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 88 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 88 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 89 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 89 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 90 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 90 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 91 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 91 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 92 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 92 of 136

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 6, 7, 8, 9 Page 93 of 136 Event

Description:

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 93 of 136

Attachment List Scenario 2 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - AP/1/A/5500/015 Case I (Failure Of Rods To Move)

ATTACHMENT 4 - AP/1/A/5500/028 Enclosure 1 (Foldout Page)

ATTACHMENT 5 - AP/1/A/5500/003 Enclosure 3 (Rod Insertion Limit Boration)

ATTACHMENT 6 - AP/1/A/5500/010 Enclosure 2 (Case II NC System Leak Foldout Page)

ATTACHMENT 7 - AP/1/A/5500/010 Enclosure 11 (Control Room Ventilation System Verification)

ATTACHMENT 8 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page)

ATTACHMENT 9 - EP/1/A/5000/E-0 Enclosure 5 (VX System Operation)

ATTACHMENT 10 - EP/1/A/5000/E-0 Enclosure 2 (Control Room Ventilation Verification)

ATTACHMENT 11 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control)

ATTACHMENT 12 - EP/1/A/5000/G-1 Enclosure 1 (Spent Fuel Pool Monitoring)

ATTACHMENT 13 - EP/1/A/5000/E-1 Enclosure 1 (Foldout Page)

Scenario #2 Catawba 2017 NRC Exam Page 94 of 136

ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK Manually actuate at least one train of SIS-actuated 1 safeguards before transition to E-1 occurs (E-0 Step 27 RNO d).

2 Manually start at least one low-head ECCS pump before transition out of E-0 (E-0 Step 27 RNO d).

Comments:

Scenario #2 Catawba 2017 NRC Exam Page 95 of 136

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 100 % MOL 860 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 for 100% power are complete.

Other Information Needed to Assume the Shift Unit 1 is at 100% power at the MOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Direction for the crew is to initiate a VQ release from A train by completing the in-progress OP/1/A/6450/017 (Containment Air Release and Addition System)

Enclosure 4.2 (Air Release Mode).

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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Catawba Nuclear Station NRC Exam June 2017 2017 INITIAL LICENSE NRC SCENARIO # 3 Scenario #3 Catawba 2017 NRC Exam Page 1 of 171

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Facility: Catawba NRC Exam 2017 Scenario No.: 3 Op Test No.: 2017301 Examiners: Operators: SRO RO BOP Initial Conditions: Unit 1 is at 50% power at the EOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 50% power at the EOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Direction for the crew is to maintain present plant conditions.

Event Event Event Malf. No.

No. Type* Description C - RO 1 IDE003I Condenser Dump Valve (1SB-27) Failure C - SRO C - RO 2 EGB004C Voltage Regulator Failure C - SRO 3 KC027 C - BOP 1A2 KC Pump Trip TS - SRO C - BOP 4 SG001B 1B S/G Tube Leak / Automatic Blowdown Isolation Failure TS - SRO N - BOP 5 SG001B N - SRO AP/09 Rapid Downpower R - RO 6 SG001B M - ALL 1B S/G Tube Rupture ISE007A 7 C - RO CF Isolation Failure ISE007B 8 ISE038 C - BOP B Train Phase A Isolation Failure

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario #3 Catawba 2017 NRC Exam Page 2 of 171

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Scenario 3 - Summary Initial Condition Unit 1 is at 50% power at the EOL. Unit 2 is at 100% power.

Turnover:

Unit 1 is at 50% power at the EOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Direction for the crew is to maintain present plant conditions.

Event 1 1SB-27 (SM Byp to Cond Ctrl #27) will fail open. Crew may enter AP/1/A/5500/028 (Secondary Steam Leak) for guidance to isolate the leak. Alternatively, the crew may use OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines) guidance to address failure.

Verifiable Action - The RO will place Steam Dump Control switches to Off-Reset.

Event 2 A failure on the Unit 1 Voltage Regulator will cause Generator Voltage to increase until the limiter becomes active and stops the increase. Crew may enter AP/1/A/5500/037 (Generator Voltage and Electric Grid Disturbances) Case I (Abnormal Generator or Grid Voltage).

Verifiable Action - The RO will manually decrease voltage back to the requirements of the voltage schedule .

Event 3 1A2 KC pump will trip. Crew will enter AP/1/A/5500/021 (Loss of Component Cooling Water) and start an available KC pump.

Verifiable Action - BOP will start an available KC pump.

Event 4 1B S/G Tube leak will develop. 1B S/G Blowdown will fail to isolate on 1EMF-33 (Condenser Air Ejector)

Trip 2 actuation. Crew will enter AP/1/A/5500/010 (Reactor Coolant Leak), Case I (NC System Leak).

Verifiable Action - BOP will manually isolate 1B S/G Blowdown, re-align condenser air ejector offgas to filtered ventilation, and adjust charging to maintain Pressurizer level. SRO will address Tech Specs.

Event 5 Crew will begin a rapid downpower per AP/1/A/5500/009 (Rapid Downpower) due to the SGTL.

Verifiable Action - RO will input a Target and Load Rate into the turbine control panel and place the Main Turbine in GO. BOP will perform a boration for a normal evolution.

Event 6 1B S/G Tube Leak will transition to a Rupture. Crew will enter EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) and transition to EP/1/A/5000/E-3 (Steam Generator Tube Rupture)

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

Event 7 Both trains of Automatic Feedwater Isolation will fail to actuate on Safety Injection.

Verifiable Action - RO will manually actuate A and B Train Main Feedwater Isolation.

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Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Event 8 Phase A Isolation (Train B) will fail to automatically initiate on Safety Injection signal.

Verifiable Action - BOP will manually initiate B train Phase A Isolation signal.

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 (1125 PSIG) or safety (prior to S/G NR level reaching 100% and an associated S/G PORV (1125 PSIG) or Safety Valve open).

Critical Task 4 - Start a KC pump prior to any NCP motor bearing temperature exceeding 195°F.

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. Critical tasks (2-3) 3 Scenario #3 Catawba 2017 NRC Exam Page 4 of 171

Catawba Nuclear Station NRC Exam June 2017 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC # 23 and load Schedule for Scenario 3.

START TIME:__________

ü ü Trigger Instructor Action Delete Final Delay Ramp Event In MAL-IDE003I (STEAM DUMP VLV 1 100 :05 1 SB27 FAIL TO POSITION)

MAL-IDE003I (STEAM DUMP VLV 10 100 :01 1 SB27 FAIL TO POSITION) 12 LOA-IDE009 (SB26 - INLET ISOL) 0 5:00 :05 1 OVR-EGB004C (VOLTAGE 2 ON :10 2 ADJUST RAISE PB)

LOA-KC028 (RACKOUT KC PMP RACK-3 3 1A2) OUT 4 MAL-SG001B (S/G B TUBE LEAK) 75 :30 4 VLV-BB002 (BB73-S/G B BLOWDOWN CTRL VLV FAIL ACTIVE 4 AUTO ACTIONS) 6 MAL-SG001B (S/G B TUBE LEAK) 400 :30 6 MAL-ISE007A (AUTO CF ISOL BLOCK 7 SIGNAL TRN A)

MAL-ISE007B (AUTO CF ISOL BLOCK 7 SIGNAL TRN B)

MAL-ISE003B (AUTO PHASE A BLOCK 8 ISOL SIGNAL TRN B)

LOA-CA017 (RACKOUT CA PUMP RACK-1A) OUT LOA-CA011 (SA3 - S/G 1B TO 14 0 4:30 :30 CAPT ISOL)

Ensure EVENT 10 = x02i184l x02i186l (Steam Dump Select OFF Either Train)

Ensure Red Collar is placed on 1A CA Pump Scenario #3 Catawba 2017 NRC Exam Page 5 of 171

Catawba Nuclear Station NRC Exam June 2017

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, Condenser Dump Valve (1SB-27) Fails Open

ü BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 1 to cause Condenser Dump Valve (1SB-27) to fail open.

ü BOOTH INSTRUCTOR ACTION IF contacted as an AO or Unit Supervisor to create a clearance to isolate 1SB-27, REPEAT the information and INSERT Trigger 12.

After 5 minutes, contact the control room and REPORT 1SB-26 is manually closed to isolate 1SB-27.

ü BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate a W/R and NCR for 1SB-27, REPEAT the information.

ü BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection notifying of steam leak from 1SB-27 failing open, REPEAT the information.

3.3 Scenario EVENT 2, Generator Voltage Regulator Failure

ü BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 2 to cause a Generator Voltage Regulator Failure.

ü BOOTH INSTRUCTOR ACTION IF contacted as TCC to monitor Real Time Contingency Analysis and report the results to the Control Room Supervisor, REPEAT the information.

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ü BOOTH INSTRUCTOR ACTION IF contacted as SOC asking for voltage requirement, REPORT Adjust voltage per the voltage operating schedule.

3.4 Scenario EVENT 3, 1A2 KC Pump Trip

ü BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause 1A2 KC pump to trip.

ü BOOTH INSTRUCTOR ACTION IF contacted as AO to perform a post start checkout of the KC pump, after 3 minutes REPORT KC pump____ looks good for continued operation.

ü BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1A2 KC pump, REPEAT the information.

ü BOOTH INSTRUCTOR ACTION IF contacted as Unit 2 control room to verify that one KC heat exchanger is aligned to provide miniflow for the RN system, REPORT 2B KC heat exchanger outlet mode switch is in MINIFLOW.

3.5 Scenario Event 4, 1B S/G Tube Leak / Automatic BB isolation failure

ü BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 4 to cause a 1B S/G Tube Leak.

ü BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection to frisk all Unit 1 S/G cation columns for activity, REPEAT the information.

ü BOOTH INSTRUCTOR ACTION IF contacted as Secondary Chemistry to sample all Unit 1 S/Gs for activity, REPEAT the information.

ü BOOTH INSTRUCTOR ACTION IF contacted as Secondary Chemistry to inform of CM polishing demineralizers being bypassed, REPEAT the information.

ü BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection to notify of current size of the leak and to perform HP/0/B/1009/003, REPEAT the information.

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ü BOOTH INSTRUCTOR ACTION IF contacted as Engineering to notify of the S/G Tube Leak, REPEAT the information.

3.6 Scenario Event 5, Rapid Downpower 3.7 Scenario Events 6, 7, 8, 1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure

ü BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 6 to cause a 1B S/G Tube Rupture.

ü BOOTH INSTRUCTOR ACTION If dispatched as an AO to unlock and close 1SA-1, REPEAT the information and INSERT Trigger 14.

After 5 minutes, contact the control room and REPORT 1SA-1 is unlocked and closed.

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Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 9 of 171 Event

Description:

Condenser Dump Valve (1SB-27) Fails Open Note To Evaluator:

At the discretion of the Lead Evaluator, the scenario may begin by having the booth operator INSERT Trigger 1 for Event 1 (Condenser Dump Valve 1SB-27 Fails Open). The crew may elect to invoke OMP 1-7 guidance to isolate a known leak and elect to not enter AP/28 (Steam Leak). AP/28 actions are included in this guide beginning on the next page.

Control Room Indications OAC Alarm for 1SB OPEN Main Steam Header Pressure - DECREASING Turbine Generator Electrical Load - DECREASING Reactor Power - INCREASING RED OPEN light for 1SB LIT Scenario #3 Catawba 2017 NRC Exam Page 9 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 10 of 171 Event

Description:

Condenser Dump Valve (1SB-27) Fails Open Scenario #3 Catawba 2017 NRC Exam Page 10 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 11 of 171 Event

Description:

Condenser Dump Valve (1SB-27) Fails Open Scenario #3 Catawba 2017 NRC Exam Page 11 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 12 of 171 Event

Description:

Condenser Dump Valve (1SB-27) Fails Open Scenario #3 Catawba 2017 NRC Exam Page 12 of 171

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Description:

Condenser Dump Valve (1SB-27) Fails Open Scenario #3 Catawba 2017 NRC Exam Page 13 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 14 of 171 Event

Description:

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Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 15 of 171 Event

Description:

Condenser Dump Valve (1SB-27) Fails Open Scenario #3 Catawba 2017 NRC Exam Page 15 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 16 of 171 Event

Description:

Condenser Dump Valve (1SB-27) Fails Open Scenario #3 Catawba 2017 NRC Exam Page 16 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 17 of 171 Event

Description:

Condenser Dump Valve (1SB-27) Fails Open Scenario #3 Catawba 2017 NRC Exam Page 17 of 171

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Description:

Condenser Dump Valve (1SB-27) Fails Open Scenario #3 Catawba 2017 NRC Exam Page 18 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 2 Page 19 of 171 Event

Description:

Generator Voltage Regulator Failure Control Room Indications OAC alarm for Generator Voltage High Generator Voltage - INCREASING Scenario #3 Catawba 2017 NRC Exam Page 19 of 171

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Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 30 of 171 Event

Description:

1A2 KC Pump Trips Control Room Indications Indicating lights for 1A2 KC pump - DARK 1AD-11, A/1 4KV ESS PWR TRAIN A TROUBLE - LIT Various KC low flow alarms on the main control boards KC discharge pressure and flow decreasing Scenario #3 Catawba 2017 NRC Exam Page 30 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 31 of 171 Event

Description:

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Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 47 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Control Room Indications 1RAD-1, B/1 1EMF-33 CSAE EXHAUST HI RAD - LIT 1RAD-1, B/5 1EMF-72 S/G B LEAKAGE HI RAD - LIT 1RAD-1, C/1 1EMF-73 S/G C LEAKAGE HI RAD - LIT EMF Module for 1EMF-33, 1EMF-72, and 1EMF-73 Trip 2 lights - LIT OAC point C1P0187 (Estimated Total Pri To Sec Leakrate) - INCREASING Pressurizer Level indication - DECREASING Scenario #3 Catawba 2017 NRC Exam Page 47 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 48 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 48 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 49 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 49 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 50 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 50 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 51 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 51 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 52 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 52 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 53 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 53 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 54 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 54 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 55 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 55 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 56 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Technical Specification 3.4.18, Condition B, was added to form ES-D-2 for this event.

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Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 57 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 57 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 58 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 58 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 59 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 59 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 60 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 60 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 61 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 61 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 62 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 62 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 63 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 63 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 64 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 64 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 65 of 171 Event

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate Scenario #3 Catawba 2017 NRC Exam Page 65 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 66 of 171 Event

Description:

Rapid Downpower Scenario #3 Catawba 2017 NRC Exam Page 66 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 67 of 171 Event

Description:

Rapid Downpower Scenario #3 Catawba 2017 NRC Exam Page 67 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 68 of 171 Event

Description:

Rapid Downpower Scenario #3 Catawba 2017 NRC Exam Page 68 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 69 of 171 Event

Description:

Rapid Downpower Scenario #3 Catawba 2017 NRC Exam Page 69 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 70 of 171 Event

Description:

Rapid Downpower Scenario #3 Catawba 2017 NRC Exam Page 70 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 71 of 171 Event

Description:

Rapid Downpower Scenario #3 Catawba 2017 NRC Exam Page 71 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 72 of 171 Event

Description:

Rapid Downpower Scenario #3 Catawba 2017 NRC Exam Page 72 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 73 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Control Room Indications 1RAD-3, E/5 1EMF26, 27, 28, 29, S/G A, B, C, D STEAM LINE - LIT EMF Module for 1EMF-27 Trip 2 light - LIT Pressurizer Level indication - DECREASING RAPIDLY Scenario #3 Catawba 2017 NRC Exam Page 73 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 74 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 74 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 75 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 75 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 76 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 76 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 77 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 77 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 78 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 78 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 79 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 79 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 80 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 80 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 81 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 81 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 82 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 82 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 83 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 83 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 84 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 84 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 85 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 85 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 86 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 86 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 87 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 87 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 88 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 88 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 89 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 89 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 90 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 90 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 91 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 91 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 92 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 92 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 93 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 93 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 94 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 94 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 95 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 95 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 96 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 96 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 97 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 97 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 98 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 98 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 99 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 99 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 100 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 100 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 101 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 101 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 102 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 102 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 103 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 103 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 104 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 104 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 105 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 105 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 106 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 106 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 107 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 107 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 108 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 108 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 109 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 109 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 110 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 110 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 111 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 111 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 112 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 112 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 113 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 113 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 114 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 114 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 115 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 115 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 116 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 116 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 117 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 117 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 118 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 118 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 119 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 119 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 120 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 120 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 121 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 121 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 122 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 122 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 123 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 123 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 124 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 124 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 125 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 125 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 126 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 126 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 127 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 127 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 128 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 128 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 129 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 129 of 171

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6, 7, 8 Page 130 of 171 Event

Description:

1B S/G Tube Rupture / CF Isolation Failure / B Train Phase A Failure Scenario #3 Catawba 2017 NRC Exam Page 130 of 171

Attachment List Scenario 3 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - AP/1/A/5500/028 Enclosure 1 (Foldout Page)

ATTACHMENT 4 - AP/1/A/5500/021 Enclosure 1 (Foldout Page)

ATTACHMENT 5 - AP/1/A/5500/037 Enclosure 1 (Unit 1 Generator Capability Curves)

ATTACHMENT 6 - AP/1/A/5500/010 Enclosure 1 (Case I S/G Tube Leak Foldout Page)

ATTACHMENT 7 - AP/1/A/5500/009 Enclosure 1 (Foldout Page)

ATTACHMENT 8 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page)

ATTACHMENT 9 - EP/1/A/5000/E-0 Enclosure 2 (Control Room Ventilation Verification)

ATTACHMENT 10 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control)

ATTACHMENT 11 - EP/1/A/5000/G-1 Enclosure 1 (Spent Fuel Pool Monitoring)

ATTACHMENT 12 - EP/1/A/5000/E-3 Enclosure 1 (Foldout Page)

ATTACHMENT 13 - OP/1/A/6150/009 Enclosure 4.2 (Boration)

Scenario #3 Catawba 2017 NRC Exam Page 131 of 171

ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK Isolate feedwater into and steam flow from the ruptured S/G 1

before a transition to ECA-3.1 occurs.

Establish/maintain an RCS temperature so that the 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 2

subcooling

• Below the RCS temperature that causes an extreme (Red Path) or a severe (Orange Path) challenge to the Subcriticality and/or Integrity status tree.

Depressurize RCS to meet S/I termination criteria before water release occurs from the ruptured S/G PORV or safety 3

(prior to S/G N/R level reaching 100% and an associated S/G PORV or Safety Valve open).

Start a KC pump prior to any NCP motor bearing 4

temperature exceeding 195°F.

Comments:

Scenario #3 Catawba 2017 NRC Exam Page 132 of 171

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 50 % EOL 256 PPM per OAC Controlling Procedure

• OP/1/A/6100/003 (Controlling Procedure for Unit Operation), Enclosure 4.1 (Power Increase).

The steps up through 3.50 are complete.

Other Information Needed to Assume the Shift

• Unit 1 is at 50% power at the EOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and is expected to be returned to service in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Direction for the crew is to maintain present plant conditions.

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Scenario #3 Catawba 2017 NRC Exam Page 133 of 171

ATTACHMENT 3 Scenario #3 Catawba 2017 NRC Exam Page 134 of 171

ATTACHMENT 3 Scenario #3 Catawba 2017 NRC Exam Page 135 of 171

ATTACHMENT 4 Scenario #3 Catawba 2017 NRC Exam Page 136 of 171

ATTACHMENT 4 Scenario #3 Catawba 2017 NRC Exam Page 137 of 171

ATTACHMENT 5 Scenario #3 Catawba 2017 NRC Exam Page 138 of 171

ATTACHMENT 6 Scenario #3 Catawba 2017 NRC Exam Page 139 of 171

ATTACHMENT 7 Scenario #3 Catawba 2017 NRC Exam Page 140 of 171

ATTACHMENT 7 Scenario #3 Catawba 2017 NRC Exam Page 141 of 171

ATTACHMENT 8 Scenario #3 Catawba 2017 NRC Exam Page 142 of 171

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ATTACHMENT 9 Scenario #3 Catawba 2017 NRC Exam Page 144 of 171

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ATTACHMENT 9 Scenario #3 Catawba 2017 NRC Exam Page 149 of 171

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ATTACHMENT 10 Scenario #3 Catawba 2017 NRC Exam Page 151 of 171

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ATTACHMENT 10 Scenario #3 Catawba 2017 NRC Exam Page 153 of 171

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ATTACHMENT 10 Scenario #3 Catawba 2017 NRC Exam Page 155 of 171

ATTACHMENT 11 Scenario #3 Catawba 2017 NRC Exam Page 156 of 171

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ATTACHMENT 12 Scenario #3 Catawba 2017 NRC Exam Page 164 of 171

ATTACHMENT 12 Scenario #3 Catawba 2017 NRC Exam Page 165 of 171

ATTACHMENT 13 Scenario #3 Catawba 2017 NRC Exam Page 166 of 171

ATTACHMENT 13 Scenario #3 Catawba 2017 NRC Exam Page 167 of 171

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ATTACHMENT 13 Scenario #3 Catawba 2017 NRC Exam Page 171 of 171

Catawba Nuclear Station NRC Exam June 2017 2017 INITIAL LICENSE NRC EXAM SCENARIO # 4 Scenario #4 Catawba 2017 NRC Exam Page 1 of 118

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Facility: Catawba NRC Exam 2017 Scenario No.: 4 Op Test No.: 2017301 Examiners: Operators: SRO RO BOP

-2 Initial Conditions: Unit 1 is at 7x10 % power at the BOL. Unit 2 is at 100% power.

-2 Turnover: Unit 1 is at 7x10 % power at the BOL. Unit 2 is at 100% power. 1A Condensate Booster Pump is tagged out for emergent motor replacement. Direction for the crew is to swap operating RN pumps by starting the 1B RN pump and securing the 1A RN pump per OP/0/A/6400/006 C (Nuclear Service Water System) Enclosure 4.7 (Starting/Securing Additional RN Pumps). Initial conditions have been verified. Chemistry has been notified of the RN pump lineup being changed and has informed operations that RN Chemical Addition system has been aligned to support the RN pump swap. The Unit 1 Cation Bed Demineralizer is not in service. Unit 2 Mixed bed demineralizers have been bypassed per step 3.2.2. Crew is to begin at step 3.2.1 of Enclosure 4.7. Following the RN pump swap, the crew is to withdraw control rods to increase reactor power to ~14 % in preparation for placing the Main Turbine online.

Event Event Event Malf. No.

No. Type* Description N - BOP 1 Swap RN pumps N - SRO 2 R - RO Increase reactor power C - RO 3 ENB008B C - SRO N36 Loss of Fission Chamber (Affects N32)

TS - SRO C - BOP 4A RL015 C RL Pump Trip C - SRO 4B SG004 TS-SRO 1A S/G N/R Level Channel 2 Fails High C - BOP 5 WL017D 1A NCDT Pump trip C - SRO C - RO 6 NCP003C 1C NC Pump High/High Vibration C - SRO EP003E 7 EQB005A M - ALL Loss of All AC Power EQB006A EQB005A 8 C - RO D/G Load Sequencers Fail To Actuate EQB006A RN003A RN003B C - BOP 9 RN Pump fails to start on power restoration RN003C C - SRO RN003D

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario #4 Catawba 2017 NRC Exam Page 2 of 118

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Scenario 4 - Summary Initial Condition

-2 Unit 1 is at 7x10 % power at the BOL. Unit 2 is at 100% power.

Turnover:

-2 Unit 1 is at 7x10 % power at the BOL. Unit 2 is at 100% power. 1A Condensate Booster Pump is tagged out for emergent motor replacement. Direction for the crew is to swap operating RN pumps by starting the 1B RN pump and securing the 1A RN pump per OP/0/A/6400/006 C (Nuclear Service Water System) Enclosure 4.7 (Starting/Securing Additional RN Pumps). Initial conditions have been verified. Chemistry has been notified of the RN pump lineup being changed and has informed operations that RN Chemical Addition system has been aligned to support the RN pump swap. The Unit 1 Cation Bed Demineralizer is not in service. Unit 2 Mixed bed demineralizers have been bypassed per step 3.2.2. Crew is to begin at step 3.2.1 of Enclosure 4.7. Following the RN pump swap, the crew is to withdraw control rods to increase reactor power to ~14 % in preparation for placing the Main Turbine online.

Event 1 BOP will perform OP/0/A/6400/006 C Enclosure 4.7 to swap operating RN pumps.

Event 2 The RO will withdraw control rods to establish a positive startup rate to increase reactor power.

Event 3 A loss of fission chamber will occur affecting both Intermediate Range channel N36 and Source Range channel N32. Crew will enter AP/1/A/5500/016 (Malfunction of Nuclear Instrumentation). SRO will address Tech Specs.

Verifiable Action - The RO will insert control rods to stabilize reactor power. The BOP will remove N32 and N36 from service.

Event 4A C Low Pressure Service Water (RL) pump will trip. Crew will enter AP/0/A/5500/038 (Loss of Conventional Low Pressure Service Water).

Verifiable Action - BOP will start A or B RL pump.

Event 4B Five (5) minutes following the C RL pump trip, 1A S/G N/R Level Channel 2 will fail High. SRO will address Tech Specs.

Event 5 1A NCDT pump will trip. Crew will use the Annunciator Response for 1AD-13 B/2 annunciator (NCDT Recirc Lo Flow) to start 1B NCDT pump.

Verifiable Action - BOP starts 1B NCDT pump.

Event 6 1C NC pump will have a high vibration develop. The crew will use the Annunciator Response for 1AD-6 B/5 annunciator (NCP Hi-Hi Vibration) to determine that a reactor trip is required, and once reactor power is < 5%, that 1C NC pump should be secured.

Verifiable Action - RO will trip Unit 1 reactor.

Scenario #4 Catawba 2017 NRC Exam Page 3 of 118

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Event 7 Once the reactor is tripped, a Loss of All AC power will occur on Unit 1.

Verifiable Action - RO will manually control S/G levels and the BOP will initiate S/I on both trains to start the D/Gs.

Event 8 Both trains D/G Load sequencers will fail to actuate. This will cause CAPT #1 to not receive a signal to start.

Verifiable Action - RO will manually start CAPT #1 to maintain S/G levels.

Event 9 Once S/I is initiated on both trains, the RN pumps will fail to start automatically.

Verifiable Action - BOP will reset ECCS and D/G load sequencers on both trains and start RN pumps as required.

Critical Task 1 - Initiate Safety Injection (S/I) on both trains to start the Unit 1 Diesel Generators by the completion of EP/1/A/5000/ECA-0.0 Step 8.

Critical Task 2 - Manually start Nuclear Service Water (RN) pumps such that the EDG does not fail because of damage caused by engine overheating. (Reference Simulator Work Request # DSG-044 for the simulator programming for this critical task)

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

1. Total malfunctions (5-8) 6

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) 1

7. Critical tasks (2-3) 2 Scenario #4 Catawba 2017 NRC Exam Page 4 of 118

Catawba Nuclear Station NRC Exam June 2017 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC # 159 and load schedule file for Scenario 4.

START TIME:__________

Trigger Instructor Action Delete Final Delay Ramp Event In MAL-ENB008B (I/R N36 LOSS OF 3 FISSION CHAMBER (AFFECTS ACTIVE 3 N32))

LOA-RL015 (RACKOUT RL PUMP RACK-4 4 C) OUT XMT-SG004 (LCF_5510 S/G 1A N/R 4 LVL CH2 TO DCS/MCB/OAC 100 5:00 4 (CFAA5510))

OVR-WL017D (NCDT PMP 1A OFF 5 ON 5 PB)

OVR-WL017A (NCDT PMP 1A OFF 5 OFF 5 LT)

MAL-NCP003C (NCP C 6 25 :15 6 VIBRATION)

MAL-EP003E (ZONE 1A and 1B 7 ACTIVE 7 LOCKOUT)

MAL-EQB006A (TRN B 7 ACTIVE 7 BLACKOUT SEQUENCER BLOCK)

MAL-EQB005A (TRN A 7 ACTIVE 7 BLACKOUT SEQUENCER BLOCK)

OVR-DG014D (D/G 1A PB (11/212) 7 ON 7 OFF PB)

OVR-DG016D (D/G 1B PB (11/407) 7 ON 7 OFF PB)

MAL-RN003A (RN PMP 1A 7 AUTO 9 FAILURE TO STRT)

MAL-RN003B (RN PMP 1B 7 AUTO 9 FAILURE TO STRT)

MAL-RN003C (RN PMP 2A 7 AUTO 9 FAILURE TO STRT)

MAL-RN003D (RN PMP 2B 7 AUTO 9 FAILURE TO STRT)

OVR-DG014D (D/G 1A PB (11/212) 11 OFF OFF PB)

Scenario #4 Catawba 2017 NRC Exam Page 5 of 118

Catawba Nuclear Station NRC Exam June 2017 OVR-DG016D (D/G 1B PB (11/407) 12 OFF OFF PB)

ANN-AD11-B03 (TRANSFORMER ON A TROUBLE)

ANN-AD11-E03 (TRANSFORMER B ON TROUBLE)

RACK-LOA-CM039 (RACKOUT CBP 1A)

OUT LOA-VI011 (EMERGENCY DIESEL 14 ON 10:00 VI & ISOL VLV)

Ensure EVENT 7 = jpplp4(1) jpplp4(2) (Reactor Trip Either Train)

Ensure EVENT 11 = jpplsia Ensure EVENT 12 = jpplsib Ensure Red Collar is placed on 1A Condensate Booster Pump Scenario #4 Catawba 2017 NRC Exam Page 6 of 118

Catawba Nuclear Station NRC Exam June 2017

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, Swap Operating RN pumps BOOTH INSTRUCTOR ACTION IF contacted as Primary Chemistry notifying of intention to bypass Unit 1 demineralizers while changing RN Pump configuration, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection notifying of intention to bypass Unit 1 demineralizers while changing RN Pump configuration, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as the AO at the RN pump house for post start check of 1B RN pump, REPORT 1B RN Pump looks good for continued operation.

BOOTH INSTRUCTOR ACTION IF contacted as Primary Chemistry notifying that Unit 1 demineralizers have been restored to service, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection notifying that Unit 1 demineralizers have been restored to service, REPEAT the information.

3.3 Scenario EVENT 2, Withdrawing Control Rods To Increase Reactor Power 3.4 Scenario EVENT 3, N36 Loss of Fission Chamber (Affects N32)

BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause a loss of fission chamber to N36 and N32.

Scenario #4 Catawba 2017 NRC Exam Page 7 of 118

Catawba Nuclear Station NRC Exam June 2017 BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for loss of fission chamber, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as Reactor Engineering informing of loss of fission chamber, REPEAT the information.

3.5 Scenario EVENTs 4A & 4B, C RL Pump Trip / 1A S/G N/R Level Channel 2 Fails High BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 4 to cause a trip of the C RL Pump.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for C RL Pump, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1A S/G N/R Level Channel 2, REPEAT the information.

3.6 Scenario EVENT 5, 1A NCDT Pump Trip BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to cause a trip of the 1A NCDT Pump.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1A NCDT Pump, REPEAT the information.

3.7 Scenario EVENT 6, 1C NC Pump High/High Vibration BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 6 to cause a High/High Vibration on 1C NC Pump.

3.8 Scenario EVENTS 7, 8, & 9, Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I BOOTH INSTRUCTOR ACTION If contacted as an AO dispatched to perform G-1 Enclosures 19 and 20, REPEAT the information and pull up and run schedule file Schedule/Operations/ECA-0.0 EMXS - SSF DG - SSF pump.sch After 5 minutes, contact the control room and REPORT G-1 Enclosures 19 & 20 are complete. The standby makeup pump is in service.

Scenario #4 Catawba 2017 NRC Exam Page 8 of 118

Catawba Nuclear Station NRC Exam June 2017 BOOTH INSTRUCTOR ACTION If contacted as an AO and dispatched to place the backup diesel VI compressor in service, REPEAT the information and INSERT SIMULATOR Trigger 14 to start the backup diesel VI compressor and tie it to the VI header.

After 10 minutes, contact the control room and REPORT Backup Diesel VI Compressor

1. 1 has been started and is tied to the VI header.

Scenario #4 Catawba 2017 NRC Exam Page 9 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 10 of 118 Event

Description:

Swap Operating RN (Nuclear Service Water) pumps Scenario #4 Catawba 2017 NRC Exam Page 10 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 11 of 118 Event

Description:

Swap Operating RN (Nuclear Service Water) pumps Scenario #4 Catawba 2017 NRC Exam Page 11 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 12 of 118 Event

Description:

Swap Operating RN (Nuclear Service Water) pumps Scenario #4 Catawba 2017 NRC Exam Page 12 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 13 of 118 Event

Description:

Swap Operating RN (Nuclear Service Water) pumps Scenario #4 Catawba 2017 NRC Exam Page 13 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 14 of 118 Event

Description:

Swap Operating RN (Nuclear Service Water) pumps Scenario #4 Catawba 2017 NRC Exam Page 14 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 15 of 118 Event

Description:

Swap Operating RN (Nuclear Service Water) pumps Scenario #4 Catawba 2017 NRC Exam Page 15 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 1 Page 16 of 118 Event

Description:

Swap Operating RN (Nuclear Service Water) pumps Scenario #4 Catawba 2017 NRC Exam Page 16 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 2 Page 17 of 118 Event

Description:

Withdraw Control Rods To Increase Reactor Power to ~14%

Scenario #4 Catawba 2017 NRC Exam Page 17 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 2 Page 18 of 118 Event

Description:

Withdraw Control Rods To Increase Reactor Power to ~14%

Scenario #4 Catawba 2017 NRC Exam Page 18 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 2 Page 19 of 118 Event

Description:

Withdraw Control Rods To Increase Reactor Power to ~14%

Scenario #4 Catawba 2017 NRC Exam Page 19 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 2 Page 20 of 118 Event

Description:

Withdraw Control Rods To Increase Reactor Power to ~14%

Scenario #4 Catawba 2017 NRC Exam Page 20 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 2 Page 21 of 118 Event

Description:

Withdraw Control Rods To Increase Reactor Power to ~14%

Scenario #4 Catawba 2017 NRC Exam Page 21 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 2 Page 22 of 118 Event

Description:

Withdraw Control Rods To Increase Reactor Power to ~14%

Scenario #4 Catawba 2017 NRC Exam Page 22 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 2 Page 23 of 118 Event

Description:

Withdraw Control Rods To Increase Reactor Power to ~14%

Scenario #4 Catawba 2017 NRC Exam Page 23 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 24 of 118 Event

Description:

N36 Loss of Fission Chamber (Also Affects N32)

Control Room Indications Flux level on N36 and N32 decrease Scenario #4 Catawba 2017 NRC Exam Page 24 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 25 of 118 Event

Description:

N36 Loss of Fission Chamber (Also Affects N32)

Scenario #4 Catawba 2017 NRC Exam Page 25 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 26 of 118 Event

Description:

N36 Loss of Fission Chamber (Also Affects N32)

Scenario #4 Catawba 2017 NRC Exam Page 26 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 27 of 118 Event

Description:

N36 Loss of Fission Chamber (Also Affects N32)

Scenario #4 Catawba 2017 NRC Exam Page 27 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 28 of 118 Event

Description:

N36 Loss of Fission Chamber (Also Affects N32)

Scenario #4 Catawba 2017 NRC Exam Page 28 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 29 of 118 Event

Description:

N36 Loss of Fission Chamber (Also Affects N32)

Scenario #4 Catawba 2017 NRC Exam Page 29 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 30 of 118 Event

Description:

N36 Loss of Fission Chamber (Also Affects N32)

Scenario #4 Catawba 2017 NRC Exam Page 30 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 31 of 118 Event

Description:

N36 Loss of Fission Chamber (Also Affects N32)

Scenario #4 Catawba 2017 NRC Exam Page 31 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 3 Page 32 of 118 Event

Description:

N36 Loss of Fission Chamber (Also Affects N32)

Scenario #4 Catawba 2017 NRC Exam Page 32 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4A Page 33 of 118 Event

Description:

C RL Pump Trip Control Room Indications OAC alarm for RL Header Pressure Low RL Header Pressure decreasing Indicating lights for C RL pump - DARK Scenario #4 Catawba 2017 NRC Exam Page 33 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4A Page 34 of 118 Event

Description:

C RL Pump Trip Scenario #4 Catawba 2017 NRC Exam Page 34 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4A Page 35 of 118 Event

Description:

C RL Pump Trip Scenario #4 Catawba 2017 NRC Exam Page 35 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4A Page 36 of 118 Event

Description:

C RL Pump Trip Scenario #4 Catawba 2017 NRC Exam Page 36 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4A Page 37 of 118 Event

Description:

C RL Pump Trip Scenario #4 Catawba 2017 NRC Exam Page 37 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4A Page 38 of 118 Event

Description:

C RL Pump Trip Scenario #4 Catawba 2017 NRC Exam Page 38 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4A Page 39 of 118 Event

Description:

C RL Pump Trip Scenario #4 Catawba 2017 NRC Exam Page 39 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4A Page 40 of 118 Event

Description:

C RL Pump Trip Scenario #4 Catawba 2017 NRC Exam Page 40 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4A Page 41 of 118 Event

Description:

C RL Pump Trip Scenario #4 Catawba 2017 NRC Exam Page 41 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4A Page 42 of 118 Event

Description:

C RL Pump Trip Scenario #4 Catawba 2017 NRC Exam Page 42 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 4B Page 43 of 118 Event

Description:

1A S/G N/R Level Channel 2 Fails High Scenario #4 Catawba 2017 NRC Exam Page 43 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 5 Page 44 of 118 Event

Description:

1A NCDT Pump Trip Control Room Indications 1AD-13, B/2 NCDT RECIRC LO FLOW - LIT Note To Evaluator:

The response for this Event is located in the alarm response for 1AD-13, B/2 NCDT RECIRC LO FLOW which is included on the following page.

Scenario #4 Catawba 2017 NRC Exam Page 44 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 5 Page 45 of 118 Event

Description:

1A NCDT Pump Trip Scenario #4 Catawba 2017 NRC Exam Page 45 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 Page 46 of 118 Event

Description:

1C NC Pump High/High Vibration Control Room Indications 1AD-6, A/5 NCP HI VIBRATION - LIT 1AD-6, B/5 NCP HI-HI VIBRATION - LIT 1C NC Pump Shaft Vibration indicating 25 mils on NC Pump Vibration Monitor Note To Evaluator:

The response for this Event is found in the alarm response for 1AD-6, B/5 (NCP HI-HI VIBRATION) which is included on the following page.

Scenario #4 Catawba 2017 NRC Exam Page 46 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 Page 47 of 118 Event

Description:

1C NC Pump High/High Vibration Scenario #4 Catawba 2017 NRC Exam Page 47 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 6 Page 48 of 118 Event

Description:

1C NC Pump High/High Vibration Scenario #4 Catawba 2017 NRC Exam Page 48 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 49 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 49 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 50 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 50 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 51 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 51 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 52 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 52 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 53 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 53 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 54 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 54 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 55 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 55 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 56 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 56 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 57 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 57 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 58 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 58 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 59 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 59 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 60 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 60 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 61 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 61 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 62 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 62 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 63 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 63 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 64 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 64 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 65 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 65 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 66 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 66 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 67 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 67 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 68 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 68 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 69 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 69 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 70 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 70 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 71 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 71 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 72 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 72 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 73 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 73 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 74 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 74 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 75 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 75 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 76 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 76 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 77 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 77 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 78 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 78 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 79 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 79 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 80 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 80 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 81 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 81 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 82 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 82 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 83 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 83 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 84 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 84 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 85 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 85 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 86 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 86 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 87 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 87 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 88 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 88 of 118

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 4 Event # 7, 8, 9 Page 89 of 118 Event

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 89 of 118

Attachment List Scenario 4 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - AP/0/A/5500/038 Enclosure 1 (Foldout Page)

ATTACHMENT 4 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page)

ATTACHMENT 5 - EP/1/A/5000/E-0 Enclosure 2 (Control Room Ventilation Verification)

ATTACHMENT 6 - EP/1/A/5000/G-1 Enclosure 1 (Spent Fuel Pool Monitoring)

ATTACHMENT 7 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control)

ATTACHMENT 8 - EP/1/A/5000/ECA-0.0 Enclosure 1 (Foldout Page)

ATTACHMENT 9 - EP/1/A/5000/ES-1.1 Enclosure 1 (Foldout Page)

Scenario #4 Catawba 2017 NRC Exam Page 90 of 118

ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK 1 Initiate Safety Injection (S/I) on both trains to start the Unit 1 Diesel Generators by the completion of EP/1/A/5000/ECA-0.0 Step 8.

2 Manually start Nuclear Service Water (RN) pumps such that the EDG does not fail because of damage caused by engine overheating.

Comments:

Scenario #4 Catawba 2017 NRC Exam Page 91 of 118

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 7x10-2 % BOL 1969 PPM per OAC Controlling Procedure OP/1/A/6100/001 (Controlling Procedure for Unit Startup), Enclosure 4.1 (Unit Startup). The steps up to 3.180 are complete.

Other Information Needed to Assume the Shift Unit 1 is at 7x10-2 % power at the BOL. Unit 2 is at 100% power. 1A Condensate Booster Pump is tagged out for emergent motor replacement. Direction for the crew is to swap operating RN pumps by starting the 1B RN pump and securing the 1A RN pump per OP/0/A/6400/006 C (Nuclear Service Water System) Enclosure 4.7 (Starting/Securing Additional RN Pumps). Initial conditions have been verified. Chemistry has been notified of the RN pump lineup being changed and has informed operations that RN Chemical Addition system has been aligned to support the RN pump swap. The Unit 1 Cation Bed Demineralizer is not in service. Unit 2 Mixed bed demineralizers have been bypassed per step 3.2.2. Crew is to begin at step 3.2.1 of Enclosure 4.7. Following the RN pump swap, the crew is to withdraw control rods to increase reactor power to ~14 % in preparation for placing the Main Turbine online.

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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Scenario #4 Catawba 2017 NRC Exam Page 92 of 118

ATTACHMENT 3 Scenario #4 Catawba 2017 NRC Exam Page 93 of 118

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Catawba Nuclear Station JPM A 2017 NRC Exam JPM A PAGE 1 OF 9

Catawba Nuclear Station JPM A 2017 NRC Exam EVALUATION SHEET Task: Emergency Borate the Reactor Coolant System Alternate Path: Yes Facility JPM #: NV-017 Safety Function: 1

Title:

Reactivity Control K/A 004 A2.14 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: Emergency Boration Rating(s): 3.8 / 3.9 CFR: 41.5 / 43/5 / 45/3 / 45/5 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

EP/1/A/5000/FR-S.1 (Nuclear Power Generation/ATW) rev. 022 Task Standard: One NV pump running with its suction aligned to the FWST and isolated from the VCT.

Validation Time: 5 minutes Time Critical: Yes No X

===============================================================

Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 9

Catawba Nuclear Station JPM A 2017 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC #150

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-IPX003A (REACTOR TRIP BKR A ACTIVE FAILURE)

MAL-IPX003B (REACTOR TRIP BKR B ACTIVE FAILURE)

VLV-NV043F (NV236B BORIC ACID TO 0

CHG PMP VLV FAIL TO POSITION)

MAL-MT007 (LOSS OF TURBINE LUBE OIL ACTIVE PRESSURE)

Instructor will act as the OATC and be manually inserting control rods when the simulator is placed in RUN.

PAGE 3 OF 9

Catawba Nuclear Station JPM A 2017 NRC Exam 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 valid reactor trip signal has been received.

• The reactor will NOT trip automatically or manually.

• A Red Path for Subcriticality is in effect.

• The OATC is inserting rods manually.

INITIATING CUES:

The Control Room Supervisor instructs you to initiate emergency boration, per EP/1/A/5000/FR-S.1, (Nuclear Power Generation/ATWS), step 4.

EXAMINER NOTE: After reading cue, provide the applicant with a copy of EP/1/A/5000/FR-S.1.

PAGE 4 OF 9

Catawba Nuclear Station JPM A 2017 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: 4. Initiate emergency boration of NC System as follows:

a. Ensure at least one NV pump - ON.

STANDARD: ___ SAT Applicant verifies red ON light lit for NV PMP 1A or 1B (1MC-10). ___ UNSAT COMMENTS:

STEP 2 4. b. OPEN 1NV-236B (Boric Acid To NV Pumps Suct).

STANDARD:

Applicant depresses the red OPEN pushbutton for 1NV-236B and verifies the red OPEN light remains dark and the green CLSD light ___ SAT remains lit on 1MC-10. 1NV-236B remains closed.

___UNSAT Examiner Note: This begins the alternate path of this JPM.

COMMENTS:

STEP 3 4. c. Ensure both boric acid transfer pump switches - IN THE "ON" POSITION.

STANDARD:

___ SAT Applicant rotates the switches for B/A XFER PMP 1A and B/A XFER PMP 1B to the ON position. ___ UNSAT COMMENTS:

PAGE 5 0F 9

Catawba Nuclear Station JPM A 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4 4. d. Verify emergency boration flow - GREATER THAN OR EQUAL TO 30 GPM.

STANDARD:

___ SAT Applicant verifies EMER BORATE FLOW (1NVP5440) indicates 0

___ UNSAT gpm (1MC-5) and transitions to the RNO.

COMMENTS:

STEP 5 4. d. RNO d. Align NV pump suction to FWST as follows:

CRITICAL

1) OPEN the following valves: STEP

• 1NV-252A (NV Pumps Suct From FWST)

• 1NV-253B (NV Pumps Suct From FWST).

STANDARD:

Applicant depresses the red OPEN pushbuttons for 1NV-252A and 1NV-253B and verifies the red OPEN light is lit and green CLSD light is dark for both valves. ___ SAT Examiner Note: This step is critical to align borated water to the ___ UNSAT suction of the charging pumps. Only ONE of the valves opened meets the Critical Step criteria.

COMMENTS:

PAGE 6 0F 9

Catawba Nuclear Station JPM A 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6 4. d. RNO d. 2) CLOSE the following valves:

CRITICAL STEP

• 1NV-188A (VCT Otlt Isol)

• 1NV-189B (VCT Otlt Isol).

STANDARD:

Applicant depresses the green CLOSE pushbutton for 1NV-188A and 1NV-189B and verifies the green CLSD light lit and red OPEN light dark for both valves.

Examiner Note: This step is critical to prevent borated water from ___ SAT going to the VCT instead of the suction of the charging pumps as long as one of the valves is ___ UNSAT closed. Closing only ONE of the valves meets the intent of the Critical Step criteria.

COMMENTS:

STEP 7 4. e. Verify the following charging line isolation valves - OPEN:

• 1NV-312A (Chrg Line Cont Isol) follows:

• 1NV-314B (Chrg Line Cont Isol).

___ SAT STANDARD:

___ UNSAT Applicant verifies the red OPEN lights lit and green CLSD lights dark on 1NV-312A and 1NV-314B.

COMMENTS:

PAGE 7 0F 9

Catawba Nuclear Station JPM A 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8 4. f. Verify Pzr pressure - LESS THAN 2335 PSIG.

STANDARD:

___ SAT Applicant verifies PZR pressure instruments (1NCP5161, 1NCP5150, 1NCP5170 and 1NCP5171) indicate less than 2335 psig (1MC-10).

___ UNSAT COMMENTS:

END OF TASK STOP TIME ________

PAGE 8 0F 9

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 valid reactor trip signal has been received.

• The reactor will NOT trip automatically or manually.

• A Red Path for Subcriticality is in effect.

• The OATC is inserting rods manually.

INITIATING CUES:

The Control Room Supervisor instructs you to initiate emergency boration, per EP/1/A/5000/FR-S.1, (Nuclear Power Generation/ATWS), step 4.

Catawba Nuclear Station JPM B 2017 NRC Exam JPM B PAGE 1 OF 8

Catawba Nuclear Station JPM B 2017 NRC Exam EVALUATION SHEET Task: Perform E-0 Actions To Ensure A Complete Containment Isolation Alternate Path: Yes Facility JPM #: N/A Safety Function: 2

Title:

Engineering Safety Features Actuation System K/A 013 A4.01 Ability to manually operate and/or monitor in the control room: ESFAS-initiated equipment which fails to actuate.

Rating(s): 4.5 / 4.8 CFR: 41.7 / 45.5 to 45.8 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) Rev 42 Task Standard: At least one train of Phase A containment isolation initiated and either 1WL-825A or 1WL-827B manually closed.

Validation Time: 5 minutes Time Critical: Yes No X

===============================================================

Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 8

Catawba Nuclear Station JPM B 2017 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC #151

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.

Instructor Action Final Delay Ramp Delete In Event MAL-NC013D (NC COLD LEG D LEAK) 27.5 :10 1 MAL-ISE003A (AUTO PHASE A ISOL BLOCK SIGNAL TRN A)

MAL-ISE003B (AUTO PHASE B ISOL BLOCK SIGNAL TRN B)

VLV-WL009A (WL825A CONT SUMP PMP ACTIVE DISCH ISOL IN FAIL AUTO ACTIONS)

VLV-WL010A (WL827B CONT SUMP PMP ACTIVE DISCH ISOL OUT FAIL AUTO ACTIONS)

When applicant is ready, INSERT EVENT 1.

PAGE 3 OF 8

Catawba Nuclear Station JPM B 2017 NRC Exam 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:

• You are the OATC

• The BOP has stepped out of the control room

• The CRS is performing an IPTE brief on Unit 2 INITIATING CUES:

• Monitor your control boards EXAMINER NOTE: After reading cue, and applicant has walked down the control boards, have the simulator operator INSERT EVENT 1. This will cause a safety injection on Unit 1. All E-0 immediate action steps will be met without any operator action. Once the applicant has announced that the Immediate Actions are complete, hand them a copy of E-0 beginning at step 6.

EXAMINER CUE: The CRS has validated that the immediate actions are complete and directs you to continue performance of E-0, beginning at Step 6.

PAGE 4 OF 8

Catawba Nuclear Station JPM B 2017 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: 6. Announce Unit 1 Safety Injection.

STANDARD:

___ SAT Applicant uses the plant paging system to make the announcement.

___ UNSAT COMMENTS:

STEP 2 7. Determine required notifications:

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

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

___ SAT STANDARD:

___UNSAT Applicant acknowledges the step and continues with E-0.

COMMENTS:

STEP 3 8. Verify all Feedwater Isolation status lights (1SI-5) - LIT.

STANDARD:

___ SAT Applicant verifies all Feedwater Isolation status lights lit on 1SI-5.

___ UNSAT COMMENTS:

PAGE 5 0F 8

Catawba Nuclear Station JPM B 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4 9. Verify Phase A Containment Isolation status as follows:

a. Phase A RESET lights - DARK.

STANDARD: ___ SAT Applicant determines that the Phase A RESET lights are lit and ___ UNSAT transitions to the RNO.

COMMENTS:

STEP 5 9.a.RNO. Initiate Phase A Isolation.

CRITICAL STANDARD: STEP Applicant depresses both of the red INITIATE pushbuttons for Train A and Train B and verifies the yellow RESET lights extinguish.

Examiner Note: It is critical for the applicant to at least initiate one train of Phase A to ensure that at least one valve in every penetration other than from the containment sump is isolated. The containment sump penetration will have to be manually isolated in the RNO for the ___ SAT following step.

___ UNSAT Examiner Note: This begins the alternate path for this JPM.

COMMENTS:

PAGE 6 0F 8

Catawba Nuclear Station JPM B 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6 9.b. Monitor Light Panel Group 5 St lights on energized train(s) -

LIT.

STANDARD:

Applicant determines that Group 5 St lights C/3 and C/10 are dark and transitions to the RNO. ___ SAT Examiner Note: It may take up to 60 seconds for all other valves to ___ UNSAT indicate isolated.

COMMENTS:

STEP 7 9.b.RNO. Align valves as necessary to ensure each penetration isolated by at least one isolation valve. CRITICAL STEP STANDARD:

Applicant depresses the green CLOSE pushbuttons for 1WL-825A and 1WL-827B and verifies the green CLSD light lit and red OPEN light dark for each valve.

Examiner Note: It is critical for the applicant to close 1 of these valves to ensure the containment sump penetration is isolated. ___ SAT Examiner Cue: Once valves have been closed, This JPM is ___ UNSAT complete.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 7 0F 8

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:

• You are the OATC

• The BOP has stepped out of the control room

• The CRS is performing an IPTE brief on Unit 2 INITIATING CUES:

• Monitor your control boards

Catawba Nuclear Station JPM C 2017 NRC Exam JPM C PAGE 1 OF 14

Catawba Nuclear Station JPM C 2017 NRC Exam EVALUATION SHEET Task: Establish NC system Bleed and Feed per EP/1/A/5000/FR-H.1 Alternate Path: Yes Facility JPM #: NC-046 Safety Function: 4P

Title:

Reactor Coolant System K/A WE05EA1.1 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 (Response to Loss of Secondary Heat Sink) rev. 42 Task Standard: Aligns S/I feed path using NI and NV pumps and opens 1NC-32B and 1NC-34A PZR PORVs to establish NC system bleed path Validation Time: 10 minutes Time Critical: Yes No X

===============================================================

Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 14

Catawba Nuclear Station JPM C 2017 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC #152.

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 Both START MAL-CA004B FAILURE OF CA PUMP B TO Both START MAL-NI001B NI PUMP B FAILURE Auto OVR-ISE043 SAFETY INJECTION INITIATE Off PB TRN B MAL-ISE002B (AUTO SI TRN B FAILS TO Active ACTUATE)

VLV-NI001F (NI9A B.I.T. DISCHARGE ISOL 0

VLV FAIL TO POSITION)

PAGE 3 OF 14

REV. 0 PAGE 4 0F 14 Catawba Nuclear Station JPM C 2017 NRC Exam 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 on Unit 1 due to a loss of both Main Feedwater pumps.

• The CA system will not function.

• Attempts to restart the Main CF pumps have been unsuccessful.

• EP/1/A/5000/FR-H.1 (Response to Loss of Secondary Heat Sink) has been entered due to a RED PATH for the Heat Sink critical safety function while performing EP/1/A/5000/ES-0.1 (Reactor Trip Response).

• Bleed and Feed initiation criteria have been met.

INITIATING CUES:

• The CRS instructs you to initiate NC system bleed and feed beginning at step 19 of EP/1/A/5000/FR-H.1. Inform the CRS when the bleed and feed path has been initiated and verified.

EXAMINER NOTE: After reading cue, provide the applicant with a copy of EP/1/A/5000/FR-H.1.

PAGE 4 OF 14

Catawba Nuclear Station JPM C 2017 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: 19. Perform Steps 20 through 24 quickly to establish NC heat removal by NC bleed and feed.

STANDARD:

___ SAT Applicant acknowledges this step.

___ UNSAT COMMENTS:

STEP 2 20. Ensure all NC pumps - OFF.

STANDARD:

___ SAT Applicant ensures the NC pumps are off.

___UNSAT COMMENTS:

PAGE 5 0F 14

Catawba Nuclear Station JPM C 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3 21. Initiate S/I.

CRITICAL STANDARD: STEP Applicant depresses the red train A and B SAFETY INJECTION INITIATE pushbuttons and verifies the red SAFETY INJECTION ACTUATED status light is lit on 1SI-13 or ECCS TRN A yellow reset light is dark on 1MC-11.

Examiner Note: This step is critical to start the NI pump and align the valves required for initiating an NC system feed path. ___ SAT Examiner Note: This begins the alternate path for this JPM. ___ UNSAT COMMENTS:

STEP 4 22. Verify NC System feed path as follows:

a. Verify the following pumps - ON:

• At least one NV pump

• At least one NI pump.

STANDARD:

___ SAT Applicant determines that at least one NV pump and one NI pump are

___ UNSAT running.

Examiner Note: Applicant may start 1B NI pump and 1B NV pump at this time due to it being a failed auto action. If not, the procedure will direct starting these pumps in the upcoming steps.

COMMENTS:

PAGE 6 0F 14

Catawba Nuclear Station JPM C 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5 22 b. Verify "NV S/I FLOW" - INDICATING FLOW.

STANDARD:

___ SAT Applicant determines that 1NVP6080 (NV S/I FLOW) on 1MC-3 indicates 0 GPM and transitions to the RNO. ___ UNSAT COMMENTS:

STEP 6 22 b. RNO Perform the following:

1) Ensure the following pumps - ON:

• NV Pumps

• NI Pumps.

___ SAT STANDARD:

___ UNSAT Applicant ensures that all NV pumps and NI pumps are running by depressing the red ON pushbuttons for any non-running pump, and verifying the red ON lights are lit and green OFF lights are dark for all pumps.

COMMENTS:

PAGE 7 0F 14

Catawba Nuclear Station JPM C 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7 22 b. RNO 2) IF at least one NV pump in service, THEN perform the following:

a) Ensure the following valves - OPEN:

• 1NV-252A (NV Pumps Suct From FWST)

• 1NV-253B (NV Pumps Suct From FWST). ___ SAT STANDARD: ___ UNSAT Applicant verifies the red OPEN lights lit and green CLSD lights dark on 1NV-252A and 1NV-253B.

COMMENTS:

STEP 8 22 b. RNO 2) b) Ensure the following valves - CLOSED:

• 1NV-188A (VCT Otlt Isol)

• 1NV-189B (VCT Otlt Isol).

STANDARD:

___ SAT Applicant determines that the green CLSD light is lit and red OPEN light

___ UNSAT is dark on 1NV-188A. Applicant determines that the green CLSD light is dark for 1NV-189B, and depresses the green CLOSE pushbutton and verifies the green CLSD light is lit and the red OPEN light is dark COMMENTS:

PAGE 8 0F 14

Catawba Nuclear Station JPM C 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 9 22 b. RNO 2) c) Ensure the following valves - OPEN:

CRITICAL STEP

• 1NI-9A (NV Pmp C/L Inj Isol)

• 1NI-10B (NV Pmp C/L Inj Isol).

STANDARD:

Applicant determines the red OPEN light is dark and green CLSD light is lit on 1NI-9A and 1NI-10B. Applicant depresses the red OPEN pushbutton for 1NI-9A but the valve will not open. Applicant depresses the red OPEN pushbutton for 1NI-10B and verifies the red OPEN light is ___ SAT lit and the green CLSD light is dark.

___ UNSAT Examiner Note: This step is critical to align an NC (Reactor Coolant) system Feed path.

COMMENTS:

STEP 10 22 b. RNO 3) IF NI Pump 1A is in service, THEN ensure the following valves - OPEN:

• 1NI-103A (NI Pump 1A Suct)

• 1NI-118A (NI Pump 1A C-Leg Inj Isol)

• 1NI-162A (NI To C-Legs Inj Hdr Isol)

___ SAT

• 1NI-100B (NI Pmps Suct From FWST).

___ UNSAT STANDARD:

Applicant determines that the red OPEN lights are lit and green CLSD lights are dark on valves 1NI-103A, 1NI-118A, 1NI-162A, and 1NI-100B.

COMMENTS:

PAGE 9 0F 14

Catawba Nuclear Station JPM C 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 11 22 b. RNO 4) IF NI Pump 1B is in service, THEN ensure the following valves - OPEN:

• 1NI-135B (NI Pump 1B Suct)

• 1NI-150B (NI Pump 1B C-Leg Inj Isol)

• 1NI-162A (NI To C-Legs Inj Hdr Isol)

___ SAT

• 1NI-100B (NI Pmps Suct From FWST).

___ UNSAT STANDARD:

Applicant verifies that the red OPEN light is lit and green CLSD light is dark on valves 1NI-135B, 1NI-150B, 1NI-162A, and 1NI-100B.

COMMENTS:

STEP 12 22 b. RNO 5) IF no feed path can be aligned, THEN perform the following:

STANDARD:

___ SAT Applicant determines that a feed path does exist and this step is N/A.

___ UNSAT COMMENTS:

PAGE 10 0F 14

Catawba Nuclear Station JPM C 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 13 23. Establish NC System bleed path as follows:

a. Ensure all Pzr PORV isolation valves - OPEN.

STANDARD:

___ SAT Applicant determines the RED lights are lit and GREEN lights are dark

___ UNSAT on valves 1NC-31B, 1NC-35B, and 1NC-33A.

COMMENTS:

STEP 14 23 b. Select "OPEN" on the following PZR PORVs:

CRITICAL STEP

• 1NC-34A (PZR PORV)

• 1NC-32B (PZR PORV).

STANDARD:

Applicant rotates switches for 1NC-34A and 1NC-32B, clockwise to the OPEN position and verifies RED lights are lit and GREEN lights are dark on both valves. ___ SAT Examiner Note: This step is critical because it establishes an NC ___ UNSAT (Reactor Coolant) system Bleed path.

COMMENTS:

PAGE 11 0F 14

Catawba Nuclear Station JPM C 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 15 23 c. Align N2 to 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).

___ SAT STANDARD:

___ UNSAT Applicant depresses the red OPEN pushbutton and verifies red OPEN light lit and green CLSD light dark on valves 1NI-438A and 1NI-439B.

COMMENTS:

STEP 16 23 d. Verify power to all Pzr PORV isolation valves -

AVAILABLE.

STANDARD:

___ SAT Applicant verifies indicating lights lit on 1NC-31B, 1NC-35B, and 1NC-33A. ___ UNSAT COMMENTS:

PAGE 12 0F 14

Catawba Nuclear Station JPM C 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 17 24. Verify the following valves - OPEN:

• 1NC-31B (PZR PORV Isol)

• 1NC-32B (PZR PORV)

• 1NC-33A (PZR PORV Isol)

• 1NC-34A (PZR PORV). ___ SAT STANDARD: ___ UNSAT Applicant verifies lights on 1NC-31B, 1NC-32B, 1NC-33A and 1NC-34A indicate OPEN.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 13 0F 14

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 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 on Unit 1 due to a loss of both Main Feedwater pumps.

• The CA system will not function.

• Attempts to restart the Main CF pumps have been unsuccessful.

• EP/1/A/5000/FR-H.1 (Response to Loss of Secondary Heat Sink) has been entered due to a RED PATH for the Heat Sink critical safety function while performing EP/1/A/5000/ES-0.1 (Reactor Trip Response).

• Bleed and Feed initiation criteria have been met.

INITIATING CUES:

• The CRS instructs you to initiate NC system bleed and feed beginning at step 19 of EP/1/A/5000/FR-H.1. Inform the CRS when the bleed and feed path has been initiated and verified.

Catawba Nuclear Station JPM D 2017 NRC Exam JPM D PAGE 1 OF 14

Catawba Nuclear Station JPM D 2017 NRC Exam EVALUATION SHEET Task: Realign CA Suction Source Alternate Path: Yes Facility JPM #: CA-085 Safety Function: 4S

Title:

Auxiliary / Emergency Feedwater System K/A 054 AA1.01 Ability to operate and/or monitor the following as they apply to the Loss of Main Feedwater (MFW): AFW controls, including the use of alternate AFW sources.

Rating(s): 4.5 / 4.4 CFR: 41.7 / 45.5 / 45.6 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

AP/1/A/5500/006 (Loss of S/G Feedwater) Rev 42 Task Standard: CA suction supply aligned to the RN system while maintaining total CA flow <

600 gpm per AP/1/A/5500/006 Case II.

Validation Time: 10 minutes Time Critical: Yes No X

===============================================================

Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 14

Catawba Nuclear Station JPM D 2017 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC #153.

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 Delete Final Delay Ramp Event In XMT-CM004 (LCS_5840 UST LVL 8.5 RECORDER BLUE)

VLV-CM012F (CM370 COND C VACUUM 0

BRKR FAIL TO POSTION)

VLV-CM011F (CM369 COND B VACUUM 0

BRKR FAIL TO POSTION)

VLV-CM010F (CM368 COND A VACUUM 0

BRKR FAIL TO POSTION)

OVR-FWP012C (CFPT 1A TRIP_RESET TRIP ON PB)

OVR-FWP015C (CFPT 1B TRIP_RESET TRIP ON PB)

VLV-CA002F (CA4 CA PMP SUCT FROM UST 1

HDR ISOL FAIL TO POSITION)

Ensure CA System Valve Control is reset.

PAGE 3 OF 14

Catawba Nuclear Station JPM D 2017 NRC Exam 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.

• The crew has performed applicable actions of EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) and transitioned to EP/1/A/5000/ES-0.1 (Reactor Trip Response).

• While performing actions of ES-0.1, 1AD-8, B/1 (UST LO LEVEL) alarmed.

• Using guidance contained in Enclosure 1 (Foldout Page), the crew has implemented AP/1/A/5500/006 (Loss of S/G Feedwater), Case II (Loss of Normal CA Supply).

INITIATING CUES:

The Control Room Supervisor instructs you to perform the actions of AP/06 Case II, beginning at Step 7.

EXAMINER NOTE: After reading cue, provide the applicant with a copy of AP/1/A/5500/006 Case II with steps 1-6 completed.

PAGE 4 OF 14

Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: 7. IF AT ANY TIME UST level is less than 10% (5,000 gal),

THEN perform the following:

a. Close 1CA-4 (CA Pmps Suct From UST).

STANDARD:

___ SAT Applicant determines that UST level is <10% on chart recorder and

___ UNSAT depresses the green CLOSE pushbutton on 1CA-4 and verifies the red OPEN light remains lit (1CA-4 will not close).

COMMENTS:

STEP 2 7. b. IF 1CA-4 will not close, THEN dispatch operator to unlock and close 1CS-19 (CA Pumps Supply From Upper Surge CRITICAL Tank) (TB1-627, 1D-30) (Key #633). STEP STANDARD:

Applicant contacts an AO and dispatches them to unlock and close 1CS-19.

Booth Operator Cue: Operator has been dispatched to unlock and close 1CS-19.

Examiner Note: It is only critical for the applicant to dispatch an ___ SAT operator to manually close 1CS-19 by the end of the scenario to isolate the suction from the UST. This ___UNSAT valve will not be closed during the performance of this JPM.

COMMENTS:

PAGE 5 0F 14

Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3 8. Maintain total CA flow less than 600 GPM in subsequent steps. CRITICAL STEP STANDARD:

Applicant uses CA flow control valves to throttle total CA flow to less than 600 GPM.

Examiner Note: This step is critical to preserve the remaining inventory of available makeup water while aligning ___ SAT an alternate source.

___ UNSAT COMMENTS:

STEP 4 9. Monitor Enclosure 1 (Foldout Page).

STANDARD:

___ SAT Applicant acknowledges step and continues.

___ UNSAT Examiner Cue: Another operator will monitor Enclosure 1.

COMMENTS:

PAGE 6 0F 14

Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5 10. Break condenser vacuum as follows:

a. Open COND A-B-C VAC BKR VLVS STANDARD:

Applicant depresses the red OPEN pushbutton for COND A-B-C VAC ___ SAT BKR VLVS and notes that the red OPEN light remains dark (vacuum breaker valves will not open). Applicant transitions to the RNO. ___ UNSAT Examiner Note: This begins the alternate path for this JPM.

COMMENTS:

STEP 6 10.a.RNO. Dispatch two (2) operators to break vacuum. REFER TO Enclosure 3 (Local Actions To Break Condenser Vacuum).

STANDARD:

Applicant dispatches two AOs to break condenser vacuum per ___ SAT Enclosure 3.

___ UNSAT Booth Operator Cue: Operators have been dispatched to break condenser vacuum per Enclosure 3.

COMMENTS:

PAGE 7 0F 14

Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7 10.b.1) Verify condenser vacuum indication - AVAILABLE.

STANDARD:

___ SAT Applicant verifies that condenser vacuum indication is available on both 1MC-1 and 1MC-13 control boards.

___ UNSAT COMMENTS:

NOTE It may take up to 10 minutes for condenser vacuum to reach 0 inches HgVac.

STEP 8 10.b.2) Verify one of the following:

• CONDENSER VACUUM (1MC-13) - 0IN HGV OR

• Dispatched operator reports no air flow into condenser.

___ SAT STANDARD:

___ UNSAT Applicant verifies condenser vacuum is not broken and operators were unsuccessful in breaking vacuum. Applicant transitions to the RNO.

Booth Operator Cue: Dispatched operators report that they are unable to manually open Condenser Vacuum Breaker valves.

COMMENTS:

PAGE 8 0F 14

Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 9 10.b.2)RNO. Shift CA pump suction to RN as follows:

CRITICAL a) IF Train A RN essential header is available, STEP THEN open the following valves:

• 1RN-250A (RN Hdr A To CA Pmp Suct Isol)

• 1CA-116A (CA Pump #1 Suct Frm RN Isol)

• 1CA-15A (CA Pump 1A Suct Frm RN Isol).

STANDARD:

Applicant determines Train A RN essential header is available and rotates the switches for 1RN-250A, 1CA-116A, and 1CA-15A to the ___ SAT OPEN position and verifies the red OPEN indicating light is lit.

___ UNSAT Examiner Note: This step is critical to ensure a makeup source of water is available to supply S/Gs for reactor decay heat removal.

COMMENTS:

PAGE 9 0F 14

Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 10 10.b.2)RNO.b) IF Train B RN essential header is available, THEN open the following valves: CRITICAL STEP

• 1RN-310B (RN Hdr B To CA Pmp Suct Isol)

• 1CA-85B (CA Pump #1 Suct Frm RN Hdr B)

• 1CA-18B (CA Pump 1B Suct Frm RN Isol).

STANDARD:

Applicant determines Train B RN essential header is available and rotates the switches for 1RN-310B, 1CA-85B, and 1CA-18B to the OPEN position and verifies the red OPEN indicating light is lit. ___ SAT Examiner Note: This step is critical to ensure a makeup source of ___ UNSAT water is available to supply S/Gs for reactor decay heat removal.

COMMENTS:

STEP 11 10.b.2)RNO.c) Ensure 1CA-6 (CA Pmps Suct From CACST) -

CLOSED.

STANDARD:

___ SAT Applicant determines that 1CA-6 is closed (normal position of this valve is closed with power removed). ___ UNSAT COMMENTS:

PAGE 10 0F 14

Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 12 10.b.2)RNO.d) IF 1CA-6 will not close, THEN dispatch operator to unlock and close 1CS-69 (U1 CACST To U1

& U2 CA Supplies) (SB-625, T-25) (Key #633).

STANDARD: ___ SAT Applicant determines that this step does not apply. ___ UNSAT COMMENTS:

STEP 13 10.b.2)RNO.e) Ensure 1CA-4 (CA Pmps Suct From UST) -

CLOSED.

STANDARD:

___ SAT Applicant depresses the green CLOSE pushbutton and verifies that the red OPEN light remains illuminated (1CA-4 will not close and an

___ UNSAT AO was previously dispatched to unlock and close 1CS-19).

COMMENTS:

PAGE 11 0F 14

Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 14 10.b.2)RNO.f) IF 1CA-4 will not close, THEN dispatch operator to unlock and close 1CS-19 (CA Pumps Supply CRITICAL From Upper Surge Tank) (TB1-627, 1D-30) (Key STEP

1. 633).

STANDARD:

Applicant determines that an operator has been previously dispatched to perform this action.

Examiner Note: It is only critical for the applicant to dispatch an operator to manually close 1CS-19 by the end of the ___ SAT scenario to isolate the suction from the UST. This valve will not be closed during the performance of ___ UNSAT this JPM.

COMMENTS:

STEP 15 10.b.2)RNO.g) Maintain S/G N/R levels between 11% - 50%.

STANDARD:

Applicant acknowledges the step and attempts to adjust CA flow as

___ SAT required.

___ UNSAT Examiner Cue: Another operator will maintain S/G levels.

COMMENTS:

PAGE 12 0F 14

Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 16 10.b.2)RNO.h) GO TO Step 17.

STANDARD:

Applicant acknowledges the step ___ SAT Examiner Cue: This JPM is complete. ___ UNSAT COMMENTS:

END OF TASK STOP TIME ________

PAGE 13 0F 14

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.

• The crew has performed applicable actions of EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) and transitioned to EP/1/A/5000/ES-0.1 (Reactor Trip Response).

• While performing actions of ES-0.1, 1AD-8, B/1 (UST LO LEVEL) alarmed.

• Using guidance contained in Enclosure 1 (Foldout Page), the crew has implemented AP/1/A/5500/006 (Loss of S/G Feedwater), Case II (Loss of Normal CA Supply).

INITIATING CUES:

The Control Room Supervisor instructs you to perform the actions of AP/06 Case II, beginning at Step 7.

Catawba Nuclear Station JPM E 2017 NRC Exam JPM E PAGE 1 OF 9

Catawba Nuclear Station JPM E 2017 NRC Exam EVALUATION SHEET Task: Operate Containment Cooling System Fans Alternate Path: No Facility JPM #: VV-001 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 / 45.5 to 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 in Max cooling mode in accordance with AP/1/A/5500/028 (Secondary Steam Leak) Step 9.

Validation Time: 5 minutes Time Critical: Yes No X

===============================================================

Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 9

Catawba Nuclear Station JPM E 2017 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC # 154.

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 Delay Ramp Delete Event Final In MAL-SM007B (STM LINE BRK INSIDE 20000 CONTAINMENT LOOP B)

Ensure LCVUs 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 3 OF 9

Catawba Nuclear Station JPM E 2017 NRC Exam 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/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.

EXAMINER NOTE: After reading the cue, provide the applicant with a copy of AP/1/A/5500/028, step 9.

PAGE 4 OF 9

Catawba Nuclear Station JPM E 2017 NRC Exam 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. ___ SAT STANDARD: ___ UNSAT Applicant determines conditions are not normal and transitions to RNO.

COMMENTS:

STEP 2: 9.aRNOa. Perform the following:

1) Evacuate containment.

STANDARD:

Applicant initiates the Containment Evacuation Alarm and may request ___ SAT the WCC to review the Containment Entry Logbook.

___UNSAT Examiner Cue: If asked, WCC reports no personnel are listed in Containment Entry Logbook.

COMMENTS:

PAGE 5 0F 9

Catawba Nuclear Station JPM E 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: 9.aRNOa. 2) Perform the following:

CRITICAL a) Start all lower containment ventilation units in low STEP speed.

STANDARD:

Applicant rotates switch VV LCVU 1C from OFF to LOW Examiner Note: This step is critical to ensure all Lower Containment Ventilation Units are providing cooling and available ___ SAT to be used in Max cooling mode in order to minimize Containment pressure. ___ UNSAT COMMENTS:

STEP 4: 9.aRNOa.2)

CRITICAL b) Start all upper containment ventilation units. STEP STANDARD:

Applicant rotates the following switches from OFF to NORM:

VV UCVU 1A VV UCVU 1C VV UCVU 1D Examiner Note: This step is critical to ensure all Upper Containment ___ SAT Ventilation Units are providing cooling and available to be used in Max cooling mode in order to minimize ___ UNSAT Containment pressure.

COMMENTS:

PAGE 6 0F 9

Catawba Nuclear Station JPM E 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: 9.aRNOa.2)

CRITICAL c) Place all upper and lower containment ventilation STEP 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 ___ SAT VV UCVU 1B VV UCVU 1C ___ UNSAT VV UCVU 1D Examiner Note: This step is critical to ensure all Containment Ventilation Units are providing maximum cooling in order to minimize Containment pressure.

COMMENTS:

STEP 6: 9.aRNOa.3) IF AT ANY TIME containment pressure reaches 1.2 PSIG, THEN perform the following:

STANDARD:

___ SAT Applicant acknowledges the continuous action statement and continues to step 4. ___ UNSAT COMMENTS:

PAGE 7 0F 9

Catawba Nuclear Station JPM E 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7: 9.aRNOa.4) GO TO Step 10.

STANDARD:

___ SAT Examiner Cue: Another operator will complete this procedure. JPM Complete

___ UNSAT COMMENTS:

END OF TASK 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 ________

PAGE 8 0F 9

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 2017 NRC Exam JPM F PAGE 1 OF 11

Catawba Nuclear Station JPM F 2017 NRC Exam EVALUATION SHEET EVALUATION SHEET Task: Reset Radiation Monitor Trip Setpoints Alternate Path: No Facility JPM #: WE-EMF-001 Safety Function: 7

Title:

Process Radiation Monitoring System K/A 073 A4.02 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/0/A/6500/080 (EMF RP86A Output Modules) rev. 17, Enclosure 4.2 (EMF RP86A Trip Setpoint Adjustment)

Task Standard: EMF50L TRIP 1 setpoint set to 6.3 E3 CPM and the TRIP 2 setpoint set to 9.0 E3 CPM per OP/0/A/6500/080 (EMF RP86A Output Modules) Enclosure 4.2 (EMF RP86A Trip Setpoint Adjustment).

Validation Time: 10 minutes Time Critical: Yes No X

===============================================================

Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 11

Catawba Nuclear Station JPM F 2017 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC # 155.

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. Ensure copy of EMF-50 setpoint log page has been replaced.

9. Place simulator in FREEZE until Examiner cue is given.

Instructor Action Delay Ramp Delete Event Final In PAGE 3 OF 11

Catawba Nuclear Station JPM F 2017 NRC Exam 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 at 100% power.

INITIATING CUES:

Following a discussion with Glenn from RP concerning a premature gaseous release termination, the Control Room Supervisor directs you to set EMF 50L setpoints using OP/0/A/6500/080 (EMF RP86A Output Modules) Enclosure 4.2 (EMF RP86A and RM1000 Trip Setpoint Adjustment) to the following values:

• Trip 1 = 6300 CPM

• Trip 2 = 9000 CPM OAC Program EMFLIB is currently not available.

EXAMINER NOTE: After reading the cue, provide the applicant with a copy of OP/0/A/6500/080 (EMF RP86A Output Modules) Enclosure 4.2 (EMF RP86A and RM1000 Trip Setpoint Adjustment).

PAGE 4 OF 11

Catawba Nuclear Station JPM F 2017 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

NOTE: 1. If desired, EMF setpoints adjustments may be performed from the EMF SETPOINT screen of OAC EMF Library (EMFLIB) Application. EMFLIB is user friendly, no procedure instructions are provided for this application.

2. The Trip Lamps can only be cleared if the activity level has decreased below the Trip Setpoint.

3. The setpoints given on release permits are already rounded to 3 significant digits and are entered into the EMF as is. Setpoints for non-release conditions are rounded up or down to 3 significant digits using standard mathematical rules for rounding.

STEP 1 3.1 IF necessary, press the clear key [CLR] to reset trip lamps STANDARD:

___ SAT Applicant verifies trip lamps dark or depresses the [CLR] key to clear alarms.

___ UNSAT COMMENTS:

STEP 2 3.2 Press the function key [FUN] to bring up the SELECT FUNCTION screen. CRITICAL STEP STANDARD:

Applicant depresses the [FUN] key to bring up the SELECT FUNCTION screen.

This step is critical, due to being the only way to get to the select function screen, which is required to input new Trip 1 and Trip 2 ___ SAT values.

___ UNSAT COMMENTS:

PAGE 5 0F 11

Catawba Nuclear Station JPM F 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3 3.3 Adjust Trip 1 Setpoint as follows:

CRITICAL 3.3.1 Press [1] for Trip 1 setting display screen. STEP STANDARD:

Applicant depresses the [1] to bring up the Trip 1 setting display screen.

This step is critical to bring up the screen that the new Trip 1 setting ___ SAT will be input into.

___ UNSAT COMMENTS:

STEP 4 3.3.2 Key in the desired Trip 1 setpoint. CRITICAL STEP STANDARD:

Applicant keys in 6300 CPM using the numeric keypad.

This step is critical to input the new Trip 1 setpoint required to meet the task standard. This new setpoint is checked in the next step. The critical requirement is for the new trip setpoint of 6300 CPM to be ___ SAT entered by the end of this JPM.

___ UNSAT COMMENTS:

PAGE 6 0F 11

Catawba Nuclear Station JPM F 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5 3.3.3 Ensure the following:

3.3.3.1 Setpoint is correctly displayed in the ENTER block on the setpoint display screen.

3.3.3.2 Setpoint is greater than the current EMF reading.

___ SAT STANDARD:

___ UNSAT Applicant ensures 6300 CPM is displayed in the ENTER block and that the setpoint is greater than the current reading on the EMF.

COMMENTS:

NOTE: Once the enter key [ENT] is pressed, the change in Trip 1 alarm setpoint is active.

STEP 6 3.3.4 Press the enter key [ENT]. This value is now displayed under TRIP 1 and the ENTER block is cleared. CRITICAL STEP STANDARD:

Applicant presses the [ENT] key and verifies the correct value under the Trip 1 on the display.

This step is critical to input the new Trip 1 setpoint. Again the critical requirement is to have the Trip 1 setpoint set to 6300 CPM by the end ___ SAT of the JPM.

___ UNSAT COMMENTS:

PAGE 7 0F 11

Catawba Nuclear Station JPM F 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7 3.3.5 Press the clear key [CLR] to return to the SELECT FUNCTION screen.

STANDARD:

___ SAT Applicant presses the [CLR] key to return to the SELECT FUNCTION screen. ___ UNSAT COMMENTS:

STEP 8 3.4 Adjust Trip 2 Setpoint as follows:

CRITICAL 3.4.1 Press [2] for Trip 2 setting display screen. STEP STANDARD:

Applicant presses [2] to bring up the Trip 2 setting display screen.

This step is critical to get to the required screen to input the new Trip ___ SAT 2 setpoint.

___ UNSAT COMMENTS:

STEP 9 3.4.2 Key in the desired Trip 2 setpoint.

CRITICAL STANDARD: STEP Applicant enters 9000 CPM using the numeric keypad.

This step is critical to input the new Trip 2 setpoint required to meet the task standard. This new setpoint is checked in the next step. The critical requirement is for the new trip setpoint of 9000 CPM to be ___ SAT entered by the end of this JPM.

___ UNSAT COMMENTS:

PAGE 8 0F 11

Catawba Nuclear Station JPM F 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 10 3.4.3 Ensure the following:

3.4.3.1 Setpoint is correctly displayed in the ENTER block on the setpoint display screen.

3.4.3.2 Setpoint is greater than the current EMF reading.

___ SAT STANDARD:

___ UNSAT Applicant ensures 9000 CPM is displayed in the ENTER block and that the entered setpoint is greater than the current reading on the EMF.

COMMENTS:

NOTE: Once the enter key [ENT] is pressed, the change in Trip 2 alarm setpoint is active.

STEP 11 3.4.4 Press the enter key [ENT]. This value is now displayed under TRIP 2 and the ENTER block is cleared. CRITICAL STEP STANDARD:

Applicant presses the [ENT] key and verifies the correct value under the Trip 2 on the display.

This step is critical to input the new Trip 2 setpoint. Again the critical ___ SAT requirement is to have the Trip 2 setpoint set to 9000 CPM by the end of the JPM. ___ UNSAT COMMENTS:

PAGE 9 0F 11

Catawba Nuclear Station JPM F 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 12 3.5 Press the clear key [CLR] twice to return to the normal display screen.

STANDARD:

___ SAT Applicant presses the [CLR] key twice to return to the normal display screen.

___ UNSAT EXAMINER CUE: Another operator will complete the procedure.

This JPM is complete.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 10 0F 11

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 at 100% power.

INITIATING CUES:

Following a discussion with Glenn from RP concerning a premature gaseous release termination, the Control Room Supervisor directs you to set EMF 50L setpoints using OP/0/A/6500/080 (EMF RP86A Output Modules) Enclosure 4.2 (EMF RP86A and RM1000 Trip Setpoint Adjustment) to the following values:

• Trip 1 = 6300 CPM

• Trip 2 = 9000 CPM OAC Program EMFLIB is currently not available.

Catawba Nuclear Station JPM G 2017 NRC Exam JPM G PAGE 1 OF 11

Catawba Nuclear Station JPM G 2017 NRC Exam 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 1NI-83 fully opened to vent 1B & 1C Cold Leg Accumulators to containment.

Validation Time: 15 minutes Time Critical: Yes No X

===============================================================

Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 11

Catawba Nuclear Station JPM G 2017 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC # 156.

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 ON TROUBLE)

ANN-AD11-E03 (TRANSFORMER B ON TROUBLE)

MAL-NC013B (NC COLD LEG B LEAK) 0.5 VLV-NI008F (NI65B ACCUM ISOL VLV FAIL 1

TO POSITION)

VLV-NI011F (NI76A ACCUM ISOL VLV FAIL 1

TO POSITION)

PAGE 3 OF 11

PAGE 4 0F 11 Catawba Nuclear Station JPM G 2017 NRC Exam 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.

PAGE 4 OF 11

Catawba Nuclear Station JPM G 2017 NRC Exam 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:

___ SAT Per initiating cue, the applicant should realize that this step is complete.

Also valve indication for each of the CLA discharge isolation valves is ___ UNSAT available, due to power already being aligned by the AO.

COMMENTS:

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: ___ SAT Applicant verifies that the yellow ECCS and D/G load sequencer ___UNSAT RESET lights are lit. Applicant acknowledges the If at any time statement.

COMMENTS:

PAGE 5 0F 11

Catawba Nuclear Station JPM G 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: 3. WHEN power is aligned, THEN perform the following: CRITICAL STEP

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.

___ SAT 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

___ UNSAT 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:

PAGE 6 0F 11

Catawba Nuclear Station JPM G 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: 3.RNOa. Perform the following:

1) Ensure containment isolation signals -

RESET:

• Phase A

• Phase B

___ SAT STANDARD:

___ UNSAT Applicant verifies that the yellow RESET lights are lit for both trains Phase A and Phase B isolations.

COMMENTS:

STEP 5: 3.RNOa.

2) Ensure 1VI-77B (VI Cont Isol) - OPEN STANDARD:

___ SAT Applicant determines that the red OPEN light lit and green CLSD light

___ UNSAT dark for 1VI-77B.

COMMENTS:

PAGE 7 0F 11

Catawba Nuclear Station JPM G 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: 3.RNOa.

3) IF VI pressure is less than 85 PSIG, THEN dispatch operator to ensure proper VI compressor operation.

___ SAT STANDARD:

___ UNSAT Applicant determines that VI pressure is ~ 90 PSIG. This step is N/A.

COMMENTS:

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:

___ SAT Applicant depresses the red OPEN pushbutton for 1NI-47A and verifies

___ UNSAT the red OPEN light lit and green CLSD light dark.

COMMENTS:

PAGE 8 0F 11

Catawba Nuclear Station JPM G 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8: 3.RNOa.4)

CRITICAL b) Place breaker 1CB-1 (behind 1MC-6)(Key STEP

1. 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 ___ SAT supply isolation valves for 1B and 1C CLAs which will be opened in the next step to allow venting the accumulators to containment. ___ UNSAT COMMENTS:

STEP 9: 3.RNOa.4)

CRITICAL c) OPEN valve for CLA(s) to be vented: STEP

• 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.

___ SAT This step is critical due to not being able to isolate these CLAs. If

___ UNSAT 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:

PAGE 9 0F 11

Catawba Nuclear Station JPM G 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 10: 3.RNOa.4)

CRITICAL d) CLOSE 1NI-47A. STEP 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. ___ SAT COMMENTS: ___ UNSAT STEP 11: 3.RNOa.4)

CRITICAL e) OPEN 1NI-83 (C-Leg Accums N2 Vent Ctrl) STEP to depressurize affected CLA(s).

STANDARD:

Applicant rotates potentiometer for 1NI-83 clockwise to full open 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 ___ SAT this point and the JPM may be terminated at your discretion. ___ UNSAT EVALUATOR CUE: Another operator will continue to vent the 1B and 1C Cold Leg Accumulators. This JPM is complete.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 10 0F 11

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 H 2017 NRC Exam JPM H PAGE 1 OF 14

Catawba Nuclear Station JPM H 2017 NRC Exam EVALUATION SHEET Task: Restore Normal Power to 1ETA From The Control Room Alternate Path: No Facility JPM #: DG3-003 Safety Function: 6

Title:

Emergency Diesel Generator (ED/G) System K/A 064 A4.07 Ability to manually operate and/or monitor in the control room: Transfer ED/G (with load) to grid.

Rating(s): 3.4 / 3.4 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/6350/002 Rev 179 Task Standard: 1ETA power being supplied from offsite through 1ATC and 1A D/G secured from the control room without a reverse power trip in accordance with OP/1/A/6350/002 (Diesel Generator Operation) Enclosure 4.17 (Shutdown of D/G 1A After An Automatic Start).

Validation Time: 12.5 minutes Time Critical: Yes No X

===============================================================

Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 14

Catawba Nuclear Station JPM H 2017 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC #157.

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 PAGE 3 OF 14

Catawba Nuclear Station JPM H 2017 NRC Exam 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 recovering from a blackout per AP/1/A/5500/007 Case I (Loss of Normal Power to an Essential Train).

• 1ATC is energized and available to supply 1ETA.

• D/G 1A Mode Select Switch is in the CTRL-RM position.

• D/G 1A Load Sequencer has been reset.

INITIATING CUES:

• The Control Room Supervisor instructs you to parallel D/G 1A to 1ETAs normal power source (1ATC) and shutdown D/G 1A per OP/1/A/6350/002 (Diesel Generator Operation) Enclosure 4.17 (Shutdown of D/G 1A After an Automatic Start) Step 3.2.

• Initial Conditions are complete.

• Concurrent Verification has been waived.

EXAMINER NOTE: After reading cue, provide the applicant with a copy of OP/1/A/6350/002 Enclosure 4.17 with the initial conditions completed.

PAGE 4 OF 14

Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: 3.2 IF shutting down the diesel from the Control Room, perform the following:

3.2.1 IF both the normal (ETA Norm Fdr Frm ATC)

AND alternate (ETA Alt Fdr Frm SATA) incoming feeder breakers are open, perform the following:

CAUTION: It is essential for the Operator to read and understand the following steps before attempting to re-synchronize the D/G and bus to the normal or alternate power source. Quick response to any changes in load and power factor when the breaker closes is required to ___ SAT reduce the likelihood of a reverse power D/G Breaker trip. ___ UNSAT 3.2.1.1 Adjust voltage using D/G 1A Volt Adjust to allow D/G 1A Volts to be one half to two divisions (50 to 200 volts) higher than Line Volts.

STANDARD:

Applicant uses the D/G voltage control pushbuttons to set D/G 1A VOLTS 50 to 200 volts higher than LINE VOLTS on 1MC-8.

COMMENTS:

PAGE 5 0F 14

Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2: 3.2.1.2 Place the D/G 1A Sync Switch in the ON position.

CRITICAL STANDARD: STEP Applicant rotates the D/G 1A Sync switch clockwise to the ON position.

Examiner Note: This step is critical to ensure that D/G 1A is in sync with the grid prior to closing the 1ETA normal incoming breaker. ___ SAT COMMENTS: ___ UNSAT STEP 3 3.2.1.3 Adjust D/G speed using D/G 1A Gov Ctrl such that the Synchroscope is moving slowly in the FAST direction, CRITICAL (approximately 1 revolution per 30 seconds). STEP STANDARD:

Applicant uses the D/G 1A Gov Ctrl pushbuttons to ensure that the Synchroscope is rotating slowly in the FAST direction.

___ SAT Examiner Note: This step is critical to prevent a reverse power trip once the Normal Feeder breaker to 1ETA is closed. ___ UNSAT COMMENTS:

PAGE 6 0F 14

Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4 CRITICAL CAUTION: The following three steps shall be performed prior to signing off STEP either step to reduce the likelihood of a reverse power D/G Breaker trip.

3.2.1.4 As the indicator reaches 1.5 min. before the vertical (synchronized) position, close one of the following breakers:

o ETA Norm Fdr Frm ATC OR o ETA Alt Fdr Frm SATA STANDARD: ___ SAT Once the Synchroscope indicator reaches the 1.5 min. before the ___ UNSAT vertical position, the applicant will depress the red CLOSE pushbutton and verify the red CLSD light lit and green OPEN light dark on the ETA Norm Fdr Frm ATC breaker. The applicant will then immediately perform the next step to prevent a reverse power D/G Breaker trip.

Examiner Note: This step is critical to parallel 1A D/G to the normal offsite circuit to meet the task standard.

COMMENTS:

PAGE 7 0F 14

Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5 3.2.1.5 Stabilize the D/G with a positive load and a lagging power factor. CRITICAL STEP STANDARD:

Applicant depresses the D/G 1A Gov Ctrl RAISE pushbutton to ensure that D/G 1A picks up a positive load.

Examiner Note: This step is critical to ensure the 1A D/G is stabilized with a positive load to prevent a reverse power D/G Breaker trip.

Examiner Note: As long as the applicant ensured that D/G 1A volts ___ SAT were 50 to 200 volts higher than line volts, power factor will be lagging, and depending on how much ___ UNSAT higher D/G 1A volts were than line volts, may be severely lagging.

COMMENTS:

PAGE 8 0F 14

Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6 3.2.1.6 IF the power factor meter indicates severely leading, (pegs high) AND power output decreases to 0 KW (pegs low), THEN IMMEDIATELY trip D/G 1A Bkr To ETA.

___ SAT STANDARD:

___ UNSAT Applicant determines that this step is not applicable and continues.

COMMENTS:

STEP 7 3.2.1.7 Place the D/G 1A Sync Switch in the OFF position.

Record time ____________

STANDARD:

___ SAT Applicant rotates the D/G 1A Sync Switch counterclockwise to the OFF

___ UNSAT position.

COMMENTS:

PAGE 9 0F 14

Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8 3.2.2 Verify one of the following breakers is closed:

o ETA Norm Fdr Frm ATC OR o ETA Alt Fdr Frm SATA

___ SAT STANDARD: ___ UNSAT Applicant verifies the red CLSD light lit for the ETA Norm Fdr Frm ATC breaker.

COMMENTS:

STEP 9 3.2.3 IF D/G 1A Bkr To ETA is open, go to Step 3.2.7.

STANDARD:

___ SAT Applicant determines that D/G 1A Bkr To ETA is closed by verifying the red CLSD light lit and this step is not applicable.

___ UNSAT COMMENTS:

PAGE 10 0F 14

Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 10 3.2.4 IF D/G load is < 2000 KW, WHILE maintaining power factor at approximately .95 lagging using D/G 1A Volt CRITICAL Adjust, adjust generator load using D/G 1A Gov Ctrl per STEP the following: {PIP 96-1185}

CAUTION: The following two steps shall be performed prior to signing off either step to reduce the likelihood of a reverse power D/G Breaker trip.

3.2.4.1 Reduce D/G load to 200 KW 3.2.4.2 Trip D/G 1A Bkr To ETA.

STANDARD:

Applicant depresses the D/G 1A Gov Ctrl LOWER pushbutton to decrease D/G 1A load to 200 KW while depressing the D/G 1A Volt Adjust LOWER pushbutton to maintain power factor at .95 lagging.

Once 200 KW load is attained, the applicant depresses the green OPEN pushbutton for D/G 1A Bkr To ETA and verifies the green OPEN ___ SAT light is lit.

___ UNSAT Examiner Note: If applicant loaded 1A D/G to > 2000 KW, step 3.2.5 will have them lower load to 2000 KW and after 15 minutes at this load, will have them decrease load to 200 KW and trip the D/G 1A breaker. If this is the case, once the applicant decreases D/G 1A load to 2000 KW, provide the following cue: 15 minutes have elapsed.

Examiner Note: Step 3.2.6 should be not applicable.

COMMENTS:

PAGE 11 0F 14

Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 11 3.2.7 Allow diesel to idle unloaded for a minimum of 5 minutes or until the following conditions are met:

o Jacket water outlet temperature is < 170°F.

o Lube oil temperature is < 170°F.

o Turbocharger exhaust temperatures have stabilized.

___ SAT STANDARD:

___ UNSAT Applicant acknowledges step and continues.

Examiner Cue: 5 minutes has elapsed.

COMMENTS:

STEP 12 3.2.8 Ensure one of the following conditions is met:

o The D/G Sequencer is RESET.

OR o Power has been removed from the D/G Sequencer.

___ SAT STANDARD:

___ UNSAT Applicant determines based off the initiating cue that D/G 1A load sequencer has been RESET and continues with the procedure.

COMMENTS:

PAGE 12 0F 14

Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 13 3.2.9 Depress D/G 1A OFF pushbutton.

CRITICAL Record time _________ STEP STANDARD:

Applicant depresses the D/G 1A green OFF pushbutton.

Examiner Note: This step is critical to shutdown 1A D/G to meet the ___ SAT JPM standard.

___ UNSAT COMMENTS:

STEP 14 3.2.10 WHEN the engine stops, dispatch Operators as necessary to verify the following:

STANDARD:

Applicant describes contacting and dispatching an AO to perform this step. ___ SAT Examiner Cue: An AO has been dispatched. Another operator will ___ UNSAT complete the remaining steps. This JPM is complete.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 13 0F 14

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 recovering from a blackout per AP/1/A/5500/007 Case I (Loss of Normal Power to an Essential Train).

• 1ATC is energized and available to supply 1ETA.

• D/G 1A Mode Select Switch is in the CTRL-RM position.

• D/G 1A Load Sequencer has been reset.

INITIATING CUES:

• The Control Room Supervisor instructs you to parallel D/G 1A to 1ETAs normal power source (1ATC) and shutdown D/G 1A per OP/1/A/6350/002 (Diesel Generator Operation) Enclosure 4.17 (Shutdown of D/G 1A After an Automatic Start) Step 3.2.

• Initial Conditions are complete.

• Concurrent Verification has been waived.

Catawba Nuclear Station JPM I 2017 NRC Exam JPM I PAGE 1 OF 10

Catawba Nuclear Station JPM I 2017 NRC Exam EVALUATION SHEET Task: Place the 2A Hydrogen Analyzer in Service Alternate Path: No Facility JPM #: VX-024 Safety Function: 5

Title:

Hydrogen Recombiner and Purge Control System (HRPS)

K/A 028 A1.01 Ability to predict and/or monitor changes in parameter (to prevent exceeding design limits) associated with operating the HRPS controls including: Hydrogen concentration Rating(s): 3.4 / 3.8 CFR: 41.5 / 45.5 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant X Perform X Simulate

References:

EP/2/A/5000/E-1 (Loss of Reactor or Secondary Coolant) Rev 26 OP/2/A/6450/010 (Containment Hydrogen Control Systems) Rev 26 Task Standard: Hydrogen Analyzer Train 2A in service monitoring upper containment via selection of Position 1.

Validation Time: 15 minutes Time Critical: Yes No X

===============================================================

Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 10

Catawba Nuclear Station JPM I 2017 NRC Exam 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 large break LOCA has occurred on Unit 2.

• The procedure currently in use is EP/2/A/5000/E-1 (Loss of Reactor or Secondary Coolant).

• Containment Hydrogen Analyzer 2B is tagged for maintenance.

INITIATING CUES:

• The Control Room Supervisor directs you to place Containment Hydrogen Analyzer 2A in service to Position 1 for sampling Upper Containment per OP/2/A/6450/010 (Containment Hydrogen Control Systems) Enclosure 4.9, step 3.1.

• All initial conditions are complete.

• Peer check has been waived.

EXAMINER NOTE: After reading cue, provide the applicant with a copy of OP/2/A/6450/010 Enclosure 4.9 with the initial conditions completed.

PAGE 3 OF 10

Catawba Nuclear Station JPM I 2017 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: 3.1 Place Hydrogen Analyzer Train A OR Train B in service.

3.1.1 IF aligning Hydrogen Analyzer Train A, proceed as follows:

3.1.1.1 Obtain Hydrogen Analyzer Control Panel Train A (2ELCP0251) key (Key #225) from WCC.

STANDARD:

___ SAT Applicant determines from the initiating cue that A train needs to be aligned and obtains the key #225.

___ UNSAT Examiner Note: Key not required to be obtained to complete this JPM task. Once key is identified give cue.

Examiner Cue: Key 225 has been obtained.

COMMENTS:

PAGE 4 0F 10

Catawba Nuclear Station JPM I 2017 NRC Exam STEP/STANDARD SAT/UNSAT NOTE: Steps 3.1.1.2 - 3.1.1.5 will be performed at Hydrogen Analyzer Control Panel 2A HACP-2A 2ELCP0251 (AB-579, DD-61). CRITICAL STEP STEP 2: 3.1.1.2 Select the desired sample location by positioning the "HYDROGEN ANALYZER SAMPLE VALVES PORTS" switch:

• Position "1" (for sampling Upper Containment)

• Position "2" (for sampling operating level)

• Position "3" (for sampling Steam Generator 1B cavity)

• Position "ALL" for sampling ALL 3 locations)

STANDARD:

___ SAT Applicant describes placing the HYDROGEN ANALYZER SAMPLE VALVES PORTS switch in position 1. ___ UNSAT Examiner Cue: Once switch is located by applicant and operation described, Switch is in position 1.

Examiner Note: This step is critical to be able to sample upper containment per the JPM standard.

COMMENTS:

PAGE 5 0F 10

Catawba Nuclear Station JPM I 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3 3.1.1.3 Verify the "POS 1: H2 ANALYZER POS 2: POST ACCIDENT SAMPLE PANEL" switch is in "POS. 1".

STANDARD:

Applicant describes verifying the switch is in POS 1. ___ SAT Examiner Cue: Once located by applicant, Switch is in position 1. ___ UNSAT COMMENTS:

PAGE 6 0F 10

Catawba Nuclear Station JPM I 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4 3.1.1.4 Insert key in "HYDROGEN ANALYZER CONT ISOLATION VALVES" key switch and turn to "OPEN" CRITICAL position. STEP STANDARD:

Applicant describes inserting the key and turning the key to the OPEN position.

Examiner Cue: Once applicant describes inserting the key and operation of the switch, Key switch is in the OPEN position.

___ SAT Examiner Note: This step is critical to open the containment isolation valves in order to be able to sample upper ___ UNSAT containment.

COMMENTS:

STEP 5 3.1.1.5 Verify the following indicating lights are lit:

• "H2 SAMPLE CONT. ISOLATION VALVES OPEN"

• Sample location(s) selected in Step 3.1.1.2.

STANDARD:

Applicant describes verifying the red OPEN light LIT for H2 Sample ___ SAT Containment Isolation Valves and the Upper Containment Sample Selected light lit. ___ UNSAT Examiner Cue: Once the lights are located, Red OPEN light is lit and Upper Containment Sample Selected light is lit.

COMMENTS:

PAGE 7 0F 10

Catawba Nuclear Station JPM I 2017 NRC Exam STEP/STANDARD SAT/UNSAT NOTE: Steps 3.1.1.6 - 3.1.1.7 will be performed inside A Train Hydrogen Analyzer Control Unit (PAMS) 2MIMT5320A (AB-579, DD-61).

STEP 6 3.1.1.6 Verify the "STANDBY/OFF" switch is in the "STANDBY" position.

STANDARD:

___ SAT Applicant describes verifying the STANDBY/OFF switch is in the

___ UNSAT STANDBY position.

Examiner Cue: Once switch is located, Switch is in the STANDBY position.

COMMENTS:

STEP 7 3.1.1.7 Place the "ON/OFF" switch in the "ON" position.

CRITICAL STANDARD: STEP Applicant describes moving the ON/OFF switch up to the ON position.

Examiner Cue: Once operation of switch is described, Switch is in the ON position and the green ON light is lit.

___ SAT Examiner Note: This step is critical to turn the Hydrogen Analyzer on.

___ UNSAT COMMENTS:

PAGE 8 0F 10

Catawba Nuclear Station JPM I 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8 3.1.1.8 Monitor H2 concentration at either of the following locations:

• "Hydrogen Analyzer Control Unit "2MIMT5320A" (AB-579, DD-61)

• "CONTAINMENT TRN A H2 ANAL" meter (2MIP5320) located on 2MC7.

___ SAT STANDARD:

___ UNSAT Applicant describes calling the control room to inform them that the hydrogen analyzers are in service and can be read on the local unit or on 2MC-7.

Examiner Cue: Hydrogen concentration will be monitored on 2MC-7.

This JPM is complete.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 9 0F 10

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 large break LOCA has occurred on Unit 2.

• The procedure currently in use is EP/2/A/5000/E-1 (Loss of Reactor or Secondary Coolant).

• Containment Hydrogen Analyzer 2B is tagged for maintenance.

INITIATING CUES:

• The Control Room Supervisor directs you to place Containment Hydrogen Analyzer 2A in service to Position 1 for sampling Upper Containment per OP/2/A/6450/010 (Containment Hydrogen Control Systems) Enclosure 4.9, step 3.1.

• All initial conditions are complete.

• Peer check has been waived.

Catawba Nuclear Station JPM J 2017 NRC Exam JPM J PAGE 1 OF 8

Catawba Nuclear Station JPM J 2017 NRC Exam EVALUATION SHEET Task: Align Seal Injection to the Unit 1 NC Pumps Alternate Path: No Facility JPM #: New Safety Function: 4S

Title:

Service Water System K/A 076 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS Rating(s): 3.5 / 3.7 CFR: 41.5 / 43.5 / 45.3 / 45.13 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant X Perform X Simulate

References:

AP/0/A/5500/020 (Loss of Nuclear Service Water) Rev 43 Task Standard: Standby Makeup Pump #1 in service providing seal injection to the Unit 1 NC Pumps.

Validation Time: 10 minutes Time Critical: Yes No X

===============================================================

Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 8

Catawba Nuclear Station JPM J 2017 NRC Exam 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 Loss of RN has occurred on Unit 1.

• Control room has entered AP/0/A/5500/020 (Loss of Nuclear Service Water).

• An operator has aligned the alternate power supply to 1EMXS per AP/20 Enclosure 4 (Align Alternate Power Supply To 1EMXS OR 2EMXS).

INITIATING CUES:

• The Control Room Supervisor directs you to place standby makeup pump #1 in service to provide seal injection to the Unit 1 NC pumps per AP/20 Enclosure 6 (Align Seal Injection to the Unit 1 NC Pumps). You are directed to use the local procedure to perform this task.

• Peer checks have been waived.

EXAMINER NOTE: Once the applicant has located the local copy of the procedure, hand the applicant a copy of AP/0/A/5500/020 Enclosure 6.

PAGE 3 OF 8

Catawba Nuclear Station JPM J 2017 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: 1. Ensure 1NV-876 (Stdby M/U To Cont Equip Sump 1A) -

CLOSED.

STANDARD:

Applicant verifies the green CLSD light lit and the red OPEN light dark ___ SAT for 1NV-876.

___ UNSAT Examiner Cue: Once located, Green light is lit.

COMMENTS:

STEP 2: 2. IF annunciator 0AD-11, C/1 (ESS MCC 1EMXS LOSS OF VOLTAGE) LIT, THEN:

STANDARD:

Applicant verifies 0AD-11, C/1 annunciator is dark and that step 2 is not ___ SAT applicable.

___ UNSAT Examiner Cue: Once the alarm window is located, Alarm is dark.

COMMENTS:

PAGE 4 0F 8

Catawba Nuclear Station JPM J 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3 3. IF UNIT 1 SSF CONTROLS ENGAGED DARK, THEN:

STANDARD:

Applicant verifies the UNIT 1 SSF CONTROLS ENGAGED light is LIT. ___ SAT Examiner Cue: Once located by applicant, Unit 1 SSF Controls ___ UNSAT Engaged light is lit.

COMMENTS:

STEP 4 4. IF UNIT 1 SSF CONTROLS ENGAGED LIT, THEN:

CRITICAL

a. Ensure the following valves - OPEN: STEP

• 1NV-865A (Stdby M/U Pump Suct Frm Xfer Tube)

• 1NV-872A (Stdby M/U Pmp Filt Otlt).

STANDARD:

Applicant describes depressing the red OPEN pushbuttons on 1NV-865A and 1NV-872A and verifying the red OPEN light is lit and green CLSD light is dark for both valves.

Examiner Cue: Once applicant describes operation of each valve, ___ SAT Red indicating light is lit.

___ UNSAT Examiner Note: This step is critical to align a suction and discharge path for Standby Makeup Pump #1.

COMMENTS:

PAGE 5 0F 8

Catawba Nuclear Station JPM J 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5 4.b. CLOSE 1NV-89A (NC Pmps Seal Ret Cont Isol).

CRITICAL STEP STANDARD:

Applicant depresses the green CLOSE pushbutton on 1NV-89A and verifies the green CLSD light lit and red OPEN light dark.

Examiner Cue: Once the valve control switch is located and operation described, Green light is lit.

___ SAT Examiner Note: This step is critical to ensure any voids in the seal leakoff line are collapsed prior to initiating flow from ___ UNSAT the standby makeup pump.

COMMENTS:

STEP 6 5. Ensure 1NV-877 (Stdby M/U To NC Pump Seal Inj) - OPEN.

STANDARD:

Applicant describes verifying the red OPEN light lit and green CLSD

___ SAT light dark for 1NV-877.

___ UNSAT Examiner Cue: Once the valve control switch is located, Red light is lit.

COMMENTS:

PAGE 6 0F 8

Catawba Nuclear Station JPM J 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7 6. Start STDBY M/U PUMP #1 by depressing ON pushbutton on SSF console. CRITICAL STEP STANDARD:

Applicant depresses the red ON pushbutton on switch for STDBY M/U PUMP #1 and verifies the red ON light lit and green OFF light dark.

Applicant may also check for Unit 1 standby makeup flow on SSF console.

Examiner Cue: Once operation of switch is described, Red ON light lit.

If Unit 1 standby makeup flow is checked, 26 GPM ___ SAT indicated.

___ UNSAT Examiner Note: This step is critical to place Standby Makeup Pump

1. 1 in service to provide seal injection flow to the Unit 1 NC Pumps.

COMMENTS:

STEP 8 7. Notify Control Room Supervisor of status of STDBY M/U PUMP #1.

STANDARD:

Applicant contacts the control room and reports that Standby Makeup

___ SAT Pump #1 is in service.

___ UNSAT Examiner Cue: Another operator will finish the procedure. This JPM is complete.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 7 0F 8

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 Loss of RN has occurred on Unit 1.

• Control room has entered AP/0/A/5500/020 (Loss of Nuclear Service Water).

• An operator has aligned the alternate power supply to 1EMXS per AP/20 Enclosure 4 (Align Alternate Power Supply To 1EMXS OR 2EMXS).

INITIATING CUES:

• The Control Room Supervisor directs you to place standby makeup pump #1 in service to provide seal injection to the Unit 1 NC pumps per AP/20 Enclosure 6 (Align Seal Injection to the Unit 1 NC Pumps). You are directed to use the local procedure to perform this task.

• Peer checks have been waived.

Catawba Nuclear Station JPM K 2017 NRC Exam JPM K PAGE 1 OF 13

Catawba Nuclear Station JPM K 2017 NRC Exam EVALUATION SHEET Task: Align Swing Inverter 1EIE to 1ERPA Alternate Path: No Facility JPM #: EPL-010 Safety Function: 6

Title:

AC Electrical Distribution System K/A 062 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) 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 X Simulate

References:

OP/1/A/6350/008 (125 VDC/120 VAC Vital Instrument and Control Power System) Enclosure 4.37 Rev 73 Task Standard: 1ERPA energized with power from swing inverter 1EIE.

Validation Time: 20 minutes Time Critical: Yes No X

===============================================================

Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 13

Catawba Nuclear Station JPM K 2017 NRC Exam 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.

• AC Panelboard 1ERPA is currently being supplied by 1VRD with inverter 1EIA shutdown per OP/1/A/6350/008 (125 VDC/120 VAC Vital Instrument and Control Power System) Enclosure 4.9 (1EIA Shutdown and Return to Service).

INITIATING CUES:

• The Control Room Supervisor directs you to align Swing Inverter 1EIE to supply AC Panelboard 1ERPA per OP/1/A/6350/008 Enclosure 4.37 (Placing in Service and Removing from Service 1EIE) beginning at step 3.3.

• Initial conditions are complete.

• Breaker padlock keys #275 and #277 have been obtained.

• All required PPE for this task has been obtained.

• Independent Verification requirements have been waived for this JPM.

EXAMINER NOTE: After reading cue, provide the applicant with a copy of OP/1/A/6350/008 Enclosure 4.37 with steps through step 3.2 complete.

PAGE 3 OF 13

Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

NOTE: Perform either Step 3.3 or 3.4 as per desired supply for 1EIE.

CRITICAL STEP 1: 3.3 IF Step 2.3 indicates that 1EDA is to supply 1EIE, align as STEP follows:

NOTE: 1EDA-F01E is padlock interlocked with 1EDC-F01D; only one breaker can be ON.

3.3.1 Remove the padlock (key #275) on 1EDA-F01E (Channel A Feeder-Swing Inverter 1EIE).

STANDARD:

Applicant describes opening the padlock on 1EDA-F01E and removing ___ SAT it.

___ UNSAT Examiner Cue: Once lock is located, Padlock removed.

Examiner Note: This step is critical to be able to operate the breaker in the next step to energize inverter 1EIE.

COMMENTS:

PAGE 4 0F 13

Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2: 3.3.2 Place 1EDA-F01E (Channel A Feeder-Swing Inverter 1EIE) in the ON position. CRITICAL STEP STANDARD:

Applicant describes rotating breaker 1EDA-F01E clockwise to the ON position.

Examiner Cue: Once breaker is located by applicant and operation described, Breaker is ON.

___ SAT Examiner Note: This step is critical to provide power to swing inverter 1EIE. ___ UNSAT COMMENTS:

STEP 3 3.3.3 Place the padlock (unlocked) near 1EDA-F01E (Channel A Feeder-Swing Inverter 1EIE).

STANDARD:

Applicant describes placing the padlock. ___ SAT Examiner Cue: Once described by applicant, Padlock placed. ___ UNSAT COMMENTS:

PAGE 5 0F 13

Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT NOTE: Step 3.3.5 must be performed immediately after Step 3.3.4 is completed. Failure to close the DC INPUT breaker immediately CRITICAL after the PRE-CHARGE pushbutton is released may result in STEP blown inverter input fuses.

STEP 4 3.3.4 Hold the PRE-CHARGE toggle switch on 1EIE in the EDA-LEFT position until the PRE-CHARGE indicator lamp has been illuminated for a minimum of 5 seconds.

STANDARD:

Applicant describes holding the toggle switch on 1EIE in the EDA-LEFT position and verifies the PRE-CHARGE light lit for a minimum of 5 ___ SAT seconds and then releases the toggle switch.

___ UNSAT Examiner Cue: Once applicant describes holding the PRE-CHARGE switch in the proper position, PRE-CHARGE indicator lamp has been illuminated for 5 seconds.

COMMENTS:

PAGE 6 0F 13

Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5 3.3.5 Place 1EIE B1 (1EIE DC Input From 1EDA) on 1EIE in the ON position. CRITICAL STEP STANDARD:

Applicant describes placing breaker 1EIE B1 in the ON position.

Examiner Cue: Once the breaker is located and proper operation described, Breaker is ON.

___ SAT Examiner Note: This step is critical to provide power to swing inverter 1EIE. ___ UNSAT COMMENTS:

STEP 6 3.4 IF Step 2.3 indicates that 1EDC is to supply 1EIE, align as follows:

STANDARD:

___ SAT Applicant determines that this step is not applicable.

___ UNSAT COMMENTS:

PAGE 7 0F 13

Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7 3.5 Place the sync selector switch on 1EME (MANUAL BYPASS SWITCH FOR SWING INVERTER 1EIE) in the SYNC ON CRITICAL position. STEP STANDARD:

Applicant describes placing the sync selector switch on 1EME to the SYNC ON position.

Examiner Cue: Once operation of switch is described, Switch is in ___ SAT the SYNC ON position.

___ UNSAT COMMENTS:

NOTE: Inverter fans are located in the top of the Inverter cabinet. A visual verification of the fans running requires that the upper cabinet door be opened.

STEP 8 3.6 Visually verify that both fans in 1EIE are running.

STANDARD:

___ SAT Applicant describes opening the upper cabinet door and verifying that

___ UNSAT both fans are running.

Examiner Cue: Both fans are running.

COMMENTS:

PAGE 8 0F 13

Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT NOTE: Inverter output voltage may be higher than specified range until inverter warms up.

STEP 9 3.7 IF inverter output voltage has NOT settled to 118 - 125 VAC within 15 minutes, contact IAE to adjust voltage.

STANDARD:

___ SAT Applicant checks inverter output voltage and determines that this step is not applicable. ___ UNSAT Examiner Cue: Once inverter output voltage found, Voltage reads 120 Volts.

COMMENTS:

STEP 10 3.8 Verify the following on 1EIE:

• INVERTER OUTPUT VOLTAGE 118 - 125.5 V

• INVERTER OUTPUT FREQUENCY 59.4 - 60.3 Hz STANDARD:

Applicant checks inverter output voltage and frequency within limits given. ___ SAT Examiner Cue: Once inverter output voltage found, Voltage reads ___ UNSAT 120 Volts.

Once inverter output frequency found, Frequency reads 60 Hz.

COMMENTS:

PAGE 9 0F 13

Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT STEP 11 3.9 Place 1EIE B2 (1EIE Inverter AC Output) on 1EIE in the ON position. CRITICAL STEP STANDARD:

Applicant describes placing breaker 1EIE B2 to the ON position.

Examiner Cue: Once operation of breaker is described, Breaker is in the ON position.

___ SAT Examiner Note: This step is critical to be able to power 1ERPA from swing inverter 1EIE. ___ UNSAT COMMENTS:

NOTE: 1. Inverter IN SYNC lights may take up to 60 minutes to illuminate as inverter circuits warmup if inverter has been shutdown for > 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

2. Both IN SYNC lamps listed in following step are powered from the same source.

STEP 12 3.10 Verify at least one of the following IN SYNC lights is illuminated:

• 1EME (MANUAL BYPASS SWITCH FOR SWING

___ SAT INVERTER 1EIE)

• 1EIE (TRAIN A VITAL SWING INVERTER)

___ UNSAT STANDARD:

Applicant describes verifying the IN SYNC lights lit.

Examiner Cue: Once the lights are located, Light is lit.

COMMENTS:

PAGE 10 0F 13

Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT NOTE: Procedure may continue before completing following step.

STEP 13 3.11 IF one of the above listed IN SYNC lights is NOT illuminated, initiate a work request to repair.

___ SAT STANDARD:

___ UNSAT Applicant determines that this step is not applicable.

COMMENTS:

STEP 14 3.12 Place the MANUAL BYPASS SWITCH on 1EME (MANUAL BYPASS SWITCH FOR SWING INVERTER CRITICAL 1EIE) to the INVERTER TO LOAD position. STEP STANDARD:

Applicant describes placing the manual bypass switch to the INVERTER TO LOAD position.

Examiner Cue: Once operation of the manual bypass switch is described, Manual Bypass Switch is in the INVERTER TO LOAD position. ___ SAT Examiner Note: This step is critical to power 1ERPA from swing ___ UNSAT inverter 1EIE.

COMMENTS:

PAGE 11 0F 13

Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT NOTE: Perform either Step 3.13 or 3.14 as per Step 2.2, applicable shutdown inverter.

STEP 15 3.13 IF Step 2.2 indicates 1EIA is shutdown, verify the output Volts and Amps on 1EIE indicate approximately the same as the AC System output Volts and Amps on the following:

• 1EME (MANUAL BYPASS SWITCH FOR SWING INVERTER 1EIE) output Volts and Amps

• 1EMA (MANUAL BYPASS SWITCH FOR INVERTER 1EIA) output Volts and Amps

___ SAT STANDARD:

___ UNSAT Applicant checks inverter output voltage and amps and compares them with 1EME and 1EMA.

Examiner Cue: Once applicant describes how to perform the step, Voltage is reading 120 Volts and Amps are reading 37 Amps on 1EIE, 1EME, and 1EMA. Another operator will complete the procedure. This JPM is complete.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 12 0F 13

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.

• AC Panelboard 1ERPA is currently being supplied by 1VRD with inverter 1EIA shutdown per OP/1/A/6350/008 (125 VDC/120 VAC Vital Instrument and Control Power System) Enclosure 4.9 (1EIA Shutdown and Return to Service).

INITIATING CUES:

• The Control Room Supervisor directs you to align Swing Inverter 1EIE to supply AC Panelboard 1ERPA per OP/1/A/6350/008 Enclosure 4.37 (Placing in Service and Removing from Service 1EIE) beginning at step 3.3.

• Initial conditions are complete.

• Breaker padlock keys #275 and #277 have been obtained.

• All required PPE for this task has been obtained.

• Independent Verification requirements have been waived for this JPM.

Catawba Nuclear Station Admin. JPM A.1-1 June 2017 NRC Exam JPM A.1-1 RO / SRO PAGE 1 OF 13

Catawba Nuclear Station Admin. JPM A.1-1 June 2017 NRC Exam EVALUATION SHEET Task: Perform Manual Shutdown Margin Calculation Alternate Path: N/A Facility JPM #: RB-127 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 / 43.5 / 45.12 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate

References:

OP/0/A/6100/006 (Reactivity Balance Calculation)

ROD Book Rev 780 Task Standard: Using OP/0/A/6100/006 Enclosure 4.3, calculates shutdown margin to be 1063

- 1097 pcm and determines that adequate shutdown margin does not exist.

This JPM must be complete within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> completion time required by T.S.

3.1.4.

Validation Time: 15 minutes Time Critical: Yes X No Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Time Critical (<1 hour)

Time Start: __________

Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 13

PAGE 3 0F 13 Catawba Nuclear Station Admin. JPM A.1-1 June 2017 NRC Exam 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:

• The Reactor Eng Analysis and Calc Toolkit (REACT) - CNS is inoperable.

• During performance of PT/0/A/4150/030 (RCCA Bank Repositioning), it was determined that Control Rods H4 and K14 were immovable and untrippable.

• IAE is investigating.

• Unit 1 conditions:

o Mode 1 at 100% RTP o Cycle burnup is 240 EFPD o Control Bank D position is 216 steps withdrawn o All other rods are at 226 steps withdrawn o Current Boron Concentration is 1200 ppmB INITIATING CUES:

• The Shift Manager has directed you to perform a shutdown margin calculation using OP/0/A/6100/006 (Reactivity Balance Calculations).

• Calculation is to be performed for current date and time.

• Initial conditions have been verified.

• Independent Verification has been waived.

• This JPM is time critical.

Calculated shutdown margin for current conditions __________ pcm Adequate shutdown margin exists (YES/NO) ___________

EXAMINER NOTE:

After reading cue, provide applicant with a copy of OP/0/A/6100/006.

PAGE 3 OF 13

Catawba Nuclear Station Admin. JPM A.1-1 June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT START TIME: _______

STEP / STANDARD SAT /

UNSAT STEP 1: 3.1 Determine the following information:

NOTE: Quantity of Misaligned Rods refers to rods that are misaligned but remain trippable. Only the total number of rods is required. (R.M.)

___ SAT

___ UNSAT STANDARD:

From the cue, the applicant records the information per the table above.

COMMENTS:

PAGE 4 OF 13

Catawba Nuclear Station Admin. JPM A.1-1 June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 2: 3.2 IF using the REACT program to complete the calculation, perform the following:

STANDARD:

___ SAT Applicant determines based of the initiating cue that this step is not applicable. ___ UNSAT COMMENTS:

NOTE: 1. A dropped rod is considered trippable. (R.M.)

2. All values are assumed positive unless otherwise indicated by parentheses. If parentheses precede the value [i.e. ( ) CRITICAL

_________ pcm], the sign provided with data must be recorded. STEP The calculations account for these sign conventions. (R.M.)

STEP 3: 3.3 IF performing the calculation manually, perform the following:

3.3.1 Determine available reactivity worth of trippable RCCAs for conditions in Step 3.1:

NOTE: Interpolation is NOT required in Step 3.3.1.1. Reactivity worth may be determined by choosing the lowest reactivity worth from Section 5.7 of the R.O.D. Manual associated with cycle burnups that bound the present cycle burnup recorded in Step 3.1. (R.M.)

3.3.1.1 Determine Total Available Rod Worth _______ pcm (Section 5.7 of R.O.D. manual) ___ SAT STANDARD: ___ UNSAT Applicant determines Total Available Rod Worth is 4949 pcm from R.O.D. Book Section 5.7 (5149 pcm per table - 200 pcm additional stuck rod worth penalty from note below the table).

Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS:

PAGE 5 OF 13

Catawba Nuclear Station Admin. JPM A.1-1 June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 4: 3.3.1.2 IF only one RCCA is untrippable, determine reactivity worth penalty for untrippable RCCA core location of Step 3.1.10 (Section 5.8 of R.O.D. manual). __________ pcm STANDARD:

___ SAT Applicant determines that this step is not applicable.

___ UNSAT COMMENTS:

STEP 5: 3.3.1.3 IF there are multiple untrippable RCCAs, perform the following:

A. Determine untrippable RCCA of Step 3.1.10 with the highest reactivity worth penalty (Section 5.8 of R.O.D.

manual). Core Location ______

___ SAT STANDARD:

___ UNSAT Applicant determines that RCCA Core Location H4 has the highest reactivity worth penalty.

COMMENTS:

PAGE 6 OF 13

Catawba Nuclear Station Admin. JPM A.1-1 June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 6: 3.3.1.3 B. Record reactivity worth of the untrippable RCCA of Step 3.3.1.3.A (Section 3.8 of R.O.D. Manual). CRITICAL

_________ pcm STEP STANDARD:

Applicant determines the reactivity worth of rod H4 per R.O.D. Section 5.8 is 473 pcm.

Examiner Note: This step is critical to ensure accurate result for final ___ SAT calculation.

___ UNSAT COMMENTS:

STEP 7: 3.3.1.3 C. Determine maximum stuck rod worth during cycle (Section 5.7 of the R.O.D. manual). CRITICAL

___________ pcm STEP STANDARD:

Applicant determines maximum stuck rod worth from R.O.D. manual section 5.7 is 885 pcm.

Examiner Note: This step is critical to ensure accurate result for final ___ SAT calculation.

___ UNSAT COMMENTS:

PAGE 7 OF 13

Catawba Nuclear Station Admin. JPM A.1-1 June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 8: 3.3.1.3 D. Calculate total untrippable RCCA reactivity worth penalty below: CRITICAL STEP STANDARD:

___ SAT Applicant calculates the Total untrippable RCCA worth penalty to be 1358 pcm. ___ UNSAT Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS:

STEP 9: 3.3.1.4 Record Total Untrippable RCCA Penalty from Step 3.3.1.2 or Step 3.3.1.3D, whichever is applicable.

__________ pcm STANDARD:

Applicant records 1358 pcm from step 3.3.1.3 D. ___ SAT

___ UNSAT COMMENTS:

PAGE 8 OF 13

Catawba Nuclear Station Admin. JPM A.1-1 June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT NOTE: Interpolation is NOT required in Step 3.3.1.5. Reactivity worth may be determined by choosing the highest reactivity worth from Section 5.6.3 of the R.O.D. Manual associated with rod positions that bound the present rod position. (R.M.)

STEP 10: 3.3.1.5 Determine Inserted Rod Worth for present bank positions:

___ SAT

___ UNSAT STANDARD:

Applicant calculates Inserted Worth of Present rod positions to be 12 pcm.

COMMENTS:

PAGE 9 OF 13

Catawba Nuclear Station Admin. JPM A.1-1 June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 11: 3.3.1.6 Calculate available reactivity worth of trippable RCCAs:

CRITICAL STEP STANDARD:

___ SAT Applicant calculates Available Reactivity Worth of Trippable RCCAs.

___ UNSAT Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS:

STEP 12: 3.3.1.7 Calculate total misaligned RCCA reactivity worth below:

___ SAT

___ UNSAT STANDARD:

Applicant determines that this step does not apply.

COMMENTS:

PAGE 10 OF 13

Catawba Nuclear Station Admin. JPM A.1-1 June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT NOTE: Interpolation of Power Defect is NOT required for Step 3.3.2.

Bounding burnups and power levels may be used to select the CRITICAL highest Power Defect from Section 5.9 of the R.O.D. manual. STEP (R.M.)

STEP 13: 3.3.2 Calculate SDM for present conditions:

STANDARD:

___ SAT Applicant calculates Present SDM to be +1063 pcm. Acceptable range

___ UNSAT of 1063 - 1097 pcm (if interpolation of power defect (1970 pcm) is performed).

Examiner Note: It is not critical for the applicant to record the + sign in the above calculation. If the applicant were to incorrectly record a - sign in the parentheses above, then this critical step would not be met.

Examiner Note: This step is critical to ensure accurate result for final calculation and to determine whether required SDM for present plant conditions is met.

COMMENTS:

PAGE 11 OF 13

Catawba Nuclear Station Admin. JPM A.1-1 June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 14: Adequate shutdown margin exists (YES/NO).

CRITICAL STANDARD: STEP Applicant determines that 1300 pcm of SDM is required for the current plant conditions and that an actual SDM of 1063 - 1097 pcm is not adequate. Applicant records NO for 2nd part of answer.

Examiner Note: This step is critical to determine that adequate SDM does not exist for the current plant conditions. ___ SAT COMMENTS: ___ UNSAT STOP TIME ________

PAGE 12 OF 13

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:

• The Reactor Eng Analysis and Calc Toolkit (REACT) - CNS is inoperable.

• During performance of PT/0/A/4150/030 (RCCA Bank Repositioning), it was determined that Control Rods H4 and K14 were immovable and untrippable.

• IAE is investigating.

• Unit 1 conditions:

o Mode 1 at 100% RTP o Cycle burnup is 240 EFPD o Control Bank D position is 216 steps withdrawn o All other rods are at 226 steps withdrawn o Current Boron Concentration is 1200 ppmB INITIATING CUES:

• The Shift Manager has directed you to perform a shutdown margin calculation using OP/0/A/6100/006 (Reactivity Balance Calculations).

• Calculation is to be performed for current date and time.

• Initial conditions have been verified.

• Independent Verification has been waived.

• This JPM is time critical.

Calculated shutdown margin for current conditions __________ pcm Adequate shutdown margin exists (YES/NO) ___________

JPM A.1-1 KEY Enclosure 4.3 OP/0/A/6100/006 Shutdown Margin - Untrippable / Misaligned Page 1 of 7 RCCA(s) - Modes 1 & 2

1. Limit and Precautions NOTE: All curves/tables used in this procedure are found in Unit One (Two) Reactor Operating Data (R.O.D.) manual. (R.M.)

1.1 This procedure is reactivity management related because it is used to verify proper balance and manipulation of reactivity using various tools (REACT, R.O.D. Manual, etc.).

1.2 Ensure all data used by this procedure are for the correct unit.

1.3 NC System T-AVG shall be maintained within +/-1 °F of T-REF in Modes 1 and 2 to reduce uncertainties in calculations.

1.4 SDM shall be 1300 pcm in Modes 1, 2, 3, and 4. (Tech Spec 3.1.1 and Enclosure 4.3, 4.4, 4.5 or 4.6) 1.5 REACT and manual calculations may NOT yield equal results due to minor differences in methods (i.e. interpolation). Reactor Engineering may be contacted if questions arise.

1.6 Independently performed calculations may NOT yield exactly the same results due to data taken at different times. The CRS and Reactor Engineering may be contacted if questions arise.

2. Initial Conditions None JPM A.1-1 KEY

JPM A.1-1 KEY Enclosure 4.3 OP/0/A/6100/006 Shutdown Margin - Untrippable / Misaligned Page 2 of 7 RCCA(s) - Modes 1 & 2

3. Procedure

_____ 3.1 Determine the following information:

NOTE: "Quantity of Misaligned Rods" refers to rods that are misaligned but remain trippable.

Only the total number of rods is required. (R.M.)

Step Description Reference Value 3.1.1 Unit N/A 1 3.1.2 Date/Time N/A Todays Date & Time 3.1.3 Present Power P1385 100 3.1.4 NC System Boron Concentration Latest sample 1200 ppm 3.1.5 Current burnup P1457 240 EFPD 3.1.6 Present control bank position OAC or Control 216 SWD on Board D Control Bank______

3.1.7 Present shutdown bank position OAC or Control 226 B _____

A _____ 226 Board 226 D _____

C _____ 226 226 E _____

3.1.8 Quantity of misaligned rods N/A 0 3.1.9 Number of untrippable RCCAs N/A 2 3.1.10 Untrippable RCCA(s) core N/A location(s) H4 , K14 N/A 3.2

_____ IF using the REACT program to complete the calculation, perform the following:

3.2.1 Access "Reactor Eng Analysis and Calc Toolkit (REACT) - CNS" from DAE.

3.2.2 Select "View" then "Reactivity Balance Calculations" on toolbar.

3.2.3 Select "SDM - Mode 1 or 2" tab in Reactivity Balance Calculations window.

JPM A.1-1 KEY

JPM A.1-1 KEY Enclosure 4.3 OP/0/A/6100/006 Shutdown Margin - Untrippable / Misaligned Page 3 of 7 RCCA(s) - Modes 1 & 2 CAUTION: All inputs must be checked carefully and corrected as needed before calculating results. The correct Unit must be specified.

NOTE: Untrippable control rods are input by clicking "Select Inoperable Rods" and any inserted shutdown banks are input using "Shutdown Banks Inserted" tab. (R.M.)

_____ 3.2.4 Enter appropriate values from Step 3.1 in "Input Data" section for the following:

"Shutdown Margin" tab "Shutdown Banks Inserted" tab

_____ 3.2.5 Obtain results as follows:

3.2.5.1 Click "Calculate" button.

3.2.5.2 Print program results.

3.2.5.3 Label printout appropriately.

3.2.5.4 Attach printout to this enclosure.

3.2.6 Sign below to document performance:

Performed by_________________________Date/Time:______/______

_____ 3.2.7 Ensure that an independent calculation per this enclosure has been separately performed.

NOTE: Independently performed calculations may NOT yield exactly the same results due to data taken at different times. The CRS and Reactor Engineering may be contacted if questions arise.

_____ 3.2.8 Verify that both performances of this enclosure yield equivalent results JPM A.1-1 KEY

JPM A.1-1 KEY Enclosure 4.3 OP/0/A/6100/006 Shutdown Margin - Untrippable / Misaligned Page 4 of 7 RCCA(s) - Modes 1 & 2

_____ 3.2.9 Perform one of the following based on results of the calculations:

_____ 3.2.9.1 IF Effective Shutdown Margin for a Present Position is greater than the Required Shutdown Margin, notify the CRS that Effective Shutdown Margin is acceptable.

OR

_____ 3.2.9.2 IF Effective Shutdown Margin for a Present Position is less than the Required Shutdown Margin, notify the CRS to apply the applicable Technical Specification Action.

_____ 3.2.10 Submit both performances of this enclosure to the Control Room Supervisor for review.

NOTE: 1. A dropped rod is considered trippable. (R.M.)

2. All values are assumed positive unless otherwise indicated by parentheses. If parentheses precede the value [i.e. ( )______________ pcm], the sign provided with data must be recorded. The calculations account for these sign conventions. (R.M.)

_____ 3.3 IF performing the calculation manually, perform the following:

_____ 3.3.1 Determine available reactivity worth of trippable RCCAs for conditions in Step 3.1:

NOTE: Interpolation is NOT required in Step 3.3.1.1. Reactivity worth may be determined by choosing the lowest reactivity worth from Section 5.7 of the R.O.D Manual associated with cycle burnups that bound the present cycle burnup recorded in Step 3.1. (R.M.)

_____ 3.3.1.1 Determine Total Available Rod Worth 4949

____________ pcm (Section 5.7 of R.O.D. manual)

N/A 3.3.1.2

_____ IF only one RCCA is untrippable, determine reactivity worth penalty for untrippable RCCA core location of Step 3.1.10 (Section 5.8 of R.O.D. manual). ____________ pcm

_____ 3.3.1.3 IF there are multiple untrippable RCCAs, perform the following:

X A. Determine untrippable RCCA of Step 3.1.10 with the highest reactivity worth penalty (Section 5.8 of ROD Manual).

H4 Core Location _________

JPM A.1-1 KEY

JPM A.1-1 KEY Enclosure 4.3 OP/0/A/6100/006 Shutdown Margin - Untrippable / Misaligned Page 5 of 7 RCCA(s) - Modes 1 & 2 X B. Record reactivity worth of the untrippable RCCA of Step 3.3.1.3.A (Section 5.8 of ROD Manual).

473

_____________ pcm X C. Determine maximum stuck rod worth during cycle (Section 885 5.7 of the R.O.D. manual). _____________ pcm X D. Calculate total untrippable RCCA reactivity worth penalty below:

Description Reference Value A.Number of Untrippable RCCAs Step 3.1.9 2 B. Highest Worth Penalty Step 3.3.1.3 B 473 pcm C. Max Stuck Rod Step 3.3.1.3 C 885 pcm Total untrippable RCCA Worth { [ (A) - 1] X (C) } + pcm Penalty for Multiple RCCAs (B) 1358

_____ 3.3.1.4 Record Total Untrippable RCCA Penalty from Step 3.3.1.2 or 1358 Step 3.3.1.3D, whichever is applicable. ______________ pcm NOTE: Interpolation is NOT required in Step 3.3.1.5. Reactivity worth may be determined by choosing the highest reactivity worth from Section 5.6.3 of the R.O.D Manual associated with rod positions that bound the present rod position. (R.M.)

_____ 3.3.1.5 Determine Inserted Rod Worth for present bank positions:

Description Reference Value A. HFP, Eq Xenon IRW for current Step 3.1.6 12

__________ pcm control bank position and current Step 3.1.5 cycle burnup (Section 5.6.3 of R.O.D. manual)

B. HFP, Eq Xenon IRW for current Step 3.1.7 0 SD E ________ pcm shutdown bank positions and Step 3.1.5 0 SD D ________ pcm current cycle burnup (Section 5.6.3 of 0 SD C ________ pcm R.O.D. manual) 0 SD B ________ pcm 0

SD A ________ pcm Inserted Worth of Present Sum of above Position 12 pcm JPM A.1-1 KEY

JPM A.1-1 KEY Enclosure 4.3 OP/0/A/6100/006 Shutdown Margin - Untrippable / Misaligned Page 6 of 7 RCCA(s) - Modes 1 & 2

_____ 3.3.1.6 Calculate available reactivity worth of trippable RCCAs:

Description Reference Value A. Total Available Rod Worth Step 3.3.1.1 4949 pcm B. Untrippable RCCAs Penalty Step 3.3.1.4 1358 pcm C. Inserted Worth of Present Step 3.3.1.5 12 pcm Position Available Reactivity Worth of Trippable RCCAs (A) - (B) - (C) 3579 pcm

_____ 3.3.1.7 Calculate total misaligned RCCA reactivity worth below:

Description Reference Value A. Quantity of Misaligned Rods Step 3.1.8 0 B. Maximum Dropped or Misaligned Section 5.7 of pcm Rod Worth ROD Manual 200 Total misaligned RCCA Reactivity (A) X (B) pcm 0

Worth NOTE: Interpolation of Power Defect is NOT required for Step 3.3.2. Bounding burnups and power levels may be used to select the highest Power Defect from Section 5.9 of the R.O.D. manual. (R.M.)

_____ 3.3.2 Calculate SDM for present conditions:

Description Reference Value A. Available reactivity worth of Step 3.3.1.6 pcm Trippable RCCAs 3579 B. Total misaligned RCCA reactivity Step 3.3.1.7 pcm Worth 0 C. Total Power Defect at present thermal Section 5.9 of pcm power (Step 3.1.3) and current cycle R.O.D. manual 2004 (1970) burnup (Step 3.1.5)

D. Transient Flux Redistribution Section 5.7 of Allowance R.O.D. manual 512 Present SDM (A) - (B) - (C) - (+ ) 1063 (1097) pcm (D)

JPM A.1-1 KEY

JPM A.1-1 KEY Enclosure 4.3 OP/0/A/6100/006 Shutdown Margin - Untrippable / Misaligned Page 7 of 7 RCCA(s) - Modes 1 & 2 3.3.3 Sign below to document performance:

Performed by_________________________Date/Time:______/______

_____ 3.3.4 Ensure that an independent calculation per this enclosure has been separately performed NOTE: Independently performed calculations may NOT yield exactly the same results due to data taken at different times. The CRS and Reactor Engineering may be contacted if questions arise.

_____ 3.3.5 Verify that both performances of this enclosure yield equivalent results

_____ 3.3.6 Perform one of the following based on results of the calculations:

_____ 3.3.6.1 IF present SDM is 1300 pcm per the applicable Technical Specification via COLR, notify the CRS that present SDM is acceptable.

OR

_____ 3.3.6.2 IF present SDM is < 1300 pcm notify the CRS to apply the applicable Technical Specification Action.

JPM A.1-1 KEY

Catawba Nuclear Station Admin. JPM A.1-2R June 2017 NRC Exam JPM A.1-2R RO PAGE 1 OF 11

Catawba Nuclear Station Admin. JPM A.1-2R June 2017 NRC Exam EVALUATION SHEET Task: Calculate Boric Acid and Water Addition to FWST Alternate Path: N/A Facility JPM #: 2016 NRC Exam JPM A.1-2R 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 / 43.5 / 45.2 / 45.6 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate

References:

OP/1/A/6200/014 (Refueling Water System), Enclosure 4.4 (FWST Makeup From Blender)

Task Standard: Applicant determines required boric acid addition of 368.8 gallons (368-370 acceptable) and reactor makeup water addition of 3402.2 gallons (3401-3403 acceptable) to complete the required FWST makeup.

Validation Time: 15 minutes Time Critical: Yes No X Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 11

PAGE 3 0F 11 Catawba Nuclear Station Admin. JPM A.1-2R June 2017 NRC Exam 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 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), determine the required amount of Boric Acid and RMWST water necessary to perform an FWST makeup from the blender as follows:

• Consider any initial conditions complete.

• 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.

Boric Acid RMWST Water EXAMINER NOTE:

After reading cue, provide applicant with a copy of OP/1/A/6200/014.

PAGE 3 OF 11

Catawba Nuclear Station Admin. JPM A.1-2R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT 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 _______________________

___ SAT

_____________ Boric Acid Tank #1

_____________ Boric Acid Tank #2

___ UNSAT STANDARD:

From the cue, applicant records S. Jackson as Chemistry person notified and checks Boric Acid Tank #1.

COMMENTS:

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

___ SAT STANDARD:

___ UNSAT From the cue, applicant determines that BAT #1 will be used and records 7500 ppmB.

COMMENTS:

PAGE 4 OF 11

Catawba Nuclear Station Admin. JPM A.1-2R June 2017 NRC Exam SAT /

STEP / STANDARD 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 (Cf) to attain the final boron concentration, CFW.

3.3.1 Initial volume of FWST _______ = Vi.

STANDARD:

___ SAT Using supplied information applicant enters the initial level of 373,875

___ UNSAT gallons.

COMMENTS:

STEP 4: 3.3.2 Final volume of FWST after makeup _______ = VFW.

STANDARD:

Using supplied information applicant enters the final level of 377,646 gallons. ___ SAT

___ UNSAT COMMENTS:

PAGE 5 OF 11

Catawba Nuclear Station Admin. JPM A.1-2R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 5: 3.3.3 Compute the total gallons of makeup water to be added to the FWST CRITICAL STEP

_________ = Vf..

STANDARD:

Applicant calculates, and records, makeup volume of 3,771 gallons.

377,646 - 373,875 = 3,771 Examiner Note: This step is critical to ensure accurate result for final ___ SAT calculation.

___ UNSAT COMMENTS:

STEP 6: 3.3.4 Initial boron concentration of water in the FWST

______ = Ci.

STANDARD:

From the cue, applicant records initial FWST boron concentration of

___ SAT 2740 ppmB.

___ UNSAT COMMENTS:

PAGE 6 OF 11

Catawba Nuclear Station Admin. JPM A.1-2R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 7: 3.3.5 Solve for the desired makeup water boron concentration, Cf. CRITICAL STEP Cf = CFW VFW - Ci Vi Cf = __________

Vf STANDARD:

Applicant calculates desired concentration of makeup water to be 737.1 ppmB Cf = (2720 x 377646) - (2740 x 373875) / 3771 = 737.1 ppmB (737-738 ppmB acceptable) ___ SAT Examiner Note: This step is critical to ensure accurate result for final ___ UNSAT calculation.

COMMENTS:

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 _________ = C1.

STANDARD:

___ SAT From the cue, applicant records Unit 1 BAT boron concentration of 7500 ppmB. ___ UNSAT COMMENTS:

PAGE 7 OF 11

Catawba Nuclear Station Admin. JPM A.1-2R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 9: 3.4.2 Boron concentration of water in RMWST

__________ = C2.:

STANDARD:

From the cue, applicant records Unit 1 RMWST boron concentration of 4 ppmB. ___ SAT

___ UNSAT COMMENTS:

STEP 10: 3.4.3 Total gallons of makeup water to be added to FWST

________ = Vf from Step 3.3.3.:

STANDARD:

Applicant records total makeup volume of 3,771 from step 3.3.3.

___ SAT COMMENTS: ___ UNSAT PAGE 8 OF 11

Catawba Nuclear Station Admin. JPM A.1-2R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 11: 3.4.4 Solve for the amount of boric acid to be added (V1) using Cf obtained in Step 3.3.5. CRITICAL STEP V1 = Vf (Cf - C2) V1 = ___________

C1 - C2 STANDARD:

Applicant calculates boric acid total of 368.8 gallons.

V1 = 3771 (737.1 - 4) / (7500 - 4) = 368.8 (368-370 acceptable)

___ SAT Examiner Note: This step is critical to ensure accurate result for final calculation. ___ UNSAT COMMENTS:

STEP 12: 3.4.5 If V1 is negative, contact the OWPM Staff for instruction on adjusting the boron concentration in the FWST.

STANDARD:

___ SAT Applicant determines that this step does not apply.

___ UNSAT COMMENTS:

PAGE 9 OF 11

Catawba Nuclear Station Admin. JPM A.1-2R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 13: 3.4.6 Solve for the amount of RMWST water to be added (V2). CRITICAL STEP V2 = Vf - V1 V2 = _________ gal.

STANDARD:

Applicant calculates required RMWST water to be 3402.2 gallons.

3771 - 368.8 = 3402.2 (3401-3403 acceptable)

Examiner Note: This step is critical to ensure accurate result for final ___ SAT calculation.

___ UNSAT COMMENTS:

STOP TIME ________

PAGE 10 OF 11

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), determine the required amount of Boric Acid and RMWST water necessary to perform an FWST makeup from the blender as follows:

• Consider any initial conditions complete.

• 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.

Boric Acid RMWST Water

Catawba Nuclear Station Admin. JPM A.1-2S June 2017 NRC Exam JPM A.1-2S SRO PAGE 1 OF 13

Catawba Nuclear Station Admin. JPM A.1-2S June 2017 NRC Exam EVALUATION SHEET Task: Calculate Boric Acid and Water Addition to FWST and determine Tech Spec actions.

Alternate Path: N/A Facility JPM #: 2016 NRC Exam JPM A.1-2S 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 / 43.5 / 45.2 / 45.6 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate

References:

OP/1/A/6200/014 (Refueling Water System), Enclosure 4.4 (FWST Makeup From Blender)

Task Standard: Applicant determines required boric acid addition of 368.8 gallons (368-370 acceptable) and reactor makeup water addition of 3402.2 gallons (3401-3403 acceptable) 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: 30 minutes Time Critical: Yes No X Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 13

PAGE 3 0F 13 Catawba Nuclear Station Admin. JPM A.1-2S June 2017 NRC Exam 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 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:

Using OP/1/A/6200/014 (Refueling Water System), perform an FWST makeup from the blender as follows:

• Consider any initial conditions complete.

• 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.

Boric Acid RMWST Water

1. 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 3 OF 13

PAGE 4 0F 13 Catawba Nuclear Station Admin. JPM A.1-2S June 2017 NRC Exam EXAMINER NOTE:

After reading cue, provide applicant with a copy of OP/1/A/6200/014.

PAGE 4 OF 13

Catawba Nuclear Station Admin. JPM A.1-2S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT 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 _______________________

___ SAT

_____________ Boric Acid Tank #1

_____________ Boric Acid Tank #2

___ UNSAT STANDARD:

From the cue, applicant records S. Jackson as Chemistry person notified and checks Boric Acid Tank #1.

COMMENTS:

PAGE 5 OF 13

Catawba Nuclear Station Admin. JPM A.1-2S June 2017 NRC Exam SAT /

STEP / STANDARD 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: ___ SAT From the cue, applicant determines that BAT #1 will be used and ___ UNSAT records 7500 ppmB.

COMMENTS:

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 (Cf) to attain the final boron concentration, CFW.

3.3.1 Initial volume of FWST _______ = Vi.

STANDARD: ___ SAT Using supplied information applicant enters the initial level of 373,875 ___ UNSAT gallons.

COMMENTS:

PAGE 6 OF 13

Catawba Nuclear Station Admin. JPM A.1-2S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 4: 3.3.2 Final volume of FWST after makeup _______ = VFW.

STANDARD:

Using supplied information applicant enters the final level of 377,646 gallons. ___ SAT

___ UNSAT COMMENTS:

STEP 5: 3.3.3 Compute the total gallons of makeup water to be added to the FWST CRITICAL STEP

_________ = Vf..

STANDARD:

Applicant calculates, and records, makeup volume of 3,771 gallons.

377,646 - 373,875 = 3,771 Examiner Note: This step is critical to ensure accurate result for final ___ SAT calculation.

___ UNSAT COMMENTS:

PAGE 7 OF 13

Catawba Nuclear Station Admin. JPM A.1-2S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 6: 3.3.4 Initial boron concentration of water in the FWST

______ = Ci.

STANDARD:

From the cue, applicant records initial FWST boron concentration of

___ SAT 2740 ppmB.

___ UNSAT COMMENTS:

STEP 7: 3.3.5 Solve for the desired makeup water boron concentration, Cf. CRITICAL STEP Cf = CFW VFW - Ci Vi Cf = __________

Vf STANDARD:

Applicant calculates desired concentration of makeup water to be 737.1 ppmB Cf = (2720 x 377646) - (2740 x 373875) / 3771 = 737.1 ppmB (737-738 ppmB acceptable)

___ SAT Examiner Note: This step is critical to ensure accurate result for final calculation. ___ UNSAT COMMENTS:

PAGE 8 OF 13

Catawba Nuclear Station Admin. JPM A.1-2S June 2017 NRC Exam SAT /

STEP / STANDARD 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 _________ = C1.

STANDARD:

___ SAT From the cue, applicant records Unit 1 BAT boron concentration of 7500 ppmB. ___ UNSAT COMMENTS:

STEP 9: 3.4.2 Boron concentration of water in RMWST

__________ = C2.:

STANDARD:

From the cue, applicant records Unit 1 RMWST boron concentration of 4 ppmB. ___ SAT

___ UNSAT COMMENTS:

PAGE 9 OF 13

Catawba Nuclear Station Admin. JPM A.1-2S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 10: 3.4.3 Total gallons of makeup water to be added to FWST

________ = Vf from Step 3.3.3.:

STANDARD:

Applicant records total makeup volume of 3,771 from step 3.3.3.

___ SAT COMMENTS: ___ UNSAT STEP 11: 3.4.4 Solve for the amount of boric acid to be added (V1) using Cf obtained in Step 3.3.5. CRITICAL STEP V1 = Vf (Cf - C2) V1 = ___________

C1 - C2 STANDARD:

Applicant calculates boric acid total of 368.8 gallons.

V1 = 3771 (737.1 - 4) / (7500 - 4) = 368.8 (368-370 acceptable)

Examiner Note: This step is critical to ensure accurate result for final ___ SAT calculation.

___ UNSAT COMMENTS:

PAGE 10 OF 13

Catawba Nuclear Station Admin. JPM A.1-2S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 12: 3.4.5 If V1 is negative, contact the OWPM Staff for instruction on adjusting the boron concentration in the FWST.

STANDARD:

___ SAT Applicant determines that this step does not apply.

___ UNSAT COMMENTS:

STEP 13: 3.4.6 Solve for the amount of RMWST water to be added (V2). CRITICAL STEP V2 = Vf - V1 V2 = _________ gal.

STANDARD:

Applicant calculates required RMWST water to be 3402.2 gallons.

3771 - 368.8 = 3402.2 (3401-3403 acceptable)

Examiner Note: This step is critical to ensure accurate result for final ___ SAT calculation.

___ UNSAT COMMENTS:

PAGE 11 OF 13

Catawba Nuclear Station Admin. JPM A.1-2S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT QUESTION 2 CRITICAL 1000: SLC 16-9.12 Condition D / LCO 3.5.4, Condition B STEP 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 requirement of SR 3.5.4.2 (Verify RWST borated water volume is 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

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. ___ SAT 1100: SLC 16-9.12 Condition D / LCO 3.5.4, Conditions B & C ___ UNSAT With an initial volume of 373,875 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.

373,875 (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.

Examiner Note: Determination of SLC 16-9.12 and TS 3.5.4 required actions (only) are critical to ensure proper actions are entered to address this adverse condition.

END OF TASK STOP TIME ________

PAGE 12 OF 13

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), determine the required amount of Boric Acid and RMWST water necessary to perform an FWST makeup from the blender as follows:

• Consider any initial conditions complete.

• 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.

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:

NRC JPM A.1-2R/S KEY Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 1 of 9

1. Limits and Precautions 1.1 Misaligning the FW System can result in draining the Refueling Water Storage Tank (FWST).

1.2 Miscalculating an FWST addition can result in boron concentration being lower than that required by the COLR.

1.3 If a Safety Injection occurs with the FW Pump in operation, the pump will lose its flowpath due to its suction valves receiving a close signal.

1.4 If either of the following occurs, a release concern may be created:

A large quantity (more than normal makeup) of non-degassed water is used for makeup to the FWST.

OR Any quantity of water with high activity (back leakage from NC into FWST) is added to the FWST.

2. Initial Conditions

_____ 2.1 Verify FWST operation per one of the following:

Normal operation per Enclosure 4.1 (FWST Normal Operation)

OR Purification per Enclosure 4.5 (FWST Purification) with the FW Pump secured OR Recirculation per Enclosure 4.6 (FWST Recirculation) with the FW Pump secured

_____ 2.2 Verify boron concentration control systems are available per OP/1/A/6150/009 (Boron Concentration Control).

_____ 2.3 IF charging has been established per OP/1/A/6200/001 (Chemical and Volume Control System), verify VCT level is adequate to allow boric acid blender alignment to the FWST for the duration of the FWST makeup.

_____ 2.4 Ensure that a pre-job briefing has been performed per AD-HU-ALL-0003 (Conduct of Pre-Job Briefings and Post-Job Critiques) that includes a discussion of reactivity management concerns with this procedure.

NRC JPM A.1-2R/S KEY

NRC JPM A.1-2R/S KEY Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 2 of 9

3. Procedure 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.

_____ 3.1 Notify Chemistry that the following Boric Acid Tank will be used for Tech Spec blending calculations {PIP 91-0449}:

Stephanie Jackson Person notified __________________________________

_____________ Boric Acid Tank #1

_____________ Boric Acid Tank #2

_____ 3.2 Document current boron concentration in the Boric Acid Tank as specified by Chemistry in Step 3.1 {PIP 91-0449}:

7500

_____________ ppmB NOTE: The final boron concentration used in the next step shall comply with COLR requirements for the current mode of operation.

_____ _____ 3.3 Determine the boron concentration of the makeup water to the FWST (Cf) to attain the final boron concentration, CFW.

3.3.1 373,875 = Vi.

Initial volume of FWST _______

3.3.2 377,646 = VFW.

Final volume of FWST after makeup _______

3.3.3 Compute the total gallons of makeup water to be added to the FWST 3,771

_________ = Vf.

Vf = VFW - Vi 3.3.4 2,740 = Ci.

Initial boron concentration of water in the FWST ______

3.3.5 Solve for the desired makeup water boron concentration, Cf.

CFW VFW - Ci Vi Cf = Cf = (2720)(377646)-(2740)(373875)

Vf 3771

= 737.1 NRC JPM A.1-2R/S KEY

NRC JPM A.1-2R/S KEY Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 3 of 9

_____ _____ 3.4 Determine the amount of boric acid and reactor makeup water to add as follows:

3.4.1 7,500 Boron Concentration of water in BAT _________ = C1.

3.4.2 Boron concentration of water in RMWST __________4 = C2.

3.4.3 3,771 Total gallons of makeup water to be added to FWST ________ = Vf from Step 3.3.3.

3.4.4 Solve for the amount of boric acid to be added (V1) using Cf obtained in Step 3.3.5.

Vf (Cf - C2) 3771(737.1-4)

V1 = V1 = = 368.8 C1 - C2 (7500-4)

_____ 3.4.5 IF V1 is negative, contact the OWPM Staff for instructions on adjusting the boron concentration in the FWST.

3.4.6 Solve for the amount of RMWST water to be added (V2).

V2 = Vf - V1 3771-368.8 3402.2 gal.

V2 = _________

NOTE: Step 3.5 assumes boric acid for FWST makeup will be supplied from BAT #1. If BAT #2 is aligned to Unit 1 per OP/1/A/6150/009 (Boron Concentration Control), Step 3.5 may be N/A'ed since both BATs are non-functional while in that alignment.

_____ 3.5 Determine effect on BAT #1 level as follows:

_____ 3.5.1 Record volume of BAT #1. (OAC Point C1P5645 (BAT Volume))

_____________ gallons

_____ 3.5.2 Determine final BAT volume by subtracting amount of acid to be added to FWST (Step 3.4.4) from initial volume (Step 3.5.1).

( )-( ) = _____________ gallons Step 3.5.1 Step 3.4.4

_____ 3.5.3 IF final BAT volume will be less than COLR requirements, perform one of the following:

_____ Place BAT #2 in service for Unit 1 per OP/1/A/6150/009 (Boron Concentration Control).

OR

_____ Declare BAT #1 non-functional per the following:

SRO Unit 1 boric acid flow path SLC 16.9-7 or 16.9-8 Unit 1 borated water source SLC 16.9-11 or 16.9-12 NRC JPM A.1-2R/S KEY

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 4 of 9

_____ _____ 3.6 Determine the final counter readings as follows:

3.6.1 Initial TOTAL MAKEUP COUNTER reading ________ = Tmi.

3.6.2 Initial BORIC ACID COUNTER reading ________ = TBi.

3.6.3 Solve for final TOTAL MAKEUP COUNTER reading (Tmf) using Vf obtained in Step 3.3.3.

Tmf = Tmi + Vf Tmf = ____________

3.6.4 Solve for final BORIC ACID COUNTER reading (TBf) using V1 obtained in Step 3.4.4.

TBf = TBi + V1 TBf = ____________

3.7 Set the following blender flow controllers to achieve the desired boron concentration and volume:

_____ 1NV-238A (B/A Xfer Pmp To Blender Ctrl)

_____ 1NV-242A (RMWST To B/A Blender Ctrl) 3.8 Ensure the selector switches for the following valves are in "AUTO":

_____ 1NV-238A (B/A Xfer Pmp To Blender Ctrl)

_____ 1NV-242A (RMWST To B/A Blender Ctrl) 3.9 Set the following counters to achieve the desired boron concentration and volume:

_____ BORIC ACID

_____ TOTAL MAKEUP

_____ _____ 3.10 Verify 1NI-96B (C-Leg Accum Chk Vlv Tst Isol) is closed.

_____ 3.11 Verify 1NB-5 (Unit 1 VCT To NB Evap Feed Demin Isol) (1ELCC0024) (AB-560, MM-52) is closed.

3.12 Place the switches for the following valves in the "CLOSE" position:

_____ 1NV-181A (B/A Blender Otlt To VCT)

_____ 1NV-186A (B/A Blender Otlt To VCT Otlt)

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 5 of 9

_____ 3.13 Close 1NV-187 (Boric Acid Blender Outlet To VCT Outlet Isol) (AB-583, KK-50, Rm 419).

3.14 Open the following valves:

_____ 1NV-183 (Boric Acid Blender Outlet To FWST & RHT Isol) (AB-585, KK-51, Rm 419)

_____ 1NV-185 (Boric Acid To FWST Isol) (AB-581, KK-51, Rm 419)

_____ 3.15 Place "NC MAKEUP MODE SELECT" switch in the "MANUAL" position.

3.16 Ensure one of the following Reactor Makeup Water Pumps is in "AUTO":

_____ "RX M/U WTR PUMP 1A" OR

_____ "RX M/U WTR PUMP 1B" 3.17 Ensure the Reactor Makeup Water Pump NOT selected to "AUTO" in Step 3.15 is in "OFF":

_____ "RX M/U WTR PUMP 1A" OR

_____ "RX M/U WTR PUMP 1B" 3.18 Ensure at least one of the following Boric Acid Transfer Pumps is in "AUTO":

_____ "B/A XFER PUMP 1A" AND/OR

_____ "B/A XFER PUMP 1B"

_____ 3.19 IF a Boric Acid Transfer Pump was NOT selected to "AUTO" in Step 3.18, ensure it is in "OFF":

_____ "B/A XFER PUMP 1A" OR

_____ "B/A XFER PUMP 1B"

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 6 of 9

_____ 3.20 IF Unit 1 is in Mode 1, 2, 3 or 4, perform the following:

_____ 3.20.1 Step 3.20.2 is an action to maintain the FWST within analyzed conditions during a Safety Injection. The designated individuals shall sign in the indicated places to document understanding of responsibilities. All required actions are to be completed prior to reaching FWST Lo Level (20%) to ensure no air entrainment occurs due to vortex formation in the FWST.

Operator in Control Room ________________________________

Shift Manager approval ___________________________________

_____ 3.20.2 IF AT ANY TIME while FWST makeup is in progress a Safety Injection occurs on Unit 1, terminate the makeup by performing the following:

_____ 3.20.2.1 Turn the "NC MAKEUP CONTROL" switch to the "STOP" position.

3.20.2.2 Ensure the following:

_____ Selected Reactor Makeup Water Pump stops.

_____ 1NV-238A (B/A Xfer Pmp To Blender Ctrl) closes.

_____ 1NV-242A (RMWST To B/A Blender Ctrl) closes.

_____ 3.21 Energize makeup control circuit by turning the "NC MAKEUP CONTROL" switch to the "START" position.

3.22 Ensure the following:

_____ Selected Reactor Makeup Water Pump starts.

_____ Selected Boric Acid Transfer Pump starts.

_____ 1NV-238A (B/A Xfer Pmp To Blender Ctrl) positions to produce desired boric acid flow.

_____ 1NV-242A (RMWST To B/A Blender Ctrl) positions to produce desired total makeup flow.

_____ 3.23 WHEN makeup is complete, turn the "NC MAKEUP CONTROL" switch to the "STOP" position.

3.24 Ensure the following:

_____ Selected Reactor Makeup Water Pump stops.

_____ Selected Boric Acid Transfer Pump stops.

_____ 1NV-238A (B/A Xfer Pmp To Blender Ctrl) closes.

_____ 1NV-242A (RMWST To B/A Blender Ctrl) closes.

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 7 of 9 3.25 Flush the flowpath for one minute as follows:

3.25.1 Place both Boric Acid Transfer Pumps in "OFF".

_____ "B/A XFER PUMP 1A"

_____ "B/A XFER PUMP 1B"

_____ 3.25.2 Place the selector switch for 1NV-238A (B/A Xfer Pmp To Blender Ctrl) in the "CLOSED" position.

_____ 3.25.3 Place the selector switch for 1NV-242A (RMWST To B/A Blender Ctrl) in the "OPEN" position.

_____ 3.25.4 Turn the "NC MAKEUP CONTROL" switch to the "START" position.

3.25.5 Ensure the following:

_____ Selected Reactor Makeup Water Pump starts.

_____ Total makeup flow indicates flow.

_____ 3.25.6 WHEN flushing is completed, turn the "NC MAKEUP CONTROL" switch to the "STOP" position.

3.25.7 Ensure the following:

_____ Selected Reactor Makeup Water Pump stops.

_____ Total makeup flow indicates no flow.

3.26 Place the selector switches for the following valves in "AUTO":

_____ 1NV-238A (B/A Xfer Pmp To Blender Ctrl)

_____ 1NV-242A (RMWST To B/A Blender Ctrl) 3.27 Close the following valves:

_____ 1NV-183 (Boric Acid Blender Outlet To FWST & RHT Isol) (AB-585, KK-51, Rm 419)

_____ 1NV-185 (Boric Acid To FWST Isol) (AB-581, KK-51, Rm 419)

_____ 3.28 Open 1NV-187 (Boric Acid Blender Outlet To VCT Outlet Isol) (AB-583, KK-50, Rm 419).

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 8 of 9 3.29 Place at least one of the following Boric Acid Transfer Pumps in "AUTO":

_____ "B/A XFER PUMP 1A" AND/OR

_____ "B/A XFER PUMP 1B"

_____ 3.30 IF needed to support plant conditions, place desired Boric Acid Transfer Pump in "ON":

_____ "B/A XFER PUMP 1A"

_____ "B/A XFER PUMP 1B"

_____ 3.31 IF desired, place the second Reactor Makeup Water Pump in "AUTO":

_____ "RX M/U WTR PUMP 1A"

_____ "RX M/U WTR PUMP 1B"

_____ 3.32 IF needed to support plant conditions, place desired Reactor Makeup Water Pump in "ON":

_____ "RX M/U WTR PUMP 1A"

_____ "RX M/U WTR PUMP 1B" 3.33 Place the selector switches for the following valves in "AUTO":

_____ 1NV-181A (B/A Blender Otlt To VCT)

_____ 1NV-186A (B/A Blender Otlt To VCT Otlt)

_____ 3.34 Align for makeup to the VCT per OP/1/A/6150/009 (Boron Concentration Control).

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 9 of 9 NOTE: FWST sample is required within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of completion of makeup.

_____ 3.35 IF either of the following conditions exists, recirculate the FWST using an NS pump:

A time constraint exists that prohibits the use of the normal recirculation of the FWST.

Unit/WCC SRO determines that NS System Availability is NOT a concern, and that recirculation via the NS is desired.

_____ 3.35.1 Place the FWST in recirculation via an NS pump per OP/1/A/6200/007 (Containment Spray System) at a flow rate of 900 GPM.

_____ 3.35.2 Notify Chemistry of the following:

Person notified ___________________________________

FWST is in recirculation with an NS Pump.

FWST is to be sampled per OP/1/A/6200/027 (Sampling Local Primary Sample Points).

_____ 3.35.3 WHEN notified by Chemistry that they are ready to obtain the sample, secure the NS pump per OP/1/A/6200/007 (Containment Spray System).

NOTE: FWST sample is required within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of completion of makeup.

_____ 3.36 IF FWST was NOT recirculated with the NS pump, perform the following:

3.36.1 Place the FWST in recirculation per one of the following:

_____ Enclosure 4.6 (FWST Recirculation).

OR

_____ Enclosure 4.5 (FWST Purification).

_____ 3.36.2 Notify Chemistry of the following:

Person notified ___________________________________

FWST is in recirculation with the FW Pump.

FWST is to be sampled per OP/1/A/6200/027 (Sampling Local Primary Sample Points).

NOTE: The FWST has been returned to normal operation as defined by Enclosure 4.1 (FWST Normal Operation) of this procedure.

3.37 Do NOT file this enclosure in the Control Copy folder of this procedure.

Catawba Nuclear Station Admin. JPM A.2 June 2017 NRC Exam JPM A.2 RO / SRO PAGE 1 OF 7

Catawba Nuclear Station Admin. JPM A.2 June 2017 NRC Exam EVALUATION SHEET Task: Use Flow Diagrams, Electrical Prints and Load Lists To Determine Leak Isolation Boundary Alternate Path: N/A Facility JPM #: 2012 NRC Exam Safety Function: N/A K/A 2.2.41 Ability to obtain and interpret station electrical and mechanical drawings.

Importance: 3.5 / 3.9 CFR: 41.10 / 45.12 / 45.13 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate

References:

Flow diagrams of the CM system (CN 1590-1.5, CN 1590-1.7), Load List for 1MXB, 6.9 KV bus one line electrical drawings Task Standard: Mechanical and electrical isolation boundary determined for work on 1CM-327 per JPM A.2 key.

Validation Time: 30 minutes Time Critical: Yes No X Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 7

PAGE 3 0F 7 Catawba Nuclear Station Admin. JPM A.2 June 2017 NRC Exam 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:

• The 1B Condensate Booster Pump has been shutdown in accordance with OP/1/A/6250/001 (Condensate and Feedwater System) and is to be tagged out for removal and replacement of 1CM-327 (1B Condensate Booster Pump Suction Header Relief Valve).

INITIATING CUES:

• The SM has directed you to use the provided materials to determine the required boundary for isolation for this work.

• You are to use the valves closest to the work being performed for isolation to minimize drain and fill time.

• Identify components, including the required position, for creation of a Clearance for replacement of 1CM-327, including:

o Mechanical isolations o Electrical isolations o Applicable Vent and Drain path

• Record your answer in the table on the following page.

EXAMINER NOTE:

After reading cue, provide applicant with a copy of CM flow diagrams (CN 1590-1.5 and CN 1590-1.7), load list for 1MXB, and 6.9 KV Switchgear one line diagrams (CN 1702-1.1, CN 1702-1.2, CN 1702-1.3, and CN 1702-1.4).

PAGE 3 OF 7

Catawba Nuclear Station Admin. JPM A.2 June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT START TIME: _______

STEP 1: Determine clearance boundary for 1CM-327 boundary.

CRITICAL STEP STANDARD:

Applicant identifies clearance boundary per table on the next page.

Note that only one vent valve or one drain valve is needed to meet the critical step.

___ SAT Examiner Note: This step is critical to be able to correctly isolate the 1B Condensate Booster Pump for replacement of ___ UNSAT 1CM-327.

COMMENTS:

PAGE 4 OF 7

Catawba Nuclear Station Admin. JPM A.2 June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT Component Position 1TB-11 Racked Out 1CM-93 Closed 1CM-94 Closed 1CM-96 Closed 1CM-97 Closed 1CM-58 Closed 1CM-306 Closed 1MXB F01D Off/Open 1MXB-R01B Off/Open

• 1CM-334 (Drain) Open

• 1CM-335 (Drain) Open

• 1CM-424 (Drain) Open

• 1CM-916 (Vent) Open

• 1CM-330 (Vent) Open

• 1CM-917 (Vent) Open STOP TIME ________

PAGE 5 OF 7

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:

• The 1B Condensate Booster Pump has been shutdown in accordance with OP/1/A/6250/001 (Condensate and Feedwater System) and is to be tagged out for removal and replacement of 1CM-327 (1B Condensate Booster Pump Suction Header Relief Valve).

INITIATING CUES:

• The SM has directed you to use the provided materials to determine the required boundary for isolation for this work.

• You are to use the valves closest to the work being performed for isolation to minimize drain and fill time.

• Identify components, including the required position, for creation of a Clearance for replacement of 1CM-327, including:

o Mechanical isolations o Electrical isolations o Applicable Vent and Drain path

• Record your answer in the table on the following page.

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

Answer Component Position

Catawba Nuclear Station Admin. JPM A.3R June 2017 NRC Exam JPM A.3R RO PAGE 1 OF 14

Catawba Nuclear Station Admin. JPM A.3R June 2017 NRC Exam EVALUATION SHEET Task: Calculate Total RL Discharge Flow Alternate Path: N/A Facility JPM #: WL-002 Safety Function: 9 K/A 2.3.11 Ability to control radiation releases Importance: 3.8 / 4.3 CFR: 41.11 / 43.4 / 45.10 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate

References:

PT/0/A/4250/011 (RL Temperature and Discharge Flow Determination)

Task Standard: Total RL Discharge Flow calculated to be 48,608 gpm (48,608 to 50,179 gpm acceptable range)

Validation Time: 22 minutes Time Critical: Yes No X Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 14

PAGE 3 0F 14 Catawba Nuclear Station Admin. JPM A.3R June 2017 NRC Exam 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:

• An LWR is in progress from Waste Monitor Tank A.

• The RL discharge header flow instrumentation is inoperable.

• PT/0/A/4250/011 (RL Temperature and Discharge Flow Determination) is in progress.

INITIATING CUES:

• The CRS directs you to calculate and record the total RL discharge flow per Enclosure 13.2 (Total Discharge Flow Calculation Sheet) of PT/0/A/4250/011.

• The following plant indications are noted:

Unit 1 Power 100%

Unit 2 Power NO Mode 0RLP5030 (RL Discharge Pressure) 67 psig 0RNP7380 (Lake Elevation) 568 feet C1P5856 (RN Calculate Total Flow) Out of service C1P5854 (RN Train A Calculated Total Flow) 14130 gpm C1P5855 (RN Train B Calculated Total Flow) 4840 gpm C1P5853 (Unit 1 Cooling Tower Evaporation) 12260 gpm RL Pumps A and B are in service RN discharge is aligned to RL discharge header OAC Databook is not available EXAMINER NOTE:

After reading cue, provide applicant with a copy of PT/0/A/4250/011 Enclosures 13.2 and 13.7.

PAGE 3 OF 14

Catawba Nuclear Station Admin. JPM A.3R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT START TIME: _______

STEP / STANDARD SAT /

UNSAT STEP 1: 1.1 Obtain Total RL Supply (A) as follows:

1.1.1 IF 0RLP5030 (Conventional LP Service Wtr Press) is NOT available contact engineering for optional indications and elevation corrections.

___ SAT STANDARD:

___ UNSAT Applicant determines per initiating cue that this step is not applicable.

COMMENTS:

PAGE 4 OF 14

Catawba Nuclear Station Admin. JPM A.3R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 2: 1.1.2 Perform the following calculations to obtain Total Discharge Head: CRITICAL STEP

___ SAT STANDARD:

___ UNSAT Applicant Calculates Total Discharge Head of 167.6 feet. (167 -168 Acceptable)

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

PAGE 5 OF 14

Catawba Nuclear Station Admin. JPM A.3R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 3: 1.1.3 Using Total Discharge Head from Step 1.1.2 obtain the RL Pump Flow value using one of the following: CRITICAL STEP

• Enclosure 13.7 OR

• OAC Databook in Secondary Systems Databook Calcs using RL Total Discharge Head vs. RL Pump Flow Rate.

STANDARD:

Applicant determines that Enclosure 13.7 should be used to determine ___ SAT RL pump flow value since the OAC Databook is not available per the initiating cue. Applicant determines RL pump flow to be 34,036 gpm. ___ UNSAT (34,036 - 35,244 gpm Acceptable)

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

PAGE 6 OF 14

Catawba Nuclear Station Admin. JPM A.3R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 4: 1.1.4 Once RL Pump Flow value is obtained, calculate Total RL Supply based on number of RL pumps in operation: CRITICAL STEP STANDARD:

Applicant calculates Total RL Supply to be 68,072 gpm. (68,072 -

70,488 gpm Acceptable)

___ SAT Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard. ___ UNSAT COMMENTS:

STEP 5: 1.1.5 Enter Total RL Supply (A) value in Step 1.4.

STANDARD:

Applicant records value for (A) in Step 1.4. ___ SAT COMMENTS: ___ UNSAT PAGE 7 OF 14

Catawba Nuclear Station Admin. JPM A.3R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 6: 1.2 IF RN discharge is aligned to the RL discharge header, obtain Total RN Flow (B) as follows:

1.2.1 IF OAC point C1P5856 (RN Calculated Total Flow) is available, perform the following:

STANDARD: ___ SAT Applicant determines per initiating cue that OAC point C1P5856 is not ___ UNSAT available and that this step is not applicable.

COMMENTS:

STEP 7: 1.2.2 IF OAC points C1P5854 (RN Train A Calculated Total Flow) AND C1P5855 (RN Train B Calculated Total Flow) are available, perform the following to obtain total RN flow:

___ SAT

___ UNSAT STANDARD:

Applicant records values for RN trains A and B calculated flow from values given in the initiating cue.

COMMENTS:

PAGE 8 OF 14

Catawba Nuclear Station Admin. JPM A.3R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 8: 1.2.3 IF either C1P5854 (RN Train A Calculated Total Flow) OR C1P5855 (RN Train B Calculated Total Flow) is NOT available, perform the following to obtain total RN flow:

STANDARD:

Applicant determines that this step is not applicable. ___ SAT

___ UNSAT COMMENTS:

STEP 9: 1.2.4 Perform the following calculations to obtain Total RN Flow:

CRITICAL STEP STANDARD:

Applicant calculates Total RN Flow (B) to be 18,970 gpm.

___ SAT Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard. ___ UNSAT COMMENTS:

PAGE 9 OF 14

Catawba Nuclear Station Admin. JPM A.3R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 10: 1.2.5 Enter Total RN Flow (B) in Step 1.4.

STANDARD:

___ SAT Applicant records value in Step 1.4.

___ UNSAT COMMENTS:

NOTE: Normal Cooling Tower evaporation loss @ 100% power is 9,000 to 14,000 gpm/unit.

STEP 11: 1.3 Obtain Total Cooling Tower Evaporation (C) as follows:

1.3.1 IF a Unit 1 NC Pump is NOT inservice AND Unit 1 is in Mode 5, 6, or No Mode, enter 0 for Unit 1 Cooling Tower Evaporation in Step 1.3.3.

___ SAT

___ UNSAT STANDARD:

Applicant determines that this step is not applicable.

COMMENTS:

PAGE 10 OF 14

Catawba Nuclear Station Admin. JPM A.3R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 12: 1.3.2 IF a Unit 2 NC Pump is NOT inservice AND Unit 2 is in Mode 5, 6, or No Mode, enter 0 for Unit 2 Cooling Tower Evaporation in Step 1.3.3.

STANDARD: ___ SAT Applicant determines per initiating cue that Unit 2 is in No Mode and ___ UNSAT enters 0 for Unit 2 evaporation in Step 1.3.3.

COMMENTS:

STEP 13: 1.3.3 Calculate Cooling Tower Total Evaporation as follows:

CRITICAL STEP STANDARD:

Applicant calculates Total Evaporation (C) to be 12,260 gpm.

___ SAT Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard. ___ UNSAT COMMENTS:

PAGE 11 OF 14

Catawba Nuclear Station Admin. JPM A.3R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 14: 1.3.4 Enter Total Evaporation (C) in Step 1.4.

STANDARD:

___ SAT Applicant enters value for Total Evaporation (C) in Step 1.4.

___ UNSAT COMMENTS:

STEP 15: 1.4 Perform the following to obtain Calculated Total RL Disch Flow: CRITICAL STEP STANDARD:

Applicant calculates the Calculated Total RL Disch Flow to be 74,782 gpm. (74,782 - 77,198 gpm Acceptable)

___ SAT Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard. ___ UNSAT COMMENTS:

PAGE 12 OF 14

Catawba Nuclear Station Admin. JPM A.3R June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT NOTE: Due to problems with current RL instrumentation (PIP C-10-4540) and discrepancies between calculated and OAC RL flow (PIP C- CRITICAL 12-1399), a safety factor is applied to the Calculated Total RL STEP Disch Flow of Step 1.4 to ensure conservative Total RL Disch Flow rates are used for dilution purposes. This is a temporary conservative action for use till RL discharge flow instrumentation problems are resolved.

STEP 16: 1.5 Apply dilution safety factor to obtain Total RL Discharge Flow from the Calculated Total RL Discharge Flow from Step 1.4 as follows:

___ SAT STANDARD:

___ UNSAT Applicant calculates Total RL Disch Flow to be 48,608 gpm. (48,608 -

50,179 gpm Acceptable)

Examiner Note: This step is critical to correctly determine Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 13 OF 14

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:

• An LWR is in progress from Waste Monitor Tank A.

• The RL discharge header flow instrumentation is inoperable.

• PT/0/A/4250/011 (RL Temperature and Discharge Flow Determination) is in progress.

INITIATING CUES:

• The CRS directs you to calculate and record the total RL discharge flow per Enclosure 13.2 (Total Discharge Flow Calculation Sheet) of PT/0/A/4250/011.

• The following plant indications are noted:

Unit 1 Power 100%

Unit 2 Power NO Mode 0RLP5030 (RL Discharge Pressure) 67 psig 0RNP7380 (Lake Elevation) 568 feet C1P5856 (RN Calculate Total Flow) Out of service C1P5854 (RN Train A Calculated Total Flow) 14130 gpm C1P5855 (RN Train B Calculated Total Flow) 4840 gpm C1P5853 (Unit 1 Cooling Tower Evaporation) 12260 gpm RL Pumps A and B are in service RN discharge is aligned to RL discharge header OAC Databook is not available Total RL Discharge Flow (Step 1.5): _____________ gpm

Catawba Nuclear Station Admin. JPM A.3S June 2017 NRC Exam JPM A.3S SRO PAGE 1 OF 15

Catawba Nuclear Station Admin. JPM A.3S June 2017 NRC Exam EVALUATION SHEET Task: Calculate Total RL Discharge Flow Alternate Path: N/A Facility JPM #: WL-001 Safety Function: N/A K/A 2.3.11 Ability to control radiation releases.

Importance: 3.8 / 4.3 CFR: 41.11 / 43.4 / 45.10 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate

References:

PT/0/A/4250/011 (RL Temperature and Discharge Flow Determination)

Task Standard: Total RL Discharge Flow calculated to be 48,608 gpm (48,608 to 50,179 gpm acceptable range) and determination that sufficient dilution flow exists for LWR

1. 2017025 approval.

Validation Time: 30 minutes Time Critical: Yes No X Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 15

PAGE 3 0F 15 Catawba Nuclear Station Admin. JPM A.3S June 2017 NRC Exam 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:

• The RL discharge header flow instrumentation is inoperable.

• An LWR package has been delivered to the control room for approval.

INITIATING CUES:

• You are directed to calculate and record the total RL discharge flow per Enclosure 13.2 (Total Discharge Flow Calculation Sheet) of PT/0/A/4250/011 and determine whether sufficient dilution flow exists to approve the LWR.

• The following plant indications are noted:

Unit 1 Power 100%

Unit 2 Power NO Mode 0RLP5030 (RL Discharge Pressure) 67 psig 0RNP7380 (Lake Elevation) 568 feet C1P5856 (RN Calculate Total Flow) Out of service C1P5854 (RN Train A Calculated Total Flow) 14130 gpm C1P5855 (RN Train B Calculated Total Flow) 4840 gpm C1P5853 (Unit 1 Cooling Tower Evaporation) 12260 gpm RL Pumps A and B are in service RN discharge is aligned to RL discharge header OAC Databook is not available EXAMINER NOTE:

After reading cue, provide applicant with a copy of PT/0/A/4250/011 Enclosures 13.2 and 13.7 and copy of LWR #2017025.

PAGE 3 OF 15

Catawba Nuclear Station Admin. JPM A.3S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT START TIME: _______

STEP / STANDARD SAT /

UNSAT STEP 1: 1.1 Obtain Total RL Supply (A) as follows:

1.1.1 IF 0RLP5030 (Conventional LP Service Wtr Press) is NOT available contact engineering for optional indications and elevation corrections.

___ SAT STANDARD:

___ UNSAT Applicant determines per initiating cue that this step is not applicable.

COMMENTS:

PAGE 4 OF 15

Catawba Nuclear Station Admin. JPM A.3S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 2: 1.1.2 Perform the following calculations to obtain Total Discharge Head: CRITICAL STEP

___ SAT STANDARD:

___ UNSAT Applicant Calculates Total Discharge Head of 167.6 feet. (167 -168 Acceptable)

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

PAGE 5 OF 15

Catawba Nuclear Station Admin. JPM A.3S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 3: 1.1.3 Using Total Discharge Head from Step 1.1.2 obtain the RL Pump Flow value using one of the following: CRITICAL STEP

• Enclosure 13.7 OR

• OAC Databook in Secondary Systems Databook Calcs using RL Total Discharge Head vs. RL Pump Flow Rate.

STANDARD:

Applicant determines that Enclosure 13.7 should be used to determine ___ SAT RL pump flow value since the OAC Databook is not available per the initiating cue. Applicant determines RL pump flow to be 34,036 gpm. ___ UNSAT (34,036 - 35,244 gpm Acceptable)

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

PAGE 6 OF 15

Catawba Nuclear Station Admin. JPM A.3S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 4: 1.1.4 Once RL Pump Flow value is obtained, calculate Total RL Supply based on number of RL pumps in operation: CRITICAL STEP STANDARD:

Applicant calculates Total RL Supply to be 68,072 gpm. (68,072 -

70,488 gpm Acceptable)

___ SAT Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard. ___ UNSAT COMMENTS:

STEP 5: 1.1.5 Enter Total RL Supply (A) value in Step 1.4.

STANDARD:

Applicant records value for (A) in Step 1.4. ___ SAT COMMENTS: ___ UNSAT PAGE 7 OF 15

Catawba Nuclear Station Admin. JPM A.3S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 6: 1.2 IF RN discharge is aligned to the RL discharge header, obtain Total RN Flow (B) as follows:

1.2.1 IF OAC point C1P5856 (RN Calculated Total Flow) is available, perform the following:

STANDARD: ___ SAT Applicant determines per initiating cue that OAC point C1P5856 is not ___ UNSAT available and that this step is not applicable.

COMMENTS:

STEP 7: 1.2.2 IF OAC points C1P5854 (RN Train A Calculated Total Flow) AND C1P5855 (RN Train B Calculated Total Flow) are available, perform the following to obtain total RN flow:

___ SAT

___ UNSAT STANDARD:

Applicant records values for RN trains A and B calculated flow from values given in the initiating cue.

COMMENTS:

PAGE 8 OF 15

Catawba Nuclear Station Admin. JPM A.3S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 8: 1.2.3 IF either C1P5854 (RN Train A Calculated Total Flow) OR C1P5855 (RN Train B Calculated Total Flow) is NOT available, perform the following to obtain total RN flow:

STANDARD:

Applicant determines that this step is not applicable. ___ SAT

___ UNSAT COMMENTS:

STEP 9: 1.2.4 Perform the following calculations to obtain Total RN Flow:

CRITICAL STEP STANDARD:

Applicant calculates Total RN Flow (B) to be 18,970 gpm.

___ SAT Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard. ___ UNSAT COMMENTS:

PAGE 9 OF 15

Catawba Nuclear Station Admin. JPM A.3S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 10: 1.2.5 Enter Total RN Flow (B) in Step 1.4.

STANDARD:

___ SAT Applicant records value in Step 1.4.

___ UNSAT COMMENTS:

NOTE: Normal Cooling Tower evaporation loss @ 100% power is 9,000 to 14,000 gpm/unit.

STEP 11: 1.3 Obtain Total Cooling Tower Evaporation (C) as follows:

1.3.1 IF a Unit 1 NC Pump is NOT inservice AND Unit 1 is in Mode 5, 6, or No Mode, enter 0 for Unit 1 Cooling Tower Evaporation in Step 1.3.3.

___ SAT

___ UNSAT STANDARD:

Applicant determines that this step is not applicable.

COMMENTS:

PAGE 10 OF 15

Catawba Nuclear Station Admin. JPM A.3S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 12: 1.3.2 IF a Unit 2 NC Pump is NOT inservice AND Unit 2 is in Mode 5, 6, or No Mode, enter 0 for Unit 2 Cooling Tower Evaporation in Step 1.3.3.

STANDARD: ___ SAT Applicant determines per initiating cue that Unit 2 is in No Mode and ___ UNSAT enters 0 for Unit 2 evaporation in Step 1.3.3.

COMMENTS:

STEP 13: 1.3.3 Calculate Cooling Tower Total Evaporation as follows:

CRITICAL STEP STANDARD:

Applicant calculates Total Evaporation (C) to be 12,260 gpm.

___ SAT Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard. ___ UNSAT COMMENTS:

PAGE 11 OF 15

Catawba Nuclear Station Admin. JPM A.3S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 14: 1.3.4 Enter Total Evaporation (C) in Step 1.4.

STANDARD:

___ SAT Applicant enters value for Total Evaporation (C) in Step 1.4.

___ UNSAT COMMENTS:

STEP 15: 1.4 Perform the following to obtain Calculated Total RL Disch Flow: CRITICAL STEP STANDARD:

Applicant calculates the Calculated Total RL Disch Flow to be 74,782 gpm. (74,782 - 77,198 gpm Acceptable)

___ SAT Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard. ___ UNSAT COMMENTS:

PAGE 12 OF 15

Catawba Nuclear Station Admin. JPM A.3S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT NOTE: Due to problems with current RL instrumentation (PIP C-10-4540) and discrepancies between calculated and OAC RL flow (PIP C- CRITICAL 12-1399), a safety factor is applied to the Calculated Total RL STEP Disch Flow of Step 1.4 to ensure conservative Total RL Disch Flow rates are used for dilution purposes. This is a temporary conservative action for use till RL discharge flow instrumentation problems are resolved.

STEP 16: 1.5 Apply dilution safety factor to obtain Total RL Discharge Flow from the Calculated Total RL Discharge Flow from Step 1.4 as follows:

___ SAT STANDARD:

___ UNSAT Applicant calculates Total RL Disch Flow to be 48,608 gpm. (48,608 -

50,179 gpm Acceptable)

Examiner Note: This step is critical to correctly determine Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

PAGE 13 OF 15

Catawba Nuclear Station Admin. JPM A.3S June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT STEP 17: Determine whether LWR #2017025 should be approved.

CRITICAL STEP STANDARD:

Applicant determines that the RL Low Flow Interlock would be set for 45,000 gpm and that sufficient dilution flow exists to approve the LWR.

Examiner Note: This step is critical to correctly determine that Total RL Flow is greater than the RL Low Flow Interlock Setpoint and that sufficient dilution flow exists to ___ SAT approve the LWR.

___ UNSAT COMMENTS:

END OF TASK STOP TIME ________

PAGE 14 OF 15

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:

• The RL discharge header flow instrumentation is inoperable.

• An LWR package has been delivered to the control room for approval.

INITIATING CUES:

• You are directed to calculate and record the total RL discharge flow per Enclosure 13.2 (Total Discharge Flow Calculation Sheet) of PT/0/A/4250/011 and determine whether sufficient dilution flow exists to approve the LWR.

• The following plant indications are noted:

Unit 1 Power 100%

Unit 2 Power NO Mode 0RLP5030 (RL Discharge Pressure) 67 psig 0RNP7380 (Lake Elevation) 568 feet C1P5856 (RN Calculate Total Flow) Out of service C1P5854 (RN Train A Calculated Total Flow) 14130 gpm C1P5855 (RN Train B Calculated Total Flow) 4840 gpm C1P5853 (Unit 1 Cooling Tower Evaporation) 12260 gpm RL Pumps A and B are in service RN discharge is aligned to RL discharge header OAC Databook is not available Total RL Discharge Flow (Step 1.5): _____________ gpm Sufficient dilution flow for LWR #2017025 approval? (YES/NO) _____________

JPM A.3 Answer Key Enclosure 13.2 PT/0/A/4250/011 Total Discharge Flow Calculation Sheet Page 1 of 3

1. Procedure 1.1 Obtain Total RL Supply (A) as follows:

N/A 1.1.1

_____ IF 0RLP5030 (Conventional LP Service Wtr Press) is NOT available contact engineering for optional indications and elevation corrections.

Engineer contacted: _____________________________

NOTE: Engineering specified optional indications and elevation corrections may be substituted for 0RLP5030 (Conventional LP Service Wtr Press) and the 3.9 psi elevation correction of following step to obtain Total Discharge Head.

_____ 1.1.2 Perform the following calculations to obtain Total Discharge Head:

RL Disch Pressure = 0RLP5030 + 3.9 psi 67 RL Disch Pressure = _________ 70.9

+ 3.9 psi = ________ps ig 568 Lake Elevation = ______________ 0RNP7380 (Lake Wylie Level) or obtained from hydro central per Step 1.1.4.2 of Enclosure 13.1 or Step 1.1.2.2 of Enclosure 13.8.

70.9 _____psig x 2.311 ft/psig) + (571.75 - ________ft

(_________ 568 167.6 t

) = _________f RL Disch Pressure Lake Elev Total Disch Head 167 - 168 Acceptable

_____ 1.1.3 Using Total Discharge Head from Step 1.1.2 obtain the RL Pump Flow value using one of the following:

X Enclosure 13.7 (RL Pumps Head / Capacity Table)

OR OAC Databook in "Secondary Systems Databook Calcs" using "RL Total Discharge Head vs. RL Pump Flow Rate".

_____ 1.1.4 Once RL Pump Flow value is obtained, calculate Total RL Supply based on number of RL pumps in operation:

34,036

__________________ 2 X ________________ 68,072

= ___________gpm (A)

RL Pump Flow Value # of pumps in operation Total RL Supply 68,072 - 70,488 Acceptable

_____ 1.1.5 Enter Total RL Supply (A) value in Step 1.4.

based on Encl 13.7 Acceptable Range JPM A.3 Answer Key

JPM A.3 Answer Key Enclosure 13.2 PT/0/A/4250/011 Total Discharge Flow Calculation Sheet Page 2 of 3

_____ 1.2 IF RN discharge is aligned to the RL discharge header, obtain Total RN Flow (B) as follows:

N/A 1.2.1

_____ IF OAC point C1P5856 (RN Calculated Total Flow) is available, perform the following:

1.2.1.1 Record the current value of C1P5856 (RN Calculated Total Flow)

C1P5856 ___________ gpm 1.2.1.2 Enter above value as Total RN Flow (B) in Step 1.4.

1.2.1.3 N/A Step 1.2.2 thru Step 1.2.5.

_____ 1.2.2 IF OAC points C1P5854 (RN Train A Calculated Total Flow) AND C1P5855 (RN Train B Calculated Total Flow) are available, perform the following to obtain total RN flow:

_____ 1.2.2.1 Record the value of C1P5854 (RN Train A Calculated Total Flow) below:

14,130 C1P5854 ___________ gpm (RN Pump Train A Flow)

_____ 1.2.2.2 Record the value of C1P5855 (RN Train B Calculated Total Flow) below:

4,840 C1P5855 ___________ gpm (RN Pump Train B Flow)

N/A 1.2.3

_____ IF either C1P5854 (RN Train A Calculated Total Flow) OR C1P5855 (RN Train B Calculated Total Flow) is NOT available, perform the following to obtain total RN flow:

_____ 1.2.3.1 Calculate RN Pump Train A flow:

__________ + __________ = __________gpm 1RNP7520 + 2RNP7520 = RN Pump Train A flow

_____ 1.2.3.2 Calculate RN Pump Train B flow:

__________ + __________ = __________gpm 1RNP7510 + 2RNP7510 = RN Pump Train B flow

_____ 1.2.4 Perform the following calculations to obtain Total RN Flow:

14,130 ______ + __________

__________ 4,840 ______ = __________

18,970 ___gpm (B)

RN Pump Train A Flow + RN Pump Train B Flow = Total RN Flow

_____ 1.2.5 Enter Total RN Flow (B) in Step 1.4.

JPM A.3 Answer Key

JPM A.3 Answer Key Enclosure 13.2 PT/0/A/4250/011 Total Discharge Flow Calculation Sheet Page 3 of 3 NOTE: Normal Cooling Tower evaporation loss @ 100% power is 9,000 to 14,000 gpm/unit.

1.3 Obtain Total Cooling Tower Evaporation (C) as follows:

N/A 1.3.1

_____ IF a Unit 1 NC Pump is NOT inservice AND Unit 1 is in Mode 5, 6, or No Mode, enter 0 for Unit 1 Cooling Tower Evaporation in Step 1.3.3.

_____ 1.3.2 IF a Unit 2 NC Pump is NOT inservice AND Unit 2 is in Mode 5, 6, or No Mode, enter 0 for Unit 2 Cooling Tower Evaporation in Step 1.3.3.

_____ 1.3.3 Calculate Cooling Tower Total Evaporation as follows:

12,260____________ + __________0_____________ = __________

__________ 12,260 _gpm (C)

Unit 1 Cooling Tower Evaporation + Unit 2 Cooling Tower Evaporation = Total Evaporation (C1P5853 or Step 1.3.1) (C2P5853 or Step 1.3.2)

_____ 1.3.4 Enter Total Evaporation (C) in Step 1.4.

_____ 1.4 Perform the following to obtain Calculated Total RL Disch Flow:

68,072 ___ + __________

__________ 18,970 ___ - __________

12,260 ___ = __________ 74,782 ___gpm Total RL Supply (A) + Total RN Flow (B) - Total Evaporati on (C) = Calculated Total RL Disch Flow 74,782 - 77,198 Acceptable NOTE: Due to problems with current RL instrumentation (PIP C-10-4540) and discrepancies between calculated and OAC RL flow (PIP C-12-1399), a safety factor is applied to the Calculated Total RL Disch Flow of Step 1.4 to ensure conservative Total RL Disch Flow rates are used for dilution purposes. This is a temporary conservative action for use till RL discharge flow instrumentation problems are resolved.

_____ 1.5 Apply dilution safety factor to obtain Total RL Discharge Flow from the Calculated Total RL Discharge Flow from Step 1.4 as follows:

74,782

________________________ 48,608 X 0.65 = _______________________ gpm Calculated Total RL Disch Flow Total RL Disch Flow Step 1.4 48,608 - 50,179 Acceptable Calculated By _________________________________ _________________

Operator/Initials Date/Time Verified By _________________________________ _________________

Operator/Initials Date/Time JPM A.3 Answer Key

JPM A.3 Answer Key Enclosure 13.7 PT/0/A/4250/011 RL Pumps Head / Capacity Table Page 1 of 1 Head Flow Head Flow Head Flow Head Flow 100 57192 146 46803 175.50 24110 200 15185 101 56997 147 46524 175.75 23824 201 14965 102 56800 148 46238 176.00 23544 202 14737 103 56602 149 45942 176.25 23271 203 14499 104 56403 150 45636 176.50 23005 204 14252 105 56202 151 45318 176.75 22747 205 13997 106 55999 152 44984 177.00 22496 206 13733 107 55795 153 44633 177.25 22252 207 13460 108 55590 154 44262 177.50 22016 208 13180 109 55383 155 43867 177.75 21787 209 12891 110 55175 156 43444 178.00 21566 210 12595 111 54966 157 42987 178.25 21352 211 12292 112 54755 158 42493 178.50 21146 212 11982 113 54543 159 41954 178.75 20947 213 11665 114 54330 160 41365 179.00 20756 214 11342 115 54116 161 40717 179.25 20571 215 11012 116 53900 162 40004 179.50 20394 216 10677 117 53683 163 39219 179.75 20224 217 10335 118 53465 164 38354 180.00 20061 218 9988 119 53246 165 37405 180.25 19904 219 9635 120 53025 166 36368 180.50 19754 220 9277 121 52804 167 35244 180.75 19611 221 8914 122 52581 168 34036 181.00 19473 222 8546 123 52357 169 32755 181.25 19341 223 8174 124 52132 170.00 31416 181.50 19215 224 7796 125 51906 170.25 31074 181.75 19095 225 7414 126 51679 170.50 30731 182.00 18980 226 7028 127 51451 170.75 30386 182.25 18870 227 6638 128 51222 171.00 30040 182.50 18764 228 6243 129 50991 171.25 29693 183 18568 229 5845 130 50760 171.50 29345 184 18224 230 5443 131 50527 171.75 28998 185 17935 231 5036 132 50293 172.00 28652 186 17689 232 4627 133 50058 172.25 28306 187 17475 233 4213 134 49821 172.50 27962 188 17286 234 3796 135 49583 172.75 27620 189 17112 235 3376 136 49343 173.00 27281 190 16949 236 2952 137 49102 173.25 26944 191 16791 237 2525 138 48859 173.50 26611 192 16635 238 2095 139 48613 173.75 26281 193 16476 239 1662 140 48365 174.00 25955 194 16314 240 1226 141 48114 174.25 25634 195 16146 241 786 142 47860 174.50 25318 196 15971 242 344 143 47603 174.75 25008 197 15788 144 47341 175.00 24703 198 15596 145 47075 175.25 24403 199 15395 Acceptable Range JPM A.3 Answer Key

Catawba Nuclear Station Admin. JPM A.4 June 2017 NRC Exam JPM A.4 SRO PAGE 1 OF 6

Catawba Nuclear Station Admin. JPM A.4 June 2017 NRC Exam EVALUATION SHEET Task: Classify an Event and fill out the Emergency Notification Form Alternate Path: N/A Facility JPM #: NEW 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)

NEI Rev 6 EAL Wallchart RP/0/A/5000/006 A (Notifications to States and Counties from the Control Room)

Task Standard: Using NEI Rev 6 EAL Wallchart and RP/0/A/5000/001, applicant classifies the event as a Site Area Emergency (SA9.1) in < 15 minutes, and then completes the Emergency Notification Form in < 15 minutes.

Validation Time: 30 minutes Time Critical: Yes X No Applicant: Time Start: __________

NAME___________________________ Docket #_______________ Time Finish: __________

Time Critical 1 (<15 min):

Time Start: __________

Time Finish: __________

Time Critical 2 (<15 min):

Time Start: __________

Time Finish: __________

Performance Rating:

Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 6

PAGE 3 0F 6 Catawba Nuclear Station Admin. JPM A.4 June 2017 NRC Exam 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:

• Both Units are at 100% RTP.

• A tornado warning has been issued for York County.

• The following events have occurred:

o AO on rounds contacts the control room to report a tornado sighted in the Switchyard.

o A Loss of Offsite Power (LOOP) occurs on Unit 2.

o A lighting pole has punctured the FWST on Unit 1 and water is spilling out into the missile shield.

INITIATING CUES:

• You are the Emergency Coordinator.

• Classify this event per RP/0/A/5000/001 (Emergency Classification).

• Emergency Coordinator Judgment is NOT to be used when making this classification.

• Fill out the Emergency Notification Form per RP/0/A/5000/006 A (Notifications to the States And Counties From the Control Room).

• This JPM is time critical.

EXAMINER NOTE:

After reading cue, provide applicant with a copy of RP/0/A/5000/001, RP/0/A/5000/006 A, and NEI Rev 6 EAL wallcharts.

PAGE 3 OF 6

Catawba Nuclear Station Admin. JPM A.4 June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT START TIME: _______

STEP / STANDARD SAT /

UNSAT Time Critical 1 Start: ____________

CRITICAL STEP 1: Classify the Event: STEP Unit 2 is in an Unusual Event (SU1.1) due to the loss of offsite power capability for > 15 minutes. Note 1 states The Emergency Coordinator should declare the event promptly upon determining that time limit has been exceeded, or will likely be exceeded.

Unit 1 is in an Alert (SA9.1) due to a tornado strike on site and the event has caused VISIBLE DAMAGE to a SAFETY SYSTEM component or structure needed for the current operating mode.

Since Unit 1 is in a higher classification than Unit 2, the emergency classification for the site will be an Alert (SA9.1).

STANDARD:

___ SAT Applicant determines from NEI Rev 6 EAL Wallchart, that Catawba is in an Alert SA9.1. ___ UNSAT Time Critical 1 Finish: ____________

Examiner Note: This step is critical to determine the proper Emergency Action Level prior to notification of the States and Counties. This time critical must be complete in < 15 minutes.

COMMENTS:

PAGE 4 OF 6

Catawba Nuclear Station Admin. JPM A.4 June 2017 NRC Exam SAT /

STEP / STANDARD UNSAT Time Critical 2 Start: ____________

CRITICAL STEP 2: Fill out Emergency Notification Form: STEP STANDARD:

Applicant properly fills out the emergency notification form within 15 minutes.

Time Critical 2 Finish: ____________

___ SAT Examiner Note: This step is critical to ensure timely and accurate notification of the States and Counties. This time ___ UNSAT critical must be complete in < 15 minutes.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 5 OF 6

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:

• Both Units are at 100% RTP.

• A tornado warning has been issued for York County.

• The following events have occurred:

o AO on rounds contacts the control room to report a tornado sighted in the Switchyard.

o A Loss of Offsite Power (LOOP) occurs on Unit 2.

o A lighting pole has punctured the FWST on Unit 1 and water is spilling out into the missile shield.

INITIATING CUES:

• You are the Emergency Coordinator.

• Classify this event per RP/0/A/5000/001 (Emergency Classification).

• Emergency Coordinator Judgment is NOT to be used when making this classification.

• Fill out the Emergency Notification Form per RP/0/A/5000/006 A (Notifications to the States And Counties From the Control Room).

• This JPM is time critical.

Declared EAL: _______________

Declaration Time: ______________

Items marked with a

• indicate critical tasks NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM MESSAGE # ________ 1 SIM:(803) ###-#### AUTHENTICATION CODE #: ___________

Confirmation Phone #: __________________

Lines 1 - 6 are required for INITIAL Notifications

1. EVENT: DRILL ACTUAL DECLARATION TERMINATION (ONLY Lines 1, 2, & 4 required)

• 2. AFFECTED SITE:

Catawba

• 3. EMERGENCY CLASSIFICATION UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY

• 4. SA9.1 EAL #______________

• Declaration Date: ____/____/____ Time: ________

Termination Date: ____/____/____ Time: ________(mark "N/A" for EAL # &Description)

The occurrence of any Table S-5 hazardous event AND EITHER: Event damage has caused EAL DESCRIPTION: _________________________________________________________________________________

indications of degraded performance in at least one train of a SAFETY SYSTEM needed for the current operating mode OR The event has caused VISIBLE DAMAGE to a SAFETY SYSTEM component or structure needed for the current operating mode

• 5. RELEASE TO THE ENVIRONMENT (caused by the emergency): X NONE IS OCCURRING HAS OCCURRED

• 6. PROTECTIVE ACTION RECOMMENDATIONS:

NONE EVACUATE: ___________________________________________________________________________________

SHELTER: ____________________________________________________________________________________

CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH ORO PLANS AND POLICIES OTHER:________________________________________________________________________________________

Lines 7-11 are NOT required for INITIAL notifications. Lines 7-11 may be provided separately for follow-up notifications.

7. PROGNOSIS: Upgrade in classification or PAR change is likely before the next follow-up notification Yes No

8. SITE UNIT(S) STATUS:

AFFECTED UNIT YES Unit 1 - _________% Power Shutdown: Date ___/_____/____Time _________

YES Unit 2 - _________% Power Shutdown: Date ___/_____/____Time _________

9. METEOROLOGICAL DATA:

Wind direction from: ________ degrees Wind Speed: _______ mph Precipitation: _______ inches Stability Class: A B C D E F G Lines 10 - 11 are completed for follow-up notifications, IF Line 5 IS OCCURRING or HAS OCCURRED is selected

10. AIRBORNE RELEASE CHARACTERIZATION: GROUND MIXED ELEVATED MAGNITUDE UNITS: Ci Ci/sec µCi/sec Noble Gases: ____________ Iodines: ____________ Particulates: ____________

11. DOSE PROJECTION: Projection period: __________ Hours Estimated Release Duration ________Hours Performed: DISTANCE TEDE (mrem) Thyroid CDE (mrem)

Date ___/_____/____ Site Boundary Time: _________ 2 Miles 5 Miles 10 Miles

12. REMARKS (As Applicable):__________________________________________________________________________

• Operator Name

13. APPROVED BY: _________________________TITLE: Emergency Coordinator

___________________Date XX XX XX

___/_____/____Time __________

14. NOTIFIED BY: ____________________________________________________Date ___/_____/____Time __________

15. RECEIVED BY (ORO use only): _______________________________________Date ___/_____/____Time __________

EM-78 / Nuclear Power Facility Emergency Notification Form / March 2016 revision

GOVERNMENT AGENCIES NOTIFIED Record the name, date, time, and agencies notified as applicable.

1. York County WP/EOC (name) deleted (date) (time)

2. Mecklenburg County WP/EOC (name) deleted (date) (time)

3. Gaston County WP/EOC (name)

(date) (time)

4. North Carolina EOC/WP (name) deleted (date) (time)

5. North Carolina Alt. WP (name) deleted (date) (time)

6. North Carolina Alt. EOC (name) deleted (date) (time)

7. South Carolina WP (name) deleted (date) (time)

8. South Carolina Alt. WP (name) deleted (date) (time)

9. South Carolina EOC (name) deleted (date) (time)

Items marked with a

• indicate critical tasks NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM MESSAGE # ________ 1 SIM:(803) ###-#### AUTHENTICATION CODE #: ___________

Confirmation Phone #: __________________

Lines 1 - 6 are required for INITIAL Notifications

1. EVENT: DRILL ACTUAL DECLARATION TERMINATION (ONLY Lines 1, 2, & 4 required)

• 2. AFFECTED SITE:

Catawba

• 3. EMERGENCY CLASSIFICATION UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY

• 4. SA9.1 EAL #______________

• Declaration Date: ____/____/____ Time: ________

Termination Date: ____/____/____ Time: ________(mark "N/A" for EAL # &Description)

The occurrence of any Table S-5 hazardous event AND EITHER: Event damage has caused EAL DESCRIPTION: _________________________________________________________________________________

indications of degraded performance in at least one train of a SAFETY SYSTEM needed for the current operating mode OR The event has caused VISIBLE DAMAGE to a SAFETY SYSTEM component or structure needed for the current operating mode

• 5. RELEASE TO THE ENVIRONMENT (caused by the emergency): X NONE IS OCCURRING HAS OCCURRED

• 6. PROTECTIVE ACTION RECOMMENDATIONS:

NONE EVACUATE: ___________________________________________________________________________________

SHELTER: ____________________________________________________________________________________

CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH ORO PLANS AND POLICIES OTHER:________________________________________________________________________________________

Lines 7-11 are NOT required for INITIAL notifications. Lines 7-11 may be provided separately for follow-up notifications.

7. PROGNOSIS: Upgrade in classification or PAR change is likely before the next follow-up notification Yes No

8. SITE UNIT(S) STATUS:

AFFECTED UNIT YES Unit 1 - _________% Power Shutdown: Date ___/_____/____Time _________

YES Unit 2 - _________% Power Shutdown: Date ___/_____/____Time _________

9. METEOROLOGICAL DATA:

Wind direction from: ________ degrees Wind Speed: _______ mph Precipitation: _______ inches Stability Class: A B C D E F G Lines 10 - 11 are completed for follow-up notifications, IF Line 5 IS OCCURRING or HAS OCCURRED is selected

10. AIRBORNE RELEASE CHARACTERIZATION: GROUND MIXED ELEVATED MAGNITUDE UNITS: Ci Ci/sec µCi/sec Noble Gases: ____________ Iodines: ____________ Particulates: ____________

11. DOSE PROJECTION: Projection period: __________ Hours Estimated Release Duration ________Hours Performed: DISTANCE TEDE (mrem) Thyroid CDE (mrem)

Date ___/_____/____ Site Boundary Time: _________ 2 Miles 5 Miles 10 Miles

12. REMARKS (As Applicable):__________________________________________________________________________

• Operator Name

13. APPROVED BY: _________________________TITLE: Emergency Coordinator

___________________Date XX XX XX

___/_____/____Time __________

14. NOTIFIED BY: ____________________________________________________Date ___/_____/____Time __________

15. RECEIVED BY (ORO use only): _______________________________________Date ___/_____/____Time __________

EM-78 / Nuclear Power Facility Emergency Notification Form / March 2016 revision

GOVERNMENT AGENCIES NOTIFIED Record the name, date, time, and agencies notified as applicable.

1. York County WP/EOC (name) deleted (date) (time)

2. Mecklenburg County WP/EOC (name) deleted (date) (time)

3. Gaston County WP/EOC (name) deleted (date) (time)

4. North Carolina EOC/WP (name) deleted (date) (time)

5. North Carolina Alt. WP (name) deleted (date) (time)

6. North Carolina Alt. EOC (name) deleted (date) (time)

7. South Carolina WP (name) deleted (date) (time)

8. South Carolina Alt. WP (name) deleted (date) (time)

9. South Carolina EOC (name) deleted (date) (time)