ML21320A328

301 File 2A2 Exam Draft Items (1).pdf

ML21320A328
Person / Time
Site:	Catawba
Issue date:	11/16/2021
From:	NRC/RGN-II
To:	Duke Energy Corp
References
Download: ML21320A328 (883)

Text

ML21320A328 Catawba Nuclear Station NRC Exam September 2021 2021 INITIAL LICENSE NRC EXAM SCENARIO # 1 Scenario #1 Catawba 2021 NRC Exam Page 1 of 150

Catawba Nuclear Station NRC Exam September 2021 Appendix D Scenario Outline Form ES-D-1 Facility: Catawba NRC Exam 2021 Scenario No.: 1 Op Test No.: 2021301 Examiners: Operators: SRO RO BOP Initial Conditions: Unit 1 is at 50% power at the MOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 50% power at the MOL. Unit 2 is at 100% power. Direction for the crew is to raise reactor power to 100%. A reactivity plan has been provided by Reactor Engineering for raising reactor power.

Event Event Event Malf. No.

No. Type* Description R - RO 1 N - BOP Raise Reactor Power N - SRO C - BOP 2 1KC-132 Fails closed C - SRO C - BOP 3 C - SRO 1KC-C37A Fails Open TS - SRO C - RO 4 Loss of both KG pumps with failure of auto turbine runback C - SRO 5 TS - SRO 1A NS Pump Loss of Power C - RO 6 Steam Leak C - SRO 7 M - ALL Steam Line Break Inside Containment C - RO 8 MSIVs fail to auto close on Main Steam Isolation C - SRO C - BOP 9 VA Unfiltered Exhaust Fans fail to secure on S/I C - SRO

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario #1 Catawba 2021 NRC Exam Page 2 of 150

Catawba Nuclear Station NRC Exam September 2021 Appendix D Scenario Outline Form ES-D-1 Scenario 1 - Summary Initial Condition Unit 1 is at 50% power at the MOL. Unit 2 is at 100% power.

Turnover:

Unit 1 is at 50% power at the MOL. Unit 2 is at 100% power. Direction for the crew is to raise reactor power to 100%. A reactivity plan has been provided by Reactor Engineering for raising reactor power.

Event 1 BOP will perform an initial dilution and RO will input desired load rate and target load into the main turbine. RO may also withdraw control rods prior to placing the main turbine in GO to initiate the raise in power.

Event History: 50% power increase at MOL last used 13 (2).

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. Crew will refer to Annunciator Response Procedure for 1AD-7 F/3 (Letdn HX Outlet Hi Temp), place 1KC-132 in Manual, and adjust CCW flow to restore letdown cooling.

Verifiable Action - BOP will manually control 1KC-132 as required.

Event History: This failure last used 19 (1).

Event 3 The Unit 1 A train KC miniflow valve 1KC-C37A will fail open. The crew will enter AP/1/A/5500/021 (Loss of Component Cooling Water) to start an additional KC pump. TS evaluation by the SRO is required.

Verifiable Action - The BOP will start an additional KC pump as directed.

Event History: KC miniflow valve failure last used 16 (2).

Event 4 The running KG (Generator Stator Cooling Water) pump will trip and the standby KG pump will fail to start requiring a turbine runback. Automatic runback will be failed requiring the RO to manually runback the main turbine. Crew will enter AP/1/A/5500/003 (Load Rejection) to address the runback. Once the manual runback is complete, the standby KG pump will start.

Verifiable Action - RO will manually runback the turbine to ~ 275 MWe. Crew will stabilize the plant at ~

25% reactor power, and place control rods to manual once the steam dumps have been closed (Tavg ~

3°F higher than Tref).

Event History: This failure last used 14 (3).

Event 5 A loss of power will occur to the 1A NS Pump. The SRO will determine appropriate TS.

Event History: This failure has not previously been used on an NRC exam.

Scenario #1 Catawba 2021 NRC Exam Page 3 of 150

Catawba Nuclear Station NRC Exam September 2021 Appendix D Scenario Outline Form ES-D-1 Event 6 A steam leak inside containment will develop from the 1C S/G. The crew will enter AP/1/A/5500/028 (Steam Leak) to address.

Verifiable Action - RO will adjust turbine load to maintain reactor power stable. Crew will initiate makeup to Unit 1 Upper Surge Tank. BOP will start all Lower Containment Ventilation Units in low speed, start all Upper Containment Ventilation Units, and place all Lower and Upper Containment Ventilation Units in MAX cooling mode.

Event History: This steam leak malfunction allowing use of AP-28 is new.

Event 7 Steam leak size will increase requiring the crew to enter EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) and eventually transition to EP/1/A/5000/E-2 (Faulted Steam Generator Isolation). Crew will isolate the faulted S/G. Once 1C S/G has completely blown down, the RO will throttle S/G PORVs on intact S/Gs to stabilize NC System Thots.

Verifiable Action - BOP will isolate feed flow to the faulted S/G. RO will throttle S/G PORVs on intact S/Gs to stabilize NC System Thots.

Event History: The last steam line break inside containment was performed in 19 (3) but was on 1B S/G.

Event 8 Once steam generator pressures lower to 775 PSIG, a Main Steam Isolation signal will be generated, but the Main Steam Isolation valves will fail to automatically close, requiring the RO to manually close them.

Verifiable Action - RO will manually close the MSIVs on Unit 1.

Event History: CNS has had single MSIVs failing to automatically close on previous exams (last one in 19 (3) - 1SM-5), but the failure of all MSIVs to close automatically on the MSI signal with manual closure of these valves possible has not been used before.

Event 9 Auxiliary Building Ventilation Unfiltered Exhaust Fans will fail to automatically secure following the Safety Injection.

Verifiable Action - BOP will manually secure the Unfiltered Exhaust Fans.

Event History: This failure was last used on 16 (3).

Manual Control of Automatic Functions Event Position Description 2 BOP Manually control Automatic Letdown HX Temperature Control Valve (1KC-132) 4 RO Manual turbine runback to ~ 275 MWe Scenario #1 Catawba 2021 NRC Exam Page 4 of 150

Catawba Nuclear Station NRC Exam September 2021 Appendix D Scenario Outline Form ES-D-1 Critical Task 1 - Runback the Main Turbine prior to Main Turbine Trip (must be below amps for 332 MW within 3.5 minutes).

Critical Task 2 - Close MSIVs and isolate CA flow to the faulted S/G prior to a severe challenge (Orange Path) on NC system Integrity CSF.

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

1. Total malfunctions (5-8) 8

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

3. Abnormal events (2-4) 4

4. Major transients (1-2) 1

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

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

7. Critical tasks (2-3) 2 Scenario #1 Catawba 2021 NRC Exam Page 5 of 150

Catawba Nuclear Station NRC Exam September 2021 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC # 13 and load schedule file for NRC Scenario 1 START TIME:__________

Scenario #1 Catawba 2021 NRC Exam Page 6 of 150

Catawba Nuclear Station NRC Exam September 2021 Trigger Instructor Action Delete Final Delay Ramp Event In ANN-AD11-B03 (TRANSFORMER ON A TROUBLE)

ANN-AD11-E03 (TRANSFORMER B ON TROUBLE)

OV_SLIM16SplncPB (KC-132 PRESS-2 :10 2 Setpoint Increment pushbutton) ED OV_SLIM16manPB (KC-132 Man PRESS-2 :11 :01 2 Pushbutton) ED VLV-NV035A (NV153A L/D HX ACTIVE 2 DIVERSION FAIL AUTO ACTIONS)

VLV-KC027F (KCC37A TRAIN A 3 RECIRC LINE ISOL VLV FAIL TO 1 :02 3 POSITION)

MAL-EHC003F (ALL TURBINE BLOCK 4 AUTO RUNBACK FAILURE)

STOP 4 LOA-EGB003 (KG PUMPS) 4 BOTH RUN B/A 4 LOA-EGB003 (KG PUMPS) 5:00 4 RES LOA-NS003 (RACKOUT NS PMP RACK-5 5 1A) OUT MAL-SM007C (STM BRK INSIDE 5 3000 :15 6 CONTAINMENT LOOP C)

MAL-SM007C (STM BRK INSIDE 7 2e+6 :15 7 CONTAINMENT LOOP C)

MAL-SM006A (SM7 MSIV A ACTIVE 8 FAILURE)

MAL-SM006B (SM5 MSIV B ACTIVE 8 FAILURE)

MAL-SM006C (SM3 MSIV C ACTIVE 8 FAILURE)

MAL-SM006D (SM1 MSIV D ACTIVE 8 FAILURE)

MAL-SM006A (SM7 MSIV A 10 ACTIVE :01 8 FAILURE)

MAL-SM006B (SM5 MSIV B 11 ACTIVE :01 8 FAILURE)

MAL-SM006C (SM3 MSIV C 12 ACTIVE :01 8 FAILURE)

MAL-SM006D (SM1 MSIV D 13 ACTIVE :01 8 FAILURE)

MAL-ISE011B (AUX BLDG FANS ACTIVE 9 FAIL TO AUTO STOP)

Scenario #1 Catawba 2021 NRC Exam Page 7 of 150

Catawba Nuclear Station NRC Exam September 2021 17 LOA-CNT002 (H2 ANALYZERS) BOTH 10:00 Ensure Event 10 = x02i071c (1SM-7 Close PB)

Ensure Event 11 = x02i074c (1SM-5 Close PB)

Ensure Event 12 = x02i079c (1SM-3 Close PB)

Ensure Event 13 = x02i082c (1SM-1 Close PB)

Ensure CRD Bank Select Switch is in MANUAL and withdraw control rods 2 steps Scenario #1 Catawba 2021 NRC Exam Page 8 of 150

Catawba Nuclear Station NRC Exam September 2021

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, Increase Reactor Power BOOTH INSTRUCTOR ACTION IF contacted as DEC-BA (Balancing Authority / SOC) by the crew to inform of commencing power increase, REPEAT the information.

BOOTH INSTRUCTOR ACTION WHEN contacted as Secondary Chemistry to obtain maximum blowdown for appropriate load (step 3.2.3.9), REPORT Maintain blowdown at current flow rates.

3.3 Scenario EVENT 2, Letdown Heat Exchanger Temperature Control Valve (1KC-132)

Fails Closed 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, KC Miniflow Valve 1KC-C37A fails open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause KC miniflow valve 1KC-C37A to fail open.

Scenario #1 Catawba 2021 NRC Exam Page 9 of 150

Catawba Nuclear Station NRC Exam September 2021 BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1KC-C37A, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as an AO to perform a post start check out of the started KC pump, after 5 minutes REPORT:

• KC pump 1A1, 1B1, 1B2 looks good for continued operation.

3.5 Scenario EVENT 4, Loss of both KG pumps / Automatic Turbine Runback Failure BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 4 to cause the running KG pump to trip and failure of the standby KG pump to start.

BOOTH INSTRUCTOR ACTION IF contacted as an AO to investigate the loss of KG, after 5 minutes REPORT:

• I do not see any reason that the running KG pump tripped, and I have the 1B KG pump in service. I will contact SPOC to help with troubleshooting the reason for the 1A KG pump trip.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for loss of KG or automatic turbine runback failure, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as DEC BA (Balancing Authority) to notify of Unit status, REPEAT the information.

3.6 Scenario EVENTS 5 & 6, 1A NS Pump Loss of Power / Steam Leak Inside Containment BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to cause a loss of power to 1A NS pump.

BOOTH INSTRUCTOR ACTION IF dispatched as an AO to the breaker for 1A NS pump, REPEAT the information.

After 5 minutes, contact the control room crew and REPORT:

• All indicating lights on the front of the breaker for 1A NS pump are dark and there is an acrid smell from the upper compartment.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1A NS pump loss of power, REPEAT the information.

Scenario #1 Catawba 2021 NRC Exam Page 10 of 150

Catawba Nuclear Station NRC Exam September 2021 BOOTH INSTRUCTOR ACTION IF contacted as RP to notify of the steam leak, REPEAT the information.

3.8 Scenario EVENTs 7, 8, and 9, Steam Line Break Inside Containment / MSIVs fail to close on MSI signal / Auxiliary Building Unfiltered Exhaust Fans fail to secure on S/I BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 7 to initiate a steam line break inside containment from the 1C S/G.

BOOTH INSTRUCTOR ACTION IF dispatched as an AO to secure all ice condenser air handling units per G-1 Enclosure 11 and to place the Hydrogen Analyzers in service per OP/1/A/6450/010, REPEAT the information and INSERT SIMULATOR Trigger 17.

After 10 minutes REPORT:

• Ice condenser air handling units have been secured per G-1 Enclosure 11 and the Hydrogen Analyzers have been placed in service per OP/1/A/6450/010.

BOOTH INSTRUCTOR ACTION IF contacted as chemistry to sample all S/Gs for activity, REPEAT the information.

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

BOOTH INSTRUCTOR ACTION IF contacted as an AO to unlock and close 1SA-4, REPEAT the information.

Scenario #1 Catawba 2021 NRC Exam Page 11 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 12 of 150 Event

Description:

Increase Reactor Power Note To Evaluator:

The scenario begins with a power increase from 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 4.3 (Dilution)

• 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.

Scenario #1 Catawba 2021 NRC Exam Page 12 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 13 of 150 Event

Description:

Increase Reactor Power Scenario #1 Catawba 2021 NRC Exam Page 13 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 14 of 150 Event

Description:

Increase Reactor Power Scenario #1 Catawba 2021 NRC Exam Page 14 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 15 of 150 Event

Description:

Increase Reactor Power Scenario #1 Catawba 2021 NRC Exam Page 15 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 16 of 150 Event

Description:

Increase Reactor Power Scenario #1 Catawba 2021 NRC Exam Page 16 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 17 of 150 Event

Description:

Increase Reactor Power Scenario #1 Catawba 2021 NRC Exam Page 17 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 18 of 150 Event

Description:

Increase Reactor Power Scenario #1 Catawba 2021 NRC Exam Page 18 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 19 of 150 Event

Description:

Increase Reactor Power Scenario #1 Catawba 2021 NRC Exam Page 19 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 20 of 150 Event

Description:

Increase Reactor Power Scenario #1 Catawba 2021 NRC Exam Page 20 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 21 of 150 Event

Description:

Increase Reactor Power Scenario #1 Catawba 2021 NRC Exam Page 21 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 22 of 150 Event

Description:

Increase Reactor Power Scenario #1 Catawba 2021 NRC Exam Page 22 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 23 of 150 Event

Description:

Letdown Heat Exchanger Temperature Control Valve (1KC-132) Fails Closed 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 DCS Alarm Letdown HX TEMP CTRL IN MAN 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 and transfer the controller to Manual. The crew will manually control 1KC-132 to increase cooling flow to the Letdown Heat Exchanger. If letdown temperature exceeds 136°F, then letdown 3-way valve 1NV-153A should bypass the mixed bed demineralizers.

Scenario #1 Catawba 2021 NRC Exam Page 23 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 2 Page 24 of 150 Event

Description:

Letdown Heat Exchanger Temperature Control Valve (1KC-132) Fails Closed Scenario #1 Catawba 2021 NRC Exam Page 24 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 25 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Control Room Indications 1AD-9, F/5 KC TRAIN A SINGLE PUMP RUNOUT - LIT RED OPEN indicating light for 1KC-C37A - LIT Various KC low flow alarms - LIT Scenario #1 Catawba 2021 NRC Exam Page 25 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 26 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 26 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 27 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 27 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 28 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 28 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 29 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 29 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 30 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 30 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 31 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 31 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 32 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 32 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 33 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 33 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 34 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 34 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 35 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 35 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 36 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 36 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 37 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 37 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 38 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 38 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 39 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 39 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 40 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 40 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 41 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 41 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 42 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 42 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 43 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 43 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 44 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 44 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 3 Page 45 of 150 Event

Description:

KC Miniflow Valve 1KC-C37A Fails Open Scenario #1 Catawba 2021 NRC Exam Page 45 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 46 of 150 Event

Description:

Loss of KG / Automatic Turbine Runback Failure Control Room Indications 1AD-1, F/6 H2-KG PANEL TROUBLE - LIT OAC indications of both KG pumps tripped Scenario #1 Catawba 2021 NRC Exam Page 46 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 47 of 150 Event

Description:

Loss of KG / Automatic Turbine Runback Failure Scenario #1 Catawba 2021 NRC Exam Page 47 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 48 of 150 Event

Description:

Loss of KG / Automatic Turbine Runback Failure Scenario #1 Catawba 2021 NRC Exam Page 48 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 49 of 150 Event

Description:

Loss of KG / Automatic Turbine Runback Failure Scenario #1 Catawba 2021 NRC Exam Page 49 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 50 of 150 Event

Description:

Loss of KG / Automatic Turbine Runback Failure Scenario #1 Catawba 2021 NRC Exam Page 50 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 51 of 150 Event

Description:

Loss of KG / Automatic Turbine Runback Failure Scenario #1 Catawba 2021 NRC Exam Page 51 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 52 of 150 Event

Description:

Loss of KG / Automatic Turbine Runback Failure Scenario #1 Catawba 2021 NRC Exam Page 52 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 53 of 150 Event

Description:

Loss of KG / Automatic Turbine Runback Failure Scenario #1 Catawba 2021 NRC Exam Page 53 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 54 of 150 Event

Description:

Loss of KG / Automatic Turbine Runback Failure Scenario #1 Catawba 2021 NRC Exam Page 54 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 55 of 150 Event

Description:

Loss of KG / Automatic Turbine Runback Failure Scenario #1 Catawba 2021 NRC Exam Page 55 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 56 of 150 Event

Description:

Loss of KG / Automatic Turbine Runback Failure Scenario #1 Catawba 2021 NRC Exam Page 56 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 57 of 150 Event

Description:

Loss of KG / Automatic Turbine Runback Failure Scenario #1 Catawba 2021 NRC Exam Page 57 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 4 Page 58 of 150 Event

Description:

Loss of KG / Automatic Turbine Runback Failure Scenario #1 Catawba 2021 NRC Exam Page 58 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 5 Page 59 of 150 Event

Description:

1A NS Pump Loss of Power Control Room Indications 1AD-11, A/1 4KV ESS PWR TRAIN A TROUBLE - LIT A Train 1.47 Bypass alarm for 1A NS Note To Evaluator:

This event does not have any specific crew response. This is an SRO Tech Spec call only.

See Attachment 12 for applicable Tech Specs.

Tech Spec 3.6.6 (Containment Spray System) Condition A (One containment spray train inoperable) - Restore containment spray train to OPERABLE status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

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Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 60 of 150 Event

Description:

Steam Leak Inside Containment on 1C S/G Control Room Indications Containment Pressure - RISING Containment Temperature - RISING Containment Humidity - RISING Scenario #1 Catawba 2021 NRC Exam Page 60 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 61 of 150 Event

Description:

Steam Leak Inside Containment on 1C S/G Scenario #1 Catawba 2021 NRC Exam Page 61 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 62 of 150 Event

Description:

Steam Leak Inside Containment on 1C S/G Scenario #1 Catawba 2021 NRC Exam Page 62 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 63 of 150 Event

Description:

Steam Leak Inside Containment on 1C S/G Scenario #1 Catawba 2021 NRC Exam Page 63 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 64 of 150 Event

Description:

Steam Leak Inside Containment on 1C S/G Scenario #1 Catawba 2021 NRC Exam Page 64 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 65 of 150 Event

Description:

Steam Leak Inside Containment on 1C S/G Scenario #1 Catawba 2021 NRC Exam Page 65 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 66 of 150 Event

Description:

Steam Leak Inside Containment on 1C S/G Scenario #1 Catawba 2021 NRC Exam Page 66 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 67 of 150 Event

Description:

Steam Leak Inside Containment on 1C S/G Scenario #1 Catawba 2021 NRC Exam Page 67 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 68 of 150 Event

Description:

Steam Leak Inside Containment on 1C S/G Scenario #1 Catawba 2021 NRC Exam Page 68 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 69 of 150 Event

Description:

Steam Leak Inside Containment on 1C S/G Scenario #1 Catawba 2021 NRC Exam Page 69 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 70 of 150 Event

Description:

Steam Leak Inside Containment on 1C S/G Scenario #1 Catawba 2021 NRC Exam Page 70 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 71 of 150 Event

Description:

Steam Leak Inside Containment on 1C S/G Scenario #1 Catawba 2021 NRC Exam Page 71 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 6 Page 72 of 150 Event

Description:

Steam Leak Inside Containment on 1C S/G Scenario #1 Catawba 2021 NRC Exam Page 72 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 73 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Control Room Indications 1FO-1, D/5 HI CONT PRESS S/I RX TRIP - LIT Unit 1 Reactor Trip and Safety Injection Scenario #1 Catawba 2021 NRC Exam Page 73 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 74 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 74 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 75 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 75 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 76 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 76 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 77 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 77 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 78 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 78 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 79 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 79 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 80 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 80 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 81 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 81 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 82 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 82 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 83 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 83 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 84 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 84 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 85 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 85 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 86 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 86 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 87 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 87 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 88 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 88 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 89 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 89 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 90 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 90 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 91 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 91 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 92 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 92 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 93 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 93 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 94 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 94 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 95 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 95 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 96 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 96 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 97 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 97 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 98 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 98 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 99 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 99 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 100 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 100 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 101 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 101 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 102 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 102 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 103 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 103 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 104 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 104 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 105 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 105 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 106 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 106 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 107 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 107 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 108 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 108 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 109 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 109 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 110 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 110 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 111 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 111 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 112 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 112 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 113 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 113 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 114 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 114 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 115 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 115 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 116 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 116 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 117 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 117 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 118 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 118 of 150

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 7,8,9 Page 119 of 150 Event

Description:

Steam Line Break Inside Containment / MSIVs fail to close on MSI / Aux. Bldg. UFXFs fail to secure on S/I Scenario #1 Catawba 2021 NRC Exam Page 119 of 150

Attachment List Scenario 1 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - AP/1/A/5500/021 Enclosure 1 (Foldout Page)

ATTACHMENT 4 - AP/1/A/5500/003 Enclosure 3 (Rod Insertion Limit Boration)

ATTACHMENT 5 - AP/1/A/5500/028 Enclosure 1 (Foldout Page)

ATTACHMENT 6 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page)

ATTACHMENT 7 - EP/1/A/5000/E-0 Enclosure 5 (VX System Operation)

ATTACHMENT 8 - EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification)

ATTACHMENT 9 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control)

ATTACHMENT 10 EP/1/A/5000/E-2 Enclosure 1 (Foldout Page)

ATTACHMENT 11 EP/1/A/5000/ES-1.1 Enclosure 1 (Foldout Page)

ATTACHMENT 12 - Scenario Specific Technical Specifications Scenario #1 Catawba 2021 NRC Exam Page 120 of 150

ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK Runback the Main Turbine prior to Main Turbine Trip (must 1

be below amps for 332 MW within 3.5 minutes).

Close MSIVs and isolate CA flow to the faulted S/G prior to a 2 severe challenge (Orange or Red Path) to the NC Integrity CSF status tree.

Comments:

Scenario #1 Catawba 2021 NRC Exam Page 121 of 150

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 50 % MOL 1117 PPM per OAC Controlling Procedure

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

The steps up to step 3.52 are complete.

Other Information Needed to Assume the Shift

• Unit 1 is at 50% power at the MOL. Unit 2 is at 100% power. Direction for the crew is to raise reactor power to 100%. A reactivity plan has been provided by Reactor Engineering for raising reactor power.

AOs Available Eight AOs are available as listed on the status board METEOROLOGICAL CONDITIONS

• Upper wind direction = 125 degrees, speed = 3 mph

• Lower wind direction = 127 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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ATTACHMENT 3 Scenario #1 Catawba 2021 NRC Exam Page 123 of 150

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ATTACHMENT 4 Scenario #1 Catawba 2021 NRC Exam Page 125 of 150

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ATTACHMENT 7 Scenario #1 Catawba 2021 NRC Exam Page 132 of 150

ATTACHMENT 8 Scenario #1 Catawba 2021 NRC Exam Page 133 of 150

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Catawba Nuclear Station NRC Exam September 2021 2021 INITIAL LICENSE NRC EXAM SCENARIO # 2 Scenario #2 Catawba 2021 NRC Exam Page 1 of 156

Catawba Nuclear Station NRC Exam September 2021 Appendix D Scenario Outline Form ES-D-1 Facility: Catawba NRC Exam 2021 Scenario No.: 2 Op Test No.: 2021301 Examiners: Operators: SRO RO BOP Initial Conditions: Unit 1 is at 75% power at the MOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 75% power at the MOL following maintenance of the 1A CFPT LF pumps. 1A CFPT has been placed back in service and current power level is being maintained while maintenance continues to monitor LF system performance. Unit 2 is at 100% power. Direction for the crew is to swap LCVUs by securing 1A LCVU and starting 1C LCVU using OP/1/A/6450/001 Encl. 4.13. The NOTE on page 4 prior to step 3.2.1.5 has been evaluated by the previous shift and a determination has been made that there is no time delay needed prior to starting 1C LCVU.

Event Event Event Malf. No.

No. Type* Description N - BOP 1 Swap operating LCVUs N - SRO C - BOP 2 C - SRO 1B RN Pump trip TS - SRO C - RO 3 Main Generator Voltage Regulator Failure C - SRO C - BOP 4 C - SRO 1C SGTL TS - SRO R - RO 5 R - SRO AP/09 Rapid Downpower N - BOP C - RO 6 Rods fail to insert in automatic during AP/09 Rapid Shutdown C - SRO 7 M - ALL 1C Steam Generator Tube Rupture C - RO 8 1C CA Flow Control Valve will not close C - SRO C - BOP 9 1NI-9A and 1NI-10B fail to open automatically on S/I C - SRO C - RO 10 MSIVs fail to close manually C - SRO

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario #2 Catawba 2021 NRC Exam Page 2 of 156

Catawba Nuclear Station NRC Exam September 2021 Appendix D Scenario Outline Form ES-D-1 Scenario 2 - Summary Initial Condition Unit 1 is at 75% power at the MOL. Unit 2 is at 100% power.

Turnover:

Unit 1 is at 75% power at the MOL following maintenance of the 1A CFPT LF pumps. 1A CFPT has been placed back in service and current power level is being maintained while maintenance continues to monitor LF system performance. Unit 2 is at 100% power. Direction for the crew is to swap LCVUs by securing 1A LCVU and starting 1C LCVU using OP/1/A/6450/001 Encl. 4.13. The NOTE on page 4 prior to step 3.2.1.5 has been evaluated by the previous shift and a determination has been made that there is no time delay needed prior to starting 1C LCVU.

Event 1 BOP will swap operating LCVUs per OP/1/A/6450/001 Encl. 4.13.

Event History: This event has previously been performed as a JPM (2019), but has never been used as a normal evolution in a scenario.

Event 2 1B RN pump will trip. Crew will enter AP/0/A/5500/020 (Loss of Nuclear Service Water) Case 1 (Loss of RN train) and start an RN pump. SRO will address Tech Specs.

Verifiable Action - BOP will manually start an RN pump as directed.

Event History: This failure last used 13 (3).

Event 3 The Unit 1 Main Generator voltage regulator will fail low. Crew will enter AP/1/A/5500/037 (Generator Voltage and Electric Grid Disturbances) Case 1 (Abnormal Generator or Grid Voltage). Crew will manually adjust Unit 1 Generator Voltage to return voltage to normal per the voltage schedule.

Verifiable Action - The RO will manually adjust Generator voltage to restore to normal per the voltage schedule.

Event History: Voltage Regulator failure last used 17 (3). However, this is the first time that voltage has been failed low.

Event 4 A S/G Tube Leak will develop on the 1C S/G. Crew will enter AP/1/A/5500/010 (Reactor Coolant Leak)

Case 1 (Steam Generator Tube Leak). Crew will adjust charging and letdown flow to stabilize Pressurizer level, will quantify the leak size, and initiate a rapid downpower. SRO will address Tech Specs.

Verifiable Action - BOP will throttle charging and letdown flow to stabilize Pressurizer level and quantify the size of the tube leak.

Event History: The last S/G Tube leak was on 1B S/G on 17(3). A 1C S/G tube leak has not been used before.

Event 5 Crew will enter AP/1/A/5500/009 (Rapid Downpower) when directed by AP/10.

Verifiable Action - RO will enter desired turbine target load and load rate and place the main turbine in GO to begin power decrease. BOP will perform boration.

Scenario #2 Catawba 2021 NRC Exam Page 3 of 156

Catawba Nuclear Station NRC Exam September 2021 Appendix D Scenario Outline Form ES-D-1 Event History: Rapid downpower last used in 17 (3).

Event 6 Control rods will fail to insert automatically during the rapid downpower. The RO will place control rods in MANUAL to control NC system Tavg.

Verifiable Action - RO will manually insert control rods to mimic automatic control.

Event History: The last automatic control rod failure was in 19 (3), but was during a spurious turbine trip.

This is the first time that this failure has been used during a rapid downpower.

Event 7 The S/G tube leak size will increase requiring the crew to manually trip the reactor and initiate safety injection due to not being able to maintain Pressurizer level. Crew will enter EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) to ensure safeguards equipment is in service as required. Crew will eventually transition to EP/1/A/5000/E-3 (Steam Generator Tube Rupture).

Verifiable Action - RO will manually trip Unit 1 reactor. BOP will initiate Safety Injection.

Event History: The last S/G tube rupture was in 17 (3) on 1B S/G. A 1C S/G tube rupture has not been used before.

Event 8 The CA flow control valve will fail to close when attempted by the RO per E-0 foldout page guidance.

Verifiable Action - RO will isolate CA flow to 1C S/G using the motor operated isolation valve.

Event History: This failure is new.

Event 9 NV pumps to Cold Leg isolation valves 1NI-9A and 1NI-10B will fail to automatically open on the Safety Injection signal.

Verifiable Action - BOP will manually open 1NI-9A and 1NI-10B.

Event History: Similar failure used on 19 (4) except 1NI-9A would not open automatically or manually.

Event 10 During implementation of E-3, the MSIVs on all S/Gs will fail to close manually. Since the ruptured S/G cannot be isolated from the intact S/Gs, a transition to EP/1/A/5000/ECA-3.1 (SGTR With Loss of Reactor Coolant - Subcooled Recovery Desired) will be made. Crew will initiate a less than 100°F/hour cooldown.

Verifiable Action - RO will initiate a less than 100°F/hour cooldown.

Event History: This failure is new.

Scenario #2 Catawba 2021 NRC Exam Page 4 of 156

Catawba Nuclear Station NRC Exam September 2021 Appendix D Scenario Outline Form ES-D-1 Manual Control of Automatic Functions Event Position Description 3 RO Main Generator Voltage Regulator Failure 6 RO Manual Insertion of Control Rods during Rapid Downpower Critical Task 1 - Restore RN flow prior to any NC pump motor bearing reaching 195°F.

Critical Task 2 - Establish high head ECCS flow prior to transition from E-0.

Critical Task 3 - Initiate Cooldown at less than 100°F/hour in order to prevent S/G overfill (S/G N/R level >100%).

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

1. Total malfunctions (5-8) 8

2. Malfunctions after EOP entry (1-2) 3

3. Abnormal events (2-4) 4

4. Major transients (1-2) 1

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

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

7. Critical tasks (2-3) 3 Scenario #2 Catawba 2021 NRC Exam Page 5 of 156

Catawba Nuclear Station NRC Exam September 2021 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC # 169 (password = gallus21) and load schedule file for NRC Scenario 2 START TIME: __________

Scenario #2 Catawba 2021 NRC Exam Page 6 of 156

Catawba Nuclear Station NRC Exam September 2021 Trigger Instructor Action Delete Final Delay Ramp Event In LOA-RN003 (RACKOUT RN PUMP RACK-2 2 1B) OUT OVR-EGB004D (VOLTAGE 3 ON :10 3 ADJUST LOWER PB) 4 MAL-SG001C (S/G C TUBE LEAK) 65 :10 4 MAL-IRX009 (RODS FAIL TO AUTO 6 MOVE) 7 MAL-SG001C (S/G C TUBE LEAK) 400 7 MAL-CA009C (MD CA CTRL VLV 100 8 CA44 FAILURE)

VLV-NI001A (NI9A B.I.T.

DISCHARGE ISOL VLV FAIL AUTO ACTIVE 9 ACTIONS)

VLV-NI002A (NI10B B.I.T.

DISCHARGE ISOL VLV FAIL AUTO ACTIVE 9 ACTIONS)

MAL-SM006E (ALL MSI (MSIV) VLV ACTIVE 10 FAIL)

LOA-VC039 (MNL RST OF LATCH 13 FOR CHILLER B HI COND PRESS RESET 5:00 2 TRP DUE TO LOSS RN)

Scenario #2 Catawba 2021 NRC Exam Page 7 of 156

Catawba Nuclear Station NRC Exam September 2021

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 2, 1B RN Pump Trip BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 2 to cause 1B RN Pump to trip.

BOOTH INSTRUCTOR ACTION IF dispatched as an AO to perform a post start check of 1A/2A/2B RN pump, REPEAT the information.

After 5 minutes, contact the control room crew and REPORT:

• Post start check of 1A/2A/2B RN pump is complete. The pump looks good for continued operation.

BOOTH INSTRUCTOR ACTION WHEN contacted as an AO to locally reset YC chiller, REPEAT the information. INSERT SIMULATOR Trigger 13.

After 5 minutes REPORT:

• YC Chiller B has been reset and has re-started.

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

BOOTH INSTRUCTOR ACTION IF contacted as Environmental chemistry to report RN pump shifts, REPEAT the information.

Scenario #2 Catawba 2021 NRC Exam Page 8 of 156

Catawba Nuclear Station NRC Exam September 2021 3.3 Scenario EVENT 3, Main Generator Voltage Regulator Failure BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause Main Generator Voltage to fail low.

BOOTH INSTRUCTOR ACTION IF contacted as DEC TOP to monitor RTCA indications, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for the Main Generator Voltage Regulator, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as DEC BA to determine CNS Generator Voltage requirements, REPORT:

• Adjust voltage per the operating schedule.

BOOTH INSTRUCTOR ACTION IF contacted as DEC TOP or BA to determine if switchyard (grid) voltage adequate and reliable, REPORT:

• Yes, switchyard and grid voltage are adequate and reliable.

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

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1C S/G tube leakage, REPEAT the information.

BOOTH INSTRUCTOR ACTION IF contacted as RP to frisk all S/G cation columns, REPEAT the information.

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

BOOTH INSTRUCTOR ACTION IF contacted as RP to notify of the size of the S/G tube leak, REPEAT the information.

Scenario #2 Catawba 2021 NRC Exam Page 9 of 156

Catawba Nuclear Station NRC Exam September 2021 3.5 Scenario EVENTS 7/8/9/10, 1C SGTR / 1C CA Flow Ctrl Vlv failed open / 1NI-9A & 1NI-10B fail to auto open / MSIVs fail to close manually BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 7 to cause a 1C S/G Tube Rupture.

BOOTH INSTRUCTOR ACTION IF dispatched as an AO to unlock and close 1SA-4, REPEAT the information.

Scenario #2 Catawba 2021 NRC Exam Page 10 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 11 of 156 Event

Description:

Swap Operating Lower Containment Ventilation Units Scenario #2 Catawba 2021 NRC Exam Page 11 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 12 of 156 Event

Description:

Swap Operating Lower Containment Ventilation Units Scenario #2 Catawba 2021 NRC Exam Page 12 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 13 of 156 Event

Description:

Swap Operating Lower Containment Ventilation Units Scenario #2 Catawba 2021 NRC Exam Page 13 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 14 of 156 Event

Description:

Swap Operating Lower Containment Ventilation Units Scenario #2 Catawba 2021 NRC Exam Page 14 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 15 of 156 Event

Description:

Swap Operating Lower Containment Ventilation Units Scenario #2 Catawba 2021 NRC Exam Page 15 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 16 of 156 Event

Description:

Swap Operating Lower Containment Ventilation Units Scenario #2 Catawba 2021 NRC Exam Page 16 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 17 of 156 Event

Description:

Swap Operating Lower Containment Ventilation Units Scenario #2 Catawba 2021 NRC Exam Page 17 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 18 of 156 Event

Description:

1B RN Pump Trip Control Room Indications 1AD-12, A/2 RN ESSENTIAL HDR A PRESSURE - LO - LIT 1AD-12, A/5 RN ESSENTIAL HDR B PRESSURE - LO - LIT 1AD-11, D/1 4KV ESS PWR TRAIN B TROUBLE - LIT Indicating lights for 1B RN pump - DARK OAC alarm for RN Header A & B pressure - LOW Scenario #2 Catawba 2021 NRC Exam Page 18 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 19 of 156 Event

Description:

1B RN Pump Trip Scenario #2 Catawba 2021 NRC Exam Page 19 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 20 of 156 Event

Description:

1B RN Pump Trip Scenario #2 Catawba 2021 NRC Exam Page 20 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 21 of 156 Event

Description:

1B RN Pump Trip Scenario #2 Catawba 2021 NRC Exam Page 21 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 22 of 156 Event

Description:

1B RN Pump Trip Scenario #2 Catawba 2021 NRC Exam Page 22 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 23 of 156 Event

Description:

1B RN Pump Trip Scenario #2 Catawba 2021 NRC Exam Page 23 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 24 of 156 Event

Description:

1B RN Pump Trip Scenario #2 Catawba 2021 NRC Exam Page 24 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 25 of 156 Event

Description:

1B RN Pump Trip Scenario #2 Catawba 2021 NRC Exam Page 25 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 2 Page 26 of 156 Event

Description:

1B RN Pump Trip Scenario #2 Catawba 2021 NRC Exam Page 26 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 27 of 156 Event

Description:

Main Generator Voltage Regulator Failure Control Room Indications OAC alarm for Generator Voltage - LOW 1AD-1, D/6 EHC SYSTEM FAULT - LIT Scenario #2 Catawba 2021 NRC Exam Page 27 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 28 of 156 Event

Description:

Main Generator Voltage Regulator Failure Scenario #2 Catawba 2021 NRC Exam Page 28 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 29 of 156 Event

Description:

Main Generator Voltage Regulator Failure Scenario #2 Catawba 2021 NRC Exam Page 29 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 30 of 156 Event

Description:

Main Generator Voltage Regulator Failure Scenario #2 Catawba 2021 NRC Exam Page 30 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 31 of 156 Event

Description:

Main Generator Voltage Regulator Failure Scenario #2 Catawba 2021 NRC Exam Page 31 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 32 of 156 Event

Description:

Main Generator Voltage Regulator Failure Scenario #2 Catawba 2021 NRC Exam Page 32 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 33 of 156 Event

Description:

Main Generator Voltage Regulator Failure Scenario #2 Catawba 2021 NRC Exam Page 33 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 34 of 156 Event

Description:

Main Generator Voltage Regulator Failure Scenario #2 Catawba 2021 NRC Exam Page 34 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 35 of 156 Event

Description:

Main Generator Voltage Regulator Failure Scenario #2 Catawba 2021 NRC Exam Page 35 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 36 of 156 Event

Description:

Main Generator Voltage Regulator Failure Scenario #2 Catawba 2021 NRC Exam Page 36 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 3 Page 37 of 156 Event

Description:

Main Generator Voltage Regulator Failure Scenario #2 Catawba 2021 NRC Exam Page 37 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 38 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto 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 Count rate on 1EMF RISING Pressurizer Level - LOWERING Scenario #2 Catawba 2021 NRC Exam Page 38 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 39 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 39 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 40 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 40 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 41 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 41 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 42 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 42 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 43 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 43 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 44 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 44 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 45 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 45 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 46 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 46 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 47 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 47 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 48 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 48 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 49 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 49 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 50 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 50 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 51 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 51 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 52 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 52 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 53 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 53 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 54 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 54 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 55 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 55 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 56 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 56 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 57 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 57 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 58 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 58 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 59 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 59 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 60 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 60 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 61 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 61 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 62 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 62 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 63 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 63 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 64 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 64 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 65 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 65 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 4,5,6 Page 66 of 156 Event

Description:

1C Steam Generator Tube Leak / Rapid Downpower / Rods Fail to Insert in Auto Scenario #2 Catawba 2021 NRC Exam Page 66 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 67 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Control Room Indications Pressurizer Level - LOWERING UNCONTROLLED 1RAD-3, E/5 1EMF26, 27, 28, 29, S/G A, B, C, D STEAMLINE - LIT 1C S/G N/R Level - RISING UNCONTROLLED Scenario #2 Catawba 2021 NRC Exam Page 67 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 68 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 68 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 69 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 69 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 70 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 70 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 71 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 71 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 72 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 72 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 73 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 73 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 74 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 74 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 75 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 75 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 76 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 76 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 77 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 77 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 78 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 78 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 79 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 79 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 80 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 80 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 81 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 81 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 82 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 82 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 83 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 83 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 84 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 84 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 85 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 85 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 86 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 86 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 87 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 87 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 88 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 88 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 89 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 89 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 90 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 90 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 91 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 91 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 92 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 92 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 93 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 93 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 94 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 94 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 95 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 95 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 96 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 96 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 97 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 97 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 98 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 98 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 99 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 99 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 100 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 100 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 101 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 101 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 102 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 102 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 103 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 103 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 104 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 104 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 105 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 105 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 106 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 106 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 107 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 107 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 108 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 108 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 109 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 109 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 110 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 110 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 111 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 111 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 112 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 112 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 113 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 113 of 156

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 7,8,9,10 Page 114 of 156 Event

Description:

1C Steam Generator Tube Rupture / 1C CA Flow Control Valve Failed Open / 1NI-9A & 1NI-10B Fail to Auto Open / MSIVs Fail to Close Manually Scenario #2 Catawba 2021 NRC Exam Page 114 of 156

Attachment List Scenario 1 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - AP/0/A/5500/020 Enclosure 1 (Foldout Page)

ATTACHMENT 4 - AP/1/A/5500/010 Enclosure 1 (Foldout Page)

ATTACHMENT 5 - AP/1/A/5500/009 Enclosure 1 (Foldout Page)

ATTACHMENT 6 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page)

ATTACHMENT 7 - EP/1/A/5000/E-0 Enclosure 2 (Ventilation System Verification)

ATTACHMENT 8 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control)

ATTACHMENT 9 EP/1/A/5000/E-3 Enclosure 1 (Foldout Page)

ATTACHMENT 10 EP/1/A/5000/ECA-3.1 Enclosure 1 (Foldout Page)

ATTACHMENT 11 - Scenario Specific Technical Specifications Scenario #2 Catawba 2021 NRC Exam Page 115 of 156

ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK Restore RN flow prior to any NC pump motor bearing 1

temperature reaching 195°F.

2 Establish high head ECCS flow prior to transition from E-0.

Initiate cooldown at less than 100°F/hour in order to prevent 3

S/G overfill (S/G N/R level > 100%.

Comments:

Scenario #2 Catawba 2021 NRC Exam Page 116 of 156

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 75 % MOL 998 PPM per OAC Controlling Procedure

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

The steps up to step 3.49 are complete.

Other Information Needed to Assume the Shift

• Unit 1 is at 75% power at the MOL following maintenance of the 1A CFPT LF pumps. 1A CFPT has been placed back in service and current power level is being maintained while maintenance continues to monitor LF system performance.

• Unit 2 is at 100% power.

• Direction for the crew is to swap LCVUs by securing 1A LCVU and starting 1C LCVU using OP/1/A/6450/001 Encl. 4.13. The NOTE on page 4 prior to step 3.2.1.5 has been evaluated by the previous shift and a determination has been made that there is no time delay needed prior to starting 1C LCVU.

AOs Available Eight AOs are available as listed on the status board METEOROLOGICAL CONDITIONS

• Upper wind direction = 125 degrees, speed = 3 mph

• Lower wind direction = 127 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 September 2021 2021 INITIAL LICENSE NRC EXAM SCENARIO # 3 Scenario #3 Catawba 2021 NRC Exam Page 1 of 121

Catawba Nuclear Station NRC Exam September 2021 Appendix D Scenario Outline Form ES-D-1 Facility: Catawba NRC Exam 2021 Scenario No.: 3 Op Test No.: 2021301 Examiners: Operators: SRO RO BOP Initial Conditions: Unit 1 is at 100% power at the BOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 100% power at the BOL. Unit 2 is at 100% power. 1B CA Pump is removed from service for PMs. 1B 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 />. Tech Spec 3.7.5 Condition B is in effect. Direction for the crew is to initiate a downpower to

~85% in preparation for performing the Turbine Control Valve Movement PT.

Event Event Event Malf. No.

No. Type* Description R - RO 1 N - BOP Unit 1 Downpower to ~85%

N - SRO C - BOP 2 1NV-294 fails open C - SRO C - RO 3 C - SRO 1NC-32B fails open, able to be manually closed TS - SRO C - BOP 4 C - SRO 1ETA Blackout (D/G does not start)

TS - SRO C - RO 5 Continuous rod motion / 2 stuck rods on reactor trip C - SRO 6** M - ALL CAPT#1 Overspeed Trip / Loss of CFPT Vacuum / Loss of Heat Sink C - BOP 7 1NV-37A failed closed C - SRO

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

• • During the loss of heat sink event, the crew attempted and successfully started the 1A Turbine Driven Main Feed Pump. The pump started and came up to rated turbine speed. It was expected that the Turbine Driven Feed Pumps would not RESET due to low vacuum conditions and it was not the success path written into the scenario. To drive the crew to depressurize SGs and to feed the SG's with the Condensate System, the operating booth tripped the 1A Turbine Main Feed Pump by inserting a low vacuum signal. When the crew attempted the 1B Turbine Main Feed Pump, it would not reset due to the low vacuum signal. The crew then proceeded to SG depressurization and feeding with the Condensate system. The allowance of the Main Feed Pump start with a C-9, low vacuum condition is under evaluation by the licensee training and simulator personnel.

Scenario #3 Catawba 2021 NRC Exam Page 2 of 121

Catawba Nuclear Station NRC Exam September 2021 Appendix D Scenario Outline Form ES-D-1 Scenario 3 - Summary Initial Condition Unit 1 is at 100% power at the BOL. Unit 2 is at 100% power.

Turnover:

Unit 1 is at 100% power at the BOL. Unit 2 is at 100% power. 1B CA Pump is removed from service for PMs. 1B 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 downpower to ~85% in preparation for performing the Turbine Control Valve Movement PT.

Event 1 Unit 1 downpower to ~85%. BOP will perform a boration per OP/1/A/6150/009 (Boron Concentration Control) Encl. 4.2 (Boration). RO will input a target load and load rate into the Main Turbine control panel and initiate the downpower per OP/1/B/6300/001 (Turbine Generator).

Event History: This downpower at BOL has not been performed before.

Event 2 1NV-294 (Charging flow control valve) will fail full open.

Verifiable Action - BOP will place 1NV-294 in manual and will manually control charging flow to stabilize Pressurizer Level.

Event History: This failure has not been used before on an NRC exam.

Event 3 Pressurizer PORV 1NC-32B fails open. RO will manually close 1NC-32B. Crew will enter AP/1/A/5500/011 (Pressurizer Pressure Anomalies) Case 1 (Pressurizer Pressure Decreasing). SRO will refer to Tech Specs.

Verifiable Action - RO will manually close 1NC-32B.

Event History: This Pressurizer PORV failure last used on 17(1), but was not able to be manually closed.

Event 4 A Blackout will occur on essential bus 1ETA. D/G 1A will fail to start resulting in no power on 1ETA. Crew will enter AP/1/A/5500/007 (Loss of Normal Power) Case 2 (Loss of All Power to an Essential Train) to address the failure. SRO will refer to Tech Specs.

Verifiable Action - The BOP will start an RN pump and KC pumps on B train on Unit 1. RO will maintain reactor power.

Event History: This failure has not been used before on an NRC exam.

Event 5 Control rods will begin to insert continuously. RO will perform the immediate actions of AP/1/A/5500/015 (Rod Control Malfunctions) Case II (Continuous Rod Movement) and trip the Unit 1 reactor.

Verifiable Action - RO will perform the immediate actions of AP/1/A/5500/015 (Rod Control Malfunctions) Case 2 (Continuous Rod Movement), and manually trip Unit 1 Reactor. During the reactor trip, 2 control rods will fail to fully insert. This will require the BOP to initiate emergency boration in EP/1/A/5000/ES-0.1 (Reactor Trip Response) to maintain shutdown margin.

Scenario #3 Catawba 2021 NRC Exam Page 3 of 121

Catawba Nuclear Station NRC Exam September 2021 Appendix D Scenario Outline Form ES-D-1 Event History: Continuous rod movement last used in 16 (3). Having 2 stuck rods on reactor trip last used in 19 (1).

Event 6 Following reactor trip, the crew will enter EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) and subsequently transition to EP/1/A/5000/ES-0.1 (Reactor Trip Response). CAPT#1 will eventually trip on overspeed. Once S/G N/R levels lower to < 11% in all S/Gs, crew will transition to EP/1/A/5000/FR-H.1 (Loss of Secondary Heat Sink). Following reactor trip, both CFPTs will lose vacuum.

Verifiable Action - BOP will trip the NC pumps and RO will depressurize S/Gs to allow feed flow to be provided to the S/Gs via Hotwell and Condensate Booster Pumps.

Event History: Similar failure was last used in 16 (2). Loss of CFPT vacuum failure last used in 19 (1) but was prior to the reactor trip.

Event 7 When step is reached in FR-H.1 to initiate NC system depressurization, Auxiliary Spray Valve 1NV-37A will not open.

Verifiable Action - BOP will use a Pressurizer PORV to lower NC system pressure.

Event History: This failure was last used in 16 (2).

Manual Control of Automatic Functions Event Position Description 2 BOP 1NV-294 Failing open requiring manual control of Pressurizer Level Scenario #3 Catawba 2021 NRC Exam Page 4 of 121

Catawba Nuclear Station NRC Exam September 2021 Appendix D Scenario Outline Form ES-D-1 Critical Task 1 - Control charging line flow to prevent a reactor trip on Pressurizer Hi level (2/3 Pressurizer Levels > 92%).

Critical Task 2 - Close Pressurizer PORV prior to a manual or automatic reactor trip on Pressurizer low pressure.

Critical Task 3 - Establish feedwater flow to at least one S/G before NC feed and bleed is required

(<24% W/R level in 3 out of 4 S/G).

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) 2

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

7. Critical tasks (2-3) 3 Scenario #3 Catawba 2021 NRC Exam Page 5 of 121

Catawba Nuclear Station NRC Exam September 2021 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC # 152 and load schedule file for NRC Scenario 3 START TIME: __________

Scenario #3 Catawba 2021 NRC Exam Page 6 of 121

Catawba Nuclear Station NRC Exam September 2021 Trigger Instructor Action Delete Final Delay Ramp Event In LOA-CA018 (RACKOUT CA PUMP RACK-1B) OUT MAL-NV012E (NV VLV 294 FAIL 2 ACTIVE 2 OPEN)

MAL-NV012E (NV VLV 294 FAIL 9 ACTIVE :01 2 OPEN)

MAL-EP008A (LOSS OF 4160V 4 ACTIVE 4 BUS ETA)

ANN-AD19-F04 (YN CRITICAL 3 ON :05 3 TROUBLE)

VLV-NC005F (NC32B PZR PORV 11 1 :05 3 FAIL TO POSITION)

VLV-NC005F (NC32B PZR PORV 13 1 :01 3 FAIL TO POSITION)

OVR-IRX005B (SEL SW - CRD 5 ON 5 BANK SELECT MAN POS)

OVR-IRX006A (ROD MOTION SW 5 ON 5 IN POS)

MAL-IRX015K8 (PERMANENTLY 14 130 5 STUCK ROD K8-38A)

MAL-IRX015D4 (PERMANENTLY 14 220 5 STUCK ROD D4)

MAL-CA005 (CA PUMP MECH-14 1:00 6 OVERSPEED TRIP) ANICAL MAL-EHC002 (TURBINE TRIP 14 AUTO :06 6 FAILURE)

MAL-CF001A (LOSS OF CFPT 1A 14 100 7 VACUUM)

MAL-CF001B (LOSS OF CFPT 1B 14 100 VACUUM)

VLV-NV014F (NV37A PRZR SPRAY LINE ISOL VLV FAIL TO 0 8 POSITION)

OVR-IRX005A (SEL SW - CRD 5 OFF 5 BANK SELECT AUTO POS)

Ensure red cover placed on 1B CA Pump Ensure EVENT 9 = ov_d9mod111slimbytes(7) (1NV-294 Manual PB)

Ensure EVENT 11 = x5ri017a (AD-19 Alarm Acknowledge PB)

Ensure EVENT 13 = x10i279c Ensure EVENT 14 = jpplp4(1) jpplp4(2) (Reactor Trip Either Train)

Ensure 1B NV pump is in service Scenario #3 Catawba 2021 NRC Exam Page 7 of 121

Catawba Nuclear Station NRC Exam September 2021 Ensure control rods are in MANUAL

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 2, 1NV-294 Fails Open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 2 to cause 1NV-294 to fail open.

BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1NV-294, REPEAT the information.

3.3 Scenario EVENT 3, YN Critical Trouble Alarm / Pressurizer PORV 1NC-32B fails open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause a YN critical trouble alarm.

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

3.4 Scenario EVENT 4, 1ETA blackout BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 4 to cause a blackout of 1ETA.

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

Scenario #3 Catawba 2021 NRC Exam Page 8 of 121

Catawba Nuclear Station NRC Exam September 2021 BOOTH INSTRUCTOR ACTION IF contacted as an AO to perform a load shed of 1ETA per Enclosure 8, wait 5 minutes and then run schedule file to load shed 1ETA.

After 5 minutes contact the Control Room crew and REPORT:

• Load Shed of 1ETA per Enclosure 8 is complete. There is an 86N relay picked up on 1ETA.

3.5 Scenario EVENT 5, Continuous Rod Motion / 2 Stuck Rods on Reactor Trip BOOTH INSTRUCTOR ACTION WHEN control rods begin to insert, THEN ENSURE SIMULATOR Trigger 5 INSERTED to cause control rods to continuously insert.

3.6 Scenario EVENTs 6, 7, 8, CAPT#1 Overspeed Trip / Loss of Secondary Heat Sink /

Loss of CFPT vacuum / 1NV-37A failed closed Scenario #3 Catawba 2021 NRC Exam Page 9 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 10 of 121 Event

Description:

Unit 1 Power Decrease Note To Evaluator:

The scenario begins with a power decrease from 100% 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.

Scenario #3 Catawba 2021 NRC Exam Page 10 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 11 of 121 Event

Description:

Unit 1 Power Decrease Scenario #3 Catawba 2021 NRC Exam Page 11 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 12 of 121 Event

Description:

Unit 1 Power Decrease Scenario #3 Catawba 2021 NRC Exam Page 12 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 13 of 121 Event

Description:

Unit 1 Power Decrease Scenario #3 Catawba 2021 NRC Exam Page 13 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 14 of 121 Event

Description:

Unit 1 Power Decrease Scenario #3 Catawba 2021 NRC Exam Page 14 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 15 of 121 Event

Description:

Unit 1 Power Decrease Scenario #3 Catawba 2021 NRC Exam Page 15 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 16 of 121 Event

Description:

Unit 1 Power Decrease Scenario #3 Catawba 2021 NRC Exam Page 16 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 17 of 121 Event

Description:

Unit 1 Power Decrease Scenario #3 Catawba 2021 NRC Exam Page 17 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 18 of 121 Event

Description:

Unit 1 Power Decrease Scenario #3 Catawba 2021 NRC Exam Page 18 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 19 of 121 Event

Description:

Unit 1 Power Decrease Scenario #3 Catawba 2021 NRC Exam Page 19 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 20 of 121 Event

Description:

Unit 1 Power Decrease Scenario #3 Catawba 2021 NRC Exam Page 20 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 21 of 121 Event

Description:

Unit 1 Power Decrease Scenario #3 Catawba 2021 NRC Exam Page 21 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 22 of 121 Event

Description:

Unit 1 Power Decrease Scenario #3 Catawba 2021 NRC Exam Page 22 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 23 of 121 Event

Description:

Unit 1 Power Decrease Scenario #3 Catawba 2021 NRC Exam Page 23 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 24 of 121 Event

Description:

Unit 1 Power Decrease Scenario #3 Catawba 2021 NRC Exam Page 24 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 2 Page 25 of 121 Event

Description:

Charging Control Valve 1NV-294 Fails Open Control Room Indications DCS alarm for 1NV-294 being full open Pressurizer Level - RISING Note To Evaluator:

The failing open of 1NV-294 will initially only cause a DCS alarm. The crew should notice the rise in charging line flow. The crew should place 1NV-294 in manual and set a control band for Pressurizer Level for the BOP to maintain. Preventing Pressurizer Level from raising above 92% is Critical Task #1. Once the BOP has control of 1NV-294, and Pressurizer Level is trending towards reference level, the scenario may continue at the discretion of the lead evaluator by having the booth operator INSERT Trigger 3 (YN Critical Trouble alarm). When this alarm is acknowledged on 1AD-19, Pressurizer PORV 1NC-32B will fail open.

Scenario #3 Catawba 2021 NRC Exam Page 25 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 2 Page 26 of 121 Event

Description:

Charging Control Valve 1NV-294 Fails Open Scenario #3 Catawba 2021 NRC Exam Page 26 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 2 Page 27 of 121 Event

Description:

Charging Control Valve 1NV-294 Fails Open Scenario #3 Catawba 2021 NRC Exam Page 27 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 28 of 121 Event

Description:

YN Critical Trouble alarm / Pressurizer PORV 1NC-32B Fails Open Control Room Indications 1AD-6, C/13 PORV NC-32B ACTUATED - LIT 1AD-6, F/8 PZR LO PRESS CONTROL - LIT Pressurizer Pressure - LOWERING Scenario #3 Catawba 2021 NRC Exam Page 28 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 29 of 121 Event

Description:

YN Critical Trouble alarm / Pressurizer PORV 1NC-32B Fails Open Scenario #3 Catawba 2021 NRC Exam Page 29 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 30 of 121 Event

Description:

YN Critical Trouble alarm / Pressurizer PORV 1NC-32B Fails Open Scenario #3 Catawba 2021 NRC Exam Page 30 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 31 of 121 Event

Description:

YN Critical Trouble alarm / Pressurizer PORV 1NC-32B Fails Open Scenario #3 Catawba 2021 NRC Exam Page 31 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 32 of 121 Event

Description:

YN Critical Trouble alarm / Pressurizer PORV 1NC-32B Fails Open Scenario #3 Catawba 2021 NRC Exam Page 32 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 3 Page 33 of 121 Event

Description:

YN Critical Trouble alarm / Pressurizer PORV 1NC-32B Fails Open Scenario #3 Catawba 2021 NRC Exam Page 33 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 34 of 121 Event

Description:

1ETA Blackout with failure of 1A D/G to start Control Room Indications Multiple alarms for annunciator panel 1AD LIT Alarms associated with RN and KC low flows - LIT A train essential equipment indications - DARK Scenario #3 Catawba 2021 NRC Exam Page 34 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 35 of 121 Event

Description:

1ETA Blackout with failure of 1A D/G to start Scenario #3 Catawba 2021 NRC Exam Page 35 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 36 of 121 Event

Description:

1ETA Blackout with failure of 1A D/G to start Scenario #3 Catawba 2021 NRC Exam Page 36 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 37 of 121 Event

Description:

1ETA Blackout with failure of 1A D/G to start Scenario #3 Catawba 2021 NRC Exam Page 37 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 38 of 121 Event

Description:

1ETA Blackout with failure of 1A D/G to start Scenario #3 Catawba 2021 NRC Exam Page 38 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 39 of 121 Event

Description:

1ETA Blackout with failure of 1A D/G to start Scenario #3 Catawba 2021 NRC Exam Page 39 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 40 of 121 Event

Description:

1ETA Blackout with failure of 1A D/G to start Scenario #3 Catawba 2021 NRC Exam Page 40 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 41 of 121 Event

Description:

1ETA Blackout with failure of 1A D/G to start Scenario #3 Catawba 2021 NRC Exam Page 41 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 42 of 121 Event

Description:

1ETA Blackout with failure of 1A D/G to start Scenario #3 Catawba 2021 NRC Exam Page 42 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 43 of 121 Event

Description:

1ETA Blackout with failure of 1A D/G to start Scenario #3 Catawba 2021 NRC Exam Page 43 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 44 of 121 Event

Description:

1ETA Blackout with failure of 1A D/G to start Scenario #3 Catawba 2021 NRC Exam Page 44 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 45 of 121 Event

Description:

1ETA Blackout with failure of 1A D/G to start Scenario #3 Catawba 2021 NRC Exam Page 45 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 4 Page 46 of 121 Event

Description:

1ETA Blackout with failure of 1A D/G to start Scenario #3 Catawba 2021 NRC Exam Page 46 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 47 of 121 Event

Description:

Control Rods Insert Continuously / Two Rods Fail to Insert on Reactor Trip Control Room Indications Control Rods - INSERTING with no demand NC System Tavg - LOWERING Scenario #3 Catawba 2021 NRC Exam Page 47 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 5 Page 48 of 121 Event

Description:

Control Rods Insert Continuously / Two Rods Fail to Insert on Reactor Trip Scenario #3 Catawba 2021 NRC Exam Page 48 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 49 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 49 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 50 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 50 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 51 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 51 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 52 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 52 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 53 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 53 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 54 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 54 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 55 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 55 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 56 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 56 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 57 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 57 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 58 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 58 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 59 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 59 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 60 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 60 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 61 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 61 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 62 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 62 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 63 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 63 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 64 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 64 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 65 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 65 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 66 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 66 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 67 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 67 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 68 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 68 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 69 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 69 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 70 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 70 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 71 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 71 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 72 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 72 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 73 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 73 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 74 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 74 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 75 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 75 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 76 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 76 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 77 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 77 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 78 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 78 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 79 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 79 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 80 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 80 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 81 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 81 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 82 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 82 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 83 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 83 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 84 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 84 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 85 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 85 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 86 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 86 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 87 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 87 of 121

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 6,7,8 Page 88 of 121 Event

Description:

CAPT#1 Overspeed Trip / Loss of Heat Sink / Loss of CFPT Vacuum / 1NV-37A Fails Closed Scenario #3 Catawba 2021 NRC Exam Page 88 of 121

Attachment List Scenario 3 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - AP/1/A/5500/007 Enclosure 1 (Foldout Page)

ATTACHMENT 4 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page)

ATTACHMENT 5 - EP/1/A/5000/ES-0.1 Enclosure 1 (Foldout Page)

ATTACHMENT 6 - EP/1/A/5000/ES-0.1 Enclosure 2 (NC Temperature Control)

ATTACHMENT 7 - EP/1/A/5000/FR-H.1 Enclosure 1 (Foldout Page)

ATTACHMENT 8 - EP/1/A/5000/FR-H.1 Enclosure 9 (S/G BB and NM Valve Checklist)

ATTACHMENT 9 EP/1/A/5000/FR-H.1 Enclosure 4 (Maintaining Pzr pressure below P-11)

ATTACHMENT 10 - Scenario Specific Technical Specifications Scenario #3 Catawba 2021 NRC Exam Page 89 of 121

ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK Control Charging flow to prevent a Reactor Trip on 1

Pressurizer High Level of 92%.

Close Pressurizer PORV prior to a manual or automatic 2

reactor trip on Pressurizer low pressure.

Establish feedwater flow to at least one S/G prior to meeting 3

bleed and feed criteria (<24% W/R level in 3 out of 4 S/Gs).

Comments:

Scenario #3 Catawba 2021 NRC Exam Page 90 of 121

ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 100 % BOL 1366 PPM per OAC Controlling Procedure

• OP/1/A/6100/003 (Controlling Procedure for Unit Operation), Enclosure 4.3 (Operation Between 85 and 100%). The steps through step 3.2.5 are complete.

Other Information Needed to Assume the Shift

• Unit 1 is at 100% power at the BOL. Unit 2 is at 100% power. 1B CA Pump is removed from service for PMs. 1B 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 />. Tech Spec 3.7.5 Condition B is in effect. Direction for the crew is to initiate a downpower to ~85% in preparation for performing the Turbine Control Valve Movement PT.

AOs Available Eight AOs are available as listed on the status board METEOROLOGICAL CONDITIONS

• Upper wind direction = 125 degrees, speed = 3 mph

• Lower wind direction = 127 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 2021 NRC Exam Page 91 of 121

ATTACHMENT 3 Scenario #3 Catawba 2021 NRC Exam Page 92 of 121

ATTACHMENT 3 Scenario #3 Catawba 2021 NRC Exam Page 93 of 121

ATTACHMENT 3 Scenario #3 Catawba 2021 NRC Exam Page 94 of 121

ATTACHMENT 4 Scenario #3 Catawba 2021 NRC Exam Page 95 of 121

ATTACHMENT 4 Scenario #3 Catawba 2021 NRC Exam Page 96 of 121

ATTACHMENT 4 Scenario #3 Catawba 2021 NRC Exam Page 97 of 121

ATTACHMENT 5 Scenario #3 Catawba 2021 NRC Exam Page 98 of 121

ATTACHMENT 6 Scenario #3 Catawba 2021 NRC Exam Page 99 of 121

ATTACHMENT 6 Scenario #3 Catawba 2021 NRC Exam Page 100 of 121

ATTACHMENT 6 Scenario #3 Catawba 2021 NRC Exam Page 101 of 121

ATTACHMENT 6 Scenario #3 Catawba 2021 NRC Exam Page 102 of 121

ATTACHMENT 6 Scenario #3 Catawba 2021 NRC Exam Page 103 of 121

ATTACHMENT 6 Scenario #3 Catawba 2021 NRC Exam Page 104 of 121

ATTACHMENT 7 Scenario #3 Catawba 2021 NRC Exam Page 105 of 121

ATTACHMENT 8 Scenario #3 Catawba 2021 NRC Exam Page 106 of 121

ATTACHMENT 8 Scenario #3 Catawba 2021 NRC Exam Page 107 of 121

ATTACHMENT 9 Scenario #3 Catawba 2021 NRC Exam Page 108 of 121

ATTACHMENT 9 Scenario #3 Catawba 2021 NRC Exam Page 109 of 121

ATTACHMENT 9 Scenario #3 Catawba 2021 NRC Exam Page 110 of 121

ATTACHMENT 10 Scenario #3 Catawba 2021 NRC Exam Page 111 of 121

ATTACHMENT 10 Scenario #3 Catawba 2021 NRC Exam Page 112 of 121

ATTACHMENT 10 Scenario #3 Catawba 2021 NRC Exam Page 113 of 121

ATTACHMENT 10 Scenario #3 Catawba 2021 NRC Exam Page 114 of 121

ATTACHMENT 10 Scenario #3 Catawba 2021 NRC Exam Page 115 of 121

ATTACHMENT 10 Scenario #3 Catawba 2021 NRC Exam Page 116 of 121

ATTACHMENT 10 Scenario #3 Catawba 2021 NRC Exam Page 117 of 121

ATTACHMENT 10 Scenario #3 Catawba 2021 NRC Exam Page 118 of 121

ATTACHMENT 10 Scenario #3 Catawba 2021 NRC Exam Page 119 of 121

ATTACHMENT 10 Scenario #3 Catawba 2021 NRC Exam Page 120 of 121

ATTACHMENT 10 Scenario #3 Catawba 2021 NRC Exam Page 121 of 121

Catawba Nuclear Station JPM A 2021 NRC Exam JPM A PAGE 1 OF 9

Catawba Nuclear Station JPM A 2021 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 2021 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC #141

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 2021 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 2021 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 2021 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 2021 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 2021 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.

CNS RESPONSE TO NUCLEAR POWER GENERATION/ATWS PAGE NO.

EP/1/A/5000/FR-S.1 1 of 33 Revision 26 A. Purpose This procedure provides actions to add negative reactivity to a core which is observed to be critical when expected to be shutdown.

B. Symptoms or Entry Conditions This procedure is entered from:

a. EP/1/A/5000/E-0 (Reactor Trip or Safety Injection), when reactor trip is not verified and manual trip is not effective.

b. EP/1/A/5000/F-0 (Critical Safety Function Status Trees), (SUBCRITICALITY) on either a RED or ORANGE condition.

c. EP/1/A/5000/FR-S.2 (Response to Loss of Core Shutdown), Step 1, when I/R or W/R power trending up.

CNS RESPONSE TO NUCLEAR POWER GENERATION/ATWS PAGE NO.

EP/1/A/5000/FR-S.1 2 of 33 Revision 26 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED C. Operator Actions CAUTION NC pumps should NOT be tripped with reactor power greater than 5% to prevent fuel damage.

1. Verify Reactor Trip: Perform the following:

All rod bottom lights - LIT a. Trip reactor.

All reactor trip and bypass breakers - b. IF reactor will not trip, THEN insert OPEN rods.

I/R power - TRENDING DOWN.

2. Verify Turbine Trip: Perform the following:

All turbine stop valves - CLOSED a. Trip turbine.

b. IF turbine will not trip, THEN perform the following:

1) Depress "MANUAL" pushbutton on turbine control panel.

2) Rapidly CLOSE control valves by simultaneously depressing "CONTROL VALVE LOWER" and "FAST RATE" pushbuttons.

3) IF control valves will not close, THEN CLOSE the following:

All MSIVs All MSIV bypass valves.

CNS RESPONSE TO NUCLEAR POWER GENERATION/ATWS PAGE NO.

EP/1/A/5000/FR-S.1 3 of 33 Revision 26 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

3. Verify CA pumps running as follows:

a. Motor driven CA pumps - ON. a. Start motor driven CA pump(s).

b. 3 S/G N/R levels - GREATER THAN b. Ensure CA Pump #1 - RUNNING.

11%.

4. Initiate Emergency Boration of NC System as follows:

a. Ensure at least one NV pump - ON.

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

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

d. Verify emergency boration flow - d. Align NV pump suction to FWST as GREATER THAN OR EQUAL TO 30 follows:

GPM.

1) OPEN the following valves:

1NV-252A (NV Pumps Suct From FWST) 1NV-253B (NV Pumps Suct From FWST).

2) CLOSE the following valves:

1NV-188A (VCT Otlt Isol) 1NV-189B (VCT Otlt Isol).

CNS RESPONSE TO NUCLEAR POWER GENERATION/ATWS PAGE NO.

EP/1/A/5000/FR-S.1 4 of 33 Revision 26 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

4. (Continued)

e. Verify the following charging line e. Perform the following:

isolation valves - OPEN:

1) Align NV pump suction to FWST 1NV-312A (Chrg Line Cont Isol) as follows:

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

a) OPEN the following valves:

1NV-252A (NV Pumps Suct From FWST) 1NV-253B (NV Pumps Suct From FWST).

b) CLOSE the following valves:

1NV-188A (VCT Otlt Isol) 1NV-189B (VCT Otlt Isol).

2) Ensure the following valves -

OPEN:

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

f. Verify Pzr pressure - LESS THAN f. Perform the following:

2335 PSIG.

1) Verify the following valves - OPEN.

All Pzr PORVs All Pzr PORV isolation valves.

2) IF any Pzr PORV(s) OR isolation valves closed, THEN OPEN Pzr PORV(s) and isolation valves as required to reduce Pzr pressure to less than 2135 PSIG.

CNS RESPONSE TO NUCLEAR POWER GENERATION/ATWS PAGE NO.

EP/1/A/5000/FR-S.1 5 of 33 Revision 26 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

5. Verify the following Monitor Light Ensure the following VQ isolation Panel Group 5 St lights on energized valves - CLOSED:

train - LIT:

1VQ-2A (VQ Fan Suct From Cont Isol)

I/2 1VQ-3B (VQ Fan Suct From Cont Isol)

I/3 1VQ-15B (Cont Air Add Cont Isol)

I/10 1VQ-16A (Cont Air Add Cont Isol).

H/11.

6. Verify S/I status as follows:

a. "SAFETY INJECTION ACTUATED" a. Perform the following:

status light (1SI-13) - LIT.

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

2) GO TO Step 7.

b. WHEN manpower AND time permits, THEN verify proper system alignments as follows:

REFER TO Enclosure 1 (System Verification Following S/I Actuation)

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

Catawba Nuclear Station JPM B 2021 NRC Exam JPM B PAGE 1 OF 11

Catawba Nuclear Station JPM B 2021 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 17 (Isolating Cold Leg Accumulators)

Task Standard: AP/1/A/5500/027 (Shutdown LOCA) Enclosure 17 (Isolating Cold Leg Accumulators) is performed and 1B & 1C Cold Leg Accumulators are isolated and 1NI-83 fully opened to vent 1A & 1D 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 B 2021 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC # 142.

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-NI005F (NI54A ACCUM ISOL VLV FAIL 1

TO POSITION)

VLV-NI014F (NI88B ACCUM ISOL VLV FAIL 1

TO POSITION)

PAGE 3 OF 11

Catawba Nuclear Station JPM B 2021 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 17 (Isolating Cold Leg Accumulators).

EXAMINER NOTE: After reading the cue, provide the applicant with a copy of AP/1/A/5500/027 Enclosure 17.

PAGE 4 OF 11

Catawba Nuclear Station JPM B 2021 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 B 2021 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-65B & 1NI-76A. Applicant also verifies the red OPEN light lit and green CLSD light dark for valves 1NI-54A & 1NI-88B and transitions to the RNO.

___ SAT The critical part of this step is to close isolation valves 1NI-65B & 1NI-76A. 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 B 2021 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 B 2021 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: CRITICAL STEP a) OPEN 1NI-47A (C-Leg Accum N2 Sup Cont Isol)

STANDARD:

Applicant depresses the red OPEN pushbutton for 1NI-47A and verifies the red OPEN light lit and green CLSD light dark.

___ SAT This step is critical to prevent binding of nitrogen supply isolation valves due to high differential pressure. ___ UNSAT COMMENTS:

PAGE 8 0F 11

Catawba Nuclear Station JPM B 2021 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.

Examiner Cue: If asked, Key #11 has been obtained.

___ SAT This step is critical to place power on Cold Leg Accumulator Nitrogen supply isolation valves for 1A and 1D CLAs which will be opened in ___ UNSAT the next step to allow venting the accumulators to containment.

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-50 and 1NI-84.

___ 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 B 2021 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 1A and 1D 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 1A and 1D CLAs.

This step is critical to vent the 1A and 1D CLAs.

NOTE TO EVALUATOR: The time to fully vent the 1A & 1D 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 1A and 1D 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 17 (Isolating Cold Leg Accumulators).

CNS SHUTDOWN LOCA PAGE NO.

AP/1/A/5500/027 187 of 189 Enclosure 17 - Page 1 of 3 Revision 44 Isolating Cold Leg Accumulators ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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).

2. Ensure S/I - RESET:

a. ECCS. a. Locally reset ECCS. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 4 (ECCS Master Reset).

b. D/G load sequencers. b. Dispatch operator to open affected sequencer(s) control power breaker:

1EDE-F01F (Diesel Generator Load Sequencer Panel 1DGLSA)

(AB-577, BB-46, Rm 496) 1EDF-F01F (Diesel Generator Load Sequencer Panel 1DGLSB)

(AB-560, BB-46, Rm 372).

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

CNS SHUTDOWN LOCA PAGE NO.

AP/1/A/5500/027 188 of 189 Enclosure 17 - Page 2 of 3 Revision 44 Isolating Cold Leg Accumulators ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

3. WHEN power aligned, THEN perform the following:

a. CLOSE the following valves: a. Perform the following:

1NI-54A (C-Leg Accum A Disch 1) Ensure containment isolation Isol) signals - RESET:

1NI-65B (C-Leg Accum B Disch Phase A Isol)

Phase B.

1NI-76A (C-Leg Accum C Disch Isol) 2) Ensure 1VI-77B (VI Cont Isol) -

OPEN.

1NI-88B (C-Leg Accum D Disch Isol). 3) IF VI pressure less than 85 PSIG, THEN perform the following:

a) Dispatch operator to ensure proper VI compressor operation.

b) Restore VI while continuing with this procedure. REFER TO AP/0/A/5500/022 (Loss of Instrument Air).

(RNO continued on next page)

CNS SHUTDOWN LOCA PAGE NO.

AP/1/A/5500/027 189 of 189 Enclosure 17 - Page 3 of 3 Revision 44 Isolating Cold Leg Accumulators ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

3. (Continued)

4) Vent any unisolated CLA as follows:

a) OPEN 1NI-47A (C-Leg Accum N2 Sup Cont Isol).

b) Place breaker 1CB-1 (behind 1MC-6) (Key #11) to - ON.

c) OPEN valve for CLA(s) to be vented:

1NI-50 (C-Leg Accum A N2 Supply Isol) 1NI-61 (C-Leg Accum B N2 Supply Isol) 1NI-72 (C-Leg Accum C N2 Supply Isol) 1NI-84 (C-Leg Accum D N2 Supply Isol).

d) CLOSE 1NI-47A.

e) OPEN 1NI-83 (C-Leg Accums N2 Vent Ctrl) to depressurize affected CLA(s).

f) IF any unisolated CLA(s) cannot be vented, THEN consult Station Management for further actions.

b. Notify dispatched operator to remove power from all CLA isolation valves.

REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 9 (Power Alignment for CLA Valves).

Catawba Nuclear Station JPM C 2021 NRC Exam JPM C PAGE 1 OF 16

Catawba Nuclear Station JPM C 2021 NRC Exam EVALUATION SHEET Task: Restore CA Flow Following Bleed and Feed Alternate Path: Yes Facility JPM #: NEW Safety Function: 4S

Title:

Loss of Secondary Heat Sink K/A EPE05 EA1.1 Ability to operate and/or monitor the following as they apply to the Loss of Secondary Heat Sink: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Rating(s): 4.1 / 4.0 CFR: 41.7 / 45.5 / 45.6 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

EP/1/A/5000/FR-H.1 (Loss of Secondary Heat Sink) Rev 48 Task Standard: CA flow restored to 1A and/or 1B Steam Generators from the 1A CA pump with suction aligned to the RN system.

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 16

Catawba Nuclear Station JPM C 2021 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC # 143.

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-CA004A (FAILURE OF CA PUMP A TO AUTO START)

MECH-MAL-CA005 (CA PUMP OVERSPEED TRIP)

ANICAL MAL-CF001A (LOSS OF CFPT 1A VACUUM) 100 MAL-CF001B (LOSS OF CFPT 1B VACUUM) 100 MAL-EHC002 (TURBINE TRIP FAILURE) BOTH VLV-CA002F (CA4 CA PMP SUCT FROM UST 0

HDR ISOL FAIL TO POSITION)

PAGE 3 OF 16

Catawba Nuclear Station JPM C 2021 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 following a reactor trip due to a loss of all feedwater.

• Bleed and Feed has been established per EP/1/A/5000/FR-H.1.

• CA flow control valves have been closed per Step 37.

• Report from AO and Maintenance in the field that 1A CA pump is ready to be started has just been received.

INITIATING CUES:

• The CRS instructs you to perform Step 7 to establish CA flow from 1A CA pump.

Examiner Note: After reading cue, provide the applicant with a copy of EP/1/A/5000/FR-H.1 Step 7.

PAGE 4 OF 16

Catawba Nuclear Station JPM C 2021 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1 7. Attempt to establish CA flow to at least one S/G as follows:

a. Verify 1AD-8, B/1 UST LO LEVEL - DARK.

___ SAT STANDARD:

___ UNSAT Applicant determines that 1AD-8, B/1 is dark.

COMMENTS:

STEP 2 7.b Verify 1CA-4 (CA Pmps Suct From UST) - OPEN.

STANDARD:

___ SAT Applicant determines that 1CA-4 is closed and transitions to the RNO.

___UNSAT COMMENTS:

PAGE 5 0F 16

Catawba Nuclear Station JPM C 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3 7.b.RNO Perform the following:

1) OPEN 1CA-4.

STANDARD:

Applicant depresses the red OPEN pushbutton and verifies the red

___ SAT OPEN light remains dark and the green CLSD light remains lit.

Applicant determines the valve will not open and continues in the

___ UNSAT RNO.

Examiner Note: This begins the alternate path of this JPM.

COMMENTS:

PAGE 6 0F 16

Catawba Nuclear Station JPM C 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4 7.b.RNO.2) IF no suction source can be aligned, THEN OPEN CRITICAL the following valves: STEP

• 1RN-250A (RN Hdr A to CA Pmp Suct Isol)

• 1CA-116A (CA Pump #1 Suct Frm RN Hdr A)

• 1CA-15A (CA Pump 1A Suct Frm RN Isol)

• 1CA-85B (CA Pump #1 Suct Frm RN Hdr B)

• 1CA-18B (CA Pump 1B Suct Frm RN Isol)

• 1RN-310B (RN Hdr B To CA Pmp Suct Isol)

STANDARD:

Applicant rotates switches for the listed valves clockwise to the OPEN

___ SAT position and verifies the red OPEN lights lit and green CLOSED lights dark.

___ UNSAT Examiner Note: This step is critical to align a suction flowpath to the CA pumps. Only 1RN-250A and 1CA-15A are required to be opened to meet this critical step due to the 1A CA pump being the only available source for CA flow.

COMMENTS:

STEP 5 7.c Verify proper CA pump status as follows:

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

STANDARD:

___ SAT Applicant determines that power is not available to 1B CA pump by

___ UNSAT observing the indicating lights dark and transitions to the RNO.

COMMENTS:

PAGE 7 0F 16

Catawba Nuclear Station JPM C 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6 7.c.1) Perform the following:

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

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

STANDARD: ___ SAT Applicant determines that power is available to 1ETB and dispatches an ___ UNSAT operator to determine cause of breaker failure.

Examiner Cue: Once contacted as an AO, Operator dispatched to determine cause of breaker failure.

COMMENTS:

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

STANDARD:

___ SAT Applicant determines 1AD-5, F/3 is lit and transitions to the RNO.

___ UNSAT COMMENTS:

PAGE 8 0F 16

Catawba Nuclear Station JPM C 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8 7.c.2) RNO Perform the following:

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

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

c) GO TO Step 7.d STANDARD:

___ SAT Applicant determines that the CAPT T/V CTRL is closed and transitions

___ UNSAT to the RNO.

Examiner Cue: Operator dispatched to open the trip and throttle valve.

COMMENTS:

STEP 9 7.d Ensure all CA isolation valves - OPEN.

STANDARD:

___ SAT Applicant verifies all CA isolation valve red OPEN lights lit and green CLSD lights dark.

___ UNSAT COMMENTS:

PAGE 9 0F 16

Catawba Nuclear Station JPM C 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 10 7.e Verify all CA flow control valves - OPEN.

STANDARD:

___ SAT Applicant verifies all CA flow control valves are closed and transitions to the RNO.

___ UNSAT COMMENTS:

STEP 11 7.e RNO Perform the following:

1) IF valve(s) closed as required by Step 37, THEN GO TO Step 7.f.

2) OPEN affected valve(s).

STANDARD:

___ SAT Applicant determines from cue sheet that the CA flow control valves were closed per step 37 and proceeds to Step 7.f.

___ UNSAT Examiner Cue: If asked why the CA flow control valves are closed, reply CA flow control valves were closed per Step 37.

COMMENTS:

PAGE 10 0F 16

Catawba Nuclear Station JPM C 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 12 7.f Start all available CA pumps.

CRITICAL STANDARD: STEP Applicant depresses the 1A CA pump red ON pushbutton and verifies the red ON light lit and green OFF light dark.

Examiner Note: This step is critical to provide CA flow to the 1A and/or 1B S/Gs to meet the JPM standard. ___ SAT COMMENTS: ___ UNSAT STEP 13 7.g Verify total CA flow - GREATER THAN 450 GPM.

STANDARD:

___ SAT Applicant determines that total CA flow is < 450 GPM and transitions to the RNO.

___ UNSAT COMMENTS:

PAGE 11 0F 16

Catawba Nuclear Station JPM C 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 14 7.g RNO Perform the following:

1) IF only one motor driven CA pump on, AND its discharge path cannot be aligned to associated S/Gs, THEN evaluate aligning flow to other S/Gs through motor driven CA train A/B cross-tie alignment. REFER TO Enclosure 3 (Motor Driven CA Pump Train A/B Cross-Tie Alignment).

___ SAT STANDARD:

___ UNSAT Applicant determines that this step is not applicable and continues in the RNO.

Examiner Note: A copy of Encl. 3 has been provided if the applicant asks for it.

COMMENTS:

STEP 15 7.g RNO 2) IF any CA pump on, AND Step 37 has been implemented, THEN GO TO Enclosure 7 (S/G CA Flow Restoration).

STANDARD:

Applicant determines from cue sheet that Step 37 has been ___ SAT implemented and transitions to Enclosure 7.

___ UNSAT Examiner Note: Provide applicant with a copy of FR-H.1 Encl. 7. The following steps are from Encl. 7.

COMMENTS:

PAGE 12 0F 16

Catawba Nuclear Station JPM C 2021 NRC Exam STEP/STANDARD SAT/UNSAT NOTE:

• It may be preferable to feed 1B or 1C S/G first, to maintain steam supply to CAPT.

• Selecting S/G with the highest level will reduce risk of thermal shock to S/G when reestablishing feed flow.

• The available feed source will also determine which S/G can be fed.

STEP 16 1. Select one S/G to be fed.

STANDARD:

Applicant determines that either 1A or 1B S/G will be fed since the 1A CA pump is the only source of feed at this time. ___ SAT COMMENTS: ___ UNSAT STEP 17 2. Verify core exit T/Cs - STABLE OR TRENDING DOWN.

STANDARD:

Applicant determines from the OAC or plasma display that CETs are ___ SAT trending down.

___ UNSAT COMMENTS:

PAGE 13 0F 16

Catawba Nuclear Station JPM C 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 18 3. THROTTLE open CA flow control valve to selected S/G to establish feed flow rate less than or equal to 100 GPM. CRITICAL STEP STANDARD:

Applicant turns flow control knob clockwise to establish flow to either 1A or 1B S/G.

Examiner Note: This step is critical to establish CA flow to either 1A or 1B S/G.

___ SAT Examiner Cue: If asked, Containment pressure has remained less than 3 PSIG. ___ UNSAT COMMENTS:

STEP 19 4. Maintain feed flow rate less than or equal to 100 GPM until W/R S/G level greater than 12% (21% ACC).

STANDARD:

___ SAT Applicant determines that W/R level is > 12% on both 1A and 1B S/Gs.

___ UNSAT COMMENTS:

CAUTION Feed flow rates should be controlled to raise S/G level and prevent excessive NC System cooldown.

PAGE 14 0F 16

Catawba Nuclear Station JPM C 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 20 5. WHEN W/R S/G level greater than 12% (21% ACC), THEN feed flow can be raised to desired rate.

STANDARD:

___ SAT Applicant determines that feed flow can be raised to desired rate.

___ UNSAT COMMENTS:

STEP 21 6. Slowly establish flow to any intact S/G with W/R level greater than 12% (21% ACC).

STANDARD:

Applicant determines that W/R level is > 12% on both 1A and 1B S/Gs and establishes flow to the S/G that has not been fed to this point by rotating the flow control knob in the clockwise direction. ___ SAT Examiner Cue: Once applicants determine that W/R level in the S/G ___ UNSAT being fed is rising, the JPM may be terminated by informing the applicant Another operator will continue with FR-H.1. This JPM is complete.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 15 0F 16

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

• Unit 1 is in Mode 3 following a reactor trip due to a loss of all feedwater.

• Bleed and Feed has been established per EP/1/A/5000/FR-H.1.

• CA flow control valves have been closed per Step 37.

• Report from AO and Maintenance in the field that 1A CA pump is ready to be started has just been received.

INITIATING CUES:

• The CRS instructs you to perform Step 7 to establish CA flow from 1A CA pump.

CNS RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE NO.

EP/1/A/5000/FR-H.1 3 of 134 Revision 48 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

5. Verify NC System feed and bleed required as follows:

a. W/R level in at least 3 S/Gs - LESS a. Perform the following:

THAN 24% (36% ACC).

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

2) WHEN criteria satisfied, THEN GO TO Step 21.

3) GO TO Step 6.

b. GO TO Step 21.

6. Ensure S/G BB and NM valves closed.

REFER TO Enclosure 9 (S/G BB and NM Valve Checklist).

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

a. Verify 1AD-8, B/1 "UST LO LEVEL" - a. Perform the following:

DARK.

1) REFER TO AP/1/A/5500/006 (Loss of S/G Feedwater).

2) GO TO Step 7.c.

CNS RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE NO.

EP/1/A/5000/FR-H.1 4 of 134 Revision 48 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

7. (Continued)

b. Verify 1CA-4 (CA Pmps Suct From b. Perform the following:

UST) - OPEN.

1) OPEN 1CA-4.

2) IF no suction source can be aligned, THEN OPEN the following valves:

1RN-250A (RN Hdr A To CA Pmp Suct Isol) 1CA-116A (CA Pump #1 Suct Frm RN Hdr A) 1CA-15A (CA Pump 1A Suct Frm RN Isol) 1CA-85B (CA Pump #1 Suct Frm RN Hdr B) 1CA-18B (CA Pump 1B Suct Frm RN Isol) 1RN-310B (RN Hdr B To CA Pmp Suct Isol).

c. Verify proper CA pump status as follows:

1) Power to both motor driven CA 1) Perform the following:

pumps - AVAILABLE.

IF 1ETA OR 1ETB de-energized, THEN restore power to affected essential bus.

REFER TO AP/1/A/5500/007 (Loss of Normal Power).

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

CNS RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE NO.

EP/1/A/5000/FR-H.1 5 of 134 Revision 48 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

7. (Continued)

2) 1AD-5, F/3 "CAPT MECH OS 2) Perform the following:

TRIP" - DARK.

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

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

c) GO TO Step 7.d.

3) "CAPT TRIP T/V CTRL" - OPEN. 3) Perform the following:

a) OPEN valve.

b) IF valve will not open, THEN dispatch operator to open CAPT trip and throttle valve.

4) Verify the following valves - OPEN: 4) Place CA Pump #1 to "ON".

1SA-2 (S/G 1B SM To CAPT) 1SA-5 (S/G 1C SM To CAPT).

d. Ensure all CA isolation valves -

OPEN.

e. Verify all CA flow control valves - e. Perform the following:

OPEN.

1) IF valve(s) closed as required by Step 37, THEN GO TO Step 7.f.

2) OPEN affected valve(s).

f. Start all available CA pumps.

CNS RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE NO.

EP/1/A/5000/FR-H.1 6 of 134 Revision 48 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

7. (Continued)

g. Verify total CA flow - GREATER g. Perform the following:

THAN 450 GPM.

1) IF only one motor driven CA pump on, AND its discharge path cannot be aligned to associated S/Gs, THEN evaluate aligning flow to other S/Gs through motor driven CA train A/B cross-tie alignment.

REFER TO Enclosure 3 (Motor Driven CA Pump Train A/B Cross-Tie Alignment).

2) IF any CA pump on, AND Step 37 has been implemented, THEN GO TO Enclosure 7 (S/G CA Flow Restoration).

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

a) Maintain flow to restore N/R level in at least one S/G to greater than 11% (29% ACC).

b) IF AT ANY TIME N/R level in at least one S/G trends up to greater than 11% (29% ACC) prior to reaching feed and bleed initiation criteria, THEN perform the following:

(1) IF NC System OR S/G depressurization in progress to feed S/G(s) from CM, THEN stabilize the following:

NC pressure S/G pressure.

(2) RETURN TO procedure and step in effect.

(RNO continued on next page)

CNS RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE NO.

EP/1/A/5000/FR-H.1 7 of 134 Revision 48 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

7. (Continued) c) Dispatch operator to verify proper CA valve alignment.

REFER TO Enclosure 2 (Local CA Flowpath Restoration).

d) IF AT ANY TIME CA flow restored greater than 450 GPM prior to meeting feed and bleed initiation criteria, THEN perform Step 7.

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

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

b) Dispatch operator to verify proper CA valve alignment.

REFER TO Enclosure 2 (Local CA Flowpath Restoration).

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

5) GO TO Step 8.

CNS RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE NO.

EP/1/A/5000/FR-H.1 8 of 134 Revision 48 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

7. (Continued)

h. Verify feed and bleed - PREVIOUSLY h. Perform the following:

ESTABLISHED (Steps 22 through 26 completed). 1) IF NC System OR S/G depressurization in progress to feed S/G(s) from CM, THEN stabilize the following:

NC pressure S/G pressure.

2) RETURN TO procedure and step in effect.

i. GO TO Step 39.

8. Verify Condenser Steam Dump as follows:

a. Verify condenser available as follows: a. GO TO Step 9.

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

b. Verify steam dumps in - T-AVG b. GO TO Step 9.

MODE.

c. Place steam dumps in pressure mode as follows:

1) Place steam dumps in -

PRESSURE MODE.

2) Ensure "STM DUMP CTRL" - SET AT 1090 PSIG STEAM HEADER PRESSURE.

9. Stop all NC pumps.

CNS RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE NO.

EP/1/A/5000/FR-H.1 91 of 134 Enclosure 7 - Page 1 of 3 Revision 48 S/G CA Flow Restoration ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE It may be preferable to feed 1B or 1C S/G first, to maintain steam supply to CAPT.

Selecting S/G with highest level will reduce risk of thermal shock to S/G when reestablishing feed flow.

The available feed source will also determine which S/G can be fed.

1. Select one S/G to be fed.

2. Verify core exit T/Cs - STABLE OR Perform the following:

TRENDING DOWN.

a. THROTTLE open CA flow control valve to establish flow rate required to lower core exit T/Cs temperature.

b. IF core exit T/Cs continue to trend up, THEN THROTTLE open CA flow control valves to feed other S/Gs as needed to lower core exit T/Cs temperature.

c. IF CA flow cannot be established to at least one S/G, THEN perform the following:

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

2) GO TO Section C. (Operator Actions), Step 37.

d. GO TO Step 6.

CNS RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE NO.

EP/1/A/5000/FR-H.1 92 of 134 Enclosure 7 - Page 2 of 3 Revision 48 S/G CA Flow Restoration ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

3. THROTTLE open CA flow control valve IF CA flow cannot be established to at to selected S/G to establish feed flow least one S/G, THEN perform the rate less than or equal to 100 GPM. following:

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

b. GO TO Section C. (Operator Actions),

Step 37.

4. Maintain feed flow rate less than or equal to 100 GPM until W/R S/G level greater than 12% (21% ACC).

CAUTION Feed flow rates should be controlled to raise S/G level and prevent excessive NC System cooldown.

5. WHEN W/R S/G level greater than 12%

(21% ACC), THEN feed flow can be raised to desired rate.

6. Slowly establish flow to any intact S/G with W/R level greater than 12%

(21% ACC).

7. Verify the following: Do not continue in this enclosure until both conditions met.

NC T-Hot associated with S/G(s) being fed - TRENDING DOWN Core Exit T/Cs - TRENDING DOWN.

CNS RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE NO.

EP/1/A/5000/FR-H.1 93 of 134 Enclosure 7 - Page 3 of 3 Revision 48 S/G CA Flow Restoration ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

8. Verify S/G(s) being fed - INTACT. Perform the following:

a. IF S/G being fed faulted OR ruptured, THEN establish feedwater flow to another S/G observing previous flowrate requirements.

b. IF an intact S/G not available to be fed, THEN establish feed flow to ruptured or faulted S/G.

c. WHEN ruptured OR faulted S/G no longer required for heat sink, THEN isolate feed flow to ruptured or faulted S/G.

9. GO TO Section C. (Operator Actions),

Step 39.

CNS RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE NO.

EP/1/A/5000/FR-H.1 76 of 134 Enclosure 3 - Page 1 of 2 Revision 48 Motor Driven CA Pump Train A/B Cross-Tie Alignment ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION Aligning single motor driven CA pump to more than two S/Gs can lead to pump runnout if control valves are opened too far or if they fail open.

NOTE 1A CA pump is normally aligned to 1A and 1B S/Gs. 1B CA pump is normally aligned to 1C and 1D S/Gs. Opening train A/B cross-tie will allow either motor driven CA pump to feed any S/G.

1. Verify 1A CA pump - ON. GO TO Step 4.

2. CLOSE the following CA flow control Perform the following:

valves:

a. Dispatch operator to close the 1CA-44 (CA Pump 1B Flow To S/G 1C) following valves. REFER TO Enclosure 14 (Unit 1 Local CA Flow 1CA-40 (CA Pump 1B Flow To S/G Control Valve Operation):

1D).

1CA-44 (CA Pump 1B Flow To S/G 1C) (AB-552, CC-DD, 52-53, Rm 250) (Ladder needed) 1CA-40 (CA Pump 1B Flow To S/G 1D) (AB-553, BB-49, Rm 250)

(Ladder needed).

b. Do not continue until valves in previous step - CLOSED.

3. GO TO Step 6.

4. Verify 1B CA pump - ON. Exit this enclosure.

CNS RESPONSE TO LOSS OF SECONDARY HEAT SINK PAGE NO.

EP/1/A/5000/FR-H.1 77 of 134 Enclosure 3 - Page 2 of 2 Revision 48 Motor Driven CA Pump Train A/B Cross-Tie Alignment ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

5. CLOSE the following CA flow control Perform the following:

valves:

a. Dispatch operator to close the 1CA-60 (CA Pump 1A Flow To S/G 1A) following valves. REFER TO Enclosure 14 (Unit 1 Local CA Flow 1CA-56 (CA Pump 1A Flow To S/G Control Valve Operation):

1B).

1CA-60 (CA Pump 1A Flow To S/G 1A) (AB-551, BB-CC, 49-50, Rm 250) (Ladder needed) 1CA-56 (CA Pump 1A Flow To S/G 1B) (AB-552, DD-52, Rm 250)

(Ladder needed).

b. Do not continue until valves in previous step - CLOSED.

6. Limit motor driven CA pump flow in the following steps to less than 500 GPM.

7. Dispatch operator to unlock and open IF valve(s) will not open, THEN the following valves while monitoring perform the following to reduce P CA flow: across valves:

1CA-111 (1A & 1B CA Pump Disch a. Stop motor driven CA pump.

X-over To S/G Isol) (AB-552, BB-50, Rm 250) b. Notify dispatched operator to open valves prior to starting pump.

1CA-112 (1A & 1B CA Pump Disch X-over To S/G Isol) (AB-552, BB-50, c. Start motor driven CA pump.

Rm 250).

8. THROTTLE open CA flow control Notify dispatched operator to throttle valves to desired flow rate. local valves as required. REFER TO Enclosure 14 (Unit 1 Local CA Flow Control Valve Operation).

Catawba Nuclear Station JPM D 2021 NRC Exam JPM D PAGE 1 OF 10

Catawba Nuclear Station JPM D 2021 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 46 Task Standard: At least one train of Phase A containment isolation initiated and either 1NV-10A or 1NV-15B manually closed and either 1WL-805A or 1WL-807B 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 10

Catawba Nuclear Station JPM D 2021 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC # 144.

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 A ISOL BLOCK SIGNAL TRN B)

VLV-NV009A (NV10A L/D ORIFICE 1B ISOL ACTIVE CNTRL FAIL AUTO ACTIONS)

VLV-NV012A (NV15B L/D ISOL OUTSIDE ACTIVE CNMT VLV FAIL AUTO ACTIONS)

VLV-WL007A (WL805A NCDT PMPS DISCH ACTIVE CONT ISOL IN FAIL AUTO ACTIONS)

VLV-WL008A (WL807B NCDT PMPS DISCH ACTIVE CONT ISOL OUT FAIL AUTO ACTIONS)

When applicant is ready, INSERT EVENT 1.

PAGE 3 OF 10

Catawba Nuclear Station JPM D 2021 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 10

Catawba Nuclear Station JPM D 2021 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: 1. Monitor Enclosure 1 (Foldout Page).

STANDARD:

___ SAT Applicant will monitor Foldout Page actions once immediate actions are performed and verified.

___ UNSAT COMMENTS:

STEP 2: 2. Verify Reactor Trip:

• All rod bottom lights - LIT

• All reactor trip and bypass breakers - OPEN

• I/R power - TRENDING DOWN.

___ SAT STANDARD:

___ UNSAT Applicant verifies the reactor is tripped.

COMMENTS:

STEP 3: 3. Verify Turbine Trip:

• All turbine stop valves - CLOSED.

STANDARD: ___ SAT Applicant determines the turbine is tripped. ___ UNSAT COMMENTS:

PAGE 5 0F 10

Catawba Nuclear Station JPM D 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: 4. Verify 1ETA and 1ETB - ENERGIZED.

STANDARD:

Applicant verifies that 1ETA and 1ETB are energized by use of status ___ SAT lights or by verifying the indicating lights lit for KC valves on both A and B trains. ___ UNSAT COMMENTS:

STEP 5: 5. Verify S/I actuated:

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

LIT.

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

LIT.

STANDARD:

Applicant determines that safety injection has actuated.

___ SAT Examiner Note: Once applicant announces that his immediate actions

___ UNSAT are complete, hand them a copy of E-0 completed through step 5 and provide the following cue:

The CRS has validated that the immediate actions are complete and directs you to continue performance of E-0, beginning at Step 6.

COMMENTS:

PAGE 6 0F 10

Catawba Nuclear Station JPM D 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: 6. Announce Unit 1 Safety Injection.

STANDARD:

___ SAT Applicant uses the plant paging system to make the announcement.

___ UNSAT COMMENTS:

STEP 7 7. Determine required notifications:

• REFER TO AD-EP-ALL-0111 (Control Room Activation of the ERO)

• REFER TO AD-LS-ALL-0006 (Notification/Reportability Evaluation) ___ SAT STANDARD: ___UNSAT Applicant acknowledges the step and continues with E-0.

COMMENTS:

STEP 8 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 7 0F 10

Catawba Nuclear Station JPM D 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 9 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 10 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 letdown penetration is isolated. The letdown 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 8 0F 10

Catawba Nuclear Station JPM D 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 11 9.b. Monitor Light Panel Group 5 St lights on energized train(s)

- LIT.

STANDARD:

Applicant determines that Group 5 St lights B/1, B/12, C/1, and C/12 are ___ SAT dark and transitions to the RNO.

___ UNSAT Examiner Note: It may take up to 60 seconds for all other valves to indicate isolated.

COMMENTS:

STEP 12 9.b.RNO. Align valves as necessary to ensure each penetration isolated by at least one isolation valve. CRITICAL STEP STANDARD:

Applicant rotates the switch for 1NV-10A counterclockwise to the CLOSE position and verifies the green closed light is lit and red open light dark. Applicant depresses the green CLOSE pushbutton for 1NV-15B and verifies the green CLSD light lit and red OPEN light dark.

Applicant depresses the green CLOSE pushbutton for 1WL-805A and 1WL-807B and verifies the green CLSD light lit and red OPEN light dark on both valves.

Examiner Note: It is critical for the applicant to close 1 of the valves ___ SAT in each penetration (either 1NV-10A or 1NV-15B and either 1WL-805A or 1WL-807B) to ensure the ___ UNSAT penetration is isolated.

Examiner Cue: Once valves have been closed, 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:

• 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

CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO.

EP/1/A/5000/E-0 4 of 49 Revision 46 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED C. Operator Actions

1. Monitor Enclosure 1 (Foldout Page).

2. Verify Reactor Trip: Perform the following:

All rod bottom lights - LIT a. Trip reactor.

All reactor trip and bypass breakers - b. IF reactor will not trip, THEN OPEN concurrently perform the following:

I/R power - TRENDING DOWN. Implement EP/1/A/5000/F-0 (Critical Safety Function Status Trees)

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

3. Verify Turbine Trip: Perform the following:

All turbine stop valves - CLOSED. a. Trip turbine.

b. IF turbine will not trip, THEN perform the following:

1) Depress "MANUAL" pushbutton on turbine control panel.

2) Rapidly CLOSE control valves by simultaneously depressing "CONTROL VALVE LOWER" and "FAST RATE" pushbuttons.

3) IF control valves will not close, THEN CLOSE the following valves:

All MSIVs All MSIV bypass valves.

CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO.

EP/1/A/5000/E-0 5 of 49 Revision 46 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

4. Verify 1ETA and 1ETB - ENERGIZED. Perform the following:

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

b. WHEN time allows, THEN attempt to restore power to de-energized switchgear while continuing with this procedure. REFER TO AP/1/A/5500/007 (Loss of Normal Power).

CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO.

EP/1/A/5000/E-0 6 of 49 Revision 46 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

5. Verify S/I actuated:

a. "SAFETY INJECTION ACTUATED" a. Perform the following:

status light (1SI-13) - LIT.

1) Verify conditions requiring S/I:

Pzr pressure - LESS THAN 1845 PSIG OR Containment pressure -

GREATER THAN 1.2 PSIG.

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

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

IF 1ETA OR 1ETB de-energized, THEN ensure the following pumps running on energized bus:

NV pump KC pumps RN pump.

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

GO TO EP/1/A/5000/ES-0.1 (Reactor Trip Response).

b. Both E/S load sequencer actuated b. Initiate S/I.

status lights (1SI-14) - LIT.

6. Announce "Unit 1 Safety Injection".

CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO.

EP/1/A/5000/E-0 7 of 49 Revision 46 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

7. Determine required notifications:

REFER TO AD-EP-ALL-0111 (Control Room Activation of the ERO)

REFER TO AD-LS-ALL-0006 (Notification/Reportability Evaluation).

8. Verify all Feedwater Isolation status Perform the following:

lights (1SI-5) - LIT.

a. Initiate Feedwater Isolation.

b. IF proper status light indication not obtained, THEN CLOSE valves.

9. Verify Phase A Containment Isolation status as follows:

a. Phase A "RESET" lights - DARK. a. Initiate Phase A Isolation.

b. Monitor Light Panel Group 5 St lights b. Align valves as necessary to ensure on energized train(s) - LIT. each penetration isolated by at least one isolation valve.

CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO.

EP/1/A/5000/E-0 8 of 49 Revision 46 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

10. Verify Phase B actuation as follows:

a. Verify containment pressure - HAS a. Perform the following:

REMAINED LESS THAN 3 PSIG.

1) Verify Phase B Isolation actuated as follows:

a) Phase B Isolation "RESET" lights - DARK.

b) IF Phase B Isolation "RESET" lights lit, THEN initiate Phase B Isolation.

c) Verify following monitor light panel lights on energized train(s) - LIT:

Group 1 Sp lights Group 5 Sp lights Group 5 St light L/11.

d) IF monitor light panel not in correct alignment, THEN ensure correct alignment.

2) Stop all NC pumps.

3) Maintain seal injection flow.

4) Energize H2 igniters.

(RNO continued on next page)

CNS REACTOR TRIP OR SAFETY INJECTION PAGE NO.

EP/1/A/5000/E-0 9 of 49 Revision 46 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

10. (Continued)

5) Dispatch operator to perform the following:

a) Secure all ice condenser air handling units. REFER TO EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 11 (Securing All Ice Condenser Units).

b) Place containment H2 analyzers in service. REFER TO OP/1/A/6450/010 (Containment Hydrogen Control Systems).

6) WHEN 9 minutes elapsed, THEN verify proper VX System operation.

REFER TO Enclosure 5 (VX System Operation).

7) GO TO Step 11.

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

Catawba Nuclear Station JPM E 2021 NRC Exam JPM E PAGE 1 OF 15

Catawba Nuclear Station JPM E 2021 NRC Exam EVALUATION SHEET Task: Align the NS System for Cold Leg Recirculation Alternate Path: Yes Facility JPM #: NS-106 Safety Function: 5

Title:

Containment Integrity K/A 026 A4.01 Ability to manually operate and/or monitor in the control room: CSS controls Rating(s): 4.5 / 4.3 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/ES-1.3 (Transfer to Cold Leg Recirculation) Enclosure 2. Rev.031 Task Standard: Aligns NS system for Cold Leg Recirculation with suction valves from the FWST closed, spray header containment isolations open, 1B NS Pump running, and proper RN flow to the 1B NS Heat Exchanger.

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 15

Catawba Nuclear Station JPM E 2021 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC # 145.

3. Enter the password.

4. Select Yes on the INITIAL CONDITION RESET pop-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE Extra Operator is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

Instructor Action Final Delay Ramp Delete In Event MAL-NC013A (NC COLD LEG A LEAK) 27.5 VLV-NS009F (NS18A NS PMP A SUCT 0

FROM CNMT SUMP FAIL TO POSITION)

PAGE 3 OF 15

REV. 0 PAGE 4 0F 15 Catawba Nuclear Station JPM E 2021 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 LOCA has occurred on Unit 1.

• EP/1/A/5000/ES-1.3, (Transfer to Cold Leg Recirculation) has been implemented.

INITIATING CUES:

The CRS instructs you to align NS to Cold Leg Recirculation per Enclosure 2 of ES-1.3.

Examiner Note: After reading cue, provide the applicant with a copy of EP/1/A/5000/ES-1.3 Enclosure 2.

PAGE 4 OF 15

Catawba Nuclear Station JPM E 2021 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: 1. Verify both NS pumps - OFF.

STANDARD:

___ SAT Applicant verifies that 1A and 1B NS pumps are off .

___ UNSAT COMMENTS:

STEP 2 2. CLOSE the following valves: CRITICAL STEP

• 1NS-20A (NS Pump 1A Suct From FWST)

• 1NS-3B (NS Pump 1B Suct From FWST).

STANDARD:

Applicant depresses the green CLOSE pushbuttons for 1NS-20A and 1NS-3B. ___ SAT Examiner Note: This step is critical to ensure suction flowpath is only ___ UNSAT from the containment sump.

COMMENTS:

PAGE 5 0F 15

Catawba Nuclear Station JPM E 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3 3. Verify containment pressure - GREATER THAN 3 PSIG STANDARD:

Applicant verifies containment pressure is greater than 3 psig on ___ SAT 1NSP5040, 1NSP5050, 1NSP5060 or 1NSP5070 on 1MC-11 or on the OAC or on any chart recorder containing containment pressure. ___ UNSAT COMMENTS:

STEP 4 4. Verify at least one of the following annunciators - LIT:

• 1AD-20, B/3 "CONT. SUMP LEVEL >3.3 ft" OR

• 1AD-21, B/3 "CONT. SUMP LEVEL >3.3 ft". ___ SAT STANDARD: ___ UNSAT Applicant verifies that at least 1AD-20, B/3 or 1AD-21, B/3 is lit on 1MC-7 COMMENTS:

PAGE 6 0F 15

Catawba Nuclear Station JPM E 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5 5. Align NS Train 1A to containment sump as follows:

a. Verify NS Pump 1A - AVAILABLE TO RUN.

STANDARD: ___ SAT Applicant verifies that NS Pump 1A is available to run. ___ UNSAT COMMENTS:

STEP 6 5. b. Verify 1NI-185A (ND Pump 1A Cont Sump Suct) - OPEN.

STANDARD:

___ SAT Applicant verifies that 1NI-185A is open.

___ UNSAT COMMENTS:

STEP 7 5. c. Verify NS Pump 1B - OFF STANDARD:

___ SAT Applicant verifies that NS Pump 1B is off.

___ UNSAT COMMENTS:

PAGE 7 0F 15

Catawba Nuclear Station JPM E 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8 5. d. OPEN 1NS-29A (NS Spray Hdr 1A Cont Isol).

CRITICAL STANDARD: STEP Applicant depresses the red OPEN pushbutton for 1NS-29A on 1MC-11.

Examiner Note: This step is critical to provide a flowpath from the pump to the containment spray rings. ___ SAT COMMENTS: ___ UNSAT STEP 9 5. e. OPEN 1NS-32A (NS Spray Hdr 1A Cont Isol).

CRITICAL STANDARD: STEP Applicant depresses the red OPEN pushbutton for 1NS-32A on 1MC-11.

Examiner Note: This step is critical to provide a flowpath from the pump to the containment spray rings. ___ SAT COMMENTS: ___ UNSAT STEP 10 5. f. Verify 1NS-20A (NS Pump 1A Suct From FWST) -

CLOSED.

STANDARD:

___ SAT Applicant verifies that 1NS-20A is closed.

___ UNSAT COMMENTS:

PAGE 8 0F 15

Catawba Nuclear Station JPM E 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 11 5. g. OPEN 1NS-18A (NS Pmp A Suct From Cont Sump).

STANDARD:

Applicant depresses the red OPEN pushbutton for 1NS-18A on 1MC-

11. The valve will not open. No RNO step available for this step. ___ SAT Applicant proceeds to next step.

___ UNSAT Examiner Note: This begins the alternate path for this JPM.

COMMENTS:

STEP 12 5. h. Verify the following valves - OPEN:

• 1NS-29A (NS Spray Hdr 1A Cont Isol)

• 1NS-32A (NS Spray Hdr 1A Cont Isol)

• 1NS-18A (NS Pmp A Suct From Cont Sump). ___ SAT STANDARD: ___ UNSAT Applicant verifies that 1NS-29A and 1NS-32A are open and that 1NS-18A is closed and transitions to the RNO.

COMMENTS:

PAGE 9 0F 15

Catawba Nuclear Station JPM E 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 13 5.h RNO. IF any valve remains CLOSED or INTERMEDIATE for over 25 seconds, THEN GO TO Step 6.

STANDARD:

___ SAT Applicant proceeds to Step 6 in order to place 1B NS train in service.

___ UNSAT COMMENTS:

STEP 14 6. Align NS Train 1B to containment sump as follows:

a. Verify 1NI-184B (ND Pump 1B Cont Sump Suct) - OPEN.

STANDARD: ___ SAT Applicant verifies that 1NI-184B is open. ___ UNSAT COMMENTS:

STEP 15 6. b. Verify NS Pump 1A - OFF STANDARD:

___ SAT Applicant verifies that NS Pump 1A is off.

___ UNSAT COMMENTS:

PAGE 10 0F 15

Catawba Nuclear Station JPM E 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 16 6.c OPEN 1NS-15B (NS Spray Hdr 1B Cont Isol).

CRITICAL STANDARD: STEP Applicant depresses the red OPEN pushbutton for 1NS-15B and verifies the red open light is lit and green CLSD light is dark.

Examiner Note: This step is critical to provide a flowpath from the pump to the containment spray rings. ___ SAT COMMENTS: ___ UNSAT STEP 17 6.d OPEN 1NS-12B (NS Spray Hdr 1B Cont Isol).

CRITICAL STANDARD: STEP Applicant depresses the red OPEN pushbutton for 1NS-12B on 1MC-11 and verifies the red OPEN light lit and green CLSD light dark.

Examiner Note: This step is critical to provide a flowpath from the pump to the containment spray rings. ___ SAT COMMENTS: ___ UNSAT STEP 18 6.e Verify 1NS-3B (NS Pump 1B Suct From FWST) - CLOSED.

STANDARD:

___ SAT Applicant verifies green CLSD light lit and red OPEN light dark for 1NS-3B.

___ UNSAT COMMENTS:

PAGE 11 0F 15

Catawba Nuclear Station JPM E 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 19 6.f. OPEN 1NS-1B (NS Pmp B Suct From Cont Sump).

CRITICAL STANDARD: STEP Applicant depresses the red OPEN pushbutton and verifies the red OPEN light lit and green CLSD light dark for 1NS-1B.

Examiner Note: This step is critical to provide a suction path from the containment sump to the NS pump. ___ SAT COMMENTS: ___ UNSAT STEP 20 6.g. Verify the following valves - OPEN:

• 1NS-15B (NS Spray Hdr 1B Cont Isol)

• 1NS-12B (NS Spray Hdr 1B Cont Isol)

• 1NS-1B (NS Pmp B Suct From Cont Sump) ___ SAT STANDARD: ___ UNSAT Applicant verifies that listed valves are open.

COMMENTS:

STEP 21 6.h. Verify containment pressure - GREATER THAN 1 PSIG.

STANDARD:

___ SAT Applicant verifies that containment pressure is > 1 PSIG.

___ UNSAT COMMENTS:

PAGE 12 0F 15

Catawba Nuclear Station JPM E 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 22 6.i Start NS Pump 1B.

CRITICAL STANDARD: STEP Applicant depresses the red ON pushbutton for 1B NS pump and verifies the red ON light lit and green OFF light dark.

Examiner Note: This step is critical to initiate containment spray flow. ___ SAT COMMENTS: ___ UNSAT CAUTION: Exceeding 4650 GPM RN flow through an NS Hx will cause damage to the Hx tubes.

STEP 23 6.j.1) Align RN to NS Hx 1B as follows:

Verify at least one of the following:

• All Unit 1 and Unit 2 RN pumps - ON OR

• RN System - ALIGNED FOR SINGLE SUPPLY HEADER OPERATION ___ SAT STANDARD: ___ UNSAT Applicant verifies that all Unit 1 and Unit 2 RN pumps are on.

COMMENTS:

PAGE 13 0F 15

Catawba Nuclear Station JPM E 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 24 6.j.2) OPEN 1RN-225B (NS Hx 1B Inlet Isol).

CRITICAL STANDARD: STEP Applicant depresses the red OPEN pushbutton for 1RN-225B and verifies the red OPEN light lit and green CLSD light dark.

Examiner Note: This step is critical to provide cooling of containment spray. ___ SAT COMMENTS: ___ UNSAT STEP 25 6.j.3). WHEN 1RN-225B begins to open, THEN OPEN 1RN-229B (NS Hx 1B Otlt Isol) CRITICAL STEP STANDARD:

Applicant depresses and holds the red OPEN pushbutton for 1RN-229B and verifies the red OPEN light lit and green CLSD light dark.

Examiner Note: This step is critical to provide cooling of containment spray.

___ SAT Examiner Cue: Once cooling water has been established: Another operator will continue this enclosure. JPM complete. ___ UNSAT COMMENTS:

END OF TASK STOP TIME ________

PAGE 14 0F 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:

• A LOCA has occurred on Unit 1.

• EP/1/A/5000/ES-1.3, (Transfer to Cold Leg Recirculation) has been implemented.

INITIATING CUES:

The CRS instructs you to align NS to Cold Leg Recirculation per Enclosure 2 of ES-1.3.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 25 of 41 Enclosure 2 - Page 1 of 12 Revision 31 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. Verify both NS pumps - OFF. Perform the following:

a. IF all the following conditions met:

NS in service NS suction aligned to containment sump RN established to associated NS Hx, THEN RETURN TO procedure section and step in effect.

b. Ensure both NS pumps - OFF.

2. CLOSE the following valves:

1NS-20A (NS Pump 1A Suct From FWST) 1NS-3B (NS Pump 1B Suct From FWST).

3. Verify containment pressure - Perform the following:

GREATER THAN 3 PSIG.

a. Wait up to 20 seconds for 1NS-20A and 1NS-3B to close.

b. OPEN 1NS-18A (NS Pmp A Suct From Cont Sump).

c. OPEN 1NS-1B (NS Pmp B Suct From Cont Sump).

d. IF AT ANY TIME containment pressure goes above 3 PSIG, THEN perform Enclosure 2 (Aligning NS for Recirculation).

e. RETURN TO procedure section and step in effect.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 26 of 41 Enclosure 2 - Page 2 of 12 Revision 31 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

4. Verify at least one of the following Perform the following:

annunciators - LIT:

a. WHEN at least one "CONT. SUMP 1AD-20, B/3 "CONT. SUMP LEVEL LEVEL >3.3 ft" annunciator - LIT,

>3.3 ft" THEN GO TO Step 5.

OR b. Do not continue in this enclosure until at least one annunciator - LIT.

1AD-21, B/3 "CONT. SUMP LEVEL

>3.3 ft".

5. Align NS train 1A to containment sump as follows:

a. Verify NS pump 1A - AVAILABLE TO a. GO TO Step 6.

RUN.

b. Verify 1NI-185A (ND Pump 1A Cont b. GO TO Step 6.

Sump Suct) - OPEN.

c. Verify NS pump 1B - OFF. c. IF NS pump 1B running AND RN established to NS Hx 1B, THEN perform the following:

1) Ensure 1NS-20A (NS Pump 1A Suct From FWST) - CLOSED.

2) Ensure 1NS-18A (NS Pmp A Suct From Cont Sump) - OPEN.

3) GO TO Step 7.

d. OPEN 1NS-29A (NS Spray Hdr 1A d. GO TO Step 6.

Cont Isol).

e. OPEN 1NS-32A (NS Spray Hdr 1A e. GO TO Step 6.

Cont Isol).

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 27 of 41 Enclosure 2 - Page 3 of 12 Revision 31 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

5. (Continued)

f. Verify 1NS-20A (NS Pump 1A Suct f. IF 1NS-20A remained OPEN or From FWST) - CLOSED. INTERMEDIATE for over 20 seconds, THEN GO TO Step 6.

g. OPEN 1NS-18A (NS Pmp A Suct From Cont Sump).

h. Verify the following valves - OPEN: h. IF any valve remains CLOSED or INTERMEDIATE for over 25 seconds, 1NS-29A (NS Spray Hdr 1A Cont THEN GO TO Step 6.

Isol) 1NS-32A (NS Spray Hdr 1A Cont Isol) 1NS-18A (NS Pmp A Suct From Cont Sump).

i. Verify containment pressure - i. Perform the following:

GREATER THAN 1 PSIG.

1) CLOSE the following valves:

1NS-29A (NS Spray Hdr 1A Cont Isol) 1NS-32A (NS Spray Hdr 1A Cont Isol).

2) IF AT ANY TIME containment pressure exceeds 1 PSIG, THEN RETURN TO Step 4.

3) GO TO Step 7.

j. Start NS pump 1A. j. GO TO Step 6.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 28 of 41 Enclosure 2 - Page 4 of 12 Revision 31 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

5. (Continued)

CAUTION Exceeding 4650 GPM RN flow through an NS Hx will cause damage to the Hx tubes.

k. Align RN to NS Hx 1A as follows:

1) Verify at least one of the following: 1) Perform the following to support NS Hx cooling flow:

All Unit 1 and Unit 2 RN pumps -

ON a) IF only one A train RN pump on, THEN CLOSE Unit 2 OR 2RN-48B (RN Supply X-Over Isol).

RN System - ALIGNED FOR SINGLE SUPPLY HEADER b) IF only A train RN pumps on, OPERATION. THEN CLOSE one of the following Unit 2 valves:

2RN-47A (RN Supply X-Over Isol)

OR 2RN-48B (RN Supply X-Over Isol).

2) OPEN 1RN-144A (NS Hx 1A Inlet Isol).

3) WHEN 1RN-144A begins to open, THEN OPEN 1RN-148A (NS Hx 1A Otlt Isol).

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 29 of 41 Enclosure 2 - Page 5 of 12 Revision 31 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

6. Align NS train 1B to containment sump as follows:

a. Verify 1NI-184B (ND Pump 1B Cont a. GO TO Step 7.

Sump Suct) - OPEN.

b. Verify NS pump 1A - OFF. b. IF NS pump 1A running AND RN established to NS Hx 1A, THEN perform the following:

1) Ensure 1NS-3B (NS Pump 1B Suct From FWST) - CLOSED.

2) Ensure 1NS-1B (NS Pmp B Suct From Cont Sump) - OPEN.

3) GO TO Step 7.

c. OPEN 1NS-15B (NS Spray Hdr 1B c. GO TO Step 7.

Cont Isol).

d. OPEN 1NS-12B (NS Spray Hdr 1B d. GO TO Step 7.

Cont Isol).

e. Verify 1NS-3B (NS Pump 1B Suct e. IF 1NS-3B remained OPEN or From FWST) - CLOSED. INTERMEDIATE for over 20 seconds, THEN GO TO Step 7.

f. OPEN 1NS-1B (NS Pmp B Suct From Cont Sump).

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 30 of 41 Enclosure 2 - Page 6 of 12 Revision 31 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

6. (Continued)

g. Verify the following valves - OPEN: g. IF any valve remains CLOSED or INTERMEDIATE for over 25 seconds, 1NS-15B (NS Spray Hdr 1B Cont THEN GO TO Step 7.

Isol) 1NS-12B (NS Spray Hdr 1B Cont Isol) 1NS-1B (NS Pmp B Suct From Cont Sump).

h. Verify containment pressure - h. Perform the following:

GREATER THAN 1 PSIG.

1) CLOSE the following valves:

1NS-15B (NS Spray Hdr 1B Cont Isol) 1NS-12B (NS Spray Hdr 1B Cont Isol).

2) IF AT ANY TIME containment pressure exceeds 1 PSIG, THEN RETURN TO Step 4.

3) GO TO Step 7.

i. Start NS pump 1B.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 31 of 41 Enclosure 2 - Page 7 of 12 Revision 31 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

6. (Continued)

CAUTION Exceeding 4650 GPM RN flow through an NS Hx will cause damage to the Hx tubes.

j. Align RN to NS Hx 1B as follows:

1) Verify at least one of the following: 1) Perform the following to support NS Hx cooling flow:

All Unit 1 and Unit 2 RN pumps -

ON a) IF only one B train RN pump on, THEN CLOSE Unit 2 OR 2RN-47A (RN Supply X-Over Isol).

RN System - ALIGNED FOR SINGLE SUPPLY HEADER b) IF only B Train RN pumps on, OPERATION. THEN CLOSE one of the following Unit 2 valves:

2RN-48B (RN Supply X-Over Isol)

OR 2RN-47A (RN Supply X-Over Isol).

2) OPEN 1RN-225B (NS Hx 1B Inlet Isol).

3) WHEN 1RN-225B begins to open, THEN OPEN 1RN-229B (NS Hx 1B Otlt Isol).

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 32 of 41 Enclosure 2 - Page 8 of 12 Revision 31 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

7. Verify proper NS alignment as follows:

a. Verify 1NS-18A (NS Pmp A Suct a. Perform the following:

From Cont Sump) - OPEN.

1) IF 1NI-185A (ND Pump 1A Cont Sump Suct) open AND 1NS-20A (NS Pump 1A Suct From FWST) closed, THEN OPEN 1NS-18A.

2) DO NOT start 1A NS pump until aligned to containment sump.

b. Verify 1NS-1B (NS Pmp B Suct From b. Perform the following:

Cont Sump) - OPEN.

1) IF 1NI-184B (ND Pump 1B Cont Sump Suct) open AND 1NS-3B (NS Pump 1B Suct From FWST) closed, THEN OPEN 1NS-1B.

2) DO NOT start 1B NS pump until aligned to containment sump.

c. Verify NS pump 1A - ON. c. Ensure the following valves -

CLOSED:

1NS-29A (NS Spray Hdr 1A Cont Isol) 1NS-32A (NS Spray Hdr 1A Cont Isol).

d. Verify NS pump 1B - ON. d. Ensure the following valves -

CLOSED:

1NS-15B (NS Spray Hdr 1B Cont Isol) 1NS-12B (NS Spray Hdr 1B Cont Isol).

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 33 of 41 Enclosure 2 - Page 9 of 12 Revision 31 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

8. IF AT ANY TIME NS flow lost OR RN flow lost to operating NS Hx, THEN start other NS pump as follows:

a. Ensure affected NS pump - OFF.

b. CLOSE the following valves for affected train:

A Train:

1NS-29A (NS Spray Hdr 1A Cont Isol) 1NS-32A (NS Spray Hdr 1A Cont Isol) 1RN-148A (NS Hx 1A Otlt Isol) 1RN-144A (NS Hx 1A Inlet Isol).

B Train:

1NS-12B (NS Spray Hdr 1B Cont Isol) 1NS-15B (NS Spray Hdr 1B Cont Isol) 1RN-229B (NS Hx 1B Otlt Isol) 1RN-225B (NS Hx 1B Inlet Isol).

c. Verify both the following Unit 2 valves c. IF affected valve closed to support NS

- OPEN: Hx cooling flow, THEN ensure valve -

RETURNED TO PREVIOUS 2RN-47A (RN Supply X-Over Isol) ALIGNMENT.

2RN-48B (RN Supply X-Over Isol).

d. RETURN TO Step 4 in this enclosure.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 34 of 41 Enclosure 2 - Page 10 of 12 Revision 31 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

9. Verify adequate RN heat sink as Perform the following:

follows:

a. Ensure the following valves - OPEN:

RN System - SUCTION ALIGNED TO LAKE WYLIE 1RN-3A (RN P/H Pit A Isol From SNSWP)

RN essential header temperatures at one of the following locations - LESS 1RN-4B (RN P/H Pit B Isol From THAN OR EQUAL TO 93°F: SNSWP) 1MC-9 1RN-58B (RN Hdr B Ret To SNSWP)

OR 1RN-63A (RN Hdr A Ret To RO Logbook. SNSWP) 1RN-846A (D/G 1A Hx Ret To SNSWP) 1RN-848B (D/G 1B Hx Ret To SNSWP) 2RN-846A (D/G 2A Hx Ret To SNSWP) 2RN-848B (D/G 2B Hx Ret To SNSWP).

(RNO continued on next page)

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 35 of 41 Enclosure 2 - Page 11 of 12 Revision 31 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

9. (Continued)

b. Ensure the following valves -

CLOSED:

1RN-1A (RN P/H Pit A Isol From Lake) 1RN-2B (RN P/H Pit A Isol From Lake) 1RN-5A (RN P/H Pit B Isol From Lake) 1RN-6B (RN P/H Pit B Isol From Lake) 1RN-53B (Station RN Disch Hdr X-Over) 1RN-54A (Station RN Disch Hdr X-Over) 1RN-57A (Station RN Disch To RL Sys) 1RN-843B (Station RN Disch To RL Sys) 1RN-847A (D/G 1A Hx Ret To Lake) 1RN-849B (D/G 1B Hx Ret To Lake) 2RN-847A (D/G 2A Hx Ret To Lake) 2RN-849B (D/G 2B Hx Ret To Lake).

10. Verify any NS pump - ON. Exit this enclosure.

CNS TRANSFER TO COLD LEG RECIRCULATION PAGE NO.

EP/1/A/5000/ES-1.3 36 of 41 Enclosure 2 - Page 12 of 12 Revision 31 Aligning NS for Recirculation ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

11. Notify Control Room Supervisor this enclosure shall remain in effect until current or subsequent procedures provide alternate guidance.

12. IF AT ANY TIME containment pressure less than 1 PSIG, THEN perform the following:

a. Ensure NS pump - OFF.

b. CLOSE the following valves for affected train:

A Train:

1NS-29A (NS Spray Hdr 1A Cont Isol) 1NS-32A (NS Spray Hdr 1A Cont Isol) 1RN-148A (NS Hx 1A Otlt Isol) 1RN-144A (NS Hx 1A Inlet Isol).

B Train:

1NS-12B (NS Spray Hdr 1B Cont Isol) 1NS-15B (NS Spray Hdr 1B Cont Isol) 1RN-229B (NS Hx 1B Otlt Isol) 1RN-225B (NS Hx 1B Inlet Isol).

c. Verify both the following Unit 2 valves c. IF affected valve closed to support NS

- OPEN: Hx cooling flow, THEN ensure valve -

RETURNED TO PREVIOUS 2RN-47A (RN Supply X-Over Isol) ALIGNMENT.

2RN-48B (RN Supply X-Over Isol).

d. IF AT ANY TIME containment pressure exceeds 3 PSIG, THEN RETURN TO Step 4 in this enclosure.

Catawba Nuclear Station JPM F 2021 NRC Exam JPM F PAGE 1 OF 10

Catawba Nuclear Station JPM F 2021 NRC Exam EVALUATION SHEET Task: Manually align Essential power to 1FTB from 1ETB per AP/1/A/5500/007 Case 1 Step 10 Alternate Path: No Facility JPM #: EP-018 Safety Function: 6

Title:

A.C. Electrical Distribution K/A 062A4.01 Ability to manually operate and/or monitor in the control room: All breakers (including available switchyard)

Rating(s): 3.3 / 3.1 CFR: 41.7 / 45.5 to 45.8 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

AP/1/A/5500/007 Case I Task Standard: Applicant manually energizes 1FTB from 1ETB.

Validation Time: 10 minutes Time Critical: Yes No X

===============================================================

Applicant: Time Start: __________

NAME__________________________ Docket #_____________ Time Finish: __________

Performance Rating: Performance Time _____

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 10

Catawba Nuclear Station JPM F 2021 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC # 146.

3. Enter the password.

4. Select Yes on the INITIAL CONDITION RESET pop-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE Extra Operator is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

Instructor Action Final Delay Ramp Delete In Event LOA-EP095 (600VLXH BKR LXH-4B) OPEN 1 LOA-EP095 (600V LC LXH BKR LXH-4B) CLOSE 2 MAL-EQB001B (D/G 1B LOAD SEQUENCER R1 FAILURE)

PAGE 3 OF 10

Catawba Nuclear Station JPM F 2021 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.

INITIATING CUES:

• Unit 1 has experienced a B Train blackout due to a failure of 1ATD. The 1B D/G is supplying 1ETB. The crew has implemented AP/1/A/5500/07 Case 1 (Loss of Normal Power to an Essential Train). The CRS has directed you to perform step 10.

EXAMINER NOTE: After reading Initiating Cue, provide the applicant with a copy of AP/1/A/5500/007 Case 1 step 10.

PAGE 4 OF 10

Catawba Nuclear Station JPM F 2021 NRC Exam START TIME: _______

STEP/STANDARD SAT/UNSAT STEP 1: 10. Verify B/O busses are energized as follows:

a. 1AD-11, K/3 "4KV B/O BUS FTA VOLTAGE LO" -

DARK.

STANDARD: ___ SAT Applicant will verify 1AD-11, K/3 is DARK ___ UNSAT COMMENTS:

STEP 2 10.b 1AD-11, K/4 "4KV B/O BUS FTB VOLTAGE LO" - DARK.

STANDARD:

___ SAT Applicant will note that 1AD-11, K/4 is LIT and will transition to the RNO column.

___ UNSAT COMMENTS:

PAGE 5 0F 10

Catawba Nuclear Station JPM F 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3 10.b.RNO b. Perform the following:

1) Ensure breaker "FTB B/O NORM FDR FRM ATD" - OPEN.

___ SAT STANDARD:

___ UNSAT Applicant will verify breaker is open COMMENTS:

STEP 4 10.b. RNO b. CRITICAL STEP

2) Dispatch operator to open 1LXH-4B (Incoming Breaker Fed From Xfmr TXH)

(SB-594, U-30).

STANDARD:

Applicant will contact the booth and dispatch an operator to open 1LXH-4B

___ SAT Booth Operator: Insert Event 1 to open 1LXH-4B.

___ UNSAT Examiner Note: This step is critical to prevent overloading 1FTB during realignment to ETB in the following steps.

COMMENTS:

PAGE 6 0F 10

Catawba Nuclear Station JPM F 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5 10.b. RNO b.

3) IF S/I has actuated, THEN ensure "ECCS TRN B" reset.

___ SAT STANDARD:

___ UNSAT Applicant will determine that this step does not apply.

COMMENTS:

STEP 6 10.b RNO b.

CRITICAL

4) Reset "D/G 1B LOAD SEQ RESET". STEP STANDARD:

Applicant will depress the D/G 1B LOAD SEQ REST pushbutton Examiner Note: This step is critical to gain manual control of the ___ SAT breakers in subsequent steps.

___ UNSAT COMMENTS:

PAGE 7 0F 10

Catawba Nuclear Station JPM F 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7 10.b. RNO b.

CRITICAL

5) WHEN notified by dispatched operator that STEP 1LXH-4B is open, THEN perform the following:

a) Close breaker "FTB B/O ALT FDR FRM ETB".

STANDARD:

Once notified, applicant will close breaker

___ SAT Booth Operator: Contact Control Room and inform operator that 1LXH-4B is open. ___ UNSAT Examiner Note: This step is critical to energize 1FTB from 1ETB.

COMMENTS:

STEP 8 10.b. RNO b.5)

CRITICAL b) Close breaker "ETB ALT FDR TO FTB". STEP STANDARD:

Applicant will close the breaker.

___ SAT Examiner Note: This step is critical to energize 1FTB from 1ETB.

___ UNSAT COMMENTS:

PAGE 8 0F 10

Catawba Nuclear Station JPM F 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 9 10.b. RNO b.5)

CRITICAL c) Notify dispatched operator to close STEP 1LXH-4B (Incoming Breaker Fed From Xfmr 1TXH) (SB-594, U-30).

STANDARD:

Applicant will contact the booth and notify dispatched operator to close 1LXH-4B.

Booth Operator : Insert Event 2 to close 1LXH-4B.

Examiner Note: This step is critical to re-energize 1LXH. ___ SAT Examiner Cue: Following breaker closure, Another operator will ___ UNSAT continue steps of this procedure. JPM 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:

• Unit 1 is operating at 100% power.

INITIATING CUES:

• Unit 1 has experienced a B Train blackout due to a failure of 1ATD. The 1B D/G is supplying 1ETB. The crew has implemented AP/1/A/5500/07 Case 1 (Loss of Normal Power to an Essential Train). The CRS has directed you to perform step 10.

CNS LOSS OF NORMAL POWER PAGE NO.

AP/1/A/5500/007 7 of 280 Case I Revision 86 Loss of Normal Power to an Essential Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

10. Verify B/O busses energized as follows:

a. 1AD-11, K/3 "4KV B/O BUS FTA a. Perform the following:

VOLTAGE LO" - DARK.

NOTE Both ND Hx Bypass valves fail closed on loss of 1LXI (1FTA).

1) IF ND pump 1A operating in Residual Heat Removal Mode, THEN perform the following:

a) Place "PWR DISCON FOR 1NI173A" in "THROT".

b) THROTTLE 1NI-173A (ND Hdr 1A To Cold Legs C&D) to stabilize NC temperature.

2) IF ND pump 1B operating in Residual Heat Removal Mode, THEN perform the following:

a) Place "PWR DISCON FOR 1NI178B" in "THROT".

b) THROTTLE 1NI-178B (ND Hdr 1B To Cold Legs A&B) to stabilize NC temperature.

3) Ensure breaker "FTA B/O NORM FDR FRM ATC" - OPEN.

4) Dispatch operator to open 1LXI-4B (Incoming Breaker Fed From Xfmr 1TXI) (SB-594, U-V, 29-30).

5) IF S/I actuated, THEN ensure "ECCS TRN A" reset.

6) Reset "D/G 1A LOAD SEQ RESET".

(RNO continued on next page)

CNS LOSS OF NORMAL POWER PAGE NO.

AP/1/A/5500/007 8 of 280 Case I Revision 86 Loss of Normal Power to an Essential Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

10. (Continued)

7) WHEN notified by dispatched operator 1LXI-4B open, THEN perform the following:

a) CLOSE breaker "FTA B/O ALT FDR FRM ETA".

b) CLOSE breaker "ETA ALT FDR TO FTA".

c) Notify dispatched operator to close 1LXI-4B (Incoming Breaker Fed From Xfmr 1TXI)

(SB-594, U-V, 29-30).

b. 1AD-11, K/4 "4KV B/O BUS FTB b. Perform the following:

VOLTAGE LO" - DARK.

1) Ensure breaker "FTB B/O NORM FDR FRM ATD" - OPEN.

2) Dispatch operator to open 1LXH-4B (Incoming Breaker Fed From Xfmr 1TXH) (SB-594, U-30).

3) IF S/I actuated, THEN ensure "ECCS TRN B" reset.

4) Reset "D/G 1B LOAD SEQ RESET".

5) WHEN notified by dispatched operator 1LXH-4B open, THEN perform the following:

a) CLOSE breaker "FTB B/O ALT FDR FRM ETB".

b) CLOSE breaker "ETB ALT FDR TO FTB".

c) Notify dispatched operator to close 1LXH-4B (Incoming Breaker Fed From Xfmr 1TXH)

(SB-594, U-30).

CNS LOSS OF NORMAL POWER PAGE NO.

AP/1/A/5500/007 9 of 280 Case I Revision 86 Loss of Normal Power to an Essential Train ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

11. Verify B/O loads in service as follows:

a. Maintain D/G load less than 5750 KW.

b. Ensure proper B/O sequencer(s) loading as follows:

REFER TO Enclosure 2 (Blackout Loads)

Dispatch operator to ensure all required in plant loads energized OR on. REFER TO Enclosure 3 (Local Blackout Loads).

c. Ensure Spent Fuel Pool cooling established. REFER TO AP/1/A/5500/041 (Loss of Spent Fuel Cooling or Level).

12. Verify VI pressure - GREATER THAN REFER TO AP/0/A/5500/022 (Loss of 85 PSIG AND STABLE. Instrument Air).

Catawba Nuclear Station JPM G 2021 NRC Exam JPM G PAGE 1 OF 11

Catawba Nuclear Station JPM G 2021 NRC Exam 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. 18, 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 G 2021 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC # 147.

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 G 2021 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 G 2021 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 G 2021 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 G 2021 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 G 2021 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 G 2021 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 G 2021 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.

Enclosure 4.2 OP/0/A/6500/080 EMF RP86A and RM1000 Trip Setpoint Page 1 of 3 Adjustment Information Use

1. Limits and Precautions 1.1 The EMF RP86A and RM1000 green "OPERATE" light goes dark and the failure relay de-energizes under any of the following conditions:

The operate/calibrate switch is set to calibrate Loss of high voltage Loss of signal (0 counts in 2 minutes)

Safety loop open Loss of power 1.2 If an EMF RP86A and RM1000 Trip 1 is set higher than Trip 2, the entered value will be accepted.

2. Initial Conditions Verify a need to adjust the EMF setpoints.

3. Procedure 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.

3.1 IF necessary, press the clear key [CLR] to reset trip lamps.

3.2 Press the function key [FUN] to bring up the "SELECT FUNCTION" screen.

Enclosure 4.2 OP/0/A/6500/080 EMF RP86A and RM1000 Trip Setpoint Page 2 of 3 Adjustment Information Use 3.3 Adjust Trip 1 Setpoint as follows:

3.3.1 Press [1] for Trip 1 setting display screen.

3.3.2 Key in the desired Trip 1 setpoint.

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.

NOTE: Once the enter key [ENT] is pressed, the change in Trip 1 alarm setpoint is active.

3.3.4 Press the enter key [ENT]. This value is now displayed under "TRIP 1" and the "ENTER" block is cleared.

3.3.5 Press the clear key [CLR] to return to the "SELECT FUNCTION" screen.

3.4 Adjust Trip 2 Setpoint as follows:

3.4.1 Press [2] for Trip 2 setting display screen.

3.4.2 Key in the desired Trip 2 setpoint.

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.

NOTE: Once the enter key [ENT] is pressed, the changes in Trip 2 alarm setpoint is active.

3.4.4 Press the enter key [ENT]. This value is now displayed under "TRIP 2" and the "ENTER" block is cleared.

3.5 Press the clear key [CLR] twice to return to the normal display screen.

3.6 Enter the new EMF setpoints on the Control Room EMF Setpoint Log.

3.7 Sign the Control Room EMF Setpoint Log in the appropriate box.

3.8 IF applicable, document the RP personnel that supplied the setpoints in the Control Room EMF Setpoint Log.

Enclosure 4.2 OP/0/A/6500/080 EMF RP86A and RM1000 Trip Setpoint Page 3 of 3 Adjustment Information Use 3.9 A separate Operator shall perform the following:

3.9.1 Verify that the correct setpoints are entered in the Control Room EMF Setpoint Log.

3.9.2 Sign the IV BY block on the Control Room EMF Setpoint Log.

Catawba Nuclear Station JPM H 2021 NRC Exam JPM H PAGE 1 OF 14

Catawba Nuclear Station JPM H 2021 NRC Exam EVALUATION SHEET Task: Place KC in Parallel Operation per OP/1/A/6400/005 Alternate Path: No Facility JPM #: KC-085 Safety Function: 8

Title:

Plant Service Systems K/A 008 A4.01 Ability to manually operate and/or monitor in the control room: CCW indications and controls Rating(s): 3.3 / 3.1 CFR: 41.7 / 45.5 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

OP/1/A/6400/005 (Component Cooling System) Rev. 132 Enclosure 4.4 (Operation of Additional KC Pumps/Parallel Operation)

Task Standard: KC Pump 1A1 is started and 1A KC HX OTLT MODE switch is placed in KC TEMP position to place KC in parallel operation.

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 H 2021 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC # 148

3. Ensure 1B2 KC pump in operation

4. Place simulator in RUN and acknowledge any alarms.

5. ENSURE Extra Operator is present in the simulator.

6. 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 2021 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:

1. Unit 1 is at 100% power.

2. A work list item has been generated to place Unit 1 KC in parallel operation in preparation for Aux Safeguards Testing early next shift.

INITIATING CUES:

1. The CRS instructs you to place KC in parallel operation by performing Encl.

4.4 of OP/1/A/6400/005. You are to start 1A1 KC pump. Pre-start pump checkout has been successfully completed. Initial conditions have previously been verified and signed off. You are to begin at step 3.4.

2. The Cation Bed Demineralizer is NOT in service.

3. CV is waived for this JPM.

Examiner Note: After reading cue, provide the applicant with a copy of OP/1/A/6400/005 Encl. 4.4.

PAGE 4 OF 14

Catawba Nuclear Station JPM H 2021 NRC Exam START TIME: _______

STEP/STANDARD SAT/UNSAT STEP 1: 3.4 IF placing KC train 1A in parallel operation with KC Train 1B with the trains cross connected, complete the following steps:

3.4.1 Complete the following steps to ensure the RN system has miniflow protection:

3.4.1.1 IF a Unit 2 KC Hx discharge valve is in the MINIFLOW position, perform the following:

A. Ensure the associated inlet valve is open:

• 2RN-287A (KC Hx 2A Inlet Isol)

• 2RN-347B (KC Hx 2B Inlet Isol)

B. Ensure a complete RN flow path exists ___ SAT from the RN pumps through the applicable Hx to the discharge. ___ UNSAT STANDARD:

Applicant asks Unit 2 operator to verify which KC heat exchanger is in service and whether its respective heat exchanger inlet valve is open.

Applicant determines RN system is in normal lineup and has a flowpath through 2B KC heat exchanger to the discharge by looking at the OAC graphic.

Examiner Cue: 2B KC heat exchanger is in the MINIFLOW position and 2RN-347B is open.

COMMENTS:

PAGE 5 0F 14

Catawba Nuclear Station JPM H 2021 NRC Exam STEP 2: 3.1.4.2 IF no Unit 2 KC Hxs are available for RN miniflow, establish miniflow per OP/0/A/6400/006 C (Nuclear Service Water System) as necessary to maintain RN flow > 8600 GPM per operating RN pump.

STANDARD: ___ SAT Applicant determines this step is N/A. 2B KC heat exchanger is ___UNSAT available for miniflow.

COMMENTS:

STEP 3: 3.4.2 Ensure 1RN-287A (KC Hx 1A Inlet Isol) is open.

STANDARD:

Applicant determines that the red OPEN light is lit and green CLSD ___ SAT light is dark on 1RN-287A.

___ UNSAT COMMENTS:

STEP 4: 3.4.3 Ensure KC HX A OTLT MODE is in KC TEMP.

CRITICAL STANDARD: STEP Applicant rotates KC HX A OTLT MODE switch counter clockwise to the KC TEMP position.

Examiner Note: This step is critical in order to maintain consistent temperature in the 1A KC train and prevent reactivity excursions due to flowrate changes (and associated ___ SAT letdown temperature changes) following the start of 1A1 KC Pump. ___ UNSAT COMMENTS:

PAGE 6 0F 14

Catawba Nuclear Station JPM H 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: 3.4.4 IF letdown is in service per OP/1/A/6200/001 (Chemical and Volume Control System) perform the following:

3.4.4.1 Verify the Cation Bed Demineralizer is NOT in service per OP/1/A/6200/001 (Chemical and Volume Control System).

STANDARD: ___ SAT Applicant requests information concerning status of the Cation Bed ___ UNSAT Demineralizer.

Examiner Cue: The Cation Bed Demineralizer is not in service.

COMMENTS:

STEP 6: 3.4.4.2 Record position of 1NV-153A (Letdn Hx Otlt 3-Way Vlv)

Recorded valve position _______________

STANDARD:

___ SAT Applicant records position of 1NV-153A to be the AUTO/DEMIN

___ UNSAT position.

COMMENTS:

PAGE 7 0F 14

Catawba Nuclear Station JPM H 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7: 3.4.4.3 IF letdown flow is through the demineralizers, notify Primary Chemistry that the demineralizers will be bypassed while shifting KC pumps.

Person notified ___________________

STANDARD:

___ SAT Applicant contacts Primary Chemistry and informs them that the demineralizers will be bypassed.

___ UNSAT Examiner Cue: This is Steve in Primary Chemistry. I understand that the letdown demineralizers will be bypassed while shifting KC pumps.

COMMENTS:

PAGE 8 0F 14

Catawba Nuclear Station JPM H 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8: 3.4.4.4 IF letdown flow is through the demineralizers, notify Radiation Protection that the demineralizers will be bypassed while shifting KC Pumps.

Person notified ______________________

STANDARD:

___ SAT Applicant contacts Radiation Protection and informs them that the demineralizers will be bypassed.

___ UNSAT Examiner Cue: This is Gary in Radiation Protection. I understand that the letdown demineralizers will be bypassed while shifting KC pumps.

COMMENTS:

STEP 9: 3.4.4.5 Place 1NV-153A (Letdn Hx Otlt 3-Way Vlv) in the VCT position.

STANDARD:

Applicant rotates switch for 1NV-153A counter clockwise to the VCT ___ SAT position and verifies the white light lit and red light dark.

___ UNSAT COMMENTS:

CAUTION: 5700 GPM discharge header flow per operating KC Pump shall NOT be exceeded PAGE 9 0F 14

Catawba Nuclear Station JPM H 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 10: 3.4.5 Start either KC Train 1A pump:

CRITICAL STEP

• KC PUMP A1

• OR

• KC PUMP A2 STANDARD:

Per initiating cue, applicant will start 1A1 KC pump by depressing the red ON pushbutton and verifying the red ON light lit and green OFF light dark.

___ SAT Examiner Note: This step is critical because on A train KC pump has to be started to place KC in parallel operation per the

___ UNSAT JPM standard.

Examiner Cue: Following pump start, 1A1 KC pump post start check is complete - Good for continued operation.

COMMENTS:

STEP 11: 3.4.6 IF KC flow requirement in the Train 1A header is >

5700 gpm, perform the following:

STANDARD:

___ SAT Applicant determines this step is not applicable.

___ UNSAT COMMENTS:

NOTE: One pump running is preferred as long as flow is < 5700 gpm.

PAGE 10 0F 14

Catawba Nuclear Station JPM H 2021 NRC Exam STEP/STANDARD SAT/UNSAT CAUTION:

• The time two KC pumps in a train are operating with header flow less than 5700 gpm shall be minimized.

• Operating two KC pumps in a train with header flow less than 4850 gpm has the potential for a strong pump versus weak pump interaction, which can impact minimum flow capacity.

STEP 12: 3.4.7 IF KC flow requirement in the 1A header is < 5700 gpm AND it is desirable to place the second Train 1A pump in service, perform the following:

STANDARD: ___ SAT Applicant determines this step is not applicable. ___ UNSAT COMMENTS:

PAGE 11 0F 14

Catawba Nuclear Station JPM H 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 13: 3.4.8 IF letdown is in service per OP/1/A/6200/001 (Chemical and Volume Control System), WHEN KC flow and temperature have stabilized, perform the following:

3.4.8.1 IF 1NV-153A (Letdn Hx Otlt 3-Way Vlv) position was recorded as DEMIN in Step 3.7.4.2 AND no other reason exists for it to remain in the VCT position, return it to AUTO as follows:

A. Place 1NV-153A in the DEMIN position. (RM)

___ SAT STANDARD:

___ UNSAT Applicant will rotate switch for 1NV-153A clockwise to the DEMIN position, verifying the red light lit and white light dark, and then return the switch to the AUTO position.

Examiner Cue: Using time compression, KC flow and temperature have stabilized.

COMMENTS:

STEP 14: 3.4.8.1.B Verify 1NV-153A returns to AUTO.

STANDARD:

Applicant verifies switch position in AUTO. ___ SAT COMMENTS: ___ UNSAT PAGE 12 0F 14

Catawba Nuclear Station JPM H 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 15: 3.4.8.2 IF letdown flow is through the demineralizers, notify Primary Chemistry that the demineralizers have been restored to service.

Person notified ___________________

STANDARD:

___ SAT Applicant contacts Primary Chemistry and lets them know that the demineralizers have been returned to service.

___ UNSAT Examiner Cue: This is Steve with Primary Chemistry. I understand that the letdown demineralizers have been returned to service.

COMMENTS:

STEP 16: 3.4.8.3 IF letdown flow is through the demineralizers, notify Radiation Protection that the demineralizers have been restored to service.

Person notified ___________________

STANDARD:

Applicant contacts Radiation Protection and lets them know that the demineralizers have been returned to service. ___ SAT Examiner Cue: This is Gary with Radiation Protection. I understand ___ UNSAT that the letdown demineralizers have been returned to service.

Examiner Cue: Another operator will finish the procedure. 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:

1. Unit 1 is at 100% power.

2. A work list item has been generated to place Unit 1 KC in parallel operation in preparation for Aux Safeguards Testing early next shift.

INITIATING CUES:

1. The CRS instructs you to place KC in parallel operation by performing Encl.

4.4 of OP/1/A/6400/005. You are to start 1A1 KC pump. Pre-start pump checkout has been successfully completed. Initial conditions have previously been verified and signed off. You are to begin at step 3.4.

2. The Cation Bed Demineralizer is NOT in service.

3. CV is waived for this JPM.

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 1 of 20 Operation

1. Limits and Precautions 1.1 This procedure is Reactivity Management related because it controls activities that can affect core reactivity by changing letdown temperature. (R.M.)

1.2 The maximum discharge header flow for each operating KC pump is 5700 gpm.

1.3 When manually operating any motor operated valve, minimize the torque applied to the handwheel.

1.4 After manual operation, maintenance or packing adjustment of any safety related motor operated valve, it shall be cycled electrically to ensure reliable automatic operation.

1.5 KC pump minimum flow is 1100 gpm.

1.6 While running just one KC Pump, making KC flow adjustments in a gradual manner will minimize total KC System flow fluctuations. (PIP 96-1894) 1.7 The time two KC pumps in a train are operating with header flow less than 5700 gpm shall be minimized.

1.8 Operating two KC pumps in a train with header flow less than 4850 gpm has the potential for a "strong pump" versus "weak pump" interaction, which can impact minimum flow capacity.

2. Initial Conditions AA 2.1

_____ Verify one train of KC is operating per Enclosure 4.1 (System Startup).

AA 2.2

_______ Notify Radwaste of the intent to change the current KC system pump lineup.

AA 2.3

_____ IF in Mode 1 or 2, ensure R3 reactivity management controls established per AD-OP-ALL-0203 (Reactivity Management). (R.M.)

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 2 of 20 Operation

3. Procedure NOTE: Steps 3.1 through 3.9 are independent of each other and may be performed in any order.

N/A 3.1

_____ IF an operating KC Train has a single pump in operation with the idle pump in that train available AND it is desired to start the additional pump in the train, THEN perform one of the following:

_____ 3.1.1 IF KC flow requirements on the train are > 5700 gpm, perform the following:

_____ 3.1.1.1 Ensure the appropriate miniflow valve is closed:

_____ _____

• 1KC-C37A (Train A Miniflow Isol)

OR

_____ _____

• 1KC-C40B (Train B Miniflow Isol) 3.1.1.2 Start the idle pump in the train:

_____ * "KC PUMP A1" OR

_____ * "KC PUMP A2" OR

_____ * "KC PUMP B1" OR

_____ * "KC PUMP B2"

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 3 of 20 Operation NOTE: One pump running is preferred as long as flow is < 5700 gpm.

CAUTION:

• The time two KC pumps in a train are operating with header flow less than 5700 gpm shall be minimized.

• Operating two KC pumps in a train with header flow less than 4850 gpm has the potential for a "strong pump" versus "weak pump" interaction, which can impact minimum flow capacity.

_____ 3.1.2 IF KC flow requirement in the train is < 5700 gpm AND it is desired to start the additional pump in the train, perform the following:

3.1.2.1 Start the idle pump in the train:

_____ * "KC PUMP A1" OR

_____ * "KC PUMP A2" OR

_____ * "KC PUMP B1" OR

_____ * "KC PUMP B2"

_____ 3.1.2.2 Ensure minimum flow requirements are met.

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 4 of 20 Operation NOTE: One pump running is preferred as long as flow is < 5700 gpm.

N/A 3.2

_____ IF both KC pumps in an operating train are running AND flow requirement in that operating train is < 5700 gpm, perform the following:

_______ 3.2.1 IF required, throttle KC flow to the inservice KF heat exchanger as necessary to prevent KC pump runout:

_____

• 1KC-149 (KF Hx 1A Cool Wtr Otlt)

_____

• 1KC-156 (KF Hx 1B Cool Wtr Otlt)

_____ 3.2.2 IF AT ANY TIME KC Train flow approaches 5700 gpm while performing the next step, ensure the appropriate miniflow valve is closed:

_____ _____

• 1KC-C37A (Train A Miniflow Isol)

OR

_____ _____

• 1KC-C40B (Train B Miniflow Isol) 3.2.3 Stop one of the operating pumps:

_____ * "KC PUMP A1" OR

_____ * "KC PUMP A2" OR

_____ * "KC PUMP B1" OR

_____ * "KC PUMP B2" 3.2.4 Perform the following for the KF cooling loops that are in service:

_____ 3.2.4.1 IF 1A KF Cooling Loop is in service, adjust 1KC-149 (KF Hx 1A Cool Wtr Otlt) flow controller on 1MC11 to 3000 gpm or as necessary to maintain Spent Fuel Pool temperature < 125F.

_____ 3.2.4.2 IF 1B KF Cooling Loop is in service, adjust 1KC-156 (KF Hx 1B Cool Wtr Otlt) flow controller on 1MC11 to 3000 gpm or as necessary to maintain Spent Fuel Pool temperature < 125F.

AA 3.3

_____ IF additional KC flow is needed AND both pumps in the operating loop are running OR KC is in single pump operation with the idle pump in the operating train NOT available, place KC in parallel operation per Step 3.4, 3.5, 3.7 or 3.8 as applicable.

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 5 of 20 Operation

_____ 3.4 IF placing KC Train 1A in parallel operation with KC Train 1B with the trains cross-connected, complete the following steps:

NOTE: RN System minimum flow protection is normally established using an idle KC train.

3.4.1 Complete the following steps to ensure the RN System has miniflow protection:

_____ 3.4.1.1 IF a Unit 2 KC Hx discharge valve is in the "MINIFLOW" position, perform the following:

A. Ensure the associated inlet valve is open:

_____ _____

• 2RN-287A (KC Hx 2A Inlet Isol)

_____ _____

• 2RN-347B (KC Hx 2B Inlet Isol)

_____ B. Ensure a complete RN flow path exists from the RN Pumps through the applicable Hx to the discharge.

_____ 3.4.1.2 IF no Unit 2 KC Hxs are available for RN miniflow, establish miniflow per OP/0/A/6400/006 C (Nuclear Service Water System) as necessary to maintain RN flow 8600 gpm per operating RN Pump.

_____ _____ 3.4.2 Ensure 1RN-287A (KC Hx 1A Inlet Isol) is open.

_______ 3.4.3 Ensure "KC HX 1A OTLT MODE" is in "KC TEMP".

_______ 3.4.4 IF letdown is in service per OP/1/A/6200/001 (Chemical and Volume Control System) perform the following: (R.M.)

_____ 3.4.4.1 Verify the Cation Bed Demineralizer is NOT in service per OP/1/A/6200/001 (Chemical and Volume Control System).

_____ 3.4.4.2 Record position of 1NV-153A (Letdn Hx Otlt 3-Way Vlv).

Recorded valve position________________

_____ 3.4.4.3 IF letdown flow is through the demineralizers, notify Primary Chemistry that the demineralizers will be bypassed while shifting KC Pumps.

Person notified ____________________________

_____ 3.4.4.4 IF letdown flow is through the demineralizers, notify Radiation Protection that the demineralizers will be bypassed while shifting KC Pumps.

Person notified ____________________________

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 6 of 20 Operation

_____ 3.4.4.5 Place 1NV-153A (Letdn Hx Otlt 3-Way Vlv) in the "VCT" position.

CAUTION: 5700 gpm discharge header flow per each operating KC pump shall NOT be exceeded.

3.4.5 Start either KC Train 1A pump:

_____ * "KC PUMP A1" OR

_____ * "KC PUMP A2"

_____ 3.4.6 IF KC flow requirement in the Train 1A header is > 5700 gpm, perform the following:

_____ _____ 3.4.6.1 Ensure 1KC-C37A (Train A Miniflow Isol) is closed.

3.4.6.2 Start the remaining KC Train 1A pump:

_____ * "KC PUMP A1" OR

_____ * "KC PUMP A2" NOTE: One pump running is preferred as long as flow is < 5700 gpm.

CAUTION:

• The time two KC pumps in a train are operating with header flow less than 5700 gpm shall be minimized.

• Operating two KC pumps in a train with header flow less than 4850 gpm has the potential for a "strong pump" versus "weak pump" interaction, which can impact minimum flow capacity.

_____ 3.4.7 IF KC flow requirement in the Train 1A header is < 5700 gpm AND it is desired to place the second Train 1A pump in service, perform the following:

3.4.7.1 Start the remaining KC Train 1A pump:

_____ * "KC PUMP A1" OR

_____ * "KC PUMP A2"

_____ 3.4.7.2 Ensure minimum flow requirements are met.

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 7 of 20 Operation

_____ 3.4.8 IF letdown is in service per OP/1/A/6200/001 (Chemical and Volume Control System), WHEN KC flow and temperature have stabilized perform the following: (R.M.)

_____ 3.4.8.1 IF 1NV-153A (Letdn Hx Otlt 3-Way Vlv) position was recorded as "DEMIN" in Step 3.4.4.2 AND no other reason exists for it to remain in the "VCT" position, return it to "AUTO" as follows:

_____ A. Place 1NV-153A in the "DEMIN" position. (R.M.)

B. Verify 1NV-153A returns to "AUTO".

_____ 3.4.8.2 IF letdown flow is through the demineralizers, notify Primary Chemistry that the demineralizers have been restored to service.

Person notified ____________________________

_____ 3.4.8.3 IF letdown flow is through the demineralizers, notify Radiation Protection that the demineralizers have been restored to service.

Person notified ___________________________

NOTE: At this point, KC Train 1A and 1B are in parallel service.

_____ 3.4.9 IF RN miniflow was established per Step 3.4.1.2, WHEN no longer needed, secure unneeded flow paths.

_____ 3.4.10 IF Train 1A is to be secured, leaving Train 1B in service as per Enclosure 4.1 (System Startup), go to Step 3.6.

_____ 3.5 IF placing KC Train 1A in parallel operation with KC Train 1B with the trains NOT cross-connected, complete the following steps:

NOTE: RN System minimum flow protection is normally established using an idle KC train.

3.5.1 Complete the following steps to ensure the RN System has miniflow protection:

_____ 3.5.1.1 IF a Unit 2 KC Hx discharge valve is in the "MINIFLOW" position, perform the following:

A. Ensure the associated inlet valve is open:

_____ _____

• 2RN-287A (KC Hx 2A Inlet Isol)

_____ _____

• 2RN-347B (KC Hx 2B Inlet Isol)

_____ B. Ensure a complete RN flow path exists from the RN Pumps through the applicable Hx to the discharge.

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 8 of 20 Operation

_____ 3.5.1.2 IF no Unit 2 KC Hxs are available for RN miniflow, establish miniflow per OP/0/A/6400/006 C (Nuclear Service Water System) as necessary to maintain RN flow 8600 gpm per operating RN Pump.

_____ _____ 3.5.2 Ensure 1RN-287A (KC Hx 1A Inlet Isol) is open.

_______ 3.5.3 Ensure "KC HX 1A OTLT MODE" is in "KC TEMP".

_____ _____ 3.5.4 Ensure 1KC-56A (KC To ND Hx 1A Sup Isol) is closed.

CAUTION: 5700 gpm discharge header flow per each operating KC pump shall NOT be exceeded.

3.5.5 Start either KC Train 1A pump:

_____ * "KC PUMP A1" OR

_____ * "KC PUMP A2"

_____ _____ 3.5.6 Ensure 1KC-C37A (Train A Miniflow Isol) opens.

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 9 of 20 Operation

_____ 3.5.7 IF KC flow requirement in the Train 1A header is > 5700 gpm, perform the following:

_____ _____ 3.5.7.1 Ensure 1KC-C37A (Train A Miniflow Isol) is closed.

_____ 3.5.7.2 IF Train 1A header flow is > 5700 gpm, start the remaining KC Train 1A pump:

_____ * "KC PUMP A1" OR

_____ * "KC PUMP A2" NOTE: One pump running is preferred as long as flow is < 5700 gpm.

CAUTION:

• The time two KC pumps in a train are operating with header flow less than 5700 gpm shall be minimized.

• Operating two KC pumps in a train with header flow less than 4850 gpm has the potential for a "strong pump" versus "weak pump" interaction, which can impact minimum flow capacity.

_____ 3.5.8 IF KC flow requirement in the Train 1A header is < 5700 gpm AND it is desired to place the second Train 1A pump in service, perform the following:

3.5.8.1 Start the remaining KC Train 1A pump:

_____ * "KC PUMP A1" OR

_____ * "KC PUMP A2"

_____ 3.5.8.2 Ensure minimum flow requirements are met.

_____ 3.5.9 IF RN miniflow was established per Step 3.5.1.2, WHEN no longer needed, secure unneeded flow paths.

NOTE: At this point, KC Train 1A and 1B are in parallel service with KC Train 1A isolated from the Aux and Rx Bldg Non-Ess Headers.

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 10 of 20 Operation

_____ 3.6 IF Train 1A is to be secured, leaving Train 1B in service as per Enclosure 4.1 (System Startup), complete the following steps:

_____ 3.6.1 Notify Radwaste of the intent to change the current KC system pump lineup.

_____ 3.6.2 IF KC Trains 1A and 1B are NOT cross-connected, ensure that any component required to support unit operation is NOT being cooled by KC Train 1A.

_____ 3.6.3 IF letdown is in service per OP/1/A/6200/001 (Chemical and Volume Control System), perform the following: (R.M.)

_____ 3.6.3.1 Verify the Cation Bed Demineralizer is NOT in service per OP/1/A/6200/001 (Chemical and Volume Control System).

_____ 3.6.3.2 Record position of 1NV-153A (Letdn Hx Otlt 3-Way Vlv).

Recorded valve position _______________

_____ 3.6.3.3 IF letdown flow is through the demineralizers, notify Primary Chemistry that the demineralizers will be bypassed while shifting KC Trains.

Person notified ____________________________

_____ 3.6.3.4 IF letdown flow is through the demineralizers, notify Radiation Protection that the demineralizers will be bypassed while shifting KC Trains.

Person notified ____________________________

_____ 3.6.3.5 Place 1NV-153A (Letdn Hx Otlt 3-Way Vlv) in the "VCT" position.

3.6.4 Adjust the following flow controllers on 1MC11 to zero gpm flow:

_____

• 1KC-149 (KF Hx 1A Cool Wtr Otlt)

_____

• 1KC-156 (KF Hx 1B Cool Wtr Otlt) 3.6.5 Stop all KC Train 1A pumps:

_____ * "KC PUMP A1"

_____ * "KC PUMP A2"

_______ 3.6.6 Place "KC HX 1A OTLT MODE" in "MINIFLOW".

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 11 of 20 Operation 3.6.7 Perform the following for the KF cooling loops that are in service:

_____ 3.6.7.1 IF 1A KF Cooling Loop is in service, adjust 1KC-149 (KF Hx 1A Cool Wtr Otlt) flow controller on 1MC11 to 3000 gpm or as necessary to maintain Spent Fuel Pool temperature < 125F.

_____ 3.6.7.2 IF 1B KF Cooling Loop is in service, adjust 1KC-156 (KF Hx 1B Cool Wtr Otlt) flow controller on 1MC11 to 3000 gpm or as necessary to maintain Spent Fuel Pool temperature < 125F.

_____ _____ 3.6.8 IF AT ANY TIME KC Train 1B flow approaches 5700 gpm while performing the next step, ensure 1KC-C40B (Train B Miniflow Isol) is closed.

NOTE: One pump running is preferred as long as flow is < 5700 gpm.

_____ 3.6.9 IF KC flow requirements are < 5700 gpm AND both KC Train 1B pumps are running, stop either KC Train 1B pump:

_____ * "KC PUMP B1" OR

_____ * "KC PUMP B2" NOTE: At this point, KC Train 1B is in service as per Enclosure 4.1 (System Startup).

_____ 3.6.10 IF RN flow has been established through components other than the Unit 2 KC Hx's for RN miniflow, secure unneeded flow paths.

_____ 3.6.11 IF letdown is in service per OP/1/A/6200/001 (Chemical and Volume Control System), WHEN KC flow and temperature have stabilized, perform the following: (R.M.)

_____ 3.6.11.1 IF 1NV-153A (Letdn Hx Otlt 3-Way Vlv) position was recorded as "DEMIN" in Step 3.6.3.2 AND no other reason exists for it to remain in the "VCT" position, return it to "AUTO" as follows:

_____ A. Place 1NV-153A in the "DEMIN" position. (R.M.)

B. Verify 1NV-153A returns to "AUTO".

_____ 3.6.11.2 IF letdown flow is through the demineralizers, notify Primary Chemistry that the demineralizers have been restored to service.

Person notified ____________________________

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 12 of 20 Operation

_____ 3.6.11.3 IF letdown flow is through the demineralizers, notify Radiation Protection that the demineralizers have been restored to service.

Person notified ____________________________

_____ 3.7 IF placing KC Train 1B in parallel operation with KC Train 1A with the trains cross-connected, complete the following steps:

NOTE: RN System minimum flow protection is normally established using an idle KC train.

3.7.1 Complete the following steps to ensure the RN System has miniflow protection:

_____ 3.7.1.1 IF a Unit 2 KC Hx discharge valve is in the "MINIFLOW" position, perform the following:

A. Ensure the associated inlet valve is open:

_____ _____

• 2RN-287A (KC Hx 2A Inlet Isol)

_____ _____

• 2RN-347B (KC Hx 2B Inlet Isol)

_____ B. Ensure a complete RN flow path exists from the RN Pumps through the applicable Hx to the discharge.

_____ 3.7.1.2 IF no Unit 2 KC Hxs are available for RN miniflow, establish miniflow per OP/0/A/6400/006 C (Nuclear Service Water System) as necessary to maintain RN flow 8600 gpm per operating RN Pump.

_____ _____ 3.7.2 Ensure 1RN-347B (KC Hx 1B Inlet Isol) is open.

_______ 3.7.3 Ensure "KC HX 1B OTLT MODE" is in "KC TEMP".

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 13 of 20 Operation

_______ 3.7.4 IF letdown is in service per OP/1/A/6200/001 (Chemical and Volume Control System) perform the following: (R.M.)

_____ 3.7.4.1 Verify the Cation Bed Demineralizer is NOT in service per OP/1/A/6200/001 (Chemical and Volume Control System).

_____ 3.7.4.2 Record position of 1NV-153A (Letdn Hx Otlt 3-Way Vlv).

Recorded valve position________________

_____ 3.7.4.3 IF letdown flow is through the demineralizers, notify Primary Chemistry that the demineralizers will be bypassed while shifting KC Pumps.

Person notified ____________________________

_____ 3.7.4.4 IF letdown flow is through the demineralizers, notify Radiation Protection that the demineralizers will be bypassed while shifting KC Pumps.

Person notified ____________________________

_____ 3.7.4.5 Place 1NV-153A (Letdn Hx Otlt 3-Way Vlv) in the "VCT" position.

CAUTION: 5700 gpm discharge header flow per operating KC Pump shall NOT be exceeded.

3.7.5 Start either KC Train 1B pump:

_____ * "KC PUMP B1" OR

_____ * "KC PUMP B2"

_____ 3.7.6 IF KC flow requirement in the Train 1B header is > 5700 gpm, perform the following:

_____ _____ 3.7.6.1 Ensure 1KC-C40B (Train B Miniflow Isol) is closed.

3.7.6.2 Start the remaining KC Train 1B pump:

_____ * "KC PUMP B1" OR

_____ * "KC PUMP B2"

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 14 of 20 Operation NOTE: One pump running is preferred as long as flow is < 5700 gpm.

CAUTION:

• The time two KC pumps in a train are operating with header flow less than 5700 gpm shall be minimized.

• Operating two KC pumps in a train with header flow less than 4850 gpm has the potential for a "strong pump" versus "weak pump" interaction, which can impact minimum flow capacity.

_____ 3.7.7 IF KC flow requirement in the Train 1B header is < 5700 gpm AND it is desired to place the second Train 1B pump in service, perform the following:

3.7.7.1 Start the remaining KC Train 1B pump:

_____ * "KC PUMP B1" OR

_____ * "KC PUMP B2"

_____ 3.7.7.2 Ensure minimum flow requirements are met.

_____ 3.7.8 IF letdown is in service per OP/1/A/6200/001 (Chemical and Volume Control System), WHEN KC flow and temperature have stabilized perform the following: (R.M.)

_____ 3.7.8.1 IF 1NV-153A (Letdn Hx Otlt 3-Way Vlv) position was recorded as "DEMIN" in Step 3.7.4.2 AND no other reason exists for it to remain in the "VCT" position, return it to "AUTO" as follows:

_____ A. Place 1NV-153A in the "DEMIN" position. (R.M.)

B. Verify 1NV-153A returns to "AUTO".

_____ 3.7.8.2 IF letdown flow is through the demineralizers, notify Primary Chemistry that the demineralizers have been restored to service.

Person notified ____________________________

_____ 3.7.8.3 IF letdown flow is through the demineralizers, notify Radiation Protection that the demineralizers have been restored to service.

Person notified ___________________________

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 15 of 20 Operation NOTE: At this point, KC Train 1A and 1B are in parallel service.

_____ 3.7.9 IF RN miniflow was established per Step 3.7.1.2, WHEN no longer needed, secure unneeded flow paths.

_____ 3.7.10 IF Train 1B is to be secured, leaving Train 1A in service as per Enclosure 4.1 (System Startup), go to Step 3.9.

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 16 of 20 Operation

_____ 3.8 IF placing KC Train 1B in parallel operation with KC Train 1A with the trains NOT cross-connected, complete the following steps:

NOTE: RN System minimum flow protection is normally established using an idle KC train.

3.8.1 Complete the following steps to ensure the RN System has miniflow protection:

_____ 3.8.1.1 IF a Unit 2 KC Hx discharge valve is in the "MINIFLOW" position, perform the following:

A. Ensure the associated inlet valve is open:

_____ _____

• 2RN-287A (KC Hx 2A Inlet Isol)

_____ _____

• 2RN-347B (KC Hx 2B Inlet Isol)

_____ B. Ensure a complete RN flow path exists from the RN Pumps through the applicable Hx to the discharge.

_____ 3.8.1.2 IF no Unit 2 KC Hxs are available for RN miniflow, establish miniflow per OP/0/A/6400/006 C (Nuclear Service Water System) as necessary to maintain RN flow 8600 gpm per operating RN Pump.

_____ _____ 3.8.2 Ensure 1RN-347B (KC Hx 1B Inlet Isol) is open.

_______ 3.8.3 Ensure "KC HX 1B OTLT MODE" is in "KC TEMP".

_____ _____ 3.8.4 Ensure 1KC-81B (KC To ND Hx 1B Sup Isol) is closed.

CAUTION: 5700 gpm discharge header flow per operating KC Pump shall NOT be exceeded.

3.8.5 Start either KC Train 1B pump:

_____ * "KC PUMP B1" OR

_____ * "KC PUMP B2"

_____ _____ 3.8.6 Ensure 1KC-C40B (Train B Miniflow Isol) opens

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 17 of 20 Operation

_____ 3.8.7 IF KC flow requirement in the Train 1B header is > 5700 gpm, perform the following:

_____ _____ 3.8.7.1 Ensure 1KC-C40B (Train B Miniflow Isol) is closed.

_____ 3.8.7.2 IF Train 1B header flow is > 5700 gpm, start the remaining KC Train 1B pump:

_____ * "KC PUMP B1" OR

_____ * "KC PUMP B2" NOTE: One pump running is preferred as long as flow is < 5700 gpm.

CAUTION:

• The time two KC pumps in a train are operating with header flow less than 5700 gpm shall be minimized.

• Operating two KC pumps in a train with header flow less than 4850 gpm has the potential for a "strong pump" versus "weak pump" interaction, which can impact minimum flow capacity.

_____ 3.8.8 IF KC flow requirement in the Train 1B header is < 5700 gpm AND it is desired to place the second Train 1B Pump in service, perform the following:

3.8.8.1 Start the remaining KC Train 1B pump:

_____ * "KC PUMP B1" OR

_____ * "KC PUMP B2"

_____ 3.8.8.2 Ensure minimum flow requirements are met.

_____ 3.8.9 IF RN miniflow was established per Step 3.8.1.2, WHEN no longer needed, secure unneeded flow paths.

NOTE: At this point, KC Train 1A and 1B are in parallel service with KC Train 1B isolated from the Aux and Rx Bldg Non-Ess Headers.

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 18 of 20 Operation

_____ 3.9 IF Train 1B is to be secured, leaving Train 1A in service as per Enclosure 4.1 (System Startup), complete the following steps.

_____ 3.9.1 Notify Radwaste of the intent to change the current KC system pump lineup.

_____ 3.9.2 IF KC Trains 1A and 1B are NOT cross-connected, ensure that any component required to support unit operation is NOT being cooled by KC Train 1B.

_______ 3.9.3 IF letdown is in service per OP/1/A/6200/001 (Chemical and Volume Control System) perform the following: (R.M.)

_____ 3.9.3.1 Verify the Cation Bed Demineralizer is NOT in service per OP/1/A/6200/001 (Chemical and Volume Control System).

_____ 3.9.3.2 Record position of 1NV-153A (Letdn Hx Otlt 3-Way Vlv).

Recorded valve position________________

_____ 3.9.3.3 IF letdown flow is through the demineralizers, notify Primary Chemistry that the demineralizers will be bypassed while shifting KC Pumps.

Person notified ____________________________

_____ 3.9.3.4 IF letdown flow is through the demineralizers, notify Radiation Protection that the demineralizers will be bypassed while shifting KC Pumps.

Person notified ____________________________

_____ 3.9.3.5 Place 1NV-153A (Letdn Hx Otlt 3-Way Vlv) in the "VCT" position.

3.9.4 Adjust the following flow controllers on 1MC11 to zero gpm flow:

_____

• 1KC-149 (KF Hx 1A Cool Wtr Otlt)

_____

• 1KC-156 (KF Hx 1B Cool Wtr Otlt) 3.9.5 Stop all KC Train 1B pumps:

_____ * "KC PUMP B1"

_____ * "KC PUMP B2"

_______ 3.9.6 Place "KC HX 1B OTLT MODE" in "MINIFLOW".

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 19 of 20 Operation 3.9.7 Perform the following for the KF cooling loops that are in service:

_____ 3.9.7.1 IF 1A KF Cooling Loop is in service, adjust 1KC-149 (KF Hx 1A Cool Wtr Otlt) flow controller on 1MC11 to 3000 gpm or as necessary to maintain Spent Fuel Pool temperature < 125F.

_____ 3.9.7.2 IF 1B KF Cooling Loop is in service, adjust 1KC-156 (KF Hx 1B Cool Wtr Otlt) flow controller on 1MC11 to 3000 gpm or as necessary to maintain Spent Fuel Pool temperature < 125F.

_____ _____ 3.9.8 IF KC Train 1A flow approaches 5700 gpm while performing the next step, ensure 1KC-C37A (Train A Miniflow Isol) is closed.

NOTE: One pump running is preferred as long as flow is < 5700 gpm.

_____ 3.9.9 IF KC flow requirements are < 5700 gpm AND both KC Train 1A pumps are running, stop either KC Train 1A pump:

_____ * "KC PUMP A1" OR

_____ * "KC PUMP A2" NOTE: At this point, KC Train 1A is in service as per Enclosure 4.1 (System Startup).

_____ 3.9.10 IF RN flow has been established through components other than the Unit 2 KC Hx's for RN miniflow, secure unneeded flow paths.

Enclosure 4.4 OP/1/A/6400/005 Operation Of Additional KC Pumps/Parallel Page 20 of 20 Operation

_____ 3.9.11 IF letdown is in service per OP/1/A/6200/001 (Chemical and Volume Control System), WHEN KC flow and temperature have stabilized perform the following: (R.M.)

_____ 3.9.11.1 IF 1NV-153A (Letdn Hx Otlt 3-Way Vlv) position was recorded as "DEMIN" in Step 3.9.3.2 AND no other reason exists for it to remain in the "VCT" position, return it to "AUTO" as follows:

_____ A. Place 1NV-153A in the "DEMIN" position. (R.M.)

B. Verify 1NV-153A returns to "AUTO".

_____ 3.9.11.2 IF letdown flow is through the demineralizers, notify Primary Chemistry that the demineralizers have been restored to service.

Person notified ____________________________

_____ 3.9.11.3 IF letdown flow is through the demineralizers, notify Radiation Protection that the demineralizers have been restored to service.

Person notified ___________________________

3.10 File this enclosure in the designated storage cabinet.

Catawba Nuclear Station JPM I 2021 NRC Exam JPM I PAGE 1 OF 9

Catawba Nuclear Station JPM I 2021 NRC Exam EVALUATION SHEET Task: Local ESPS Alignment to 1ETA through 1ATC Alternate Path: No Facility JPM #: NEW Safety Function: 6

Title:

Loss of Offsite and Onsite Power (Station Blackout)

K/A EPE 055 EA2.03 Ability to determine or interpret the following as they apply to a Station Blackout: Actions necessary to restore power.

Rating(s): 3.9 / 4.7 CFR: 43.5 / 45.13 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant X Perform X Simulate

References:

EP/2/A/5000/ECA-0.0 (Loss of All AC Power) Encl. 52 (Local ESPS Alignment to 2ETB through 2ATD)

Task Standard: Both ESPS D/Gs started with ESPS Switchgear supply breaker to Unit 1 and Unit 2 6.9Kv switchgear and 2TD-12 closed.

Validation Time: 10 minutes Time Critical: Yes No X

===============================================================

Applicant: Time Start: ___________

NAME______________________ Docket #_____________ Time Finish: ___________

Performance Time ______

Performance Rating:

SAT ____ UNSAT ____

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 9

Catawba Nuclear Station JPM I 2021 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 2 is in Mode 3 following a Loss of All AC power

• EP/2/A/5000/ECA-0.0 has been entered

• Neither of the Emergency D/Gs could be started

• Management has determined that power will be restored to 2ETB from ESPS through 2ATD INITIATING CUES:

• ECA-0.0 Enclosure 52 (Local ESPS Alignment to 2ETB through 2ATD) has been entered and Steps 1 & 2 are complete. The Control Room Supervisor has instructed you to perform ECA-0.0 Enclosure 52 beginning at step 3.

Examiner Note: Provide applicant with a copy of EP/2/A/5000/ECA-0.0, Enclosure 52.

PAGE 3 OF 9

Catawba Nuclear Station JPM I 2021 NRC Exam START TIME _________

STEP/STANDARD SAT/UNSAT STEP 1: 3. Perform the following on 0ELCP0091 (ESPS Diesel Generator Emergency Control Panel):

a. Ensure the following breakers - OPEN:

• ESPS SWGR SUPPLY BKR TO U1 & U2 6.9 KV SWGR

• 1TA-13 SWGR INCOMING FDR FROM ESPS SWGR

• 1TB-2 SWGR INCOMING FDR FROM ESPS SWGR

• 2TC-13 SWGR INCOMING FDR FROM ESPS SWGR

• 2TD-12 SWGR INCOMING FDR FROM ESPS ___ SAT SWGR

___ UNSAT Examiner Cue: As applicant describes verifying breaker status for ESPS SWGR SUPPLY BKR and 2TD-12, green light is lit. For 1TA-13, 1TB-2, and 2TC-13, Breaker green flag is shown.

STANDARD:

Applicant verifies the green OPEN lights lit and red CLOSE lights dark or breaker green flag showing for the listed breakers.

COMMENTS:

PAGE 4 0F 9

Catawba Nuclear Station JPM I 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2: 3.b Verify the following lights - LIT:

• D/G #1 READY TO START

• D/G #2 READY TO START Examiner Cue: As applicant describes verifying the lights lit, Light is lit. ___ SAT STANDARD: ___UNSAT Applicant verifies both D/G ready to start lights lit.

COMMENTS:

STEP 3: 3.c Start ESPS DGs by depressing the following pushbuttons:

CRITICAL STEP

• D/G #1 START pushbutton

• D/G #2 START pushbutton Examiner Cue: As applicant describes depressing the D/G start pushbuttons, Button has been depressed and D/G red running lights lit.

STANDARD:

Applicant describes depressing the D/G start pushbuttons. ___ SAT Examiner Note: This step is critical to allow power restoration to ___ UNSAT 2ETB from ESPS.

COMMENTS:

NOTE

• Up to two minutes may elapse from pressing the START pushbuttons to READY TO LOAD indicating lights illuminate.

• While TROUBLE light may momentarily illuminate during start up.

PAGE 5 0F 9

Catawba Nuclear Station JPM I 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: 3.d Verify the following lights:

• D/G # 1 RUNNING red light - LIT

• D/G # 2 RUNNING red light - LIT

• ESPS GENERATOR #1 OUTPUT BREAKER red light - LIT

• ESPS GENERATOR #2 OUTPUT BREAKER red light - LIT

• D/G #1 READY TO LOAD amber light - LIT

• D/G #2 READY TO LOAD amber light - LIT ___ SAT Examiner Cue: As applicant describes verifying each light, Light is ___ UNSAT LIT.

STANDARD:

Applicant describes verifying the listed lights lit.

COMMENTS:

PAGE 6 0F 9

Catawba Nuclear Station JPM I 2021 NRC Exam STEP 5: 4. Contact Control Room for the following:

a. Verify the following switches in OFF

• HTWL PUMP 2C

• CM BSTR PUMP 2C.

b. Verify 2ETB load shed - COMPLETE.

c. Verify 2ETB aligned to ATD.

Examiner Cue: Once applicant contacts the control room, 2C hotwell

___ SAT and condensate booster pump switches are in the OFF position, 2ETB load shed is complete, and

___ UNSAT 2ETB is aligned to ATD.

STANDARD:

Applicant contacts the control room for the required information.

COMMENTS:

STEP 6: 5. CLOSE ESPS SWGR SUPPLY BKR to U1 & U2 6.9 KV SWGR. CRITICAL STEP Examiner Cue: As applicant describes rotating pistol grip for the listed breaker to the CLOSE position, Pistol grip rotated clockwise to the CLOSE position and red light is lit and green light is dark.

STANDARD:

Applicant describes rotating the pistol grip for breaker clockwise to the CLOSE position. ___ SAT Examiner Note: This step is critical to allow power restoration to ___ UNSAT 2ETB from ESPS.

COMMENTS:

PAGE 7 0F 9

Catawba Nuclear Station JPM I 2021 NRC Exam STEP 7: 6. CLOSE 2TD-12 SWGR INCOMING FDR FROM ESPS SWGR. CRITICAL STEP Examiner Cue: As applicant describes rotating pistol grip for the listed breaker, Pistol grip rotated clockwise to the CLOSE position and red light is lit and green light is dark.

STANDARD:

Applicant describes rotating the pistol grip for breaker clockwise to the CLOSE position. ___ SAT Examiner Note: This step is critical to allow power restoration to ___ UNSAT 2ETB from ESPS.

COMMENTS:

STEP 8: 7. WHEN 2ATD aligned to 2ETB, THEN notify Control Room to close 4KV XFMR 2ATD FDR on 1MC-11.

Examiner Cue: As applicant describes contacting the control room, 4KV XFMR 2ATD FDR has been closed. Another operator will continue with the procedure. This JPM is complete.

___ SAT STANDARD:

___ UNSAT Applicant describes contacting the control room to close the appropriate breaker.

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:

• Unit 2 is in Mode 3 following a Loss of All AC power

• EP/2/A/5000/ECA-0.0 has been entered

• Neither of the Emergency D/Gs could be started

• Management has determined that power will be restored to 2ETB from ESPS through 2ATD INITIATING CUES:

• ECA-0.0 Enclosure 52 (Local ESPS Alignment to 2ETB through 2ATD) has been entered and Steps 1 & 2 are complete. The Control Room Supervisor has instructed you to perform ECA-0.0 Enclosure 52 beginning at step 3.

CNS LOSS OF ALL AC POWER PAGE NO.

EP/2/A/5000/ECA-0.0 263 of 316 Enclosure 52 - Page 1 of 17 Revision 59 Local ESPS Alignment to 2ETB through 2ATD ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE Steps 1 and 2 can be performed in any order or concurrently.

1. Ensure 2GTB (Incoming Feeder From Xfmr 2ATD) (TB-568, 2F-17) - OPEN.

2. Align 2TD as follows:

NOTE Steps 2.a through 2.e may be performed in any order or concurrently.

a. Verify the following 2TD lockout relays a. Perform the following:

reset:

1) Notify Control Room Supervisor.

86T/2TD (2TD-04 cubicle) 86BNA/2TD05 (2TD-05 cubicle)

NOTE It is acceptable to continue 86NA1/2TD05 (2TD-05 cubicle) in this enclosure if discrepancies are expected 86BS/2TD07 (2TD-07 cubicle) to be resolved.

86S/2TD07 (2TD-07 cubicle) 2) Do not continue attempts to energize 2TD until all lockouts 86BNB/2TD09 (2TD-09 cubicle) evaluated and cleared.

86NB1/2TD09 (2TD-09 cubicle) 86NA2/2SCPD (2SCPD panel) 86NB2/2SCPD (2SCPD panel).

CNS LOSS OF ALL AC POWER PAGE NO.

EP/2/A/5000/ECA-0.0 264 of 316 Enclosure 52 - Page 2 of 17 Revision 59 Local ESPS Alignment to 2ETB through 2ATD ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2. (Continued)

b. Verify the following breakers - b. Rack out affected breaker(s) as RACKED OUT: follows:

2TD-05 (Normal B Incoming Feeder 1) Open sliding door in compartment From XFMR 2T1B) door.

2TD-09 (Normal A Incoming Feeder 2) Verify breaker "OPEN" per From Xfmr 2T1A) mechanical "OPEN-CLOSE" flag.

2TD-10 (2D RC Pump Motor). 3) Engage racking tool.

4) Push racking unlocking lever left and rotate racking crank counterclockwise 1/4 turn.

5) Release racking unlocking lever.

6) Continue cranking counterclockwise until unlocking lever snaps back and racking mechanism automatically stops in "TEST".

7) Push racking unlocking lever to left and rotate racking crank counterclockwise 1/4 turn.

8) Release racking unlocking lever.

9) Continue cranking counterclockwise until unlocking lever snaps back and racking mechanism automatically stops in "DISCONNECT".

10) Remove racking tool.

11) Close sliding door in compartment door.

CNS LOSS OF ALL AC POWER PAGE NO.

EP/2/A/5000/ECA-0.0 265 of 316 Enclosure 52 - Page 3 of 17 Revision 59 Local ESPS Alignment to 2ETB through 2ATD ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2. (Continued)

c. Verify 2TD-04 (6900/4160 VAC XFMR c. Rack in breaker as follows:

2ATD) - RACKED IN.

1) Verify breaker "OPEN" per mechanical "OPEN-CLOSE" flag.

2) Ensure closing springs toggle switch in "ON" position.

3) Verify breaker in "DISCONNECT".

4) Ensure compartment doors closed.

5) Open sliding door in compartment door.

6) Engage racking tool.

7) Push racking unlocking lever to left and rotate racking crank clockwise 1/4 turn.

8) Release racking unlocking lever.

9) Continue cranking clockwise until unlocking lever snaps back and racking mechanism automatically stops in "TEST".

10) Push rotating unlocking lever to left and rotate racking crank clockwise 1/4 turn.

11) Release racking unlocking lever.

12) Continue cranking clockwise until unlocking lever snaps back and racking mechanism automatically stops in "CONNECT".

13) Remove racking tool.

14) Close sliding door in compartment door.

CNS LOSS OF ALL AC POWER PAGE NO.

EP/2/A/5000/ECA-0.0 266 of 316 Enclosure 52 - Page 4 of 17 Revision 59 Local ESPS Alignment to 2ETB through 2ATD ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2. (Continued)

CAUTION The 6.9 KV bus must be de-energized while racking the breaker from "TEST" to "CONNECT".

d. Verify 2TD-12 (2TD SWGR d. Rack in 2TD-12 (2TD SWGR INCOMING FDR FROM ESPS INCOMING FDR FROM ESPS SWGR) - RACKED IN. SWGR) as follows:

1) Open sliding door in compartment door.

2) Verify breaker "OPEN" per mechanical "OPEN-CLOSE" flag.

3) Verify breaker in "DISCONNECT".

4) Engage racking tool.

5) Push racking unlocking lever to left and rotate racking crank clockwise 1/4 turn.

6) Release racking unlocking lever.

7) Continue cranking clockwise until unlocking lever snaps back and racking mechanism automatically stops in "TEST".

8) Push rotating unlocking lever to left and rotate racking crank clockwise 1/4 turn.

9) Release racking unlocking lever.

10) Continue cranking clockwise until unlocking lever snaps back and racking mechanism automatically stops in "CONNECT".

11) Remove racking tool.

(RNO continued on next page)

CNS LOSS OF ALL AC POWER PAGE NO.

EP/2/A/5000/ECA-0.0 267 of 316 Enclosure 52 - Page 5 of 17 Revision 59 Local ESPS Alignment to 2ETB through 2ATD ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2. (Continued)

12) Close sliding door in compartment door.

NOTE If the "7 KV BUS 2TD MODE SEL" switch is in "AUTO", the breaker will auto close when taken to "CONNECT".

e. Verify 2TD-07 (7KV Bus 2TD Tie Bkr) e. Perform the following:

- RACKED IN.

1) Rack in 2TD-07 (7KV Bus 2TD Tie Bkr) as follows:

a) Verify breaker "OPEN" per mechanical "OPEN-CLOSE" flag.

b) Ensure power control toggle switch in "ON" position.

c) Verify breaker in "DISCONNECT".

d) Ensure compartment doors closed.

e) Open sliding door in compartment door.

f) Engage racking tool.

g) Push racking unlocking lever to left and rotate racking crank clockwise 1/4 turn.

h) Release racking unlocking lever.

(RNO continued on next page)

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2. (Continued) i) Continue cranking clockwise until unlocking lever snaps back and racking mechanism automatically stops in "TEST".

j) Push rotating unlocking lever to left and rotate racking crank clockwise 1/4 turn.

k) Release racking unlocking lever.

l) Continue cranking clockwise until unlocking lever snaps back and racking mechanism automatically stops in "CONNECT".

m) Remove racking tool.

n) Close sliding door in compartment door.

2) Notify Control Room to place "7 KV BUS 2TD MODE SEL" switch in "AUTO" to close 2TD-07.

3) IF 2TD-07 cannot be closed in Control Room, THEN perform the following:

a) Obtain breaker manual pull cord from break glass station located near breaker racking tool storage location.

b) Attach pull cord to "CLOSE" lever at bottom of breaker.

c) Do not stand in front of breaker cubicle.

d) Pull cord to close breaker.

e) Notify Control Room of status of 2TD-07.

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2. (Continued)

f. Ensure the following breakers -

OPEN:

2TD-03 (6900 VAC Switchgear RCP2D Feeder) 2TD-04 (6900/4160 VAC XFMR 2ATD) 2TD-06 (6900/600 VAC Xfrmr 2TXD) 2TD-08 (2C2 Heater Drain Tank Pump Motor) 2TD-11 (2C Condensate Booster Pump Motor) 2TD-13 (2C Hotwell Pump Motor) 2TD-12 (2TD SWGR Incoming FDR From ESPS SWGR) 2TD-14 (6900/600 VAC Xfrmr 2STXD) 2TD-15 (6900/600 VAC Xfmr 2TXF).

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3. Perform the following on 0ELCP0091 (ESPS Diesel Generator Emergency Control Panel) (SERV-594, U-31):

a. Ensure the following breakers -

OPEN:

"ESPS SWGR SUPPLY BKR TO U1 & U2 6.9 KV SWGR" "1TA-13 SWGR INCOMING FDR FROM ESPS SWGR" "1TB-2 SWGR INCOMING FDR FROM ESPS SWGR" "2TC-13 SWGR INCOMING FDR FROM ESPS SWGR" "2TD-12 SWGR INCOMING FDR FROM ESPS SWGR".

NOTE ESPS cannot be started from the ESPS Diesel Generator Emergency Control Panel if the ESPS Mode select switch is in the test position.

b. Verify the following white lights - LIT: b. Perform the following:

"DG #1 READY TO START" 1) Ensure 0EQSCA3003CSMODE (ESPS SWGR MODE SELECT "DG #2 READY TO START". SWITCH) on 0EQSCA3003 (ESPS SWGR CONTROL PANEL) set to "EMERGENCY" mode (YRD/E-594, 44-X, 56-Y, Bldg 77163).

2) IF DG start lights NOT lit, THEN notify Control Room.

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3. (Continued)

c. Start ESPS DGs by depressing the following pushbuttons:

"DG #1 START" pushbutton "DG #2 START" pushbutton.

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3. (Continued)

NOTE Up to two minutes may elapse from pressing the "START" pushbuttons to "READY TO LOAD" indicating lights illuminate.

White "TROUBLE" light may momentarily illuminate during start up.

d. Verify the following lights: d. Perform the following:

"D/G # 1 RUNNING" red light - LIT 1) IF both "DG #1 READY TO LOAD" and "DG #2 READY TO LOAD" "D/G # 2 RUNNING" red light - LIT lights dark, THEN perform the following:

"ESPS GENERATOR #1 OUTPUT BREAKER" red light - LIT a) Notify Control Room Supervisor that 2ETB cannot "ESPS GENERATOR #2 OUTPUT be energized by ESPS.

BREAKER" red light - LIT b) GO TO Step 13 to secure "DG #1 READY TO LOAD" amber ESPS.

light - LIT

2) IF either "DG #1 READY TO "DG #2 READY TO LOAD" amber LOAD" OR "DG #2 READY TO light - LIT. LOAD" lights lit, THEN perform the following:

a) Notify Control Room Supervisor to REFER TO Enclosure 55 (ESPS Operation With One D/G) to evaluate if 2ETB should be energized with one ESPS D/G.

(RNO continued on next page)

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3. (Continued) b) Perform one of the following based on Control Room Supervisor evaluation:

IF Control Room Supervisor determines ESPS should be used with one D/G, THEN GO TO Step 4.

OR IF Control Room Supervisor determines ESPS should NOT be used, THEN GO TO Step 13 to secure ESPS.

4. Contact Control Room for the following:

a. Verify the following switches in "OFF":

"HTWL PUMP 2C" "CM BSTR PUMP 2C".

b. Verify 2ETB load shed - COMPLETE.

c. Verify 2ETB aligned to 2ATD.

5. CLOSE "ESPS SWGR SUPPLY BKR to U1 & U2 6.9 KV SWGR".

6. CLOSE "2TD-12 SWGR INCOMING FDR FROM ESPS SWGR".

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7. WHEN 2ATD aligned to 2ETB, THEN IF "4KV XFMR 2ATD FDR" cannot be notify Control Room to close "4KV closed in Control Room, THEN CLOSE XFMR 2ATD FDR" on 2MC-11. 2TD-04 (6900/4160 VAC XFMR 2ATD) as follows:

a. Obtain breaker manual pull cord from break glass station located near breaker racking tool storage location.

b. Attach pull cord to "CLOSE" lever at bottom of breaker.

c. Do not stand in front of breaker cubicle.

d. Pull cord to close breaker.

e. Notify Control Room of status of 2TD-04.

8. IF notified by Control Room to close 2ETB-03 (Normal Incoming Feeder From Xfmr 2ATD), THEN perform the following:

a. Obtain breaker manual pull cord from break glass station located near breaker racking tool storage location.

b. Attach pull cord to "CLOSE" lever at bottom of breaker.

c. Do not stand in front of breaker cubicle.

d. Pull cord to close breaker.

e. Notify Control Room of status of 2ETB-03.

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9. WHEN notified by Control Room, THEN CLOSE the following load center normal incoming breakers from 2ETB:

2ELXB-4B (Normal Incoming Breaker Fed From Xfmr 2ETXB) (AB-560, AA-67, Rm 362) 2ELXD-4B (Normal Incoming Breaker Fed from Xfmr 2ETXD) (AB-560, AA-68, Rm 362).

10. WHEN time allows, THEN tag the following breakers:

2TD-05 (Normal B Incoming Feeder From XFMR 2T1B) 2TD-09 (Normal A Incoming Feeder From Xfmr 2T1A) 2TD-10 (2D RC Pump Motor).

11. Notify Control Room personnel of status.

12. Exit this enclosure.

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13. Secure ESPS as follows:

a. Perform the following on 0ELCP0091 (ESPS Diesel Generator Emergency Control Panel) (SERV-594, U-31):

NOTE The stop button must be depressed even if ESPS D/G is off to remove the run permissive.

D/G engine goes into a cool down cycle for approximately five minutes after stop buttons are depressed. The D/G ready to load light will go dark immediately, but the running light will remain lit for 5 minutes.

1) Stop ESPS D/Gs by depressing the following pushbuttons:

"DG #1 STOP" pushbutton "DG #2 STOP" pushbutton.

2) Ensure "ESPS SWGR SUPPLY BKR to U1 & U2 6.9 KV SWGR" -

OPEN.

3) Ensure "2TD-12 SWGR INCOMING FDR FROM ESPS SWGR" - OPEN.

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13. (Continued)

CAUTION The 6.9 KV bus must be de-energized while racking the breaker from "CONNECT" to "TEST".

b. Rack out 2TD-12 (2TD SWGR Incoming Fdr From ESPS SWGR) as follows:

1) Open sliding door in compartment door.

2) Verify breaker "OPEN" per mechanical "OPEN-CLOSE" flag.

3) Engage racking tool.

4) Push racking unlocking lever to left and rotate racking crank counterclockwise 1/4 turn.

5) Release racking unlocking lever.

6) Continue cranking counterclockwise until unlocking lever snaps back and racking mechanism automatically stops in "TEST".

7) Push racking unlocking lever to left and rotate racking crank counterclockwise 1/4 turn.

8) Release racking unlocking lever.

9) Continue cranking counterclockwise until unlocking lever snaps back and racking mechanism automatically stops in "DISCONNECT".

10) Remove racking tool.

11) Close sliding door in compartment door.

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13. (Continued)

c. Rack in the following breakers per Step 13.d:

1) 2TD-05 (Normal B Incoming Feeder From XFMR 2T1B)

2) 2TD-09 (Normal A Incoming Feeder From Xfmr 2T1A)

3) 2TD-10 (2D RC Pump Motor).

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13. (Continued)

d. Rack in each breaker as follows:

1) Verify breaker "OPEN" per mechanical "OPEN-CLOSE" flag.

2) Ensure closing springs toggle switch in "ON" position.

3) Verify breaker in "DISCONNECT".

4) Ensure compartment doors closed.

5) Open sliding door in compartment door.

6) Engage racking tool.

7) Push racking unlocking lever to left and rotate racking crank clockwise 1/4 turn.

8) Release racking unlocking lever.

9) Continue cranking clockwise until unlocking lever snaps back and racking mechanism automatically stops in "TEST".

10) Push rotating unlocking lever to left and rotate racking crank clockwise 1/4 turn.

11) Release racking unlocking lever.

12) Continue cranking clockwise until unlocking lever snaps back and racking mechanism automatically stops in "CONNECT".

13) Remove racking tool.

14) Close sliding door in compartment door.

e. Notify Control Room personnel of status.

Catawba Nuclear Station JPM J 2021 NRC Exam JPM J PAGE 1 OF 13

Catawba Nuclear Station JPM J 2021 NRC Exam EVALUATION SHEET Task: Place 1B Hydrogen Recombiner in Service Alternate Path: No Facility JPM #: VX-025 Safety Function: 5

Title:

Hydrogen Recombiner and Purge Control System K/A 028 A2.01 Malfunctions or operations on the HRPS; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: Hydrogen Recombiner power setting, determined by using plant data book Rating(s): 3.4 / 3.6 CFR: 41.5 / 43.5 / 45.3 / 45.13 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant X Perform Simulate X

References:

OP/1/A/6450/010 (Containment Hydrogen Control Systems) rev. 44, Enclosure 4.10 (Operation of the Hydrogen Recombiners Following a LOCA)

Unit 1 Revised Data Book, Figure 10 Task Standard: Hydrogen Recombiner 1B in service with Power Adjust POT set to approximately 58 KW (Acceptable Range of 57- 59 KW) per Figure 10 of the Unit 1 Revised Data Book.

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 13

Catawba Nuclear Station JPM J 2021 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 LOCA has occurred on Unit 1.

INITIATING CUES:

• The CRS instructs you to place Hydrogen Recombiner 1B in service at the required power per OP/1/A/6450/010 (Containment Hydrogen Control Systems), Enclosure 4.10 (Operation of the Hydrogen Recombiners Following a LOCA), steps 3.1 through 3.3.14.

• All initial conditions are complete.

• Containment pressure is 4.3 psig.

• Containment hydrogen concentration is 5% as indicated on 1MC-7.

• Hydrogen Recombiner 1A is tagged for maintenance.

Examiner Note: After reading cue, provide the applicant with a copy of OP/1/A/6450/010 rev. 44, Enclosure 4.10 signed off through step 2.2 and a copy of Unit 1 Revised Data Book Figure 10.

PAGE 3 OF 13

Catawba Nuclear Station JPM J 2021 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1 3.1 Ensure the H2 Skimmer Fans running per Enclosure 4.13 (Emergency Manual Operation of the H2 Skimmer Fans)

Examiner Cue: Hydrogen Skimmer Fans 1A & 1B are running per Enclosure 4.13.

___ SAT STANDARD:

___ UNSAT Applicant acknowledges cue and signs off the step.

COMMENTS:

CAUTION: Hydrogen Recombiners are NOT operated with hydrogen concentration > 6%

without TSC approval.

NOTE: 1. If desired to place both Hydrogen Recombiners in service, Steps 3.2 and 3.3 may be performed in conjunction.

2. If desired to place both Hydrogen Recombiners in service, use additional Enclosure 4.11 (Hydrogen Recombiner Heater Temperature Log).

3. Placing Hydrogen Recombiner 1A in service is preferred for ALARA consideration.

STEP 2 3.2 IF placing Hydrogen Recombiner 1A in service, perform the following at 1ELCP0139 (1A Hydrogen Recombiner Control Panel) (AB-577, DD-52, Rm 494):

STANDARD:

___ SAT Applicant determines that per the cue sheet, Hydrogen Recombiner 1A

___UNSAT is tagged out for maintenance, and that this step is N/A.

COMMENTS:

PAGE 4 0F 13

Catawba Nuclear Station JPM J 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3 3.3 IF placing Hydrogen Recombiner 1B in service, perform the following at 1ELCP0140 (1B Hydrogen Recombiner Control Panel) (AB-560, DD-52, Rm 370):

3.3.1 Ensure the POWER OUT SWITCH is in the OFF position.

STANDARD: ___ SAT Applicant locates the Power Out Switch and ensures it is in the OFF ___ UNSAT position.

Examiner Cue: The POWER OUT SWITCH is in the OFF position.

COMMENTS:

STEP 4 3.3.2 Ensure the POWER ADJUST potentiometer is set to zero (000).

STANDARD:

___ SAT Applicant verifies the POWER ADJUST potentiometer is set to 000.

___ UNSAT Examiner Cue: The POWER ADJUST pot is set to zero (000).

COMMENTS:

PAGE 5 0F 13

Catawba Nuclear Station JPM J 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5 3.3.3 IF the POWER IN AVAILABLE light is DARK, ensure 1EMXL-F07C (1B Electric Hydrogen Recombiner Power Supply Panel) (AB-560, BB-47) is in the ON position.

Examiner Cue: The POWER IN AVAILABLE light is lit.

___ SAT STANDARD:

___ UNSAT Applicant determines that with the POWER IN AVAILABLE light being lit, this step is N/A.

COMMENTS:

STEP 6 3.3.4 Place the POWER OUT SWITCH in the ON position.

CRITICAL Examiner Cue: After applicant describes placing the POWER OUT STEP SWITCH up to the ON position, The POWER OUT SWITCH is in the ON position.

STANDARD:

Applicant places the POWER OUT SWITCH up to the ON position.

Examiner Note: This step is critical to place the hydrogen recombiner ___ SAT in service.

___ UNSAT COMMENTS:

PAGE 6 0F 13

Catawba Nuclear Station JPM J 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7 3.3.5 Verify that the red indicating light is lit.

Examiner Cue: After finding the indicating light on the switch plate inform the applicant - The RED light on the switch plate is lit.

___ SAT STANDARD:

___ UNSAT Applicant finds the red indicating light on the switch plate and verifies that it is lit.

COMMENTS:

STEP 8 3.3.6 Slowly turn the POWER ADJUST potentiometer clockwise until 5 KW is indicated on the POWER OUT meter.

Examiner Cue: After explaining operation of the potentiometer in the clockwise direction, inform applicant - The POWER OUT meter rises to 5 KW. ___ SAT STANDARD:

___ UNSAT Applicant describes turning the potentiometer clockwise to increase the POWER OUTPUT meter reading to 5 KW.

COMMENTS:

PAGE 7 0F 13

Catawba Nuclear Station JPM J 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 9 3.3.7 Maintain a 5 KW output for 10 minutes.

Examiner Cue: Using time compression, 10 minutes has elapsed.

STANDARD: ___ SAT Applicant describes maintaining this power output for 10 minutes. ___ UNSAT COMMENTS:

STEP 10 3.3.8 Slowly advance the POWER ADJUST setting until an output of 10 KW is obtained on the POWER OUT meter.

Examiner Cue: After explaining the operation of the potentiometer in the clockwise direction inform applicant - The POWER OUT meter rises to 10 KW.

___ SAT STANDARD:

___ UNSAT Applicant describes turning the potentiometer clockwise to increase the POWER OUTPUT meter reading to 10 KW.

COMMENTS:

STEP 11 3.3.9 Maintain a 10 KW output for 10 minutes.

Examiner Cue: Using time compression, 10 minutes has elapsed.

STANDARD: ___ SAT Applicant describes maintaining this power output for 10 minutes. ___ UNSAT COMMENTS:

PAGE 8 0F 13

Catawba Nuclear Station JPM J 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 12 3.3.10 Advance the POWER ADJUST setting until an output of 20 KW is obtained on the POWER OUT meter.

Examiner Cue: After explaining the operation of the potentiometer in the clockwise direction inform applicant - The POWER OUT meter rises to 20 KW.

___ SAT STANDARD:

___ UNSAT Applicant describes turning the potentiometer clockwise to increase the POWER OUTPUT meter reading to 20 KW.

COMMENTS:

STEP 13 3.3.11 Maintain a 20 KW output for 5 minutes.

Examiner Cue: Using time compression, 5 minutes has elapsed.

STANDARD: ___ SAT Applicant describes maintaining this power output for 5 minutes. ___ UNSAT COMMENTS:

PAGE 9 0F 13

Catawba Nuclear Station JPM J 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 14 3.3.12 Determine Hydrogen Recombiner 1B power setting as follows: CRITICAL STEP 3.3.12.1 Determine KW value from Figure 10 of the Unit 1 Revised Data Book.

Examiner Note: The applicant will use the copy of Unit 1 Revised Data Book Figure 10 provided with the initiating cue.

STANDARD:

Applicant determines that the KW value from Figure 10 is 54 KW ___ SAT (Acceptable Range is 53 - 55 KW).

___ UNSAT Examiner Note: This step is critical in determining the proper power setting for the given containment conditions.

COMMENTS:

STEP 15 3.3.12.2 H2 concentration (1MC-7) ________ %

STANDARD:

___ SAT Applicant determines from cue sheet that hydrogen concentration is 5%.

___ UNSAT COMMENTS:

PAGE 10 0F 13

Catawba Nuclear Station JPM J 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 16 3.3.12.3 IF H2 concentration is > 3.5%, add 4 KW to calculation.

CRITICAL STANDARD: STEP Applicant determines that H2 concentration is > 3.5% and adds 4 KW to the calculation.

Examiner Note: This step is critical in determining the proper power setting for the given containment conditions. ___ SAT COMMENTS: ___ UNSAT STEP 17 3.3.12.4 Calculate KW as follows:

CRITICAL 54 + 4 = 58 KW STEP Step 3.3.12.1 Step 3.3.12.3 or N/A STANDARD:

Applicant calculates the required power setting to be 58 KW (Acceptable Range is 57 - 59 KW).

___ SAT Examiner Note: This step is critical in determining the proper power setting for the given containment conditions. ___ UNSAT COMMENTS:

PAGE 11 0F 13

Catawba Nuclear Station JPM J 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 18 3.3.13 Advance the POWER ADJUST setting until the POWER OUT meter indicates the value calculated in CRITICAL 3.3.12.4. Adjust POWER ADJUST as necessary to STEP maintain this output.

Examiner Cue: After explaining the operation of the potentiometer in the clockwise direction inform applicant - The POWER OUT meter rises to 58 KW.

STANDARD:

Applicant describes turning the potentiometer clockwise to increase the POWER OUTPUT meter reading to 58 KW (Acceptable Range is 57 - ___ SAT 59 KW).

___ UNSAT Examiner Note: This step is critical to set the necessary power output setting for the given containment conditions.

COMMENTS:

STEP 19 3.3.14 Notify the NCO that Hydrogen Recombiner 1B is now in service.

Person notified _______________________

STANDARD:

___ SAT Applicant calls the control room and notifies them that 1B Hydrogen Recombiner is in service.

___ UNSAT Examiner Cue: Unit 1 Control Room, this is Greg. Repeat any additional information given.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 12 0F 13

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

May 2015 NRC Initial License Exam JPM I INITIAL CONDITIONS:

• A LOCA has occurred on Unit 1.

INITIATING CUES:

• The CRS instructs you to place Hydrogen Recombiner 1B in service at the required power per OP/1/A/6450/010 (Containment Hydrogen Control Systems), Enclosure 4.10 (Operation of the Hydrogen Recombiners Following a LOCA), steps 3.1 through 3.3.14.

• All initial conditions are complete.

• Containment pressure is 4.3 psig.

• Containment hydrogen concentration is 5% as indicated on 1MC-7.

• Hydrogen Recombiner 1A is tagged for maintenance.

Enclosure 4.10 OP/1/A/6450/010 Operation of the Hydrogen Recombiners Page 1 of 7 Following a LOCA

1. Limits and Precautions 1.1 Hydrogen concentrations greater than 3.5% are combustible.

1.2 The maximum electric hydrogen recombiners heater temperature is 1400F.

1.3 Hydrogen Recombiners and Hydrogen Ignitors are NOT operated with hydrogen concentration 6% without TSC approval.

2. Initial Conditions AA 2.1

_______ Verify operation of the Hydrogen Recombiner is required per appropriate emergency procedures.

AA 2.2

_______ Request RP coverage due to increasing radiation levels at Hydrogen Recombiner panels during a LOCA.

Gary Johnson Person notified ____________________________________

3. Procedure

_____ 3.1 Ensure the H2 Skimmer Fans running per Enclosure 4.13 (Emergency Manual Operation of the H2 Skimmer Fans).

CAUTION: Hydrogen Recombiners are NOT operated with hydrogen concentration 6% without TSC approval.

NOTE: 1. If desired to place both Hydrogen Recombiners in service, Steps 3.2 and 3.3 may be performed in conjunction.

2. If desired to place both Hydrogen Recombiners in service, use additional Enclosure 4.11 (Hydrogen Recombiner Heater Temperature Log).

3. Placing Hydrogen Recombiner 1A in service is preferred for ALARA consideration.

_____ 3.2 IF placing Hydrogen Recombiner 1A in service, perform the following at 1ELCP0139 (1A Hydrogen Recombiner Control Panel) (AB-577, DD-52, Rm 494):

3.2.1 Ensure the "POWER OUT SWITCH" is in the "OFF" position.

3.2.2 Ensure the "POWER ADJUST" potentiometer is set to zero (000).

_____ _____ 3.2.3 IF the "POWER IN AVAILABLE" light is DARK, ensure 1EMXK-F07C (1A Electric Hydrogen Recombiner Power Supply Panel) (AB-577, BB-47) is in the "ON" position:

3.2.4 Place the "POWER OUT SWITCH" in the "ON" position

Enclosure 4.10 OP/1/A/6450/010 Operation of the Hydrogen Recombiners Page 2 of 7 Following a LOCA 3.2.5 Verify that the red indicating light is lit.

3.2.6 Slowly turn the "POWER ADJUST" potentiometer clockwise until 5 KW is indicated on the "POWER OUT" meter.

3.2.7 Maintain a 5 KW output for 10 minutes.

3.2.8 Slowly advance the "POWER ADJUST" setting until an output of 10 KW is obtained on the "POWER OUT" meter.

3.2.9 Maintain a 10 KW output for 10 minutes.

3.2.10 Advance the "POWER ADJUST" setting until an output of 20 KW is obtained on the "POWER OUT" meter.

3.2.11 Maintain a 20 KW output for 5 minutes.

3.2.12 Determine Hydrogen Recombiner 1A power setting as follows:

_____ 3.2.12.1 Determine KW value from Figure 10 of the Unit One Revised Data Book. ______ KW VALUE

_____ 3.2.12.2 H2 concentration (1MC7) ________%

_____ 3.2.12.3 IF H2 concentration is > 3.5%, add 4KW to calculation.

_____ 3.2.12.4 Calculate KW as follows:

_________ + __________ = ______ KW Step 3.2.12.1 Step 3.2.12.3 or N/A

_____ 3.2.13 Advance the "POWER ADJUST" setting until the "POWER OUT" meter indicates the value calculated in 3.2.12.4. Adjust "POWER ADJUST" as necessary to maintain this output.

_______ 3.2.14 Notify NCO that Hydrogen Recombiner 1A is now in service.

Person notified ___________________________________

Enclosure 4.10 OP/1/A/6450/010 Operation of the Hydrogen Recombiners Page 3 of 7 Following a LOCA CAUTION: The maximum electric hydrogen recombiner heater temperature is 1400F.

NOTE: 1. Temperature stabilization may take up to 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The heater temperatures are considered stabilized when the channels are within 60F of each other and the average temperature is 1225F. (CNM-1399.36-0010)

2. Hydrogen Recombiner Heater 1A Temperature is monitored from 1VXCR5000 (Train A Hydrogen Recombiner Heater Temperature Recorder) located on 1ELCP0299 (AB-577, DD-52, Rm 494).

3. 1VXCR5000 is a touch screen video monitor. Touching the screen while in screen saver mode will display the main menu. The thermocouple temperatures will be displayed when the "Digital" icon is selected. The "Return" icon on the lower left of the screen returns to the main menu.

3.2.15 Record hourly the Hydrogen Recombiner 1A Heater Temperature for each of the three thermocouples on Enclosure 4.11 (Hydrogen Recombiner Heater Temperature Log) until stabilized.

3.2.16 WHEN the Hydrogen Recombiner Heater 1A Temperature has stabilized per Enclosure 4.11 (Hydrogen Recombiner Heater Temperature Log), perform the following:

_____ 3.2.16.1 IF the thermocouples are inaccurate, proceed to Step 3.2.17.

3.2.16.2 Adjust "POWER ADJUST" potentiometer as necessary to maintain recombination temperature of 1225-1400F as read on 1VXCR5000 (Train A Hydrogen Recombiner Heater Temperature Recorder).

3.2.16.3 Verify the "POWER OUT" meter indicates > the value calculated in Step 3.2.12.4

Enclosure 4.10 OP/1/A/6450/010 Operation of the Hydrogen Recombiners Page 4 of 7 Following a LOCA 3.2.17 Every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, measure containment hydrogen concentration AND adjust recombiner power for the duration of recombiner operation as follows:

_____ 3.2.17.1 Determine KW value from Figure 10 of the Unit One Revised Data Book. ______ KW VALUE

_____ 3.2.17.2 H2 concentration (1MC7) ________%

_____ 3.2.17.3 IF H2 concentration has increased by .5% OR is > 3.5%, add 4KW to calculation.

_____ 3.2.17.4 Calculate KW as follows:

_________ + __________ = ______ KW Step 3.2.17.1 Step 3.2.17.3 or N/A

_____ 3.2.17.5 Advance the "POWER ADJUST" setting until the "POWER OUT" meter indicates the value calculated in 3.2.17.4. Adjust "POWER ADJUST" as necessary to maintain this output.

3.2.17.6 Monitor Hydrogen Recombiner Heater Temperature per Steps 3.2.15 and 3.2.16 to prevent temperature from exceeding 1400F.

_____ 3.3 IF placing Hydrogen Recombiner 1B in service, perform the following at 1ELCP0140 1B Hydrogen Recombiner Control Panel) (AB-560, DD-52, Rm 370):

3.3.1 Ensure the "POWER OUT SWITCH" is in the "OFF" position.

3.3.2 Ensure the "POWER ADJUST" potentiometer is set to zero (000).

_____ _____ 3.3.3 IF the "POWER IN AVAILABLE" light is DARK, ensure 1EMXL-F07C (1B Electric Hydrogen Recombiner Power Supply Panel) (AB-560, BB-47) is in the "ON" position:

3.3.4 Place the "POWER OUT SWITCH" in the "ON" position.

3.3.5 Verify that the red indicating light is lit.

3.3.6 Slowly turn the "POWER ADJUST" potentiometer clockwise until 5 KW is indicated on the "POWER OUT" meter.

3.3.7 Maintain a 5 KW output for 10 minutes.

3.3.8 Slowly advance the "POWER ADJUST" setting until an output of 10 KW is obtained on the "POWER OUT" meter.

3.3.9 Maintain a 10 KW output for 10 minutes.

Enclosure 4.10 OP/1/A/6450/010 Operation of the Hydrogen Recombiners Page 5 of 7 Following a LOCA 3.3.10 Advance the "POWER ADJUST" setting until an output of 20 KW is obtained on the "POWER OUT" meter.

3.3.11 Maintain a 20 KW output for 5 minutes.

3.3.12 Determine Hydrogen Recombiner 1B power setting as follows:

_____ 3.3.12.1 Determine KW value from Figure 10 of the Unit One Revised Data Book.

_____ 3.3.12.2 H2 concentration (1MC7) ________%

_____ 3.3.12.3 IF H2 concentration is > 3.5%, add 4KW to calculation.

_____ 3.3.12.4 Calculate KW as follows:

_________+ __________ = ______ KW Step 3.3.12.1 Step 3.3.12.3 or N/A

_____ 3.3.13 Advance the "POWER ADJUST" setting until the "POWER OUT" meter indicates the value calculated in 3.3.12.4. Adjust "POWER ADJUST" as necessary to maintain this output.

_______ 3.3.14 Notify NCO that Hydrogen Recombiner 1B is now in service.

Person notified ___________________________________

CAUTION: The maximum electric hydrogen recombiner heater temperature is 1400F.

NOTE: 1. Temperature stabilization may take up to 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The heater temperatures are considered stabilized when the channels are within 60F of each other and the average temperature is 1225F. (CNM-1399.36-0010)

2. Hydrogen Recombiner Heater 1B Temperature is monitored from 1VXCR5500 (Train B Hydrogen Recombiner Heater Temperature Recorder) located on 1ELCP0300 (AB-560, DD-52, Rm 370).

3. 1VXCR5500 is a touch screen video monitor. Touching the screen while in screen saver mode will display the main menu. The thermocouple temperatures will be displayed when the "Digital" icon is selected. The "Return" icon on the lower left of the screen returns to the main menu.

3.3.15 Record hourly the Hydrogen Recombiner Heater 1B Temperature for each of the three thermocouples on Enclosure 4.11 (Hydrogen Recombiner Heater Temperature Log), until stabilized.

Enclosure 4.10 OP/1/A/6450/010 Operation of the Hydrogen Recombiners Page 6 of 7 Following a LOCA 3.3.16 WHEN the Hydrogen Recombiner Heater 1B Temperature has stabilized per Enclosure 4.11 (Hydrogen Recombiner Heater Temperature Log), perform the following:

_____ 3.3.16.1 IF the thermocouples are inaccurate, proceed to Step 3.3.17.

3.3.16.2 Adjust "POWER ADJUST" potentiometer as necessary to maintain recombination temperature of 1225-1400F as read on1VXCR5500 (Train B Hydrogen Recombiner Heater Temperature Recorder).

3.3.16.3 Verify the "POWER OUT" meter indicates > the value calculated in Step 3.3.12.4.

3.3.17 Every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, measure containment hydrogen concentration AND adjust recombiner power for the duration of recombiner operation as follows:

_____ 3.3.17.1 Determine KW value from Figure 10 of the Unit One Revised Data Book. ______ KW VALUE

_____ 3.3.17.2 H2 concentration (1MC7) ________%

_____ 3.3.17.3 IF H2 concentration has increased by .5% OR is > 3.5%, add 4KW to calculation.

_____ 3.3.17.4 Calculate KW as follows:

_________ + __________ = ______ KW Step 3.3.17.1 Step 3.3.17.3 or N/A

_____ 3.3.17.5 Advance the "POWER ADJUST" setting until the "POWER OUT" meter indicates the value calculated in 3.3.17.4. Adjust "POWER ADJUST" as necessary to maintain this output.

3.3.17.6 Monitor Hydrogen Recombiner Heater Temperature per Steps 3.3.15 and 3.3.16 to prevent temperature from exceeding 1400F.

_____ 3.4 IF operation of Hydrogen Recombiner 1A is no longer required, perform the following on panel 1ELCP0139 (1A Hydrogen Recombiner Power Control Panel):

_______ 3.4.1 Turn the "POWER ADJUST" potentiometer on the control panel to zero (000).

_______ 3.4.2 Place the "POWER OUT SWITCH" on the control panel in the "OFF" position.

_____ 3.5 IF operation of Hydrogen Recombiner 1B is no longer required, perform the following on panel 1ELCP0140 (1B Hydrogen Recombiner Power Control Panel):

_______ 3.5.1 Turn the "POWER ADJUST" potentiometer on the control panel to zero (000).

_______ 3.5.2 Place the "POWER OUT SWITCH" on the control panel in the "OFF" position.

Enclosure 4.10 OP/1/A/6450/010 Operation of the Hydrogen Recombiners Page 7 of 7 Following a LOCA 3.6 Do NOT file a copy of this enclosure in the designated storage cabinet.

Unit 1 Data Book Source: TP/1/A/1200/11 68 66 64 62 60 Power (kW) 58 56 54 52 A Train B Train 50 2 3 4 5 6 7 8 9 10 Post- LOCA Containment Pressure (psig)

Rev. 0, 6/30/98 Figure 10 - Unit 1 Hydrogen Recombiners Post-LOCA Power Consumption Page 10

Catawba Nuclear Station JPM K 2021 NRC Exam JPM K PAGE 1 OF 7

Catawba Nuclear Station JPM K 2021 NRC Exam EVALUATION SHEET Task: Break Condenser Vacuum Locally Alternate Path: No Facility JPM #: CA-084 Safety Function: 4S

Title:

Main Turbine Generator (MT/G) System K/A 045 A1.06 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including: Expected response of secondary plant parameters following T/G trip Rating(s): 3.3 / 3.7 CFR: 41.5 / 45.5 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant X Perform X Simulate

References:

AP/1/A/5500/006 (Loss of S/G Feedwater) Rev 45 Enclosure 3 Task Standard: Enclosure 3 has been completed with the first vacuum breaker opened within 10 minutes.

Validation Time: 8 minutes Time Critical: Yes X No

===============================================================

Applicant: Time Start: ___________

NAME______________________ Docket #_____________ Time Finish: ___________

Time Critical (<10 minutes)

Time Start: __________

Performance Rating: Time Finish: __________

SAT ____ UNSAT ____ Performance Time ______

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

===============================================================

COMMENTS PAGE 2 OF 7

Catawba Nuclear Station JPM K 2021 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 following a reactor trip.

INITIATING CUES:

• The Control Room Supervisor instructs you to perform AP/1/A/5500/006 (Loss of S/G Feedwater) Enclosure 3 (Local Actions to Break Condenser Vacuum).

This JPM is TIME CRITICAL; time begins when you acknowledge the task.

EXAMINER NOTE: Provide applicant with a copy of AP/1/A/5500/006, Enclosure 3.

PAGE 3 OF 7

Catawba Nuclear Station JPM K 2021 NRC Exam Critical Time Start: Record Time that applicant acknowledges the task _________.

STEP/STANDARD SAT/UNSAT CAUTION High air flow rates will exist when vacuum breakers are first opened. Stay clear of pipe end. CRITICAL STEP STEP 1: 1 Break condenser vacuum by opening the following valves:

• 1CM-368 (2A Main Cond Shell Vacuum Bkr) (TB1-600,1F- 26) (Ladder needed)

• 1CM-369 (2B Main Cond Shell Vacuum Bkr) (TB1-603, 1F- 24) (Ladder needed)

• 1CM-370 (2C Main Cond Shell Vacuum Bkr) (TB1-605, 1F-22) (Ladder needed).

Examiner Note: The critical end time is when the applicant describes opening the first valve. Due to the height of the valves, no fall protection will be required.

Examiner Cue: When applicant describes engaging lever and rotating handwheel counter clockwise to open the ___ SAT following valve then: A large volume of airflow is heard. ___ UNSAT Examiner Note: This step is critical in order to open correct valves for breaking vacuum.

Critical Time End:

STANDARD:

Applicant will describe opening the valves: 1CM-368, 1CM-369, 1CM-370.

COMMENTS:

PAGE 4 0F 7

Catawba Nuclear Station JPM K 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2 2 Secure steam to CSAEs as follows:

CRITICAL

a. Close the following valves: STEP

• 1SA-22 (Main Steam To CSAE) (TB1-594, 1M-32)

• 1SA-27 (Aux Steam To CSAE) (TB-594, 1M-27).

STANDARD:

Applicant will describe closing 1SA-22 and 1SA-27.

Examiner Cue: As applicant properly describes closing the valves ___ SAT give cue as appropriate, Valve turns until resistance is felt. ___UNSAT Examiner Note: This step is critical, because if it is not performed, the CSAEs will continue to pull vacuum COMMENTS:

STEP 3 b. WHEN time and manpower permit, THEN complete the shutdown of the CSAEs. REFER TO OP/1/B/6300/006 (Main Vacuum).

STANDARD:

Applicant will read the step ___ SAT Examiner Cue: The Control Room Supervisor has instructed ___ UNSAT another operator to complete the shutdown of the CSAEs.

COMMENTS:

PAGE 5 0F 7

Catawba Nuclear Station JPM K 2021 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4 3. WHEN requested by Control Room Supervisor, THEN verify condenser vacuum broken as follows:

a. Inspect each vacuum breaker for absence of air flow into condenser.

b. Notify Control Room Supervisor of results.

STANDARD: ___ SAT Applicant will inspect each vacuum breaker for the absence of air flow ___ UNSAT into the condenser and will report to the Control Room Supervisor.

Examiner Cue: After each inspection, No air flow into condenser.

COMMENTS:

STOP TIME________

PAGE 6 0F 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:

• Unit 1 is in Mode 3 following a reactor trip.

INITIATING CUES:

• The Control Room Supervisor instructs you to perform AP/1/A/5500/006 (Loss of S/G Feedwater) Enclosure 3 (Local Actions to Break Condenser Vacuum).

This JPM is TIME CRITICAL; time begins when you acknowledge the task.

CNS LOSS OF S/G FEEDWATER PAGE NO.

AP/1/A/5500/006 21 of 21 Enclosure 3 - Page 1 of 1 Revision 45 Local Actions To Break Condenser Vacuum CAUTION High air flow rates will exist when vacuum breakers are first opened. Stay clear of pipe end.

1. Break condenser vacuum by opening the following valves:

1CM-368 (1A Main Cond Shell Vacuum Bkr) (TB1-600,1F-26) (Ladder needed) 1CM-369 (1B Main Cond Shell Vacuum Bkr) (TB1-603, 1F-24) (Ladder needed) 1CM-370 (1C Main Cond Shell Vacuum Bkr) (TB1-605, 1F-22) (Ladder needed).

2. Secure steam to CSAEs as follows:

a. CLOSE the following valves:

1SA-22 (Main Steam To CSAE) (TB1-594, 1M-32) 1SA-27 (Aux Steam To CSAE) (TB-594, 1M-27).

b. WHEN time and manpower permit, THEN complete the shutdown of CSAEs. REFER TO OP/1/B/6300/006 (Main Vacuum).

3. WHEN requested by Control Room Supervisor, THEN verify condenser vacuum broken as follows:

a. Inspect each vacuum breaker for absence of air flow into condenser.

b. Notify Control Room Supervisor of results.

Catawba Nuclear Station Admin. JPM A.1-1R September 2021 NRC Exam JPM A.1-1R RO PAGE 1 OF 10

Catawba Nuclear Station Admin. JPM A.1-1R September 2021 NRC Exam EVALUATION SHEET Task: Calculate Reactor Vessel Head Venting Time Alternate Path: N/A Facility JPM #: New Safety Function: N/A K/A G 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:

EP/1/A/5000/FR-I.3 Response to Voids in Reactor Vessel, Enclosure 2 (rev 19) and images of control room gauges needed to perform head vent calculation.

Task Standard: Reactor vessel head maximum allowable vent time calculated as follows: Value A calculated to be 9434 - 9698; Value B calculated to be 7075 - 12123:

Value C determined to be 2750 - 3250; Maximum allowable vent time T is calculated to be 2.1 - 4.4 minutes.

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 Admin. JPM A.1-1R September 2021 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Insert the following malfunctions:

Instructor Action Final Delay Ramp Delete In Event XMT-VV010 (TVV_5090 LOWER CNT AIR TEMP 145 A MTR)

XMT-VV011 (TVV_5110 LOWER CNT AIR TEMP 145 B MTR)

XMT-VV014 (TVV_5170 LOWER CNT AIR TEMP 145 C MTR)

XMT-VV015 (TVV_5190 LOWER CNT AIR TEMP 145 D MTR)

XMT-VX003 (XMI_5320 CNT TRN A H2 ANAL 2

MTR)

XMT-VX004 (XMI_5330 CNT TRN B H2 ANAL 2

MTR)

XMT-CNT009 (PNS_5090 CNT PRESS MTR (PI-3.5 937))

XMT-CNT008 (PNS_5060 CNT PRESS MTR (PI-3.5 936))

XMT-CNT007 (PNS_5050 CNT PRESS MTR (PI-3.5 935))

XMT-CNT006 (PNS_5040 CNT PRESS MTR (PI-3.5 934))

XMT-CNT011 (PNS_5380 CNT TRN B PRESS 3.5 MTR)

XMT-CNT010 (PNS_5370 CNT TRN A PRESS 3.5 MTR)

IND-NC023 (PNC_5120 LOOP B HOT LEG W/R 900 PRESS MTR (PI-405))

IND-NC024 (PNC_5140 LOOP C HOT LEG W/R 900 PRESS MTR (PI-403))

3. Take digital photographs of the gauges listed above or provide control board mimics from the instructor station.

NOTE TO EVALUATOR: These have been provided as part of the JPM package for each applicant.

PAGE 3 OF 10

Catawba Nuclear Station Admin. JPM A.1-1R September 2021 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 LOCA is in progress on Unit 1 INITIATING CUES:

• The CRS directs you to calculate and record the maximum reactor vessel head venting time per EP/1/A/5000/FR-I.3 (Response to Voids in Reactor Vessel)

Enclosure 2 (Allowable Hydrogen Venting Time)

EXAMINER NOTE: Each applicant should receive a copy of FR-I.3 Enclosure 2 as well as 4 pictures of control room gauges for:

• H2 Analyzers

• Containment Pressure

• Lower Containment Air Temperatures

• Loop B and C Hot Leg W/R Pressure PAGE 4 OF 10

Catawba Nuclear Station Admin. JPM A.1-1R September 2021 NRC Exam START TIME: _______

PAGE 5 0F 10

Catawba Nuclear Station Admin. JPM A.1-1R September 2021 NRC Exam STEP 1: Step 1 CRITICAL Calculate A where A = 9500 X (P + 14.7) X 492 STEP 14.7 (T+460)

Where: P = Containment pressure (PSIG)

T = Lower Containment temperature (°F)

STANDARD:

Calculate A:

Determine containment pressure as 3.4 psig to 3.6 psig.

Determine Lower Containment Temperature as 140°F - 150°F.

Using 3.4, 140 A = 9500 X (3.4 + 14.7) X 492 = 9591.7 14.7 (140+460)

Using 3.4, 150 A = 9500 X (3.4 + 14.7) X 492 = 9434.5 14.7 (150+460)

___ SAT Using 3.6, 140 A = 9500 X (3.6 + 14.7) X 492 = 9697.7 14.7 (140+460) ___ UNSAT Using 3.6, 150 A = 9500 X (3.6 + 14.7) X 492 = 9538.7 14.7 (150+460)

NOTE TO EXAMINER: Acceptable band for value of A is 9434 - 9698.

This step is critical to properly perform this task and to meet the JPM standard to calculate the maximum head vent time for the containment conditions given.

COMMENTS:

PAGE 6 0F 10

Catawba Nuclear Station Admin. JPM A.1-1R September 2021 NRC Exam STEP 2: Step 2 CRITICAL Calculate B where B = (3 - H) X A STEP Where H = Containment Hydrogen Concentration (%)

STANDARD:

Determine H2 concentration as between 1.75% and 2.25%.

Using bounding values of A (9434 to 9698):

B = (3 - 1.75) X 9434 = 11792.5 B = (3 - 1.75) X 9698 = 12122.5 B = (3 - 2.25) X 9434 = 7075.5 ___ SAT B = (3 - 2.25) X 9698 = 7273.5 ___UNSAT NOTE TO EXAMINER: Acceptable range for value of B is 7075 -

12123.

This step is critical to properly perform this task and to meet the JPM standard to calculate the maximum head vent time for the containment conditions given.

COMMENTS:

PAGE 7 0F 10

Catawba Nuclear Station Admin. JPM A.1-1R September 2021 NRC Exam STEP 3: Step 3 Determine C from the curve for the current NC system pressure. CRITICAL STEP STANDARD:

Determines NC pressure from pictures as 875 psig to 925 psig.

Determines C (hydrogen flow rate) as between 2,750 - 3,250 SCFM.

This step is critical to properly perform this task and to meet the JPM ___ SAT standard to calculate the maximum head vent time for the conditions given. ___ UNSAT COMMENTS:

PAGE 8 0F 10

Catawba Nuclear Station Admin. JPM A.1-1R September 2021 NRC Exam STEP 4 Enclosure 5 Step 4 Calculate T: CRITICAL STEP T= B / C = Venting time in minutes STANDARD:

Using bounding values for B and C:

T = 7075 / 2750 = 2.57 minutes T = 7075 / 3250 = 2.18 minutes T = 12123 / 2750 = 4.40 minutes T = 12123 / 3250 = 3.73 minutes ___ SAT

___ UNSAT NOTE TO EXAMINER: Maximum allowable venting time acceptable band is 2.1 - 4.4 minutes (2 minutes 6 seconds to 4 minutes 24 seconds).

This step is critical to properly perform this task and to meet the JPM standard to calculate the maximum head vent time for the containment conditions given.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 9 0F 10

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

• A LOCA is in progress on Unit 1 INITIATING CUES:

• The CRS directs you to calculate and record the maximum reactor vessel head venting time per EP/1/A/5000/FR-I.3 (Response to Voids in Reactor Vessel)

Enclosure 2 (Allowable Hydrogen Venting Time)

CNS RESPONSE TO VOIDS IN REACTOR VESSEL PAGE NO.

EP/1/A/5000/FR-I.3 30 of 38 Enclosure 2 - Page 1 of 1 Revision 19 Allowable Hydrogen Venting Time CALCULATION OF MAXIMUM ALLOWABLE VENTING TIME STEP 1: Calculate A (P + 14.7) 492 A = 9,500 x x 14.7 (T + 460) where: P = Containment pressure (PSIG)

T = Lower containment temperature (deg F)

STEP 2: Calculate B B = (3 - H) x A where: H = Containment hydrogen concentration (%)

STEP 3: Determine C from the curve for the current NC system pressure.

STEP 4: Calculate T T = B/C = Venting time in minutes NC pressure ______ PSIG. Maximum allowable venting time ______ minutes.

Catawba Nuclear Station Admin. JPM A.1-2R September 2021 NRC Exam JPM A.1-2R RO PAGE 1 OF 8

Catawba Nuclear Station Admin. JPM A.1-2R September 2021 NRC Exam EVALUATION SHEET Task: Determine Rod Insertion Limit Boration Alternate Path: N/A Facility JPM #: New Safety Function: N/A K/A 2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

Importance: 4.1 / 4.3 CFR: 41.10 / 43.6 / 45.6 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate

References:

AP/1/A/5500/003 (Load Rejection) Rev 47 Enclosure 3 (Rod Insertion Limit Boration)

Unit 1 ROD Book Task Standard: Applicant determines the Rod Insertion Limit to be between 39-42 steps withdrawn on Control Bank D, Calculated values for R = 796 - 823 PCM, P =

1084 PCM, A = 261 - 288 PCM, Differential Boron Worth = -6.47 PCM/PPM, C

= 40.34 - 44.51 PPM, D = 940 - 945 PPM, and calculates the required amount of boric acid to add to the NC system to restore rods to 10 steps above RIL is 411 - 515 gallons.

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 Admin. JPM A.1-2R September 2021 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 has experienced a runback from 85% RTP following a Zone A Lockout

• Current reactor power is 48% RTP

• Unit 1 is at 250 EFPD

• Annunciator 1AD-2, B/9 (CONTROL ROD BANK LO-LO LIMIT) is LIT

• Control Bank D rods are currently 20 steps withdrawn

• Current NC System Boron concentration is 900 ppm INITIATING CUES:

• The CRS has directed you to borate the NC system as necessary to maintain control rods above the insertion limit per AP/1/A/5500/003 (Load Rejection) Enclosure 3 (Rod Insertion Limit Boration) step 2.

• You are to determine the amount of Boric Acid required to restore control rods to 10 STEPS ABOVE the required rod insertion limit and record below.

Boric Acid addition required: gallons EXAMINER NOTE:

After reading cue, provide applicant with a copy of AP/1/A/5500/003 Enclosure 3 and the ROD book for Unit 1 PAGE 3 OF 8

Catawba Nuclear Station Admin. JPM A.1-2R September 2021 NRC Exam START TIME: _______

STEP / STANDARD SAT /

UNSAT STEP 1: 2.a IF initial reactor power was 100%, THEN borate NC System as required to restore control rods above insertion limits.

REFER TO Unit 1 R.O.D. book, section 4.8 (Reactivity Data Sheet).

STANDARD:

___ SAT Applicant determines that initial reactor power was 85% per the initiating cue and that this step is not applicable. ___ UNSAT COMMENTS:

PAGE 4 0F 8

Catawba Nuclear Station Admin. JPM A.1-2R September 2021 NRC Exam STEP 2: 2.b IF initial reactor power was less than 100% OR Unit 1 R.O.D.

book, section 4.8 (Reactivity Data Sheet) is NOT available, CRITICAL THEN perform the following as required to restore control rods STEP above the insertion limits:

NOTE OAC point C1P1448 (Low Bank Insertion Limit Margin) and R.O.D.

Book (Section 2.2) provide rod insertion limit indication.

1) Determine control rod insertion limit. ________

STANDARD:

Applicant determines that the rod insertion limit for 48% power is ___ SAT approximately 40 steps withdrawn on Control Bank D (Acceptable Range 39-42 steps). ___ UNSAT This step is critical in order to properly determine the correct amount of boric acid to add to restore control rods to above the insertion limit.

COMMENTS:

STEP 3: 2.b.2) Calculate A (reactivity difference between required rod position and current rod position). REFER TO Unit 1 R.O.D. CRITICAL book section 5.6.3. STEP R = Required rod position IRW ______ PCM P = Current rod position IRW _______ PCM (R - P = A _________ PCM).

STANDARD:

Applicant determines R for 50 steps withdrawn (40 steps RIL + 10 steps

= 50 steps) is 805 PCM (Acceptable Range is 796 PCM - 823 PCM).

Applicant determines P for 20 steps withdrawn is 1084 PCM. Applicant

___ SAT then calculates A to be 279 PCM (Acceptable Range is 261 PCM - 288 PCM).

___ UNSAT This step is critical in order to properly determine the correct amount of boric acid to add to restore control rods to above the insertion limit.

COMMENTS:

PAGE 5 0F 8

Catawba Nuclear Station Admin. JPM A.1-2R September 2021 NRC Exam STEP 4: 2.b.3) Determine B (differential boron worth). REFER TO Unit 1 R.O.D. book section 5.5 _________ PCM/PPM.

CRITICAL STANDARD: STEP Applicant determines from ROD book section 5.5 that differential boron worth for 250 EFPD is -6.47 PCM/PPM.

This step is critical in order to properly determine the correct amount of boric acid to add to restore control rods to above the insertion limit. ___ SAT COMMENTS: ___ UNSAT STEP 5: 2.b.4) Calculate C (difference in reactivity) as follows:

CRITICAL A / B = C ________ PPM. STEP STANDARD:

Applicant calculates C to be 43.12 PPM (279 PCM / 6.47 PCM/PPM =

42.97 PPM). (Acceptable Range is 40.34 PPM - 44.51 PPM)

This step is critical in order to properly determine the correct amount ___ SAT of boric acid to add to restore control rods to above the insertion limit.

___ UNSAT COMMENTS:

PAGE 6 0F 8

Catawba Nuclear Station Admin. JPM A.1-2R September 2021 NRC Exam STEP 6: 2.b.5) Calculate D (required boron concentration) as follows:

CRITICAL E = Current Boron Concentration _______ PPM. STEP E + C = D ________ PPM STANDARD:

Applicant calculates D to be 943 PPM. (900 + 43 = 943 PPM)

(Acceptable Range is 940 PPM - 945 PPM)

___ SAT This step is critical in order to properly determine the correct amount of boric acid to add to restore control rods to above the insertion limit. ___ UNSAT COMMENTS:

STEP 7: 2.b.6) Determine required boric acid needed to raise NC System boron concentration to value D calculated in Step 2.b.5. CRITICAL REFER TO Unit 1 R.O.D. book table 4.1 or REACT STEP Boration/Dilution module. ________.

STANDARD:

Applicant determines that 442 gallons of boric acid are needed to raise NC system boron concentration from 900 PPM to 943 PPM. (Acceptable range is 411 - 515 gallons).

___ SAT This step is critical in order to properly determine the correct amount of boric acid to add to restore control rods to above the insertion limit. ___ UNSAT 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:

• Unit 1 has experienced a runback from 85% RTP following a Zone A Lockout

• Current reactor power is 48% RTP

• Unit 1 is at 250 EFPD

• Annunciator 1AD-2, B/9 (CONTROL ROD BANK LO-LO LIMIT) is LIT

• Control Bank D rods are currently 20 steps withdrawn

• Current NC System Boron concentration is 900 ppm INITIATING CUES:

• The CRS has directed you to borate the NC system as necessary to maintain control rods above the insertion limit per AP/1/A/5500/003 (Load Rejection) Enclosure 3 (Rod Insertion Limit Boration) step 2.

• You are to determine the amount of Boric Acid required to restore control rods to 10 STEPS ABOVE the required rod insertion limit and record below.

Boric Acid addition required: gallons

CNS LOAD REJECTION PAGE NO.

AP/1/A/5500/003 53 of 55 Enclosure 3 - Page 1 of 2 Revision 47 Rod Insertion Limit Boration CAUTION Failure to initiate boration within one hour of exceeding rod insertion limits may violate Tech Spec 3.1.6.

NOTE OAC point C1L4409 (Ctrl Bank Tech Spec Insertion Lmt Reached) and R.O.D Book (Section 2.2) provide rod insertion limit indication.

1. IF control rods cannot be maintained above rod insertion limits, THEN perform the following:

a. Stop any dilutions in progress.

b. Ensure control rods restored above insertion limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of exceeding limits.

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

2. Perform one of the following to restore control rods above insertion limits:

a. IF initial reactor power was 100%, THEN borate NC System as required to restore control rods above insertion limits. REFER TO Unit 1 R.O.D. book, section 4.8 (Reactivity Data Sheet).

CNS LOAD REJECTION PAGE NO.

AP/1/A/5500/003 54 of 55 Enclosure 3 - Page 2 of 2 Revision 47 Rod Insertion Limit Boration

2. (Continued)

b. IF initial reactor power was less than 100% OR Unit 1 R.O.D. book, section 4.8 (Reactivity Data Sheet) is NOT available, THEN perform the following as required to restore control rods above insertion limits:

NOTE OAC point C1P1448 (Low Bank Insertion Limit Margin) and R.O.D Book (Section 2.2) provide rod insertion limit indication.

1) Determine control rod insertion limit. ________.

2) Calculate "A" (reactivity difference between required rod position and current rod position). REFER TO Unit 1 R.O.D. book section 5.6.3.

R = Required rod position IRW _________ PCM P = Current rod position IRW _________ PCM (R - P = A __________ PCM).

3) Determine "B" (differential boron worth). REFER TO Unit 1 R.O.D. book section 5.5

______________ PCM/PPM.

4) Calculate "C" (difference in reactivity) as follows:

A / B = C ______________ PPM.

5) Calculate "D" (required boron concentration) as follows:

E = Current Boron concentration _________ PPM.

E + C = D__________ PPM.

6) Determine required boric acid needed to raise NC System boron concentration to value "D" calculated in Step 2.b.5. REFER TO Unit 1 R.O.D. book table 4.1 or REACT Boration/Dilution module. ___________.

NOTE The boric acid added to the NC System should be added in several increments within the first hour of the runback.

Due to the post transient Xenon build-in rate, the total boric acid value calculated in Step 2.b.6, may not need to be added to restore control rods above insertion limits.

7) Borate NC System as required to restore control rods above insertion limits.

Catawba Nuclear Station Admin. JPM A.2R September 2021 NRC Exam JPM A.2R RO PAGE 1 OF 7

Catawba Nuclear Station Admin. JPM A.2R September 2021 NRC Exam EVALUATION SHEET Task: Determine NC Subcooling on a loss of OAC Alternate Path: N/A Facility JPM #: CCM-003 Safety Function: N/A K/A G 2.2.12 Knowledge of surveillance procedures.

Importance: 3.7 / 4.1 CFR: 41.10 / 45.13 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate

References:

PT/1/A/4600/009 (Loss of Operator Aid Computer), Unit 1 Revised Databook Figures 57 & 58 Task Standard: Determines Tsat is 465°F - 480°F, average of the 5 highest CETs is hottest at 452°F, and Subcooling is 13°F - 28°F and fills out Enclosure 13.8 (Subcooling Data Sheet) per the key. Determines the Acceptance Criteria is NOT met.

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 7

Catawba Nuclear Station Admin. JPM A.2R September 2021 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 and has experienced a loss of OAC

• PT/1/A/4600/009 (Loss of Operator Aid Computer) is in progress

• Both trains of the plasma display monitor are inoperable INITIATING CUES:

• The CRS directs you to complete Enclosure 13.8 (Subcooling Data Sheet) to determine the °F Subcooled and if this subcooling margin meets the acceptance criteria.

T cold T hot T ave D/T Loop A 445 448 447 3 Loop B 446 450 448 4 Loop C 442 444 443 2 Loop D 443 446 445 3 5 Highest Core 454 450 453 451 452 Exit T/C Chan 1 Chan 2 Chan 3 Chan 4 W/R B W/R C Pressure 1700 1700 1700 1700 600 620 EXAMINER NOTE: Each applicant should receive a copy of PT/1/A/4600/009 Enclosure 13.8 and a copy of the Unit 1 Revised Data Book.

PAGE 3 OF 7

Catawba Nuclear Station Admin. JPM A.2R September 2021 NRC Exam START TIME: _______

STEP 1: Record lowest indicated system pressure.

STANDARD:

Applicant determines that 600 psig is the lowest pressure and records this value on the table in Enclosure 13.8. ___ SAT

___ UNSAT COMMENTS:

STEP 2: T-Sat - Using NC pressure, determine saturation temperature from the Unit 1 Revised Data Book Figure 57 or Figure 58. CRITICAL STEP STANDARD:

Applicant determines T-Sat is 465°F-480°F and records this value on the table in Enclosure 13.8.

This step is critical in determining the actual amount of subcooling on ___ SAT Unit 1 to meet the JPM standard.

___UNSAT COMMENTS:

PAGE 4 0F 7

Catawba Nuclear Station Admin. JPM A.2R September 2021 NRC Exam STEP 3: Highest NC Temp - Determine the highest NC Temp:

CRITICAL

• In Modes 1 and 2, use Loop Thot STEP

• In Modes 3-6:

o Compare the average of the 5 highest reading operable core exit T/Cs to Loop Thot.

OR o Use the operating train(s) of ND inlet temperature, Loop Thot and/or the operable core exit T/Cs.

STANDARD:

Applicant determines that the average of the 5 highest core exit T/Cs is the hottest and calculates it to be 452°F and records this value on the table in ___ SAT 3.8.

___ UNSAT This step is critical in determining the actual amount of subcooling on Unit 1 to meet the JPM standard.

COMMENTS:

STEP 4 °F Subcooled - Calculate by subtracting HIGHEST NC TEMP from T-Sat.

CRITICAL STANDARD: STEP Applicant calculates °F Subcooled to be 13°F-28°F and records this value on the table in Enclosure 13.8.

This step is critical in determining the actual amount of subcooling on ___ SAT Unit 1 to meet the JPM standard.

___ UNSAT COMMENTS:

PAGE 5 0F 7

Catawba Nuclear Station Admin. JPM A.2R September 2021 NRC Exam STEP 5 Determine if the acceptance criteria is met.

STANDARD: CRITICAL STEP Applicant determines that °F Subcooled is < the required of 30°F while shutdown and therefore the acceptance criteria is NOT met.

This step is critical in determining that the amount of subcooling present does not meet acceptance criteria for the current mode. ___ SAT COMMENTS: ___ UNSAT END OF TASK STOP TIME ________

PAGE 6 0F 7

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

• Unit 1 is in Mode 3 and has experienced a loss of OAC

• PT/1/A/4600/009 (Loss of Operator Aid Computer) is in progress

• Both trains of the plasma display monitor are inoperable INITIATING CUES:

• The CRS directs you to complete Enclosure 13.8 (Subcooling Data Sheet) to determine the °F Subcooled and if this subcooling margin meets the acceptance criteria.

T cold T hot T ave D/T Loop A 445 448 447 3 Loop B 446 450 448 4 Loop C 442 444 443 2 Loop D 443 446 445 3 5 Highest Core 454 450 453 451 452 Exit T/C Chan 1 Chan 2 Chan 3 Chan 4 W/R B W/R C Pressure 1700 1700 1700 1700 600 620

°F Subcooled: ___________

Acceptance Criteria met (Yes/No): ___________

Enclosure 13.8 PT/1/A/4600/009 Subcooling Data Sheet Page 1 of 1 CALCULATION SHEET FOR NC SYSTEM DEGREES SUBCOOLED Date/Time NC Press T-SAT Highest NC Temp F Subcooled Initials ACCEPTANCE CRITERIA:

Subcool limit is 10F while at power.

30F while shutdown.

INFORMATION:

NC Pressure - Record lowest indicated system pressure.

T-SAT - Using NC pressure, determine saturation temperature from the Unit One Revised Data Book Figure 57 or Figure 58.

Highest NC Temp - Determine the highest NC Temp:

• In Modes 1 and 2, use Loop THOT.

• In Modes 3-6:

• Compare the average of the 5 highest reading operable core exit T/Cs to Loop THOT. (This is the preferred method)

OR

• Use the operating train(s) of ND inlet temperature, Loop THOT and/or the operable core exit T/Cs.

F Subcooled - Calculate by subtracting "HIGHEST NC TEMP" from "T-SAT".

Catawba Nuclear Station Admin. JPM A.3R September 2021 NRC Exam JPM A.3R RO PAGE 1 OF 6

Catawba Nuclear Station Admin. JPM A.3R September 2021 NRC Exam EVALUATION SHEET Task: Determine Radiation Protection Requirements for an activity Alternate Path: N/A Facility JPM #: 2019 NRC Exam Admin JPM A.3R Safety Function: N/A K/A G 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Importance: 3.4 / 3.8 CFR: 41.12 / 43.4 / 45.10 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate

References:

Radiation Work Permit # 5021 Task 1, Room 105 (ND Pump 1A) Survey Map Task Standard: Correctly determine that total dose received for the job is 13 mR and maximum additional time allowed at Low Exposure Waiting Area is 42 minutes prior to exceeding 80% of RWP dose limits.

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 6

Catawba Nuclear Station Admin. JPM A.3R September 2021 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 has entered AP/1/A/5500/019 (Loss of Residual Heat Removal)

• The CRS has dispatched an AO to 1A ND pump room to vent the 1A ND pump casing when directed.

• The AO has staged himself to minimize dose while waiting.

• The following is the timeline for the venting evolution:

0730 - AO enters 1A ND Pump Room.

0800 - AO is directed to vent using 1ND-88 (1A ND Pump Seal Water Hx Inlet Vent).

0812 - Venting is complete. AO returns to the LEWA to await further instruction.

INITIATING CUES:

Based on the above time line, RWP # 5021, and Survey Maps provided and discounting any dose received during transit:

1. State the amount of dose that has been received thus far.

Amount of dose received - ________________ mR

2. Following completion of venting activity, calculate how much longer the AO can remain in the room until required to exit (based on exceeding 80% of RWP allowable dose).

Allowable time in room following venting activity - ___________ .

EXAMINER NOTE: Each applicant should receive a copy of RWP # 5021 (Task 1) and the Room Survey for rooms 105 and 110.

PAGE 3 OF 6

Catawba Nuclear Station Admin. JPM A.3R September 2021 NRC Exam START TIME: _______

STEP / STANDARD SAT /

UNSAT STEP 1 Determine dose received for the venting evolution:

CRITICAL AO is to stage themselves at the Low Exposure Waiting Area STEP (LEWA) where they wait for 30 minutes (.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />)

LEWA dose: 10 mR/hr X .5 hr = 5 mR Venting time is 12 minutes (.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)

Area dose: 40 mR/hr X .2 hr = 8 mR Total amount of dose received = 5 mR + 8 mR = 13 mR STANDARD: ___ SAT Applicant determines the total amount of dose received for the evolution to ___ UNSAT be 13 mR.

This step is critical to meet the task requirements and standard for this JPM to determine the total amount of dose received.

COMMENTS:

PAGE 4 0F 6

Catawba Nuclear Station Admin. JPM A.3R September 2021 NRC Exam STEP / STANDARD SAT /

UNSAT STEP 2 Determine allowable time in room following venting activity.

CRITICAL The RWP limits total exposure to 25 mR STEP 25 mR x 80% = 20 mR total allowable dose 20 mR - 13 mR (dose following venting) = 7 mR (remaining) 7 mR ÷ 10 mR/hr = 0.7 hr (42 minutes)

STANDARD:

Applicant determines they can remain in the room another 42 minutes, or ___ SAT until 0854.

___UNSAT This step is critical to meet the task requirements and standard for this JPM to determine the latest time that venting could complete without exceeding RWP dose requirements.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 5 0F 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:

• Unit 1 has entered AP/1/A/5500/019 (Loss of Residual Heat Removal)

• The CRS has dispatched an AO to 1A ND pump room to vent the 1A ND pump casing when directed.

• The AO has staged himself to minimize dose while waiting.

• The following is the timeline for the venting evolution:

0730 - AO enters 1A ND Pump Room.

0800 - AO is directed to vent using 1ND-88 (1A ND Pump Seal Water Hx Inlet Vent).

0812 - Venting is complete. AO returns to the LEWA to await further instruction.

INITIATING CUES:

Based on the above time line, RWP # 5021, and Survey Maps provided and discounting any dose received during transit:

1. State the amount of dose that has been received thus far.

Amount of dose received - ________________ mR

2. Following completion of venting activity, calculate how much longer the AO can remain in the room until required to exit (based on exceeding 80% of RWP allowable dose).

Allowable time in room following venting activity - ___________ .

CATAWBA NUCLEAR STATION MONTHLY ROUTINE SURVEY SHEET PERFORMED BY: / DATE/TIME: /

(print name) (initials)

Instrument/#(s) bg Counter/#: Reviewed By:

(initials)

Room 105 ND Pump 1A N

50 40 35 1ND-88 FF 54 10 LEWA T.Cabe 03-02 You Are Here HIGHEST GA*: HIGHEST CONTACT*: HIGHEST dpm/100cm2: K bg HIGHEST MASSLINN CCPM:

• Radiation readings in mRem/hr unless otherwise noted.

LEGEND: LEWA = LOW EXPOSURE WAITING AREA HS = HOT SPOT --x----x----x-- = RCZ BOUNDARY

= DIRECT = GENERAL = CONTACT = SMEAR = MASSLINN FRISK (dpm/100cm2) .

AREA >

Comments:

RWP#15

CATAWBA NUCLEAR STATION MONTHLY ROUTINE SURVEY SHEET PERFORMED BY: / DATE/TIME: /

(print name) (initials)

Instrument/#(s) bg Counter/#: Reviewed By:

(initials) 124 84 140 2ND-88 15 LEWA You Are Here HIGHEST GA*: HIGHEST CONTACT*: HIGHEST dpm/100cm2: K bg HIGHEST MASSLINN CCPM:

• Radiation readings in mRem/hr unless otherwise noted.

LEGEND: LEWA = LOW EXPOSURE WAITING AREA HS = HOT SPOT --x----x----x-- = RCZ BOUNDARY

= DIRECT = GENERAL = CONTACT = SMEAR = MASSLINN FRISK (dpm/100cm2) .

Comments:

RWP#15

INFORMATION Catawba Nuclear Station INFORMATION USE ONLY Radiation Work Permit USE ONLY AUX BUILDING ENTRY INTO PENTRATION ROOMS HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM RWP # 5021 Rev: 11 VENTING ON ECCS SYSTEMS Task # 1 AUX BUILDING ENTRY INTO PENTRATION ROOMS, HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMS ED Alarm Set Points:

Dose Alarm: 25 mrem Dose Rate Alarm: 50 mrem/hr RWP Requirements Dress Category/Work Description

• Dress Category "F" 1. Complete protection of skin and clothing is NOT required. 2. Radioactive material is handled and/or transported AND the potential for loose surface contamination >1000 dpm/100cm2 exists AND durability of surgical gloves is sufficient.

• E Dress Category "G" Entry into dry contaminated areas <25,000 dpm/100cm2 with NO climbing or physical / strenuous work. NO brushing, grinding, lapping, etc. is allowed.

• Dress Category "H" Entry into dry contaminated areas <25,000 dpm/100cm2 with NO climbing or physical / strenuous work. NO brushing, grinding, lapping, etc. is allowed.

• Dress Category "I" Work in dry contaminated areas <50,000 dpm/100cm2 with a risk of puncturing or tearing gloves or beta dose concerns to the hands. Work may involve brushing, grinding, lapping, etc. (1) (3) (4)

• Dress Category "N" Wet work, hot particle controls are required or work in highly contaminated areas. Work may involve brushing, grinding, lapping, etc. (1)

• Dress Category "Z" Special dress. See Additional Instructions.

• Modesty garments, top & bottom, are required under protective clothing where personal outer clothing is not worn

• (1) Cloth coverall are acceptable for use when allowed by RP. Gloves and booties must be secured (e.g. taped, elastic cuff) when wearing cloth coveralls

• (2) IF double SOP is not used when wearing double PCs, remove the outer layers at the source

• (3) Skull caps may be substituted for a hood when approved by RP and NO hands on work is to be performed.

• (4) For activities requiring crawling, kneeling, etc., review need for additional barrier to prevent contamination events, e.g., additional protective clothing, knee pads, use of floor covering, etc.

Protective Clothing

• F - Lab coat, glove liners, rubber gloves OR surgical gloves, booties and shoe covers

• G - Hood, coveralls, glove liners and rubber gloves, booties, and shoe covers over personal clothing (NO modesty clothing required).

• H - Hood, coveralls, glove liners and rubber gloves, booties and shoe covers, NO personal outer clothing.

• I - Hood, coveralls, glove liners, 2 pair rubber gloves, booties and shoe covers, no personal outer clothing.

• N - Hood, coveralls, water resistant/water proof suit, glove liners, 2 pair rubber gloves, booties, 2 pair shoe covers, no personal outer clothing.

• Z - Special dress Contamination Control

• Wipe down AND bag all tools and equipment prior to removal from a contaminated area as directed by RP

• Utilize facial protection (e.g. face shield, hood sock, power visor) as directed by RP

• Install catch containments OR drain rigs to prevent spills if draining components

• If installing a drain rig, use hose clamps to secure hose OR tubing connections

• If installing a drain rig, secure hose OR tubing to floor drain

• Wear disposable (plastic) booties inside of orex booties for work in wet conditions

• Change outer rubber gloves often when handling highly contaminated material as directed by RP Approved on 09/01/2019 by CAMPBELL, KENNETH C Printed on 09/01/2019 Activated on 09/01/2019

INFORMATION Catawba Nuclear Station INFORMATION USE ONLY Radiation Work Permit USE ONLY AUX BUILDING ENTRY INTO PENTRATION ROOMS HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM RWP # 5021 Rev: 11 VENTING ON ECCS SYSTEMS Task # 1 AUX BUILDING ENTRY INTO PENTRATION ROOMS, HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMS ED Alarm Set Points:

Dose Alarm: 25 mrem Dose Rate Alarm: 50 mrem/hr RWP Requirements

• Use surgical gloves in lieu of rubber gloves for the manipulation of small or specialty items as directed by RP RP Job Coverage

• Start of Job, Intermittent or No Coverage In Radiation Areas or Less

• RP Coverage Required To Transport Material > 5 mrem/hr at 30 cm

• Pre-job briefing required

• Continuous RP Coverage for aggressive work in Alpha Level III areas or Alpha Level II areas with beta-gamma to alpha ratios less than 3000:1 or where conditions could change Dosimetry Requirements

• Monitor ED periodically while inside the RCA/RCZ (once or twice per hour in low dose rate areas). Monitor more frequently in higher dose rate areas, for example every 10 to 15 minutes.

• If dress requirements prevent the monitoring of ED, and RP is not remotely monitoring (via teledose & communications), place ED external to the outmost layer of protective clothing for monitoring Respiratory Protection

• If weighted DAC-Hours are expected to result in greater than or equal to 4 DAC-Hours per person, perform a TEDE/ALARA evaluation

• Full Face Particulate (Additional Hood Required) IF warranted by TEDE ALARA Evaluation OR directed by RP

• Personal (lapel) air samplers required for Alpha Level III areas or Alpha Level II areas with beta-gamma to alpha ratios of less than 3000:1 RP Hold Points

• Breaching Contaminated System

• RP Survey Required Prior to Handling Debris or Foreign Material

• RP survey required after removal of items from contaminated systems. Decon may be necessary (as directed by RP)

• Notify RP prior to reaching OR entry into the overhead (8 feet and above)

• Accumulated Dose Higher than Expected

• Notify RP Prior to Start of Work

• A change in Alpha Level (AL I to AL II or AL III; AL II to AL III) requires additional planning for alpha considerations Stop Work Criteria

• Dose Alarm

• Unexpected dose rate alarm

• Airborne conditions higher than expected

• Actual dose rates are higher than the expected levels written on this RWP task

• Actual contamination levels are higher than the expected levels written on this RWP task Approved on 09/01/2019 by CAMPBELL, KENNETH C Printed on 09/01/2019 Activated on 09/01/2019

INFORMATION Catawba Nuclear Station INFORMATION USE ONLY Radiation Work Permit USE ONLY AUX BUILDING ENTRY INTO PENTRATION ROOMS HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM RWP # 5021 Rev: 11 VENTING ON ECCS SYSTEMS Task # 1 AUX BUILDING ENTRY INTO PENTRATION ROOMS, HEAT EXCHANGER ROOMS AND PUMP ROOMS TO PERFORM VENTING ON ECCS SYSTEMS ED Alarm Set Points:

Dose Alarm: 25 mrem Dose Rate Alarm: 50 mrem/hr RWP Requirements

• Unexpected wet conditions

• Work scope changes

• If monitoring of the ED indicates that the dose alarm set point will be exceeded prior to completing the job, leave the area and contact RP. Do not wait to receive an alarm before exiting the area

• Failure of OR sweat soaked protective clothing Expected Radiological Conditions Expected radiological conditions:

General Area Dose Rates: <0.1 mrem/hr - 50 mrem/hr High Contact Dose Rates: <0.1 mrem/hr - 1000 mrem/hr Contamination Levels: < 1000 dpm/100cm2- 100,000 dpm/100cm2 Additional Instructions Electronic Dosimeter rate alarms are established based on general area dose rates. If personnel are positioned in close proximity to primary piping and equipment they may anticipate receiving a dose rate alarm.

Z Dress - Orex Coveralls only. This is for use in clean areas only due to potential for contamination from wearing a fall harness.

Approved on 09/01/2019 by CAMPBELL, KENNETH C Printed on 09/01/2019 Activated on 09/01/2019

Catawba Nuclear Station Admin. JPM A.1-1S Sept 2021 NRC Exam JPM A.1-1S SRO PAGE 1 OF 13

Catawba Nuclear Station Admin. JPM A.1-1S Sept 2021 NRC Exam EVALUATION SHEET Task: Calculate Boric Acid and Water Addition to FWST and determine Tech Spec actions.

Alternate Path: N/A Facility JPM #: 2017 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.1-1S Sept 2021 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:

Per OP/1/A/6200/014 (Refueling Water System) Enclosure 4.4, steps 3.1 - 3.4, determine the quantity of Boric Acid and RMWST Water required for 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:

PAGE 3 OF 13

PAGE 4 0F 13 Catawba Nuclear Station Admin. JPM A.1-1S Sept 2021 NRC Exam 1100:

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.1-1S Sept 2021 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.1-1S Sept 2021 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.1-1S Sept 2021 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.1-1S Sept 2021 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.1-1S Sept 2021 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.1-1S Sept 2021 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.1-1S Sept 2021 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.1-1S Sept 2021 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. Per OP/1/A/6200/014 (Refueling Water System) Enclosure 4.4, steps 3.1 - 3.4, determine the quantity of Boric Acid and RMWST Water required for 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:

Catawba Nuclear Station Admin. JPM A.1-1S Sept 2021 NRC Exam REFERENCE HANDOUT

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 1 of 11

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 Ensure Reactivity Management controls for an R3 evolution are established per AD-OP-ALL-0203 (Reactivity Management).

_____ 2.2 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)

OR Recirculation per Enclosure 4.6 (FWST Recirculation)

_____ 2.3 Verify boron concentration control systems are available per OP/1/A/6150/009 (Boron Concentration Control).

_____ 2.4 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.

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 2 of 11

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}:

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}:

_____________ 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 (C f) to attain the final boron concentration, CFW.

3.3.1 Initial volume of FWST _______ = Vi.

3.3.2 Final volume of FWST after makeup _______ = VFW.

3.3.3 Compute the total gallons of makeup water to be added to the FWST

_________ = Vf.

Vf = VFW - Vi 3.3.4 Initial boron concentration of water in the FWST ______ = C i.

3.3.5 Solve for the desired makeup water boron concentration, C f.

CFW VFW - Ci Vi Cf = Cf =

Vf

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 3 of 11

_____ _____ 3.4 Determine the amount of boric acid and reactor makeup water to add as follows:

3.4.1 Boron Concentration of water in BAT _________ = C 1.

3.4.2 Boron concentration of water in RMWST __________ = C 2.

3.4.3 Total gallons of makeup water to be added to FWST ________ = V f 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)

V1 = V1 =

C1 - C2

_____ 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 (V 2).

V2 = Vf - V1 V2 = _________ gal.

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 4 of 11 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'd 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

_____ _____ 3.6 Determine the final counter readings as follows:

3.6.1 Initial TOTAL MAKEUP COUNTER reading ________ = T mi.

3.6.2 Initial BORIC ACID COUNTER reading ________ = T Bi.

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 = ____________

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 5 of 11 3.7 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) 3.8 Set the following blender flow controllers to achieve the desired boron concentration and volume:

_____ 1NV-238A (B/A To Blender Ctrl Vlv)

_____ 1NV-242A (RMWST To B/A Blender Ctrl) 3.9 Ensure the selector switches for the following valves are in "AUTO":

_____ 1NV-238A (B/A To Blender Ctrl Vlv)

_____ 1NV-242A (RMWST To B/A Blender Ctrl) 3.10 Set the following counters to achieve the desired boron concentration and volume:

_____ BORIC ACID

_____ TOTAL MAKEUP

_____ _____ 3.11 Verify 1NI-96B (C-Leg Accum Chk Vlv Tst Isol) is closed.

_____ 3.12 Verify 1NB-5 (Unit 1 VCT To NB Evap Feed Demin Isol) (1ELCC0024) (AB-560, MM-52) is closed.

_____ 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 IF the FWST is in recirculation alignment per one of the following enclosures:

Enclosure 4.6 (FWST Recirculation)

OR Enclosure 4.5 (FWST Purification)

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 6 of 11 THEN perform the following:

_____ 3.15.1 Secure the "FW PUMP".

Record FW Pump stop time. ____________

3.15.2 Start the FW recirc pump secured in Enclosure 4.5 (FWST Purification) OR Enclosure 4.6 (FWST Recirculation).

_____ FW Recirc Pump 1A

_____ FW Recirc Pump 1B

_____ 3.16 Place "NC MAKEUP MODE SELECT" switch in the "MANUAL" position.

3.17 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" 3.18 Ensure the Reactor Makeup Water Pump NOT selected to "AUTO" in Step 3.17 is in "OFF":

_____ "RX M/U WTR PUMP 1A" OR

_____ "RX M/U WTR PUMP 1B" 3.19 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"

_____ 3.20 IF a Boric Acid Transfer Pump was NOT selected to "AUTO" in Step 3.19, 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 7 of 11

_____ 3.21 IF Unit 1 is in Mode 1, 2, 3 or 4, perform the following:

_____ 3.21.1 Step 3.21.2 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 ___________________________________

_____ 3.21.2 IF AT ANY TIME while FWST makeup is in progress a Safety Injection occurs on Unit 1, terminate the makeup by performing the following:

_____ 3.21.2.1 Turn the "NC MAKEUP CONTROL" switch to the "STOP" position.

3.21.2.2 Ensure the following:

_____ Selected Reactor Makeup Water Pump stops.

_____ 1NV-238A (B/A To Blender Ctrl Vlv) closes.

_____ 1NV-242A (RMWST To B/A Blender Ctrl) closes.

_____ 3.22 Energize makeup control circuit by turning the "NC MAKEUP CONTROL" switch to the "START" position.

3.23 Ensure the following:

_____ Selected Reactor Makeup Water Pump starts.

_____ Selected Boric Acid Transfer Pump starts.

_____ 1NV-238A (B/A To Blender Ctrl Vlv) positions to produce desired boric acid flow.

_____ 1NV-242A (RMWST To B/A Blender Ctrl) positions to produce desired total makeup flow.

_____ 3.24 WHEN makeup is complete, turn the "NC MAKEUP CONTROL" switch to the "STOP" position.

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 8 of 11 3.25 Ensure the following:

_____ Selected Reactor Makeup Water Pump stops.

_____ Selected Boric Acid Transfer Pump stops.

_____ 1NV-238A (B/A To Blender Ctrl Vlv) closes.

_____ 1NV-242A (RMWST To B/A Blender Ctrl) closes.

3.26 Flush the flowpath for one minute as follows:

3.26.1 Place both Boric Acid Transfer Pumps in "OFF".

_____ "B/A XFER PUMP 1A"

_____ "B/A XFER PUMP 1B"

_____ 3.26.2 Place the selector switch for 1NV-238A (B/A To Blender Ctrl Vlv) in the "CLOSED" position.

_____ 3.26.3 Place the selector switch for 1NV-242A (RMWST To B/A Blender Ctrl) in the "OPEN" position.

_____ 3.26.4 Turn the "NC MAKEUP CONTROL" switch to the "START" position.

3.26.5 Ensure the following:

_____ Selected Reactor Makeup Water Pump starts.

_____ Total makeup flow indicates flow.

_____ 3.26.6 WHEN flushing is completed, turn the "NC MAKEUP CONTROL" switch to the "STOP" position.

3.26.7 Ensure the following:

_____ Selected Reactor Makeup Water Pump stops.

_____ Total makeup flow indicates no flow.

3.27 Place the selector switches for the following valves in "AUTO":

_____ 1NV-238A (B/A To Blender Ctrl Vlv)

_____ 1NV-242A (RMWST To B/A Blender Ctrl)

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 9 of 11 3.28 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)

_____ 3.29 Open 1NV-187 (Boric Acid Blender Outlet To VCT Outlet Isol) (AB-583, KK-50, Rm 419).

3.30 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"

_____ 3.31 IF needed to support plant conditions, place desired Boric Acid Transfer Pump in "ON":

_____ "B/A XFER PUMP 1A"

_____ "B/A XFER PUMP 1B"

_____ 3.32 IF desired, place the second Reactor Makeup Water Pump in "AUTO":

_____ "RX M/U WTR PUMP 1A"

_____ "RX M/U WTR PUMP 1B"

_____ 3.33 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" 3.34 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)

_____ 3.35 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 10 of 11

_____ 3.36 IF Step 3.15 was performed, THEN perform the following:

_____ 3.36.1 Secure the FW recirc pump started in Step 3.15.2.

_____ 3.36.2 Start the "FW PUMP".

Record FW Pump start time. ____________

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.

_____ 3.37 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.

_____ 3.37.1 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.

_____ 3.37.2 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).

_____ 3.37.3 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).

Enclosure 4.4 OP/1/A/6200/014 FWST Makeup From Blender Page 11 of 11 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.

IF Step 3.36 was performed, Step 3.38.1 may be N/A'd.

_____ 3.38 IF FWST was NOT recirculated with the NS pump, perform the following:

_____ 3.38.1 Place the FWST in recirculation per one of the following:

_____ Enclosure 4.6 (FWST Recirculation).

OR

_____ Enclosure 4.5 (FWST Purification).

_____ 3.38.2 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).

3.39 Do NOT file this enclosure.

NRC JPM A.1-1S KEY Enclosure 4.4 OP/l/A/6200/01 4 FWST Makeup From Blender Page 2 of 1 1

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 N otifyChemistry that the following Boric Acid Tank will be used for Tech Spec blending calculations {PIP 91-0449}:

Person notified Steph Jackson X

---

Boric Acid Tank #1

---

Boric Acid Tank #2 3.2 Document current boron concentration in the Boric Acid Tank as specified byChemistry in Step 3.1 {PIP 91-0449}:

7500 ppmB NOTE: The final boron concentration used in the next step shall comply withCOLR requirements for the current mode of operation.

3.3 Determine the boron concentration of the makeup water to the FWST (Cr) to attain the final boron concentration,CFW.

3.3.1 Initial volume ofFWST373,875=Vi.

3.3.2 Final volume ofFWST after makeup377,646=VFW.

3.3.3 Compute the total gallons of makeup water to be added to the FWST 3,771 =V f.

Vr =VFW-Vi 3.3.4 Initial boron concentration of water in the FWST 2,740 =Ci.

3.3.5 Solve for the desired makeup water boron concentration,C f.

CFWVFW-CiVi Cr =------- Cr =(2,720)(377,646)-(2,740)(373,875)

Vr 3771

=737.1 NRC JPM A.1-1S KEY

Catawba Nuclear Station Admin. JPM A.1-2S Sept 2021 NRC Exam JPM A.1-2 S SRO

Catawba Nuclear Station Admin. JPM A.1-2S Sept 2021 NRC Exam EVALUATION SHEET Task: Determine License Status Alternate Path: N/A Facility JPM #: NS07-001 Safety Function: N/A K/A 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical records, no-solo operation, maintenance of active license status.

Importance: 3.3 / 3.8 CFR: 41.10 / 43.2 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate

References:

AD-OP-ALL-0107 Maintenance of RO and SRO Licenses Task Standard: Applicant determines that RP Jones is eligible to work the CRS position on July 1, 2021, while Mike Starnes and Will Fowler are NOT eligible as actively licensed SROs for this shift.

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

Catawba Nuclear Station Admin. JPM A.1-2S Sept 2021 NRC Exam 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 evaluating the work histories of three Licensed Senior Reactor Operators.

• All three have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years.

• All three operators have worked ONLY the shifts listed for the second quarter of 2021.

• Active/Inactive status and time on shift since April 1, 2021 is as follows for each of the Senior Reactor Operators: (Work History Table Provided)

• Unit Power History o Unit 1 has remained in MODE 1 since 04/01/21 o Unit 2 entered a refueling outage on 05/04/21 and was in NO MODE from 05/15/21 - 05/22/21.

INITIATING CUES:

• Determine if each of the Senior Reactor Operators is eligible to work the CRS position on the 0700 - 1900 shift on July 1, 2021.

• Record your answer below (yes or no). If no, explain why.

Mike Starnes:

Will Fowler:

RP Jones:

EXAMINER NOTE:

After reading cue, provide applicant with a copy of AD-OP-ALL-0107 and the Work History Table provided with this JPM.

Catawba Nuclear Station Admin. JPM A.1-2S Sept 2021 NRC Exam START TIME: _________

STEP 1: Determine the Active/Inactive status of Mike Starness CRITICAL SRO License: STEP STANDARD:

From the cue, the applicant reviews the requirements of AD-OP-ALL-0107 and determines that this license is INACTIVE

• 04/02/21, 04/03/21, 05/05/21, & 05/06/21 watches met 4 of the 5 required.

• 05/21/21 watch did not count because the applicable unit was not in a required mode.

• 04/04/21 & 06/17/21 watches were not in required position. Sat __

Examiner Note: This step is critical because determining Unsat __

that Mike Starnes is NOT eligible to work, at the CRS position, on July 1, 2021 is necessary to complete the assigned task.

COMMENTS:

Catawba Nuclear Station Admin. JPM A.1-2S Sept 2021 NRC Exam STEP 2: Determine the Active/Inactive status of Will Fowlers CRITICAL SRO License: STEP STANDARD:

From the cue, the applicant reviews the requirements of AD-OP-ALL-0107 and determines that this license is INACTIVE

• 04/01/21, 04/03/21, 04/05/21, & 04/14/21 watches met 4 of the 5 required.

• 04/02/21 watch did not count because it did not constitute a full 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift.

• 05/02/21 watch was not in required position. Sat __

Examiner Note: This step is critical because determining Unsat __

that Will Fowler is NOT eligible to work, at the CRS position, on July 1, 2021 is necessary to complete the assigned task.

COMMENTS:

Catawba Nuclear Station Admin. JPM A.1-2S Sept 2021 NRC Exam STEP 3: Determine the Active/Inactive status of RP Jones CRITICAL SRO License: STEP STANDARD:

• From the cue, the applicant reviews the requirements of AD-OP-ALL-0107 and determines that this license is ACTIVE. Although 5 complete watches were not completed within the required positions and unit modes, the five 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> proficiency watches are not required to be performed in a quarter where reactivation is accomplished.

Sat __

Examiner Note: This step is critical because determining that RP Jones is eligible to work, at the Unsat __

CRS position, on July 1, 2021 is necessary to complete the assigned task.

COMMENTS:

END TIME: __________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

• You are evaluating the work histories of three Licensed Senior Reactor Operators.

• All three have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the past 2 years.

• All three operators have worked ONLY the shifts listed for the second quarter of 2021.

• Active/Inactive status and time on shift since April 1, 2021 is as follows for each of the Senior Reactor Operators: (Work History Table Provided)

• Unit Power History o Unit 1 has remained in MODE 1 since 04/01/21 o Unit 2 entered a refueling outage on 05/04/21 and was in NO MODE from 05/15/21 - 05/22/21.

INITIATING CUES:

• Determine if each of the Senior Reactor Operators is eligible to work the CRS position on the 0700 - 1900 shift on July 1, 2021.

• Record your answer below (yes or no). If no, explain why.

Mike Starnes:

Will Fowler:

RP Jones:

(RETURN TO EXAMINER UPON COMPLETION OF TASK)

Mike License was active on April 1, 2021.

Starnes 04/02/21 Worked 0700-1900 shift as CRS.

04/03/21 Worked 0700-1900 shift as Unit 1 OATC.

04/04/21 Worked 0700-1900 shift as Unit 1 Supervisor 05/05/21 Worked 0700-1900 shift as Unit 2 BOP.

05/06/21 Worked 0700-1900 shift as Unit 2 OATC.

05/21/21 Worked 1900-0700 shift as Unit 2 BOP.

06/17/21 Worked 1900-0700 shift as STA.

Will License was active on April 1, 2021.

Fowler 04/01/21 Worked 0700-1900 shift as CRS.

04/02/21 Worked 0700-1500 shift as CRS.

04/03/21 Worked 0700-1900 shift as CRS.

04/05/21 Worked 0700-1900 shift as CRS.

04/14/21 Worked 1900-0700 shift as SM.

05/02/21 Worked 0700-1900 shift as Unit 1 Supervisor RP License was inactive on April 1, 2021.

Jones 04/05/21 thru 04/09/21 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the CRS and completed all requirements for license reactivation.

04/12/21 Worked 0700-1900 shift as Unit 2 BOP.

04/13/21 Worked 0700-1900 shift as Unit 1 BOP.

05/16/21 Worked 0700-1900 shift as Unit 2 OATC.

05/18/21 Worked 1900-0700 shift as Unit 1 BOP.

05/20/21 Worked 1900-0700 shift as Unit 1 OATC.

Information Use NUCLEAR OPERATING FLEET ADMINISTRATIVE PROCEDURE AD-OP-ALL-0107 MAINTENANCE OF RO AND SRO LICENSES REVISION 3 Effective Dates:

07/01/2020 07/01/2020 07/01/2020 07/01/2020 07/01/2020 Brunswick Catawba Harris (HNP) McGuire Oconee 07/01/2020 07/01/2020 Robinson NGO

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 2 of 54 REVISION

SUMMARY

PRR 02321909 DESCRIPTION Section 3.0.3, sub-bullet: Added guidance for using licensee as an interchangeable term for Licensed Operator.

Section 4.4.1: Revised to incorporate participation in the requalification program.

Section 4.5 and Section 5.7.2: Revised 'Supervisor' to 'Superintendent'.

Section 5.2: Added section and associated guidance for Maintaining Required License Obligations (PRR 02280803 and PRR 02312224).

Section 5.3.1.a: Added guidance for Licensed Operators who will not attend training in accordance with AD-TQ-ALL-0068 (PRR 02280803).

Section 5.5.7 and sub-steps: Deleted guidance for maintaining a Shift Manager proficiency. , Step 6.a: Updated CNS and MNS NLMS codes (PRR 02300605 and PRR 02315136). , Step 6.a: Revised Requalification Training Supervisor to Operations Training Superintendent. , Step 8: Revised to incorporate 'NLMS', and revised RP Staff Representative to Licensed Operator (PRR 02320845). , Step 12: Revised Ops Training Manager to Ops Training Superintendent (PRR 02270855). , Step 15.a: Updated CNS and MNS NLMS codes (PRR 02300605 and PRR 02315136). , Table 8: Revised to delete WGDT room, revised 'AFP Hx to SFP Hx', and revised 'all levels' to 'level 1 and 2'.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 3 of 54 TABLE OF CONTENTS SECTION .......................................................................................................................... PAGE 1.0 PURPOSE ..................................................................................................................... 5 2.0 SCOPE .......................................................................................................................... 5 3.0 DEFINITIONS ................................................................................................................ 5 4.0 RESPONSIBILITIES ...................................................................................................... 6 5.0 INSTRUCTIONS ............................................................................................................ 9 5.1 Processing NRC License Applications .......................................................................... 9 5.2 Maintaining Required License Obligations..................................................................... 9 5.3 Maintaining Required Licensed Requalification Training Status .................................. 11 5.4 Medical Reporting Requirements ................................................................................ 11 5.4.1 General .......................................................................................................... 11 5.4.2 Medical Examination Process ........................................................................ 13 5.4.3 Medical Status Changes ................................................................................ 16 5.4.4 Medical Restrictions Follow-Up ...................................................................... 19 5.5 Maintaining Required On-Shift Experience (Proficiency) For Licensed Operators..................................................................................................................... 20 5.6 Activation of a New or Inactive License ....................................................................... 22 5.7 Removing a Licensed Operator From Duty for Other Than Medical or Requalification Training Status .................................................................................... 22 5.8 Activating an SRO License For Fuel Handling/Core Alterations Only .......................... 23 5.9 [CNS] Licensed Operators Qualification Report (LOQR) ............................................. 23 6.0 RECORDS................................................................................................................... 24

7.0 REFERENCES

............................................................................................................ 25 ATTACHMENTS 1 Operating Experience Maintenance For Active Licensed Operators ........................... 27 2 Activation of New or Inactive License .......................................................................... 29 3 Change In Medical Condition Affecting License Status ............................................... 40 4 Notification Of Change In Operator Status {7.1.2} ....................................................... 44 5 Common Medical Status Changes/Conditions of Licensed Operators ........................ 48

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 4 of 54 TABLE OF CONTENTS (continued)

SECTION .......................................................................................................................... PAGE ATTACHMENTS 6 Activation Of An SRO License For Fuel Handling/Core Alterations Only .................... 53

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 5 of 54 1.0 PURPOSE

1. This procedure provides guidance for maintaining and reactivating NRC Senior Reactor Operator (SRO), Reactor Operator (RO), and Limited Senior Reactor Operator (LSRO) licenses pursuant to 10 CFR Part 55, Operators' Licenses.

2.0 SCOPE

1. This procedure provides the following instructions:

Processing NRC license applications Maintaining required licensed requalification training status Maintaining required Licensed Operator medical status Maintaining required on-shift experience for Licensed Operators Certification of a new or inactive license Removing a Licensed Operator from duty for other than medical or requalification training status Activating an SRO license for fuel handling/core alterations only

2. This procedure applies to NRC licensed personnel at all operating Duke Energy nuclear sites.

3.0 DEFINITIONS

1. Active Licensed Operator Position(s): Positions that meet the NRC definition of "actively performing the duties of a Reactor Operator or Senior Reactor Operator". The following are required to be filled by individuals with active licenses, and are the only positions that can be credited for maintaining required on shift experience for Licensed Operator(s).

Shift Manager (SRO)

Control Room Supervisor (SRO)

Operator at the Controls (RO)

Balance of Plant Operator (RO)

2. Duke Energy Medical Information (DEMI): Database used by Duke Energy Occupational Health (OH) to store employee medical data.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 6 of 54 3.0 DEFINITIONS (continued)

3. Licensed Operator(s): An individual who has obtained a license issued by the Nuclear Regulatory Commission to perform the function of a Reactor Operator or Senior Reactor Operator as defined in 10 CFR 55.

Licensed Operator(s) are an interchangeable term to 'licensee' in 10 CFR 55 and in this procedure.

4. Licensed Operator Qualification Report (LOQR): A report used to track specific RO and SRO license attribute status.

5. Limited Senior Reactor Operator (LSRO): A SRO limited to fuel handling/core alteration activities only. LSROs are not required to maintain proficiency between refueling outages.

6. Medical Conditions of Concern: A new or change in medical condition (physical or mental), illness, or injury that might affect the physical or mental ability of a Licensed Operator to perform required licensed duties.

7. No Solo: Operator license restriction that requires another qualified person to be present when the restricted operator is operating or directing the operation of the controls, during all modes of operation including emergency conditions.

8. Qualified Occupational Health (OH) Personnel: Physicians and nurses employed or contracted by Duke Energy 4.0 RESPONSIBILITIES 4.1 Operations Management

1. Ensures the status and capability of Licensed Operators to perform licensed duties.

4.2 Assistant Operations Manager - Shift (AOM-Shift) or Designee

1. Ensures Licensed Operators filling Active Licensed Operator Position(s) have the opportunity to perform a minimum of five 12-hour shifts per calendar quarter.

2. Certifies Licensed Operators who are ready to resume the responsibilities of an on-shift Licensed Operator position.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 7 of 54 4.3 Shift Managers (SMs)

1. Ensures all Licensed Operators standing watch hold an active license for that position.

2. Communicates operator license status changes to the organizations identified in this procedure.

4.4 Licensed Operators

1. Understands and fulfills NRC license obligations, including participation in the operator requalification program, issued under 10 CFR 55.

2. Understands status in regards to fulfilling Licensed Operator duties.

3. Ensures immediate supervisor and qualified Occupational Health personnel are made aware of any changes in:

Prescription medication use Changes in medical status 4.5 Superintendent Nuclear Operations Training

1. Notifies the on duty SM when a Licensed Operator fails to meet the requirements of the requalification program.

2. Ensures Licensed Operators who fail to meet the requirements of the requalification program are disqualified from Nuclear Learning Management System (NLMS) activities per AD-TQ-ALL-0660, Use and Administration of the Nuclear Learning Management System (NLMS). {7.1.1}

4.6 Regulatory Affairs

1. Generates and submits all regulatory required correspondence per 10 CFR 55 in accordance with the requirements of AD-LS-ALL-0002, Regulatory Correspondence.

2. Coordinates with Occupational Health personnel on reportability determination per 10 CFR 55.23.

3. Coordinates with Operations Management on reportability determination per 10 CFR 50.74(a)(b).

4.7 Corporate Medical Director (CMD)

1. Establishes and oversees the medical components of the OH program.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 8 of 54 4.8 Examining Physician (SEP)

1. Reviews test results, performs medical examinations, and performs consultations for nuclear plant sites.

4.9 Qualified Occupational Health Personnel

1. Performs evaluations on Licensed Operator(s) when informed of changes to their medical status.

2. Provides evaluations to Operations Management concerning the ability of Licensed Operators to perform duties while taking prescription or non-prescription medications.

3. Performs biennial medical examinations per ANSI/ANS 3.4/1983.

4. Provides written documentation to Regulatory Affairs for submittal to the NRC as required by ANSI/ANS 3.4/1983.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 9 of 54 5.0 INSTRUCTIONS 5.1 Processing NRC License Applications

1. Refer to AD-TQ-ALL-0610, NRC License Application Process, for guidance associated with initial and renewal license applications, waiver requests, and associated NRC correspondence.

2. Expiration of Operator NRC licenses is governed by 10 CFR 55.55, Expiration, which states the following:

Each Operator License and Senior Operator License expires six years after the date of issuance, upon termination of employment with the facility licensee, or upon determination by the facility licensee that the licensed individual no longer needs to maintain a license.

If a licensee files an application for renewal or an upgrade of an existing license on Form NRC-398 at least 30 days before the expiration of the existing license, it does not expire until disposition of the application for renewal or for an upgraded license has been finally determined by the Commission. Filing by mail will be deemed to be complete at the time the application is deposited in the mail.

5.2 Maintaining Required License Obligations NOTE The obligations in this procedure are paraphrased requirements in 10 CFR 55.

1. All Licensed Operators shall meet the following requirements:

Neither the license nor any right under the license may be assigned or otherwise transferred.

The license is limited to the facility for which it is issued.

The license is limited to those controls of the facility specified in the license.

The license is subject to, and the licensee shall observe, all applicable rules, regulations, and orders of the Nuclear Regulatory Commission.

Maintain on-shift operating experience (i.e., active license) in accordance with Section 5.5.

If on-shift operating experience is not maintained, then prior to resumption of functions authorized by the license, refer to Section 5.6 to regain an active license.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 10 of 54 5.2 Maintaining Required License Obligations (continued)

The licensee shall notify the Nuclear Regulatory Commission within 30 days about a conviction for a felony.

The licensee shall complete a requalification program as described by

§55.59.

Compliance of 55.99 is verified by Section 5.3.

The licensee shall have a biennial medical examination.

Medical requirements shall be maintained in accordance with Section 5.4.

The licensee shall be Fit-for-Duty and shall NOT perform activities authorized by the license while under the influence of alcohol or any prescription, over-the-counter, or illegal substance that could adversely affect the licensees ability to safely and competently perform licensed duties.

The consumption, sale, or use of alcohol or illegal substances is prohibited in the protected area.

The licensee shall participate in the drug and alcohol testing program established pursuant to 10 CFR Part 26.

The licensee shall comply with any other conditions that the Commission may impose to protect health or to minimize damage to life or property.

2. If any of the following conditions exist for a Licensed Operator, then terminate the license by processing Attachment 4, Notification Of Change In Operator Status {7.1.2}:

Licensed Operator transfers to a new position in which maintaining the license is NOT desired.

Licensed Operator transfers to a different company.

Licensed Operator is no longer employed by the company.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 11 of 54 5.3 Maintaining Required Licensed Requalification Training Status

1. All Licensed Operators must comply with the requirements of the AD-TQ-ALL-0068, Licensed Operator Continuing Training Program.

a. If a Licensed Operator is reassigned to a position that does NOT require a license AND will NOT attend training in accordance with AD-TQ-ALL-0068, Licensed Operator Continuing Training Program, then process Attachment 4, Notification Of Change In Operator Status {7.1.2},

to terminate the Licensed Operator's license.

b. If a Licensed Operator has failed to meet Licensed Operator qualification requirements, then Operations Training shall disqualify the Licensed Operator from licensed duties in accordance with AD-TQ-ALL-0660, Use and Administration of the Nuclear Learning Management System (NLMS).

5.4 Medical Reporting Requirements 5.4.1 General

1. The reporting requirements for medical changes contained in this procedure apply to all Active and Inactive Licensed Operators

2. Licensed Operators are required to meet the medical requirements contained in ADMP-SAF-HSF-00091, Occupational Health Programs.

3. The OH Department will initiate notifications for changes in a medical condition that affects the ability of Licensed Operator to perform operator licensed duties in accordance with Attachment 3, Change In Medical Condition Affecting License Status

4. Licensed Operators are required to complete a biennial physical examination per ANSI/ANS 3.4/1983 conducted by the Duke Energy OH facility and the SEP.

a. The expiration date is two years to the end of the month from the examining physician's medical clearance date.

5. Prior to assuming Licensed Operator duties, Licensed Operators are required to report any physical or mental condition that might impair their ability to perform licensed duties to the License Operator's supervisor and to OH personnel.

a. Refer to Attachment 5, Common Medical Status Changes/Conditions of Licensed Operators, for examples of changes in medical conditions.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 12 of 54 5.4.1 General (continued)

6. If a change in physical or mental condition is discovered, the Licensed Operator is required to share the following information with OH personnel:

Specific details of the condition Medications Lab results Treatments Prognosis

7. Notification of a change in physical or mental condition shall be made as soon as the individual has knowledge of the change in condition.

a. Details of the medical condition are not required to be shared with supervision, just the existence of the condition and how it impacts the ability to perform licensed duties.

b. Licensed duties shall not be performed until OH personnel have determined that the Licensed Operator is able to perform licensed duties.

8. If a Licensed Operator receives a new prescription, then the Licensed Operator reports the medications to supervision and OH personnel.

a. If receiving a new prescription, then the Licensed Operator shall ask the prescribing physician if the medication may affect job performance and whether it can be taken while working.

b. Licensed duties shall not be performed until the Licensed Operator has:

Informed Occupational Health personnel Informed the Licensed Operators supervisor OH personnel determines new prescription has no impact on performing licensed duties.

9. Non-prescription medication is not required to be reported to the OH personnel except if side-effects occur (e.g., drowsiness, fatigue, dizziness).

a. Immediately notify OH personnel if side-effects occur upon taking a non-prescription medication.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 13 of 54 5.4.1 General (continued)

10. Supervision shall promptly report any medical condition that results in a restriction being placed on a Licensed Operator by a physician to OH personnel.

11. If a supervisor suspects that a medical condition may have some effect on work (e.g., broken fingers, splints, use of crutches, conditions impacting mobility), then the supervisor shall notify OH personnel even if no restrictions have been placed by a physician.

a. Most minor illnesses (e.g., flu, virus, infection) are not required to be reported to OH personnel.

b. OH personnel will initially evaluate the condition presented to them by supervision and notify the CMD or SEP as appropriate.

c. If required, then the SEP will evaluate and document the condition with a recommendation whether the medical condition should be reported to the NRC.

12. If a change in license restrictions is indicated by a medical condition, then within 30 days, notify the NRC by completing NRC Form 396, Certification of Medical Examination by Facility Licensee.

5.4.2 Medical Examination Process NOTE These instructions apply to initial, license renewal, and periodic medical evaluations.

1. The Licensed Operator's supervisor or designee performs the following:

a. Complete ADMF-SAF-HSF-00004, Facility Operator's Report Form, and ADMF-SAF-HSF-00017, Supervisor's - To Support Nuclear Occupational Medical Evaluations and Surveillances.

(1) To locate ADMF-SAF-HSF-00004 and ADMF-SAF-HSF-00017, perform the following:

(a) Go to the DAE and search under the Shortcuts tab for "FileNet P8 Fusion".

(b) Open FileNet P8 Fusion and select "Enterprise Fusion" (c) Under the search fields, select "Document Number" and type in the desired procedure to view.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 14 of 54 5.4.2 Medical Examination Process (continued)

b. Submits the completed Facility Operator's Report Form and the Supervisor's Statement forms to OH.

c. Promptly forwards ADMF-SAF-HSF-00013, Occupational Medical History Form, and ADMF-SAF-HSF-00009, Audiological History and Examination Form, to the Licensed Operator or applicant.

2. Licensed Operator or applicant performs the following:

a. Promptly responds to Duke Energy Medical Information (DEMI) notification emails.

b. Promptly completes the Occupational Medical History Form and returns it to OH.

(1) The medical examination consists of testing by the OH nurse and a medical examination performed by the physician.

(2) These are normally scheduled at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> apart to allow for the return of lab results.

(3) Contact OH to schedule the medical testing and examination.

3. OH performs the following:

a. Receives and reviews the Facility Operator's Report Form and the Supervisor's Statement for each Licensed Operator or applicant.

b. Schedules medical testing and examinations.

c. Performs medical testing and records the data.

d. Provides medical testing and examination data, the Facility Operator's Report Form, and if applicable, a NRC Form 396 to the SEP.

e. Initiates performance of Attachment 3, Change In Medical Condition Affecting License Status.

f. Completes the NRC Form 396 for permanent medical status changes.

g. Ensures a validation of the medical documents and OH database is performed by another member of OH.

h. Incorporates additional medical information provided by the SEP on the completed NRC Form 396 and forwards it to Regulatory Affairs.

i. Documents medical change in Licensed Operator's medical record.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 15 of 54 5.4.2 Medical Examination Process (continued)

j. Files the original completed forms, and any associated medical documents in the Licensed Operator's medical record.

4. SEP performs the following:

a. Schedules physician examination component of the medical examination and completes the appropriate documentation.

NOTE The discovery date on Attachment 3, Change In Medical Condition Affecting License Status is the date used for calculation of the NRC qualification expiration or for calculation of the 30-day NRC notification requirement for permanent medical changes.

b. If there are changes in the Licensed Operator's temporary or permanent medical status, then:

(1) Informs the Licensed Operator at the time of the medical examination.

(2) Notifies OH.

c. If a permanent medical status change is identified, then a required letter with additional medical information shall be prepared by the SEP with assistance from the OH staff to support the NRC Form 396 submittal.

(1) This information is transmitted to Regulatory Affairs in a sealed envelope marked as CONFIDENTIAL.

(2) Regulatory Affairs may open the sealed envelop to validate the information contained in the letter matches the information provided by the physician.

d. Submits completed medical examination documentation to OH Health.

5. Regulatory Affairs performs the following:

a. Ensures the NRC Form 396 is properly completed.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 16 of 54 5.4.2 Medical Examination Process (continued)

b. If a permanent medical change was identified, then:

Obtains Licensed Operator's signature Obtains Site VPs signatures Submits NRC Form 396 within 30 days of the medical status discovery date A letter with additional medical information may be prepared by the SEP to support the NRC Form 396 submittal. This information will be provided to the NRC in accordance with 10 CFR 2.390.

c. Forwards a copy of the submitted NRC Form 396 to:

Site Training Occupational Health Affected Licensed Operator Licensed Operator's Supervisor 5.4.3 Medical Status Changes NOTE These instructions apply to medical status changes identified independently of the routine or periodic medical examinations for Licensed Operators.

1. If any change occurs in a Licensed Operator's medical condition, then the operator performs the following:

a. Refers to Attachment 5, Common Medical Status Changes/Conditions of Licensed Operators.

b. Prior to performing licensed duties, notifies supervision and OH.

(1) If the operator is unable to notify OH of the change in medical condition, then Operations Management will notify OH.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 17 of 54 5.4.3 Medical Status Changes (continued)

2. OH performs the following upon notification of a potential medical condition change by a Licensed Operator or supervisor:

a. Obtains specific medical information and documentation pertinent to the medical condition change from the Licensed Operator.

b. Notifies SEP or CMD of the medical information obtained and follows the physician's instruction.

c. Notifies the Licensed Operator of the review with the SEP or CMD:

(1) If the physician needs to examine the Licensed Operator, then schedules an appointment with the physician.

(2) If the physician does not need to examine the Licensed Operator, then notifies the Licensed Operator of the physician's opinion.

(3) Documents all actions taken in the Licensed Operator's medical record.

3. SEP or CMD performs the following:

a. Determines the extent of the evaluation needed to make a decision regarding a potential medical condition change.

(1) May require contact between the Licensed Operator or the Licensed Operator's personal medical doctor.

b. If a clinical assessment is not required, then:

(1) Advises OH.

(2) Notifies OH personnel of the decision and provide supporting documentation.

c. If a clinical assessment is required, then determines the Licensed Operator's condition based on available medical records, results of the personal medical doctor's clinical assessment, and any special testing.

(1) Notifies OH personnel of the decision and provides supporting documentation.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 18 of 54 5.4.3 Medical Status Changes (continued)

d. If license restrictions are indicated or determined, then notify OH.

(1) If a temporary medical status change is identified, then additional clinical assessment at a future date will be warranted to determine if or when temporary restrictions may be removed.

(2) If a permanent medical status change is identified, then a required letter with additional medical information shall be prepared by the SEP with assistance from the Occupational Health staff to support the NRC Form 396 submittal.

(a) This information is transmitted to Regulatory Affairs in a sealed envelope marked as CONFIDENTIAL.

(b) Regulatory Affairs may open the sealed envelop to validate the information contained in the letter matches the information provided by the physician.

(3) If OH identifies a permanent medical status change that is not compatible with maintaining a RO or SRO license, then notify the Operations Manager (or designee) and contact Site HR for Medical Accommodations Program consideration.

4. Occupational Health performs the following upon notification of a medical status change by the SEP or CMD:

a. Initiate performance of Attachment 3, Change In Medical Condition Affecting License Status.

b. Completes the NRC Form 396 for permanent medical status changes.

c. Ensures a validation of the medical documents and OH database is performed by another member of OH.

d. Incorporates additional medical information provided by the SEP on the completed NRC Form 396 and forwards it to Regulatory Affairs.

e. Documents medical change in Licensed Operator's medical record.

f. Files the original completed forms, and any associated medical documents in the Licensed Operator's medical record.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 19 of 54 5.4.3 Medical Status Changes (continued)

5. Regulatory Affairs performs the following:

a. Ensures the NRC Form 396 is properly completed.

b. If a permanent medical change was identified, then:

Obtains Licensed Operator's signature Obtains Site VP's signatures Submits NRC Form 396 within 30 days of the medical status discovery date A letter with additional medical information may be prepared by the SEP to support the NRC Form 396 submittal. This information will be provided to the NRC in accordance with 10 CFR 2.390.

c. Forwards a copy of the submitted NRC Form 396 to:

Site Training Occupational Health Affected Licensed Operator Licensed Operator's supervisor.

5.4.4 Medical Restrictions Follow-Up

1. OH performs the following:

a. Monitors medical reevaluation dates for Licensed Operators with temporary medical restrictions.

b. Schedules follow-up testing and examinations.

2. SEP performs the following:

a. Performs the follow-up examinations and tests as necessary.

b. Completes clinical documentation and submits documentation to OH.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 20 of 54 5.4.4 Medical Restrictions Follow-Up (continued)

3. OH performs the following:

a. Obtains the clinical documents from the SEP and reviews for completeness and accuracy.

b. If the SEP reports that the temporary medical restriction is no longer valid, then the following actions are taken:

(1) Initiates performance of Attachment 3, Change In Medical Condition Affecting License Status (2) Incorporates additional medical information provided by the SEP on the completed NRC Form 396 and forwards it to Regulatory Affairs.

(3) Documents medical change in Licensed Operator's medical record.

(4) Files the original completed forms, and any associated medical documents in the Licensed Operator's medical record.

5.5 Maintaining Required On-Shift Experience (Proficiency) For Licensed Operators

1. Licensed Operators must comply with 10 CFR 55.53(e) to maintain an Active Licensed Operator Position. {7.1.1}

a. Licensed Operators must perform five 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts per calendar quarter to maintain an active license status.

b. Time as an extra RO or SRO on an Outage Unit or as RO or SRO in the Outage Command Center CANNOT be counted as an Active Licensed Operator Position.

c. Time during No Mode CANNOT be counted as an Active Licensed Operator Position.

2. Any Licensed Operator that fails to comply with 10 CFR 55.53(e) requirements shall immediately notify their supervisor. {7.1.1}

a. The Licensed Operator's supervisor shall notify Operations Training to disqualify the Licensed Operator from licensed duties in accordance with AD-TQ-ALL-0660, Use and Administration of the Nuclear Learning Management System (NLMS).

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 21 of 54 5.5 Maintaining Required On-Shift Experience (Proficiency) For Licensed Operators (continued)

3. The Licensed Operator shall document performance of standing an Active Licensed Operator Position by one of the following methods:

Attachment 1, Operating Experience Maintenance For Active Licensed Operators

'Credit for Standing Watch' eSOMS report

4. If a Licensed SRO stands all of the required proficiency watches in a SRO position, then the RO portion of the license remains active.

5. Individuals who are licensed on two (or more) similar units at a facility are not required to maintain proficiency on each of the similar units (i.e., performing required watches on a single unit will maintain the active licenses on the similar units).

6. If a Licensed SRO stands mostly RO watches, then to maintain the supervisory portion of the SRO License active, the Licensed SRO must stand at least one complete 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift per calendar quarter as either SM or CRS.

a. Failure to complete at least one complete watch during a calendar quarter as either a SM or CRS will result in the SRO License becoming inactive.

(1) The Operator may still stand watch as a RO until the SRO License is reactivated.

7. Two SROs may obtain active hours at the same time in dual unit Control Rooms as long as each SRO is assigned overall responsibility for a specific unit.

a. SROs assigned to the Control Room for oversight of specific evolutions may not accrue time that can be credited toward their calendar quarter requirement.

8. Four Reactor Operators may obtain active hours at the same time in dual unit Control Rooms as long as each is assigned either the OATC or the BOP position for a specific unit.

a. Reactor Operators assigned to the Control Room for specific evolutions may not accrue time that can be credited toward their calendar quarter requirement.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 22 of 54 5.6 Activation of a New or Inactive License

1. Licensed Operators must ensure compliance with the terms of 10 CFR55.53(e) for activation of a new or inactive license.

2. Prior to performance of Active Licensed Operator Position duties, the Licensed Operator must complete Attachment 2, Activation of New or Inactive License.

a. Five 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> proficiency watches are not required to be performed in a quarter where reactivation or initial activation is accomplished.

b. Activation hours CANNOT be counted as part of the proficiency watch standing time for the quarter.

NOTE The requirement detailed in the following step is not specified in 10 CFR 55, but are required by Duke Energy.

3. The AOM-Shift completes an evaluation, determining the need for any additional training in the following areas:

Ops Management Expectations (e.g., watch standing, communications)

Security Radiation Protection Emergency Planning Operation Major Plant Modifications 5.7 Removing a Licensed Operator From Duty for Other Than Medical or Requalification Training Status

1. If a Licensed Operator is removed from licensed duty due to management discretion, then the AOM-Shift ensures the SM and Operations Training is notified.

a. Operations Training disqualifies the Licensed Operator from licensed duties in accordance with AD-TQ-ALL-0660, Use and Administration of the Nuclear Learning Management System (NLMS).

2. As necessary, the AOM-Shift and the Superintendent Nuclear Operations Training will develop any needed remediation plan.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 23 of 54 5.7 Removing a Licensed Operator From Duty for Other Than Medical or Requalification Training Status (continued)

3. If the removal from license duty is temporary, then the condition is not required to be reported per 10 CFR 55.

4. Upon resolution of the disqualifying issue, the AOM-Shift notifies Operations Training to reinstate the Licensed Operator qualifications to perform licensed duties in accordance with AD-TQ-ALL-0660, Use and Administration of the Nuclear Learning Management System (NLMS).

5. If a Licensed Operator becomes ineligible to perform licensed duties due to lapses in non-requalification training (e.g., SCBA, Respirator Training), then the Licensed Operator informs the SM.

a. The SM notifies Operations Training to disqualify the Licensed Operator from licensed duties in accordance with AD-TQ-ALL-0660, Use and Administration of the Nuclear Learning Management System (NLMS).

b. Upon resolution of the disqualifying issue, the AOM-Shift notifies Operations Training to reinstate the Licensed Operator qualifications to perform licensed duties in accordance with AD-TQ-ALL-0660, Use and Administration of the Nuclear Learning Management System (NLMS).

5.8 Activating an SRO License For Fuel Handling/Core Alterations Only

1. Prior to an inactive Licensed Operator independently standing watch as a Fuel Handling/Core Alterations SRO, the actions contained in Attachment 6, Activation Of An SRO License For Fuel Handling/Core Alterations Only must be completed.

5.9 [CNS] Licensed Operators Qualification Report (LOQR)

1. The LOQR is a report updated to provide readily available operator license status.

a. If there is a conflict between the report and the Licensed Operator's believed qualification status, then the operator shall immediately contact the on-duty SM.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 24 of 54 5.9 [CNS] Licensed Operators Qualification Report (LOQR) (continued)

2. At a minimum, the LOQR includes:

Licensed Operator's name License status (active or inactive)

License expiration date NRC physical expiration date Restrictions placed on an operator's license

3. The LOQR shall be printed at least weekly and be readily available to the on duty Shift Manager for review and updating. {7.1.2}

6.0 RECORDS 6.1 QA Record

1. Completed Attachment 1, Operating Experience Maintenance For Active Licensed Operators as described in the attachment.

2. Completed Attachment 2, Activation of New or Inactive License as described in the attachment.

6.2 Business Record

1. Completed Attachment 3, Change In Medical Condition Affecting License Status as described in the attachment.

2. Completed Attachment 4, Notification Of Change In Operator Status {7.1.2} as described in the attachment.

3. Completed NRC Form 396. Filed by Occupational Health with the individuals medical record.

4. Completed Attachment 6, Activation Of An SRO License For Fuel Handling/Core Alterations Only as described in the attachment.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 25 of 54

7.0 REFERENCES

7.1 Commitments

1. ACR 92-797, Reactor Operator With An Inactive Licenses State Stood Brief Watch on BOP

2. CAPR 01898054-11, SRO Standing Watch with a Terminated License 7.2 Procedures

1. AD-DC-ALL-0002, Records Management

2. AD-HU-ALL-0004, Procedure Use and Adherence

3. AD-LS-ALL-0002, Regulatory Correspondence

4. AD-SY-ALL-0460, Managing Fatigue And Work Hour Limits

5. AD-TQ-ALL-0068, Licensed Operator Continuing Training Program

6. AD-TQ-ALL-0610, Nuclear Operator License Application Process

7. AD-TQ-ALL-0660, Use and Administration of the Nuclear Learning Management System (NLMS) 7.3 Miscellaneous Documents

1. 10CFR50.74, Notification of change in operator or senior operator status

2. 10CFR55.23, Certification

3. 10CFR55.25, Incapacitation because of disability or illness

4. 10CFR55, OPERATORS' LICENSES Subpart CMedical Requirements and Subpart D - Applications, Part 55.31 and Part 55.33

5. 10CFR55.53, Conditions of licenses

6. ADMF-SAF-HSF-00004, Facility Operator's Report Form

7. ADMF-SAF-HSF-00009, Audiological History and Examination Form

8. ADMF-SAF-HSF-00013, Occupational Health History Form

9. ADMF-SAF-HSF-00017, Supervisor's Statement - To Support Nuclear Occupational Medical Evaluations and Surveillances

10. ADMP-SAF-HSF-00091, Occupational Health Programs

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 26 of 54 7.3 Miscellaneous Documents (continued)

11. ANSI/ANS-3.4 - 1983, Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power Plants

12. NRC RIS 2007-29, Clarified Guidance for Licensed Operator Watch-Standing Proficiency

13. NUREG 1021, Operator Licensing Examination Standards for Power Reactors, Revision 9, Supplement 1; Section ES-605

14. NUREG 1262, Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators' Licenses

15. Regulatory Guide 1.134, Rev. 2, Medical Evaluation of Licensed Personnel at Nuclear Power Plants

16. RNP Nuclear Condition Report 224245, Including additional information on NRC Form 396

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 27 of 54 ATTACHMENT 1 Page 1 of 2

<< Operating Experience Maintenance For Active Licensed Operators >>

1. Licensed Operator's Name Employee Number

2. Active Licensed Operator Position

a. Shift Manager (SRO)

b. Control Room Supervisor (SRO)

c. Operator at the Controls (RO)

d. Balance of Plant Operator (RO)

3. Refer to Section 5.5 for the requirements for maintaining an active license.

a. Refer to Attachment 1 Step 2 and document the watches stood in Table 1.

Table 1, Licensed Operator Watch Standing Log Licensed Operator Position Shift Start Date Shift (a, b, c, or d) (Month/Day/Year) (day/night)

4. I hereby certify that the information set forth above is accurate and complete.

Licensed Operator Signature ________________________________

5. Completed copies of this attachment shall be retained in accordance with AD-DC-ALL-0002, Records Management.

6. NLMS Code:_____________________________ NLMS Entry Completed

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 28 of 54 ATTACHMENT 1 Page 2 of 2

<< Operating Experience Maintenance For Active Licensed Operators >>

Name:__________________________________ Date:______________

a. NLMS Codes:

[BNP] BN TRN LOI0006B ROO

[CNS] RO: CNROLOQR-NCN

[CNS] SRO: CNSRLOQR-NCN

[HNP] HN-OPS-LOI0014H

[MNS] MCO023

[ONS] TT4691-N Licensed Operator - Operating Experience Maintenance

[RNP] RN-OPS-LOC0001R-N QA Record Retention Rule = 421734 (Life of Plant)

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 29 of 54 ATTACHMENT 2 Page 1 of 11

<< Activation of New or Inactive License >>

1. Licensed Operator's Name:

Employee Number: Position: (RO/CRS/SM)

2. Prior to initiation of the activation process, the Licensed Operator ensures all requirements of AD-SY-ALL-0460, Managing Fatigue And Work Hour Limits, are met, including validating that the individual's status in EmpCenter is "Covered."

3. Date of initiation of the activation process:

Required Completion Date:

The required completion date must ensure that all hours required for activation are contained in the same calendar quarter.

4. Pre-job briefing completed.

AOM-Shift or SM: Date:

NOTE Step 5 through Attachment 2 Step 10 can be completed in any order.

5. An evaluation has been performed and additional training needs are identified below: (Section 5.6 Step 3)

AOM-Shift: Date:

6. I hereby certify that all requalification training is up-to-date (N/A for initial licenses).

a. For SMs and SM reliefs license reactivation, this includes verification that the SM or SM relief has participated in an active simulator evaluation (ASE) or station drill as the SM within the past two years.

Operations Training Superintendent: Date:

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 30 of 54 ATTACHMENT 2 Page 2 of 11

<< Activation of New or Inactive License >>

7. I hereby certify that medical qualifications are current.

Occupational Health Representative: Date:

8. Verify that respirator/SCBA qualifications are current in NLMS.

Licensed Operator: Date NOTE Only one individual is allowed to parallel an active Licensed Operator at a time.

9. Licensed Operator being activated will:

a. Perform 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> in an Active Licensed Operator Position to which the individual will be assigned under the direction of an active Licensed RO or SRO.

(1) Must include participation in an ongoing and off going turnover, and a shift briefing.

(2) Up to eight hours of the 40 activation hours may be spent completing the plant familiarization tour.

(3) All 40 activation hours are required to be completed in the same calendar quarter.

b. At the beginning of each shift, create a logbook entry stating the watch is being assumed under instruction.

c. At the end of each shift, obtain an active SRO or RO signature certifying that the Licensed Operator being activated worked under the signatures direction.

d. Upon completion of under instruction watch, complete Table 2, Licensed Operator Under Instruction Logbook

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 31 of 54 ATTACHMENT 2 Page 3 of 11

<< Activation of New or Inactive License >>

e. Complete a plant familiarization tour during the 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> or reactivation hours under the direction of an active Licensed SRO. Multiple personnel activating a license may participate in the same plant familiarization tour.

The plant familiarization tour shall include the following:

Up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of reactivation time (total 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />) should be spent touring the plant.

Contaminated areas or high radiation areas are not required to be accessed.

All major equipment in tour areas shall be discussed.

Plant familiarization tour shall include a review of all AO shift turnover procedures.

Discuss an plant modification recently installed.

Document the plant familiarization tour of the site specific areas using the site specific lists at the end of this attachment.

Attach a copy of the security door printouts for both the licensed individual reactivating and the active Licensed SRO associated with the plant familiarization tour.

Table 2, Licensed Operator Under Instruction Logbook Under the Direction of Date # of Hours Printed Name Signature Oncoming shift turnover Off going shift turnover

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 32 of 54 ATTACHMENT 2 Page 4 of 11

<< Activation of New or Inactive License >>

10. I hereby certify that the plant familiarization tour and 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of activation time in Step 9 are complete and were completed within the same calendar quarter.

Licensed Operator: Date:

SM (on duty): Date:

11. I hereby certify that the Training identified in Attachment 2 Step 5 is complete.

SM (in charge): Date:

12. All licensing requirements met.

Ops Training Superintendent: Date:

13. I hereby certify the Licensed Operator's qualifications and status as current and valid and the required shift functions have been performed and authorize resumption of functions defined by Technical Specifications as follows:

Licensed Operator's qualifications are current Licensed Operator's shift functions have been performed Plant tour is complete AOM-Shift: Date:

14. The individual attempting to activate a license notifies the on-duty SM to:

a. Notify Operations Training to reinstate the Licensed Operator qualifications to perform licensed duties in accordance with AD-OP-ALL-0660, Use and Administration of the Nuclear Learning Management System (NLMS).

b. [CNS] Update LOQR active/inactive license status AOM-Shift/designee OR SM/designee: Date:

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 33 of 54 ATTACHMENT 2 Page 5 of 11

<< Activation of New or Inactive License >>

15. NLMS Code:__________________________________ NLMS Entry Completed Name:_______________________________________ Date:______________

a. NLMS Codes:

[BNP] BN TRN LOI0006B ROO

[CNS] RO: CNROLOQR-N

[CNS] SRO: CNSRLOQR-N

[HNP] HN-OPS-LOI0014H

[MNS] MCO023

[ONS] TT4691-N Licensed Operator - Operating Experience Maintenance

[RNP] RN-OPS-LOC0001R-N

16. The following is retained in accordance with AD-DC-ALL-0002, Records Management.

Completed copies of this attachment.

Applicable site completed Plant Familiarization Tour table.

Any Plant Familiarization Tour table not used to complete this attachment can be discarded.

Copies of the security logs for the time spent on shift for the individual attempting to activate a license and the operator responsible for oversight of the individual attempting to activate a license.

Copies of the security records for all areas entered during the required plant familiarization tour for the operator attempting to activate a license and the operators conducting the tour.

Copies of Operations narrative log while standing watch under instruction.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 34 of 54 ATTACHMENT 2 Page 6 of 11

<< Activation of New or Inactive License >>

Table 3, Brunswick Reactivation Plant Familiarization Tour Active Licensed SRO Date Area Elapsed Time Printed Name Signature Unit 1 Reactor Building Unit 2 Reactor Building Turbine Building DG 4 Day Tanks DG Building CB HVAC Cable Spread Service Water Building Intake Structure AOG Radwaste Transformer Yard MWT - FP Area Security CAS Review of AO Turnover Sheets Total Hours QA Record Retention Rule = 421734 (Life of Plant)

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 35 of 54 ATTACHMENT 2 Page 7 of 11

<< Activation of New or Inactive License >>

Table 4, Catawba Reactivation Plant Familiarization Tour Active Licensed SRO Date Area Elapsed Time Printed Name Signature Aux Bldg Elevation 594 Aux Bldg Elevation 577 Aux Bldg Elevation 560 Aux Bldg Elevation 543 Aux Bldg Elevation 522 Unit 1 ETA/ETB Rooms Unit 2 ETA/ETB Rooms Unit 1 Cable Spreading Rm Unit 2 Cable Spreading Rm Unit 1 Spent Fuel Building Unit 2 Spent Fuel Building Unit 1 Vital Battery Area Unit 2 Vital Battery Area Unit 1 CA Pump Room Unit 2 CA Pump Room Unit 1 D/G Rooms Unit 2 D/G Rooms Unit 1 Turbine Operating Deck Unit 2 Turbine Operating Deck Unit 1 Turbine Mezz Level Unit 2 Turbine Mezz Level Unit 1 Turbine Basement Unit 2 Turbine Basement SSF Unit 1 Exterior Doghouse Unit 2 Exterior Doghouse Unit 1 Interior Doghouse Unit 2 Interior Doghouse Review of AO Turnover Sheets Total Hours QA Record Retention Rule = 421734 (Life of Plant)

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 36 of 54 ATTACHMENT 2 Page 8 of 11

<< Activation of New or Inactive License >>

Table 5, Harris Reactivation Plant Familiarization Tour Active Licensed SRO Date Area Elapsed Time Printed Name Signature RAB (all levels)

Turbine Building Diesel Generator Building Waste Processing Building Water Treatment Facility Fuel Handling Building Diesel Fuel Oil Storage Building ESW Structure ESW Screening Structure Review of AO Turnover Sheets Total Hours QA Record Retention Rule = 421734 (Life of Plant)

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 37 of 54 ATTACHMENT 2 Page 9 of 11

<< Activation of New or Inactive License >>

Table 6, McGuire Reactivation Plant Familiarization Tour Active Licensed SRO Date Area Elapsed Time Printed Name Signature Aux Bldg Elevation 767 Aux Bldg Elevation 750 Aux Bldg Elevation 733 Aux Bldg Elevation 716 Aux Bldg Elevation 695 Unit 1 ETA/ETB Rooms Unit 2 ETA/ETB Rooms Unit 1 Cable Spreading Rm Unit 2 Cable Spreading Rm Unit 1 Spent Fuel Building Unit 2 Spent Fuel Building Vital Battery Area Unit 1 CA Pump Room Unit 2 CA Pump Room Unit 1 D/G Rooms Unit 2 D/G Rooms Unit 1 Turbine Operating Deck Unit 2 Turbine Operating Deck Unit 1 Turbine Mezz Level Unit 2 Turbine Mezz Level Unit 1 Turbine Basement Unit 2 Turbine Basement SSF Unit 1 Exterior Doghouse Unit 2 Exterior Doghouse Unit 1 Interior Doghouse Unit 2 Interior Doghouse Review of AO Turnover Sheets Total Hours QA Record Retention Rule = 421734 (Life of Plant)

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 38 of 54 ATTACHMENT 2 Page 10 of 11

<< Activation of New or Inactive License >>

Table 7, Oconee Reactivation Plant Familiarization Tour Active Licensed SRO Date Area Elapsed Time Printed Name Signature CT-4 Blockhouse SSF Turbine Building Auxiliary Building Unit 1 Equipment Room Unit 1 Cable Room Unit 2 Equipment Room Unit 2 Cable Room Unit 3 Equipment Room Unit 3 Cable Room Unit 1 Control Battery Room Unit 2 Control Battery Room Unit 3 Control Battery Room Unit 1 and 2 Spent Fuel Building Unit 3 Spent Fuel Building Keowee Hydro Review of AO Turnover Sheets Total Hours QA Record Retention Rule = 421734 (Life of Plant)

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 39 of 54 ATTACHMENT 2 Page 11 of 11

<< Activation of New or Inactive License >>

Table 8, Robinson Reactivation Plant Familiarization Tour Plant tours shall include entry and visual surveillance of each room in the Turbine Building and RCA that is not specifically excluded below or in writing by the SM.

Areas excluded from the plant familiarization tour:

Containment Vessel RHR Pit Office buildings that are not part of the watchstanders normal tour Active Licensed SRO Date Area Elapsed Time Printed Name Signature CR HVAC 4kV Room E1/E2, Battery, Cable Spread Rooms Building 469 - 1st and 2nd floor AFW Pump Room Turbine Building (all levels)

Security Building (CAS)

SFP Area SFP Hx and Bit Room Auxiliary Building (level 1 and 2)

Security Pap Diesel Intake Review of AO Turnover Sheets Total Hours QA Record Retention Rule = 421734 (Life of Plant)

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 40 of 54 ATTACHMENT 3 Page 1 of 4

<< Change In Medical Condition Affecting License Status >>

Operator's Name:________________ Employee Number:__________ Date:_________

NOTE This form is to be completed when any change in medical condition affects the employees ability to perform licensed duties.

Discovery date is the date and time the Licensed Operator has notified OH of a change in medical condition.

AD-HU-ALL-0004, Procedure Use and Adherence, Section 5.6, provides guidance on how to appropriately placekeep when performing this attachment.

1. The following is completed by OH:

a. Record discovery date and time: __________/ __________

Date Time

b. Ensure documentation is placed in Licensed Operator's medical file.

(Return to work forms or Nurse's documentation).

c. Identify status of condition (circle one): PERMANENT/TEMPORARY

d. Notify CMD or SEP, if applicable.

(1) CMD or SEP Name:________________________

e. Ensure license duty eligibility is determined by qualified OH health personnel:

_____ Ineligible

_____ Eligible with the following temporary restrictions:

_____ Eligible to perform licensed duties

_____ Eligible with the following permanent restrictions

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 41 of 54 ATTACHMENT 3 Page 2 of 4

<< Change In Medical Condition Affecting License Status >>

Operator's Name:________________ Employee Number:__________ Date:_________

f. If the Licensed Operator is medically ineligible to perform licensed duties, then OH shall perform the following:

(1) Enter the Licensed Operator medical status change in the Duke Employee Medical Information (DEMI) system.

(a) If DEMI CANNOT be updated by the end of a shift after a Licensed Operator has been determined ineligible to perform licensed duty, then contact the on-duty SM to disqualify the Licensed Operator from licensed duties in accordance with AD-TQ-ALL-0660, Use and Administration of the Nuclear Learning Management System (NLMS).

SM name:____________________________

(2) Verify the Licensed Operator medical status change is reflected in NLMS.

2. OH notifies the affected Licensed Operator of the following:

a. The impact this change in medical status has on license duty eligibility.

(1) If ineligible to perform licensed duties, then provide direct and verbal notification to the Licensed Operator that licensed duties shall NOT be performed.

(a) If direct and verbal notification to the Licensed Operator CANNOT be established, then provide direct and verbal notification to the AOM-Shift that the Licensed Operator shall NOT perform licensed duties.

b. Comply with restrictions and conditions anytime the Licensed Operator performs license duties.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 42 of 54 ATTACHMENT 3 Page 3 of 4

<< Change In Medical Condition Affecting License Status >>

Operator's Name:________________ Employee Number:__________ Date:_________

c. Actions required to address the medical condition may include, but are not limited to the following:

Additional medical evaluation and treatment Obtaining appropriate medications Obtaining proper hearing enhancement devices Obtaining appropriate corrective lenses, including lenses for SCBA Obtaining therapeutic medical device

3. OH performs the following:

a. Contacts the on-duty SM.

(1) Name:_______________________________ Date:__________

b. Informs the on-duty SM of the affected Licensed Operator's change in medical status and to notify the AOM-Shift and Licensed Operator's supervisor.

c. [CNS] Informs the on-duty SM to update the LOQR.

4. If the medical condition status is determined to be permanent, then ensure a NTM is generated, documenting that a change in medical status has occurred for the affected Licensed Operator:

a. Record NTM Number:_____________

(1) Include a NTM assignment for Regulatory Affairs to complete required regulatory correspondence.

b. Transmit notification to Regulatory Affairs as follows:

(1) Send email or fax copy of this attachment.

(2) Verify information received by a member of Regulatory Affairs:

(a) Name: _____________________________________

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 43 of 54 ATTACHMENT 3 Page 4 of 4

<< Change In Medical Condition Affecting License Status >>

Operator's Name:________________ Employee Number:__________ Date:_________

c. Ensure the following:

NRC Form 396 is completed.

Corporate Medical Director or Site Examining Physician notification letter are completed per AD-LS-ALL-0002, Regulatory Correspondence.

Notification letter is delivered to Regulatory Affairs.

5. OH completes the following:

a. If permanent medical restrictions are being added, then notify Regulatory Affairs to generate correspondence and notify NRC Region II within 30 days of the date the license restriction was discovered.

b. If medical restrictions are being removed, then notify Regulatory Affairs to generate correspondence and notify NRC Region II within 30 days of the date of the medical change in condition.

c. Record NTM number:________________________

6. Place completed copies of this attachment in the Licensed Operator's medical file.

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 44 of 54 ATTACHMENT 4 Page 1 of 4

<< Notification Of Change In Operator Status >> {7.1.2}

NOTE Review NCR 01898054 {CAPR} before making any changes to this form.

Licensed Operator (name): will no longer perform the duties of a Licensed Senior/Reactor Operator effective as of the License Termination Date listed below.

Employee Number:

License Termination Date:

Describe Reason: (Transfer, termination)

NOTE The signatures below indicate that the information stated above is correct.

AOM-Shift/designee Signature Date Licensed Operator Signature Date Licensed Operator's Manager Signature Date

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 45 of 54 ATTACHMENT 4 Page 2 of 4

<< Notification Of Change In Operator Status >> {7.1.2}

NOTE The notification of change in operator status must be received by the NRC within 30 days of the effective date per 10CFR50.74.

1. AOM-Shift to ensure the following:

a. Generate an NTM for operator license termination.

b. Ensure NTM includes the following:

License Termination Date Direction to assign NTM ownership to Regulatory Affairs Direction for Regulatory Affairs to generate all necessary corrective actions for license termination per Attachment 4, Notification Of Change In Operator Status {7.1.2}

c. Notify Site Operations Training Group to commence actions to deactivate the affected operator's qualifications effective on the License Termination Date.

d. Route this form to Regulatory Affairs.

AOM-Shift/designee Signature Date NTM Number

2. Regulatory Affairs ensure the following:

a. Generate License Termination letter.

b. Assemble verification package.

(1) A copy of the termination letter shall be distributed to the following individuals for verification of accuracy prior to sending the termination letter to the NRC:

(a) Licensed Operator (b) Licensed Operator's manager (c) AOM-Shift (d) Operations Manager

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 46 of 54 ATTACHMENT 4 Page 3 of 4

<< Notification Of Change In Operator Status >> {7.1.2}

c. Create assignments within the associated license termination NTM as follows:

(1) For each NTM assignment:

Enable the CAS Lock Due Date function with site Regulatory Affairs group as Due Date Owner.

Due dates shall not exceed the License Termination Date except as provided.

(2) Create NTM assignments as follows:

[CNS] Operations to update LOQR to disqualify the Licensed Operator Occupational Health staff to update operators file/record that license is terminated.

Emergency Planning to update operator's EP file/record that license is terminated.

Operations Training Group to deactivate the operator's qualifications on the License Termination Date (not earlier nor later than License Termination Date).

Operations Training Group to file completed copy of Attachment 4, Notification Of Change In Operator Status

{7.1.2} in operator's training file with Due Date not to exceed two weeks after License Termination Date.

Other actions and assignments as desired

d. Ensure change in license status is reported to the Nuclear Regulatory Commission per 10CFR 50.74.

e. Route this form to AOM-Shift or deliver to on-duty SM/designee.

Regulatory Affairs Signature Date

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 47 of 54 ATTACHMENT 4 Page 4 of 4

<< Notification Of Change In Operator Status >> {7.1.2}

3. AOM-Shift or on-duty SM ensure the following:

[CNS] Update LOQR Route this form to the Site Occupational Health staff.

AOM-Shift or SM Signature Date

4. Occupational Health staff ensure the following:

Update operator's records.

Route this form to Emergency Planning Occupational Health personnel signature Date

5. Emergency Planning ensure the following:

Update Emergency Planning Records.

Route form to site Operations Training Group.

Emergency Planning Staff Signature Date

6. Site Operations Training Group ensure the following:

Deactivate the affected operator's qualifications as of the effective date of the license termination.

Completed copies of this attachment shall be retained in accordance with AD-DC-ALL-0002, Records Management.

Operations Training Signature Date

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 48 of 54 ATTACHMENT 5 Page 1 of 5

<< Common Medical Status Changes/Conditions of Licensed Operators >>

NOTE Complete details associated with Licensed Operator Medical Examinations is located in ADMP-SAF-HSF-00091, Occupational Health Programs.

1.0 COMMON MEDICAL CONDITIONS REQUIRING OCCUPATIONAL HEALTH AND SUPERVISION NOTIFICATION The inability to properly fit or effectively use personal protective equipment (PPE)

Impairment of the sense of smell Loss of the capacity for clear speech Hearing becomes impaired Vision changes (e.g., visual acuity, peripheral vision, color vision or depth perception)

Respiratory capacity becomes impaired Impairment of the operator's cardiovascular system (e.g., hypertension, myocardial infarction, coronary stent and coronary bypass)

Development of any type of hernia Impairment of muscular-skeletal range of motion or power Inability of the skin to tolerate PPE or decontamination procedures Changes to the endocrine or metabolic systems, such as diabetes and thyroid disorders, such that the ability to change schedules is affected, or the individual could become incapacitated if meals are delayed Impairment of the ability to form blood such as anemia, leukemia, lymphoma and multiple sclerosis Impairment of lymphatic function Impairment neurological function Development of mental, emotional, or behavioral disorders

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 49 of 54 ATTACHMENT 5 Page 2 of 5

<< Common Medical Status Changes/Conditions of Licensed Operators >>

1.0 COMMON MEDICAL CONDITIONS REQUIRING OCCUPATIONAL HEALTH AND SUPERVISION NOTIFICATION (continued)

Abnormal laboratory results Chronic fatigue Diagnosis of any cancer, including skin cancer Diagnosis of sleep apnea Use of therapeutic device such as CPAP Returning from hospitalizations due to heart attack and major surgery Elective surgery that may change or improve an individual's medical condition (e.g., lasik).

2.0 COMMON CHANGES IN MEDICAL STATUS - (NORMALLY REPORTED TO NRC)

Hypertension/Blood Pressure medication Diabetes Mellitus Vision change - near/distant Myocardial infarction or coronary stents Syncopal episode Seizure Sleep Apnea Anxiety Depression Impaired Hearing Acuity, Hearing Aid All cancers including skin cancers Drug or alcohol issues

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 50 of 54 ATTACHMENT 5 Page 3 of 5

<< Common Medical Status Changes/Conditions of Licensed Operators >>

2.0 COMMON CHANGES IN MEDICAL STATUS - (NORMALLY REPORTED TO NRC)

(continued)

Thyroid medication Glaucoma Impaired Tactile Discrimination Chemotherapy Pulmonary Embolus or Deep Vein Thrombosis Attention Deficit Hyperactivity Disorder (ADHD)

Multiple Myeloma Repair of leg aneurysm Sarcoidosis Hip or knee replacement (Reported as for information only, unless a permanent restriction is needed)

Cholesterol medication (Reported as for information only)

Sleep medications (Reported as for information only)

Olfactory Deficit EpiPen Rheumatoid Arthritis Asthma (Frequent severe attacks within previous 2 years or need for prolonged or continued use of medication)

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 51 of 54 ATTACHMENT 5 Page 4 of 5

<< Common Medical Status Changes/Conditions of Licensed Operators >>

3.0 COMMON MEDICAL CONDITIONS REQUIRING NO SOLO OPERATION Insulin requiring diabetes mellitus Myocardial infarction Coronary stents (No Solo after initial stent insertion, case by case determination)

Unexplained syncopal episodes Kidney transplant Narcolepsy Olfactory deficit Migraine Headache associated with syncope or potential incapacitation Treatment with Coumadin (warfarin) (case by case determination) 4.0 MEDICAL CONDITIONS REQUIRING RESTRICTIONS OF LICENSED OPERATORS Hypertension requiring medication Corrective lens Hearing Aid Sleep Apnea with CPAP treatment (Therapeutic Medical Device) must have documentation from personal physician stating compliance with machine.

Myocardial Infarction (No Solo)

Diabetes Mellitus requiring medication (Use of insulin is No Solo)

Insulin Pump (Therapeutic Medical Device)

Glaucoma requiring medication Unexplained syncopal episode (No Solo)

Chemotherapy (Restriction or No Solo)

Treatment with Coumadin (warfarin) (No Solo)

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 52 of 54 ATTACHMENT 5 Page 5 of 5

<< Common Medical Status Changes/Conditions of Licensed Operators >>

4.0 MEDICAL CONDITIONS REQUIRING RESTRICTIONS OF LICENSED OPERATORS (continued)

Pulmonary Embolus or Deep Vein Thrombosis (case by case determination)

Olfactory Deficit (No Solo)

Seizure Disorder (Restriction or No Solo)

Kidney Transplant (No Solo)

Migraine Headache associated with syncope or potential incapacitation (No Solo)

Impaired Tactile Discrimination (No Solo)

Attention Deficit Disorder treatment with medication EpiPen (Case by case determination based on if the operator is at risk for a severe allergic reaction and carries it at all times)

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 53 of 54 ATTACHMENT 6 Page 1 of 2

<< Activation Of An SRO License For Fuel Handling/Core Alterations Only >>

Operator's Name: Employee Number: Date:

1. Verify refueling training is up-to-date and completed successfully for the Refueling SRO/Reactor Building SRO position(s).

AOM-Shift/designee Date

2. Verify the medical qualification is current for the assigned position(s).

AOM-Shift/designee Date

3. Record the completion of at least one 12-hour (continuous time period) shift of parallel refueling operation, equipment familiarization, tours, procedure preparation for beginning of fuel movement and shift turnovers required for the assignment/return to active license duties for refueling only in the Refueling SRO/positions. During the 12-hour shift, the inactive SRO shall perform the duties related to fuel handling in parallel with an SRO assigned to the Refueling SRO position that holds an active license. No more than 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> can be credited for activities conducted prior to the actual start of fuel movement.

Date of 12-hour shift Active SRO (initials)

4. I certify the above individual for assignment/return to active Refueling SRO duties for outage ________________ (e.g., 2CR22).

SM Date

5. AOM-Shift files and retains this form for the duration of the core alteration for which the license was activated.

AOM-Shift/designee Date

MAINTENANCE OF RO AND SRO LICENSES AD-OP-ALL-0107 Rev. 3 Page 54 of 54 ATTACHMENT 6 Page 2 of 2

<< Activation Of An SRO License For Fuel Handling/Core Alterations Only >>

6. Completed copies of this attachment shall be retained in accordance with AD-DC-ALL-0002, Records Management.

AOM-Shift/designee Date

Catawba Nuclear Station Admin. JPM A.2S Sept 2021 NRC Exam JPM A.2S SRO PAGE 1 OF 7

Catawba Nuclear Station Admin. JPM A.2S Sept 2021 NRC Exam EVALUATION SHEET Task: Use Flow Diagrams and Electrical Prints to Determine Work Isolation Boundary Alternate Path: N/A Facility JPM #: New 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 diagram of the CA system (CN 2592-01), 4.16 KV bus one line electrical drawings Task Standard: Mechanical and electrical isolation boundary determined for work on 2A CA pump 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.2S Sept 2021 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 2A Auxiliary Feedwater (CA) Pump has been shutdown in accordance with OP/2/A/6250/002 (Auxliary Feedwater System) and is to be tagged out for pump casing disassembly and impeller replacement.

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 2A Auxiliary Feedwater (CA) Pump, 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 CA flow diagrams (CN 2592-01), and 4.16 KV Switchgear one line diagrams (CN 2702-2.01, CN 2702-2.02).

PAGE 3 OF 7

Catawba Nuclear Station Admin. JPM A.2S Sept 2021 NRC Exam SAT /

STEP / STANDARD UNSAT START TIME: _______

STEP 1: Determine clearance boundary for the 2A CA Pump boundary.

CRITICAL STEP STANDARD:

Applicant identifies clearance boundary per table on the next page.

Note that only one vent valve or one drain valve plus drain valve 2CA-103 is needed to meet the critical step.

___ SAT Examiner Note: This step is critical to be able to correctly isolate the 2A Auxiliary Feedwater (CA) Pump for pump casing ___ UNSAT disassembly and impeller replacement.

COMMENTS:

PAGE 4 OF 7

Catawba Nuclear Station Admin. JPM A.2S Sept 2021 NRC Exam SAT /

STEP / STANDARD UNSAT Component Position 2ETA13 Racked Out 2CA-29 Closed 2CA-87 Closed 2CA-25 Closed 2CA-154 (Drain, Can be used) Open 2CA-103 (Common Drain, Must be Open used) 2CA-153 (Drain, Can be used) Open 2CA-101 (Drain, Can be used) Open 2CA-83 (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 2A Auxiliary Feedwater (CA) Pump has been shutdown in accordance with OP/2/A/6250/002 (Auxiliary Feedwater System) and is to be tagged out for pump casing disassembly and impeller replacement.

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 2A Auxiliary Feedwater (CA) Pump, 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.3S Sept 2021 NRC Exam JPM A.3S SRO PAGE 1 OF 13

Catawba Nuclear Station Admin. JPM A.3S Sept 2021 NRC Exam EVALUATION SHEET Task: Review Liquid Waste Release Alternate Path: N/A Facility JPM #: WL-002 Safety Function: N/A K/A G 2.3.6 Ability to approve release permits Importance: 2.0 / 3.8 CFR: 41.10 / 45.12 / 45.13 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate

References:

OP/0/B/6500/113 (Operations Liquid Waste Release), Enclosure 4.1 (Liquid Waste Release from a Monitor Tank)

Task Standard: The operator will determine that the LWR (Package # 2021056) should not be released due to all of the following: incorrect EMF-49 Trip 2 setpoint, incorrect RL Flow Interlock setpoint, and incorrect 1WL-124 flowrate setpoint.

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

PAGE 3 0F 13 Catawba Nuclear Station Admin. JPM A.3S Sept 2021 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% power.

• There are currently no liquid waste releases in progress.

• The following equipment is in service:

o 1A & 1B RC Pumps o 0RLP5080 (RL Discharge Total Flow) is operable and indicating 46,400 gpm through A & B RL Discharge Headers o 1B RN Pump in normal alignment o LWR Integrator (0WLP6160) is operable

• LWR #2021056 has been delivered to the Control Room and was approved by the previous shifts CRS.

o OP/0/B/6500/113 (Operations Liquid Waste Release), Enclosure 4.1 (Liquid Waste Release from a Monitor Tank) is in progress and has been completed through step 3.14

• The Unit 1 BOP has notified you (per step 3.15) that the LWR is ready to be released.

INITIATING CUE:

Review LWR #2021056 to determine if the release should be initiated. If applicable, list all issues that would prevent release initiation.

Initiate Release YES NO circle one Reason(s) (if any)

PAGE 3 OF 13

PAGE 4 0F 13 Catawba Nuclear Station Admin. JPM A.3S Sept 2021 NRC Exam EXAMINER NOTE:

After reading cue, provide applicant with a copy of OP/0/B/6500/113, Enclosure 4.1, completed through step 3.14 and Student Handout (LWR #2021056).

PAGE 4 OF 13

Catawba Nuclear Station Admin. JPM A.3S Sept 2021 NRC Exam START TIME: _________

Examiner Note: The operator may review steps performed in Enclosure 4.1. Applicable procedure direction begins at step 3.4.

STEP 1: 3.4 CRS performs the following concerning the LWR Permit Report:

Verifies LWR Permit Report refers to correct EMF.

Verifies EMF setpoints correct.

Sat __

Signs and dates the LWR Permit Report authorizing the release.

Unsat __

STANDARD:

Operator reviews the LWR permit report and determines that the correct EMF is listed, EMF setpoints are correct, and that the authorization was properly completed.

COMMENTS:

STEP 2: 3.5 IF EMF-49 is functional, perform the following:

3.5.1 Verify EMF-49 (Low Range) is functional per SLC 16.11-2, Table 16.11-2-1 using OP/0/A/6500/080 (EMF Output Modules).

3.5.2 Sign off the "EMF Source Checked &

Sat __

Operable" blank on the LWR Permit Report.

Unsat __

STANDARD:

Operator reviews the LWR Permit Report and determines that EMF-49 has been source checked and signed off.

COMMENTS:

PAGE 5 OF 13

Catawba Nuclear Station Admin. JPM A.3S Sept 2021 NRC Exam STEP 3:

3.5.3 Set EMF-49 (Low Range) trip setpoints to CRITICAL the values listed in "SETPOINT DATA" STEP section on the LWR Permit Report using OP/0/A/6500/080 (EMF Output Modules).

3.5.4 Sign off the "EMF49L Setpoints Set (Low Range)" blank on the LWR Permit Report.

STANDARD:

Operator reviews the LWR Permit Report and determines that the EMF-49 Trip 2 setpoint has not been set to the value Sat __

listed. The operator will then determine that the release should not be initiated and list EMF-49 setpoint as one reason why. Unsat __

Examiner Note: This step is critical to determine that this release should not be initiated.

COMMENTS:

NOTE: The person performing Steps 3.5.5 and 3.5.6 shall NOT be the same as in Step 3.5.4.

STEP 4:

3.5.5 Verify the EMF-49 (Low Range) trip setpoints are set as specified in "SETPOINT DATA" section on the LWR Permit Report using OP/0/A/6500/080 (EMF Output Modules).

Sat __

3.5.6 Sign off the "(I.V.) Independent Verification" blank on the LWR Permit Unsat __

Report.

STANDARD:

Operator notes that EMF-49 Trip 2 setpoint has not been properly verified and moves on.

COMMENTS:

PAGE 6 OF 13

Catawba Nuclear Station Admin. JPM A.3S Sept 2021 NRC Exam NOTE: Monitoring for highest count rate during release using a digital EMF chart recorder does NOT require an initial setup.

STEP 5:

3.5.7 IF using the OAC to obtain the highest count rate during release, monitor OAC point C1E0263 (EMF49L Waste Liquid Sat __

Discharge).

Unsat __

STANDARD:

Operator notes this step for future use and moves on.

COMMENTS:

STEP 6: 3.6 IF EMF-49 is nonfunctional, perform the following:

STANDARD: Sat __

Operator determines that this step is not applicable.

Unsat __

COMMENTS:

STEP 7: 3.7 Complete the following steps on the LWR Permit Report documenting the RN and RL Systems status:

3.7.1 Ensure at least the number of RN and RL pumps assigned to the LWR (listed on Sat __

page 2 of LWR Permit) are operating.

3.7.2 Sign off the "Ensure number of RN Pumps Unsat __

Operating is at least #.##" blank on the LWR Permit Report where #.## is the number of RN Pumps listed on page 2 of LWR Permit.

PAGE 7 OF 13

Catawba Nuclear Station Admin. JPM A.3S Sept 2021 NRC Exam 3.7.3 Sign off the "Ensure number of RL Pumps Operating is at least #.##" blank on the LWR Permit Report where #.## is the number of RL Pumps listed on page 2 of LWR Permit.

STANDARD:

Operator determines that the proper number of RN and RL pumps are operating and properly documented.

COMMENTS:

PAGE 8 OF 13

Catawba Nuclear Station Admin. JPM A.3S Sept 2021 NRC Exam STEP 8: 3.8 IF 0RLP5080 (RL Discharge Total Flow) is operable, perform the following:

3.8.1 Enter the RL flow rate on the LWR Permit Report as read on 0RLP5080 (RL Discharge Total Flow) (located on 1MC9).

3.8.2 Sign off the "RL Flowrate _______ gpm" Sat __

blank on the LWR Permit Report.

Unsat __

STANDARD:

Operator determines that RL flowrate is properly recorded.

COMMENTS:

PAGE 9 OF 13

Catawba Nuclear Station Admin. JPM A.3S Sept 2021 NRC Exam NOTE: If RL flow drops below this setpoint, it will automatically close 1WL-124 (Waste Monit Tnk Pmps Disch) and CRITICAL terminate the release. STEP STEP 9:

3.8.3 Set the flow interlock on 0RLP5080 (RL Discharge Total Flow) to the value specified in the "SPECIAL INSTRUCTIONS FOR RELEASE" section of the LWR Permit Report.

3.8.4 Record the RL Flow interlock setpoint on the LWR Permit Report.

3.8.5 Circle the RL header or headers used for this release.

3.8.6 Sign off the "RL Flow Interlock Set @

_______ gpm for Appropriate Headers (A Sat __

and/or B)" blank on the LWR Permit Report Unsat __

STANDARD:

Operator determines the RL Flow Interlock has been set for the incorrect value. The operator will determine that this is an additional reason for which the release should not be initiated.

Examiner Note: This step is critical to determine that this release should not be initiated.

COMMENTS:

PAGE 10 OF 13

Catawba Nuclear Station Admin. JPM A.3S Sept 2021 NRC Exam STEP 10: 3.9 IF 0RLP5080 (RL Discharge Total Flow) is inoperable, perform the following:

STANDARD: Sat __

Operator determines that this step is not applicable.

Unsat __

COMMENTS:

STEP 11: 3.10 IF the LWR Integrator (Liquid Rad Waste Disch, 0WLP6160) is operable, perform the following:

3.10.1 Reset the LWR Integrator (located on 1MC11).

3.10.2 Sign off the "Reset LWR Integrator" blank Sat __

on the LWR Permit Report.

Unsat __

STANDARD:

Operator determines the LWR Integrator has been reset.

COMMENTS:

PAGE 11 OF 13

Catawba Nuclear Station Admin. JPM A.3S Sept 2021 NRC Exam STEP 12: 3.11 IF the LWR Integrator (Liquid Rad Waste Disch, 0WLP6160) is inoperable, perform the following:

STANDARD: Sat __

Operator determines that this step is not applicable.

Unsat __

COMMENTS:

STEP 13: 3.12 Set 1WL-124 (Waste Monit Tnk Pmps Disch) (located on 1MC11) to the "Recommended Release Rate (gpm)" CRITICAL specified on the LWR Permit Report. STEP 3.13 Enter the "Recommended Release Rate (gpm)" specified on the LWR Permit Report.

STANDARD:

Operator determines the 1WL-124 has NOT been set to the recommended release rate. The operator will determine that Sat __

this is an additional reason for which the release should not be initiated.

Unsat __

Examiner Note: This step is critical to determine that this release should not be initiated.

COMMENTS:

END 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:

• Both Units are at 100% power.

• There are currently no liquid waste releases in progress.

• The following equipment is in service:

o 1A & 1B RC Pumps o 0RLP5080 (RL Discharge Total Flow) is operable and indicating 46,400 gpm through A & B RL Discharge Headers o 1B RN Pump in normal alignment o LWR Integrator (0WLP6160) is operable

• LWR #2021056 has been delivered to the Control Room and was approved by the previous shifts CRS.

o OP/0/B/6500/113 (Operations Liquid Waste Release), Enclosure 4.1 (Liquid Waste Release form a Monitor Tank) is in progress and has been completed through step 3.14

• The Unit 1 BOP has notified you (per step 3.15) that the LWR is ready to be released.

INITIATING CUE:

Review LWR #2021056 to determine if the release should be initiated. If applicable, list all issues that would prevent release initiation.

Initiate Release YES NO circle one Reason(s) (if any)

Duke Energy Procedure No.

Catawba Nuclear Station OP/0/B/6500/113 Revision No.

Operations Liquid Waste Release 010 Electronic Reference No.

Continuous Use CP0095WS

OP/0/B/6500/113 Page 2 of 2 Operations Liquid Waste Release

1. Purpose To aid the operator in the correct methods of performing steps in Radwaste procedure OP/0/B/6500/015 (Discharging a Monitor Tank to the Environment) and Radiation Protection procedure HP/0/B/1004/004 (Radioactive Liquid Waste Release). Also to aid the operator as to limits and results expected while these procedures are being performed.

2. Limits and Precautions 2.1 Ensure that RN is discharging through at least one RL header.

2.2 Ensure that RN is NOT discharging to SNSWP.

2.3 If the pre-set radiation levels are exceeded on EMF-49 or the dilution flow rate drops below the setpoint for 0RLP5080 (RL Discharge Total Flow), 1WL-124 (Waste Monit Tnk Pmps Disch) will trip closed.

2.4 Releases that are interrupted by EMF-49 "HI-RAD" trips may be initiated up to a maximum of three times, including original initiation, without re-sampling per HP/0/B/1004/004 (Radioactive Liquid Waste Release).

2.5 Turbine Building Sump releases are secured if the pre-set levels are exceeded on 1/2EMF-31.

3. Procedure Refer to Section 4 (Enclosures)

4. Enclosures 4.1 Liquid Waste Release from a Monitor Tank 4.2 Discharging a Contaminated Turbine Building Sump to Holdup Pond

Enclosure 4.1 OP/0/B/6500/113 Liquid Waste Release from a Monitor Tank Page 1 of 9

1. Limits and Precautions 1.1 Ensure that RN is discharging through at least one RL header.

1.2 Ensure that RN is NOT discharging to SNSWP.

1.3 If the pre-set radiation levels are exceeded on EMF-49 or the dilution flow rate drops below the setpoint for 0RLP5080 (RL Discharge Total Flow), 1WL-124 (Waste Monit Tnk Pmps Disch) will trip closed.

1.4 Releases that are interrupted by EMF-49 "HI-RAD" trips may be initiated up to a maximum of three times, including original initiation, without re-sampling per HP/0/B/1004/004 (Radioactive Liquid Waste Release).

2. Initial Conditions CC__ 2.1 Verify Radwaste has initiated OP/0/B/6500/015 (Discharging a Monitor Tank to the Environment).

CC__ 2.2 Verify LWR (Liquid Waste Release) Permit Report has been delivered to the CRS.

3. Procedure

_____ 3.1 IF AT ANY TIME within 60 seconds after initiating the release with EMF-49 functional, 1RAD-1, F/4 "EMF-49 LIQUID WASTE DISCH LOSS OF FLOW" alarm CANNOT be cleared, the release shall be secured and EMF-49 declared nonfunctional.

_____ 3.2 IF AT ANY TIME during a release, a Site Assembly occurs, secure release and have Radwaste ensure the following valves are locked closed:

1WL-949 (RMT Outlet To Waste Monitor Tank Disch Radiation Monitor EMF-49) 1WL-113 (Waste Monitor Tank A Pump Disch To Radiation Monitor 1EMF-49) 1WL-187 (Waste Monitor Tank B Pump Disch To Radiation Monitor)

Enclosure 4.1 OP/0/B/6500/113 Liquid Waste Release from a Monitor Tank Page 2 of 9

_____ 3.3 IF AT ANY TIME during this release the OAC is out of service, initiate a 15 minute increased surveillance per OMP 2-31 (Control Room Instrumentation Status) to verify:

3.3.1 The following RN valves remain OPEN:

1RN-57A (Station RN Disch To RL Sys) 1RN-843B (Station RN Disch To RL Sys) 1RN-54A (Station RN Disch Hdr X-Over) 1RN-53B (Station RN Discharge Hdr X-Over) 1RN-1A (RN P/H Pit A Isol From Lake) 1RN-2B (RN P/H Pit A Isol From Lake) 1RN-5A (RN P/H Pit B Isol From Lake) 1RN-6B (RN P/H Pit B Isol From Lake) 3.3.2 The following valves remain CLOSED:

1RN-3A (RN P/H Pit A Isol From SNSWP) 1RN-4B (RN P/H Pit B Isol From SNSWP) 1RN-63A (RN Hdr A Return To SNSWP) 1RN-58B (RN Hdr B Return To SNSWP)

_____ 3.3.3 IF any of the above RN Valve(s) are found out of position, secure the release immediately.

NOTE: 1. The following steps are to be completed, the information is to be entered and the appropriate steps (designated by "0") signed off on the LWR Permit Report.

2. Verifying EMF setpoints correct requires:

Verification that Trip 1 is higher than background Verification that Trip 2 is higher than Trip 1

3. Steps 3.4 - 3.16 provide instructions for completing the "COMPLETE PRIOR TO RELEASE" section of the LWR Permit Report.

BB

_____ 3.4 CRS performs the following concerning the LWR Permit Report:

CRS X Verifies LWR Permit Report refers to correct EMF.

X Verifies EMF setpoints correct.

X Signs and dates the LWR Permit Report authorizing the release.

Enclosure 4.1 OP/0/B/6500/113 Liquid Waste Release from a Monitor Tank Page 3 of 9 CC__ 3.5 IF EMF-49 is functional, perform the following:

CC__ 3.5.1 Verify EMF-49 (Low Range) is functional per SLC 16.11-2, Table 16.11-2-1 using OP/0/A/6500/080 (EMF Output Modules).

CC__ 3.5.2 Sign off the "EMF Source Checked & Operable" blank on the LWR Permit Report.

CC__ 3.5.3 Set EMF-49 (Low Range) trip setpoints to the values listed in "SETPOINT DATA" section on the LWR Permit Report using OP/0/A/6500/080 (EMF Output Modules).

CC__ 3.5.4 Sign off the "EMF49L Setpoints Set (Low Range)" blank on the LWR Permit Report.

NOTE: The person performing Steps 3.5.5 and 3.5.6 shall NOT be the same as in Step 3.5.4.

DD__ 3.5.5 Verify the EMF-49 (Low Range) trip setpoints are set as specified in "SETPOINT DATA" section on the LWR Permit Report using OP/0/A/6500/080 (EMF Output Modules).

DD__ 3.5.6 Sign off the "(I.V.) Independent Verification" blank on the LWR Permit Report.

NOTE: Monitoring for highest count rate during release using a digital EMF chart recorder does NOT require an initial setup.

CC__ 3.5.7 IF using the OAC to obtain the highest count rate during release, monitor OAC point C1E0263 (EMF49L Waste Liquid Discharge).

N/A CC 3.6 IF EMF-49 is nonfunctional, perform the following:

_____ 3.6.1 Notify Radiation Protection to take action per HP/0/B/1004/004 (Radioactive Liquid Waste Release).

Person notified _____________________________________

_____ 3.6.2 N/A the following steps on the LWR Permit Report:

"EMF Source Checked" "EMF49L Setpoints Set (Low Range)"

"(I.V.) Independent Verification"

Enclosure 4.1 OP/0/B/6500/113 Liquid Waste Release from a Monitor Tank Page 4 of 9 3.7 Complete the following steps on the LWR Permit Report documenting the RN and RL Systems status:

CC__ 3.7.1 Ensure at least the number of RN and RL pumps assigned to the LWR (listed on page 2 of LWR Permit) are operating.

CC___ 3.7.2 Sign off the "Ensure number of RN Pumps Operating is at least #.##" blank on the LWR Permit Report where #.## is the number of RN Pumps listed on page 2 of LWR Permit.

CC__ 3.7.3 Sign off the "Ensure number of RL Pumps Operating is at least #.##" blank on the LWR Permit Report where #.## is the number of RL Pumps listed on page 2 of LWR Permit.

CC__ 3.8 IF 0RLP5080 (RL Discharge Total Flow) is operable, perform the following:

CC__ 3.8.1 Enter the RL flow rate on the LWR Permit Report as read on 0RLP5080 (RL Discharge Total Flow) (located on 1MC9).

CC__ 3.8.2 Sign off the "RL Flowrate _______ gpm" blank on the LWR Permit Report.

NOTE: If RL flow drops below this setpoint, it will automatically close 1WL-124 (Waste Monit Tnk Pmps Disch) and terminate the release.

CC__ 3.8.3 Set the flow interlock on 0RLP5080 (RL Discharge Total Flow) to the value specified in the "SPECIAL INSTRUCTIONS FOR RELEASE" section of the LWR Permit Report.

CC__ 3.8.4 Record the RL Flow interlock setpoint on the LWR Permit Report.

CC__ 3.8.5 Circle the RL header or headers used for this release.

CC__ 3.8.6 Sign off the "RL Flow Interlock Set @ _______ gpm for Appropriate Headers (A and/or B)" blank on the LWR Permit Report.

N/A CC 3.9 IF 0RLP5080 (RL Discharge Total Flow) is inoperable, perform the following:

_____ 3.9.1 Estimate the flow rate every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per PT/0/A/4250/011 (RL Temperature and Discharge Flow Determination).

_____ 3.9.2 Record estimated flow rate on the LWR Permit Report and attach copies of all enclosures used to the LWR Permit Report.

_____ 3.9.3 Sign off the "RL Flowrate _______ gpm" blank on the LWR Permit Report.

Enclosure 4.1 OP/0/B/6500/113 Liquid Waste Release from a Monitor Tank Page 5 of 9 CAUTION: Setting the RL flow interlock at "0" overrides the interlock on 1WL-124 (Waste Monit Tnk Pmps Disch). RL flow rate shall be closely monitored and the release stopped if the flow drops below the RL Flow interlock Setting specified on the "SPECIAL INSTRUCTIONS FOR RELEASE" Section of the LWR Permit Report.

_____ 3.9.4 Set the RL flow interlock on "0".

_____ 3.9.5 Record the RL Flow interlock setpoint on the LWR Permit Report.

_____ 3.9.6 Note on the LWR Permit Report that the RL Flow interlock is inoperable.

_____ 3.9.7 Circle the RL header or headers used for this release.

_____ 3.9.8 Sign the "RL Flow Interlock Set @ _______ gpm for Appropriate Headers (A and/or B)" blank on the LWR Permit Report.

CC__ 3.10 IF the LWR Integrator (Liquid Rad Waste Disch, 0WLP6160) is operable, perform the following:

CC__ 3.10.1 Reset the LWR Integrator (located on 1MC11).

CC__ 3.10.2 Sign off the "Reset LWR Integrator" blank on the LWR Permit Report.

N/A CC 3.11 IF the LWR Integrator (Liquid Rad Waste Disch, 0WLP6160) is inoperable, perform the following:

_____ 3.11.1 Notify Radwaste that Alternate Flow Instruments, Data and Data Sheets per OP/0/B/6500/015 (Discharging a Monitor Tank to the Environment) must be used to determine volume released.

Person notified __________________________________________

_____ 3.11.2 N/A the "Reset LWR Integrator" blank on the LWR Permit Report.

CC__ 3.12 Set 1WL-124 (Waste Monit Tnk Pmps Disch) (located on 1MC11) to the "Recommended Release Rate (gpm)" specified on the LWR Permit Report.

CC__ 3.13 Enter the "Recommended Release Rate (gpm)" specified on the LWR Permit Report.

CC__ 3.14 Sign off the "1WL124 Flow Set @ _____ gpm" blank on the LWR Permit Report.

_____ 3.15 Notify the CRS that LWR is ready to be released.

Enclosure 4.1 OP/0/B/6500/113 Liquid Waste Release from a Monitor Tank Page 6 of 9

_____ 3.16 IF AT ANY TIME an automatic closure on low RL flow OR high radiation level occurs, complete the following to reopen 1WL-124 (Waste Monit Tnk Pmps Disch):

_____ 3.16.1 Reset 1WL-124 (Waste Monit Tnk Pmps Disch) to "0".

_____ 3.16.2 Set 1WL-124 (Waste Monit Tnk Pmps Disch) (located on 1MC11) to the "Recommended Release Rate (gpm)" specified on the LWR Permit Report.

NOTE: The Liquid Waste Release is now ready to be initiated per OP/0/B/6500/015 (Discharging a Monitor Tank to the Environment). Subsequent steps in this procedure are to be completed after the release is terminated.

_____ 3.17 Close 1WL-124 (Waste Monit Tnk Pmps Disch).

NOTE: The LWR integrator reading shall be recorded prior to flushing.

_____ 3.18 IF the LWR Integrator (Liquid Rad Waste Disch, 0WLP6160) is operable, perform the following:

_____ 3.18.1 Record the volume released on the LWR Permit Report.

Volume released = Integrator reading X 10.

_____ 3.18.2 Sign off the "Volume Released ______ gal" blank on the LWR Permit Report.

_____ 3.18.3 Reset the LWR Integrator.

_____ 3.18.4 Sign off the "Reset LWR Integrator" blank on the LWR Permit Report.

_____ 3.19 IF the LWR Integrator (Liquid Rad Waste Disch, 0WLP6160) is inoperable, perform the following:

_____ 3.19.1 Record the volume released as calculated from Alternate Flow Instruments, Data and Data Sheets per OP/0/B/6500/015 (Discharging a Monitor Tank to the Environment).

_____ 3.19.2 Sign off the "Volume Released ________ gal" blank on the LWR Permit Report.

_____ 3.19.3 N/A the "Reset LWR Integrator" blank on the LWR Permit Report.

Enclosure 4.1 OP/0/B/6500/113 Liquid Waste Release from a Monitor Tank Page 7 of 9

_____ 3.20 IF EMF-49 was functional during the release, perform the following:

_____ 3.20.1 Record the EMF reading after flushing on the LWR Permit Report.

_____ 3.20.2 Sign off the "EMF Reading after Flush ________ cpm" blank on the LWR Permit Report.

3.20.3 Reset the EMF-49 (low range) setpoints as follows:

3.20.3.1 Calculate EMF-49 setpoints as follows:

_____ A. Record the un-rounded setpoint values:

Trip 2 = 3 x (EMF Reading after Flush) = ________

Trip 1 = Trip 2 x .70 = ________

NOTE: The EMF setpoints are rounded to 3 significant digits (using standard mathematical rounding) before entry on EMF. For example 2342 cpm = 2.34E+03 and 1635 cpm =

1.64E+03.

_____ B. Round the setpoints calculated in Step 3.20.3.1A to 3 significant digits in scientific notation:

Trip 2 = _______ cpm Trip 1 = _______ cpm

_____ 3.20.3.2 Set EMF-49 (low range) Trip 1 and Trip 2 setpoints to the values determined in Step 3.20.3.1B per OP/0/A/6500/080 (EMF Output Modules).

_____ 3.20.3.3 Enter Trip 1 and Trip 2 setpoints on the LWR Permit Report.

_____ 3.20.4 Sign off the "Reset EMF49L Setpoints EMF Reading (cpm) after Flush"

____________ cpm X 3 = _________ (Trip2)

Trip 2 X .70 = ___________(Trip 1)" blank on the LWR Permit Report.

Enclosure 4.1 OP/0/B/6500/113 Liquid Waste Release from a Monitor Tank Page 8 of 9 3.20.5 Record the highest EMF-49 reading during the release on the LWR Permit Report from one of the following:

3.20.5.1 Highest reading from OAC point C1E0263.

OR 3.20.5.2 Perform the following on the applicable digital EMF chart recorder:

_____ A. Depress the "Historical" icon. (Located at bottom of screen, left of keyboard icon)

_____ B. Select "Memory".

_____ C. Select "Start of History". (Binocular icon)

_____ D. Select "Search by Time".

_____ E. Enter the start date and start time.

_____ F. Select "Search".

NOTE: Time intervals per inch can be changed by depressing the "+" or "-" buttons.

_____ G. While viewing the digital values on the left side of the screen, scroll across the trend by depressing the ">" or ">>" buttons and obtain the highest reading.

_____ H. Depress the "Historical" icon to exit history.

_____ 3.20.6 Sign off the "Highest EMF Reading During Release:_______ cpm" blank on the LWR Permit Report.

NOTE: The person performing Step 3.20.7 shall NOT be the same individual who originally performed the associated actions in Steps 3.20.3.1 and 3.20.3.2.

_____ 3.20.7 Independently verify trip setpoints are reset as described in Steps 3.20.3.1 and IV 3.20.3.2 using OP/0/A/6500/080 (EMF Output Modules).

Enclosure 4.1 OP/0/B/6500/113 Liquid Waste Release from a Monitor Tank Page 9 of 9

_____ 3.21 IF EMF-49 was nonfunctional during the release, N/A the following steps on the LWR Permit Report:

"EMF Reading after Flush _______ cpm" "Reset EMF49L Setpoints EMF Reading (cpm) after Flush

____________ cpm X 3 = _________ (trip 2)

Trip 2 X .70 = ___________(trip 1)"

"Highest EMF Reading During Release:_______ cpm"

_____ 3.22 Set the RL flow interlock to "0".

_____ 3.23 Sign off the "RL Flow Interlock Set @ ZERO (0)".

_____ 3.24 Verify all blanks on the LWR Permit Report are properly filled out and signed or N/A'd as appropriate.

_____ 3.25 Sign and date the "COMPLETION OF RELEASE ACKNOWLEDGED:" "OPS SRO" SRO blank on the LWR Permit Report.

_____ 3.26 Place the completed LWR Permit Report in the completed release box.

3.27 Do NOT file this enclosure in the Control Copy of this procedure.

RETDAS v3.5.l <DPCCNS Rev.4.0> CANBERRA LIQUID WASTE RELEASE PERM IT REPORT LWR Number: 2021056 RL/RN PUMP DATA========================----am--------======*--=====

RL pumps assigned to release......... .... .. . . .. . ............... 1.00 RN pumps assigned to release ... , .. ,, ........................... 1. 00 Minimum RL flow interlock setpoint for radionuclides (gpm) ..... 2.76E+04

RECOMMENDED RELEASE RATE=============---====***-===-=======****=

Allowable release rate (gpm) ................................... 3.73E+02 Recommended release rate (gpm) ................................. l.OOE+02 Release rate margin (%) ........................................ 272.74

=== SETPOIN T DATA=====================================================-

EMF49L in Service . . ............ ............ . . . .. . .. . . .... . ... Yes EMF49L Background (cpm) ....................................... 3.91E+02 Cs-137 Equivalence (uCi/ml) ..... , .............................. 2.llE-06 Expected CPM......................................... , ......... l .13E+03 50 % of Expected CPM................................ , , ......... 5.64E+02 Trip l setpoint (cpm) .... , .. ,,.,, .. , ........................... 2.43E+04 Trip 2 setpoint (cpm) .......................................... 3.24E+04

• • • SPECIAL INSTRUCTIONS FOR RELEASE=========*-*--*--*=======**--*====

• RL flow interlock must be greater than or equal to 2.76E+04 gpm

• 0 EMF 49 FUNCrIONAL Performed by: Date: _Today___

Verified by: y ___

Date: _Toda L Date/Time: Today /0300 rpshiftD: Retdas Page - 2

RETDAS v3. 5 .1 <DPCCNS Rev. 4. 0> CANBERRA LWR Number: 2021056 Release ID: 2 Waste Monitor Tank "B" Release Mode: 2 BatG:h CRS AUTHORIZING RELEASE t',,,t,,,,;',('-.t;,.,,.,.,;,, DATE/TIME 7°""1 / 0500 COMPLETE PRIOR TO RELEASE': COMPLETE FOLLOWING RELEASE:

(O)EMF49L Source Checked & Operable (O)EMF49L Setpoints Set (Low Range)

TRIP 1 2.43 e4 cpm TRIP 2 2-43 e6 cpm (O)

Date/Time First Trip

/

(O){I.V.)Independent Verification (0)

Date/Time Second Trip

/

(0) e8 Ensure number of RL Pumps (0)

Date/Time Release Secured

/

---Operating is at least 1.00 (O)Ensure number of RN Pumps Operating is at least 1.00 (O} Tank Level _____ %

(0) _fi§_RL Flowrate 46,400 gpm (01 Flush per Procedure (0) ee RL Flowrate Interlock set @

---2.760 gpm For Appropriate Headers (O)___Flush secured (A, B, or A&B)

(Ol EMF Reading after Flush:

{O)Reset LWR Integrator

_______cpm (0)1WL124 Flowrate set@ 1000 gpm (0) Volume Released ___gal (0)-- Date/Time Release Started

- / (0) Reset LWR Integrator (Ol ___OWLP6160 channel check (0) Reset EMF49L Setpoints (OPS Contact)

/ _____ EMF Reading (cpm)After Flush:

______/ _______

(O)___Date/Time Release Secured ___cpm X 3 =___cpm (Trip2)

Trip 2 X 0.7 -___cpm {Tripl)

(O) ___Date/Tirne First Restart

/ (0) Highest EMF Reading

---uring Release: ___cpm (0) ---Date/Time Second Restart

/ (0) RL Flowrate Interlock Set

---@ Zero (OJ COMPLETION OF RELEASE ACKNOWLEDGED:

CRS DATE/TIME____/ ____

RP SHIFT REVIEW_____________ DATE/TIME ____/ ____

Ensure all signoffs are legible. Print name where indicated on next page.

Date/Time: Today/0300 rpshiftD: Retdas Page - 3

Catawba Nuclear Station Admin. JPM A.4S Sept 2021 NRC Exam JPM A.4S SRO PAGE 1 OF 6

Catawba Nuclear Station Admin. JPM A.4S Sept 2021 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:

AD-EP-ALL-0101 (Emergency Classification)

CSD-EP-CNS-0101-02 (EAL Wallcharts)

AD-EP-ALL-0304 (State and County Notifications)

Task Standard: Using AD-EP-ALL-0101 (Emergency Classification) CSD-EP-CNS-0101-02 (EAL Wallcharts), applicant classifies the event as an Alert (SA1.1) 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.4S Sept 2021 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 seismic event has been felt within the protected area.

• The following events have occurred:

o Annunciator 1AD-4, B/8 OBE EXCEEDED is received in the control room.

o A Loss of Offsite Power (LOOP) occurs on Unit 2.

o 2B D/G fails to start.

o The rounds AO reports the 1A NI (Safety Injection) Pump discharge piping is cracked with water leaking out at 125 drops per minute.

INITIATING CUES:

• You are the Emergency Coordinator.

• Classify this event per AD-EP-ALL-0101 (Emergency Classification).

• Emergency Coordinator Judgment is NOT to be used when making this classification.

• Fill out the Emergency Notification Form per AD-EP-ALL-0304 (State and County Notifications).

• This JPM is time critical.

EXAMINER NOTE:

After reading cue, provide applicant with a copy of AD-EP-ALL-0101 (Emergency Classification) CSD-EP-CNS-0101-02 (EAL Wallcharts) and AD-EP-ALL-0304 (State and County Notifications)

PAGE 3 OF 6

Catawba Nuclear Station Admin. JPM A.4S Sept 2021 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 Alert (SA1.1) due to the loss of all but one AC power source 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 Unusual Event (HU2.1) due to the OBE exceeded alarm being received in the control room. Alert (SA9.1) is not applicable because only one train of a required SAFETY SYSTEM needed for the current operating mode is affected.

Since Unit 2 is in a higher classification than Unit 1, the emergency classification for the site will be an Alert (SA1.1).

STANDARD: ___ SAT Applicant determines from CSD-EP-CNS-0101-02 (EAL Wallcharts), ___ UNSAT that Catawba is in an Alert SA1.1.

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.4S Sept 2021 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 seismic event has been felt within the protected area.

• The following events have occurred:

o Annunciator 1AD-4, B/8 OBE EXCEEDED is received in the control room.

o A Loss of Offsite Power (LOOP) occurs on Unit 2.

o 2B D/G fails to start.

o The rounds AO reports the 1A NI (Safety Injection) Pump discharge piping is cracked with water leaking out at 125 drops per minute.

INITIATING CUES:

• You are the Emergency Coordinator.

• Classify this event per AD-EP-ALL-0101 (Emergency Classification).

• Emergency Coordinator Judgment is NOT to be used when making this classification.

• Fill out the Emergency Notification Form per AD-EP-ALL-0304 (State and County Notifications).

• This JPM is time critical.

Declared EAL: _______________

Declaration Time: ______________

Items marked with a

• indicate critical tasks JPM A.4 KEY NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM MESSAGE # ________ 1 SIM:(803) 831-3807 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.* EAL #______________

SA1.1

• Declaration Date: ____/____/____ Time: ________

Termination Date: ____/____/____ Time: ________(mark "N/A" for EAL # & Description)

Loss of all but one AC power source to essential buses for 15 minutes or longer.

EAL DESCRIPTION: _________________________________________________________________________________

5.* RELEASE TO THE ENVIRONMENT (caused by the emergency): 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 JPM A.4 KEY

GOVERNMENT AGENCIES NOTIFIED Record the name, date, time, and agencies notified as applicable.

1. York County WP/EOC (name) 9-1-803/329-1110 (date) (time)

2. Mecklenburg County WP/EOC (name) 9-704/336-2441 (WP) 9-704/432-4120 (EOC)

(date) (time)

3. Gaston County WP/EOC (name) 9-704/866-3300 (date) (time)

4. North Carolina EOC/WP (name) 9-1-919/733-3300 (Primary) 9-1-800/858-0368 (Alt.)

(date) (time)

5. North Carolina Alt. WP (name) 9-1-828/466-5500 9-1-828/466-5501 (date) (time)

6. North Carolina Alt. EOC (name) 9-1-919/733-3300 (Primary) 9-1-800-858-0368 (Alt.)

(date) (time)

7. South Carolina WP (name) 9-1-803/737-8500 (Primary) 9-1-800/811-8045 (Alt.)

(date) (time)

8. South Carolina Alt. WP (name) 9-1-803/896-9621 (date) (time)

9. South Carolina EOC (name) 9-1-803/737-8500 (Primary) 9-1-803-737-8724 (Alt.)

(date) (time)

Information Use NUCLEAR OPERATING FLEET ADMINISTRATIVE PROCEDURE AD-EP-ALL-0101 EMERGENCY CLASSIFICATION REVISION 2 Effective Dates:

07/29/2020 07/29/2020 07/29/2020 07/29/2020 07/29/2020 Brunswick Catawba Harris (HNP) McGuire Oconee 07/29/2020 07/29/2020 Robinson NGO

EMERGENCY CLASSIFICATION AD-EP-ALL-0101 Rev. 2 Page 2 of 12 REVISION

SUMMARY

PRR 2196707 DESCRIPTION

• Section 4.1 Step 1: Changed 'Evaluating, classifying and declaring' to 'Evaluates, classifies and declares' to align with AD-DC-ALL-0202.

• Section 4.1 Step 2: New responsibility, 'Enters AD-EP-ALL-0111, Control Room Activation of the ERO'. PRR 2305765

• Section 4.2: Added '(TSC)'.

• Section 4.2 Step 1: Changed 'Evaluating, classifying and declaring' to 'Evaluates, classifies and declares' to align with AD-DC-ALL-0202.

• Section 4.2 Step 2: New responsibility, 'Enters AD-EP-ALL-0105, Activation and Operation of the Technical Support Center'.

• Section 5.1 Step 1 Old CAUTION: Deleted CAUTION.

• Section 5.1 Step 1 NOTE: Moved information from old CAUTION to NOTE. Added second bullet, 'The primary tool for determining the Emergency Classification Level (ECL) is the Emergency Classification Wallchart' (PRR 2229095).

• Section 5.1 Old Steps 1 through 3: Relocated to new Attachment 1, EAL Wallchart Guidance. PRR 2196707

• Section 5.1 Step 1: New step, 'The Emergency Classification Wallchart user may (but is not required to) consult the EAL Technical Basis Document in order to obtain additional information concerning the Initial Conditions (ICs) and EALs under classification consideration.' PRR 2229095

• Section 5.1 Step 2: New step, 'Determine emergency classification per EAL Wallchart.' PRR 2196707

• Section 5.1 Step 2.a: New step, 'If needed, then refer to Attachment 1, EAL Wallchart Guidance.' PRR 2196707

• Section 5.1 Step 3.c Bullet: Changed '[time]' to '[current time]'. PRR 2295310

• Section 5.1 Old Steps 6 through 8: Deleted Old Step 6 and relocated Old Steps 7 and 8 to new Attachment 1, EAL Wallchart Guidance. PRR 2196707

• Section 6.0 Old Step 1: Deleted 'All checklists, logs and forms completed as the result of implementing this procedure shall be collected at the end of the event and provided to the Site Emergency Preparedness Manager'; renumbered remaining step.

• Section 7.2 Old Steps 2, 3, 5, 6, 7, and 8: Deleted [BNP] 0PEP-02.1, [BNP] 0PEP-02.2.1 (PRR 2280927),

[RNP] Emergency Action Level Matrix1, [RNP] Emergency Action Level Matrix2, [RNP] Emergency Action Level Matrix3, and [RNP] EPCLA-04 (PRR 2303130); renumbered remaining references.

• Section 7.3 Old Miscellaneous Documents 2 through 8: Deleted [HNP EP-EAL (PRR 2310065),

[CNS] EP-EAL-EALMATRIX (PRR 2304471), [ONS] EP-EAL-EALMATRIX (PRR 2305242),

[MNS] EP - EAL-WALLCHART, [CNS] EPA D (PRR 2304471), [ONS] EPA SECTION D (PRR 2305242), and

[HNP] FAD-HNP-EP-EPEAL MATRIX (PRR 2310065).

• Section 7.3 Miscellaneous Document 2 through Section 7.3 Miscellaneous Document 13, Section 7.3 Miscellaneous Document 16: Added [BNP] CSD-EP-BNP-0101-01, [BNP] CSD-EP-BNP-0101-02 (PRR 2280927), [CNS] CSD-EP-CNS-0101-01, [CNS] CSD-EP-CNS-0101-02 (PRR 2304471),

[HNP] CSD-EP-HNP-0101-01, [HNP] CSD-EP-HNP-0101-02 (PRR 2310065), [MNS] CSD-EP-MNS-0101-01,

[MNS] CSD-EP-MNS-0101-02 (PRR 2298233), [ONS] CSD-EP-ONS-0101-01, [ONS] CSD-EP-ONS-0101-02 (PRR 2305242), [RNP] CSD-EP-RNP-0101-01, [RNP] CSD-EP-RNP-0101-02 (PRR 2303130), and RIS 2007-02 (PRR 2213104).

• Attachment 1: New attachment, EAL Wallchart Guidance; renumbered remaining attachment. PRR 2196707

EMERGENCY CLASSIFICATION AD-EP-ALL-0101 Rev. 2 Page 3 of 12 TABLE OF CONTENTS SECTION .......................................................................................................................... PAGE 1.0 PURPOSE ..................................................................................................................... 4 2.0 SCOPE .......................................................................................................................... 4 3.0 DEFINITIONS ................................................................................................................ 4 4.0 RESPONSIBILITIES ...................................................................................................... 4 5.0 INSTRUCTIONS ............................................................................................................ 5 5.1 Assessment, Classification and Declaration of Events .................................................. 5 5.2 Terminating from a Declared Emergency ...................................................................... 6 6.0 RECORDS..................................................................................................................... 6

7.0 REFERENCES

.............................................................................................................. 6 ATTACHMENTS 1 EAL Wallchart Guidance................................................................................................ 8 2 Event Termination Checklist ........................................................................................ 11

EMERGENCY CLASSIFICATION AD-EP-ALL-0101 Rev. 2 Page 4 of 12 1.0 PURPOSE

1. This procedure provides instruction for the evaluation, classification and declaration of an emergency at a Duke Energy nuclear site.

2. This procedure provides guidance for event termination and entry into Recovery.

2.0 SCOPE

1. This procedure applies to all Duke Energy nuclear operating sites and is continually used to assess events and conditions at the site in order to classify and declare emergencies.

3.0 DEFINITIONS None 4.0 RESPONSIBILITIES 4.1 Shift Manager

1. Evaluates, classifies and declares emergencies prior to TSC Activation.

2. Enters AD-EP-ALL-0111, Control Room Activation of the ERO.

4.2 Emergency Coordinator (TSC)

1. Evaluates, classifies and declares emergencies after activation of the TSC.

2. Enters AD-EP-ALL-0105, Activation and Operation of the Technical Support Center.

EMERGENCY CLASSIFICATION AD-EP-ALL-0101 Rev. 2 Page 5 of 12 5.0 INSTRUCTIONS 5.1 Assessment, Classification and Declaration of Events NOTE

• The highest emergency classification for which an Emergency Action Level (EAL) is exceeded shall be declared.

• The primary tool for determining the Emergency Classification Level (ECL) is the Emergency Classification Wallchart.

1. The Emergency Classification Wallchart user may (but is not required to) consult the EAL Technical Basis Document in order to obtain additional information concerning the Initial Conditions (ICs) and EALs under classification consideration.

2. Determine emergency classification per EAL Wallchart.

a. IF needed, THEN refer to Attachment 1, EAL Wallchart Guidance.

3. Declare the event using the "Update" method as follows:

a. After completing all required verifications and determining an EAL applies, the EC shall perform an update as follows:

• "Update. I intend to declare a(n) ________ [GE, SAE, Alert, UE] for EAL _______. Are there any challenges to this declaration?"

b. IF there are challenges, THEN make corrections.

c. IF there are no challenges or challenges have been resolved, THEN announce in the same update:

• "Update, at _______ [current time] a(n) _________

[GE, SAE, Alert, UE] has been declared for EAL

__________. Possible upgrades include __________.

End of update."

EMERGENCY CLASSIFICATION AD-EP-ALL-0101 Rev. 2 Page 6 of 12 5.2 Terminating from a Declared Emergency NOTE The decision to terminate an event is NOT time dependent. There is no regulatory 15 minute notification requirement for exiting a declared emergency.

1. Complete Attachment 2, Event Termination Checklist, to determine if termination conditions are met.

2. IF conditions do NOT allow event termination, THEN continue monitoring events.

3. WHEN conditions allow for event termination, THEN perform AD-EP-ALL-0110, Recovery, to complete termination of the event.

6.0 RECORDS

1. All logs, forms and records completed as result of implementing this procedure during an actual declared event shall be retained as permanent plant records.

a. Nuclear Generation Record Retention Rule number 421734, Life of Plant (LOP), Record Type Code NUC-LIC-003, Licensing Life of Plant Records.

7.0 REFERENCES

7.1 Commitments None 7.2 Procedures

1. [BNP] 0ERP, Radiological Emergency Response Plan (ERP)

2. AD-EP-ALL-0110, Recovery

3. [RNP] PLP-007, Robinson Emergency Plan

4. [HNP] PLP-201, Emergency Plan

EMERGENCY CLASSIFICATION AD-EP-ALL-0101 Rev. 2 Page 7 of 12 7.3 Miscellaneous Documents

1. [CNS] Catawba Emergency Plan

2. [BNP] CSD-EP-BNP-0101-01, EAL Technical Basis Document

3. [BNP] CSD-EP-BNP-0101-02, EAL Wallchart (Both Hot and Cold)

4. [CNS] CSD-EP-CNS-0101-01, EAL Technical Basis Document

5. [CNS] CSD-EP-CNS-0101-02, EAL Wallcharts

6. [HNP] CSD-EP-HNP-0101-01, EAL Technical Basis Document

7. [HNP] CSD-EP-HNP-0101-02, EAL Wallchart (Both Hot and Cold)

8. [MNS] CSD-EP-MNS-0101-01, EAL Technical Basis Document

9. [MNS] CSD-EP-MNS-0101-02, EAL Wallchart (Both Hot and Cold)

10. [ONS] CSD-EP-ONS-0101-01, EAL Technical Basis Document

11. [ONS] CSD-EP-ONS-0101-02, EAL Wallchart (Both Hot and Cold)

12. [RNP] CSD-EP-RNP-0101-01, EAL Technical Basis Document

13. [RNP] CSD-EP-RNP-0101-02, EAL Wallchart (Both Hot and Cold)

14. [MNS] McGuire Emergency Plan

15. [ONS] Oconee Emergency Plan

16. RIS 2007-02, Clarification of NRC Guidance for Emergency Notifications During Quickly Changing Events

EMERGENCY CLASSIFICATION AD-EP-ALL-0101 Rev. 2 Page 8 of 12 ATTACHMENT 1 Page 1 of 3

<< EAL Wallchart Guidance >>

1. Evaluate the All Conditions EAL Wallchart.

• Read the EAL Wallchart from left to right and top to bottom.

• Read the EAL Category.

• Read the EAL subcategory.

• Read the Initiating Condition.

• Read the Mode Applicability bar.

• Read the category number criterion.

• Read any applicable notes or tables.

• Determine EAL classification threshold applicability

2. IF the Reactor Coolant System temperature is greater than [BNP]

212°F OR [CNS, HNP, MNS, ONS, RNP] 200°F, THEN evaluate the Hot Conditions EAL Wallchart.

• Read the EAL Wallchart from left to right and top to bottom.

• Read the EAL Category.

• Read the EAL subcategory.

• Read the Initiating Condition.

• Read the Mode Applicability bar.

• Read the category number criterion.

• Read any applicable notes or tables.

• Determine EAL classification threshold applicability.

EMERGENCY CLASSIFICATION AD-EP-ALL-0101 Rev. 2 Page 9 of 12 ATTACHMENT 1 Page 2 of 3

<< EAL Wallchart Guidance >>

3. IF the Reactor Coolant System temperature is less than or equal to

[BNP] 212°F OR [CNS, HNP, MNS, ONS, RNP] 200°F, THEN evaluate the Cold Conditions EAL Wallchart.

• Read the EAL Wallchart from left to right and top to bottom.

• Read the EAL Category.

• Read the EAL subcategory.

• Read the Initiating Condition.

• Read the Mode Applicability bar.

• Read the category number criterion.

• Read any applicable notes or tables.

• Determine EAL classification threshold applicability.

4. Identify the highest applicable Emergency Classification Level (ECL).

5. Declare the event using the "Update" method as follows:

a. After completing all required verifications and determining an EAL applies, the EC shall perform an update as follows:

• "Update. I intend to declare a(n) ________ [GE, SAE, Alert, UE] for EAL _______. Are there any challenges to this declaration?"

b. IF there are challenges, THEN make corrections.

c. IF there are no challenges or challenges have been resolved, THEN announce in the same update:

• "Update, at _______ [current time] a(n) _________

[GE, SAE, Alert, UE] has been declared for EAL

__________. Possible upgrades include __________.

End of update."

EMERGENCY CLASSIFICATION AD-EP-ALL-0101 Rev. 2 Page 10 of 12 ATTACHMENT 1 Page 3 of 3

<< EAL Wallchart Guidance >>

6. IF the classification level is below a General Emergency, THEN continue to monitor conditions for possible ECL upgrade.

a. Return to the applicable ERO position checklist.

7. IF an EAL threshold has NOT been met or exceeded, THEN perform the following:

a. Continue to monitor conditions for potential changes to ECL.

b. Return to the applicable ERO position checklist.

EMERGENCY CLASSIFICATION AD-EP-ALL-0101 Rev. 2 Page 11 of 12 ATTACHMENT 2 Page 1 of 2

<< Event Termination Checklist >>

Site: Event:

True False N/A

1. Conditions no longer meet an Emergency Action Level and it appears unlikely that conditions will deteriorate.

List any EAL(s) which is/are still exceeded and a justification as to why a state of emergency is no longer applicable:

• If Unusual Event level Emergency Classification Levels (ECLs), then go to the comments/approval section below.

• If all other ECLs, then continue with following questions.

True False N/A

2. Plant releases of radioactive materials to the environment are under control (within Technical Specifications) or have ceased and the potential for a radioactive release is acceptably low.

3. The radioactive plume has dissipated and plume tracking is no longer required. The only environmental assessment activities in progress are those necessary to determine the extent of deposition resulting from passage of the plume.

4. In-plant radiation levels are stable or decreasing, and acceptable given the plant conditions.

5. The reactor is in a stable operating condition or shutdown condition with long-term core cooling available.

EMERGENCY CLASSIFICATION AD-EP-ALL-0101 Rev. 2 Page 12 of 12 ATTACHMENT 2 Page 2 of 2

<< Event Termination Checklist >>

True False N/A

6. The integrity of containment is within Technical Specifications limits for the current plant mode.

7. The operability and integrity of radioactive waste systems, decontamination facilities, power supplies, electrical equipment and plant instrumentation including radiation monitoring equipment is acceptable.

8. Any fire, flood, earthquake or similar emergency condition no longer exists.

9. Any security issues have been resolved.

10. Any onsite medical issues have been resolved.

11. Offsite conditions do not unreasonably limit access of outside support to the site and qualified personnel and support services are available.

12. Discussions have been held with Federal, State and County agencies and agreement has been reached and coordination established to terminate the emergency.

13. All required state, local and NRC notifications for event termination have been prepared.

It is not necessary that all responses listed above be 'TRUE'; however, all items must be considered prior to event termination from Alert or higher classification or entry into Recovery. For example, it is possible that some conditions remain which exceed an EAL threshold following a severe accident, but entry into Recovery is appropriate. Additionally, other significant items not included on this list may warrant consideration (such as severe weather).

Comments:

Approved by: Date/Time:

SM, EC or EOF Director in C&C of the event

Information Use NUCLEAR OPERATING FLEET ADMINISTRATIVE PROCEDURE AD-EP-ALL-0304 STATE AND COUNTY NOTIFICATIONS REVISION 3 Effective Dates:

08/24/2020 11/16/2020 11/16/2020 11/16/2020 08/24/2020 Brunswick Catawba Harris (HNP) McGuire Oconee 11/16/2020 11/16/2020 Robinson NGO

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 2 of 37 REVISION

SUMMARY

PRR 2322562 DESCRIPTION

• Old Section 5.2: Deleted 'Documentation'. PRR 2322562

• Section 6.0 Step 1: Changed from 'All logs, forms, and records completed as the result of implementing this procedure during the actual declared event shall be retained as permanent plant records' to 'Provide all checklists, forms, and other documentation generated by this procedure for retention in the Drill, Exercise, or actual event record package, as necessary'. PRR 2322562

• Section 6.0 Step 1.a: Changed 'Nuclear Generation Record Retention Rule Number 421734, Life of Plant (LOP), Record Type Code NUC-LIC-003, Life of Plant Records' to 'In case of an actual event, retain documentation generated by this procedure in the event record package in accordance with AD-EP-ALL-1000, Conduct of Emergency Preparedness'. PRR 2322562

• Section 6.0 Step 1.b: New step, 'In case of a Drill or Exercise, retain documentation generated by this procedure in the Drill record package in accordance with AD-EP-ALL-0803, Evaluation and Critique of Drills and Exercises'. PRR 2322562

• Section 7.2: Added AD-EP-ALL-0803 and AD-EP-ALL-1000; renumbered remaining references.

• Attachment 1: Changed 'Sample' to 'Emergency Notification Form' and placed parentheses around ENF.

• Attachment 2 Section 1.3 Step 2: Deleted 'from AD-EP-ALL-0304, State and County Notifications,'. Moved Attachment 1, Emergency Notification Form (ENF), to new Step 2.a and added 'should be used as a blank ENF' (PRR 2305089). Attachment 2 Section 1.3 Step 3 NOTE: Added bullet concerning peer check of the ENF and the means for peer check. PRR 2304167, 2304590

• Attachment 2 Section 1.4 Old Step 1.b: Deleted 'Verify the 'Recipient Name' list is correct'; renumbered remaining steps. PRR 2299450

• Attachment 2 Section 1.4 Step 2: Changed from 'If manually faxing the ENF, then transmit the fax according to the site specific fax machine's user guide to send the ENF' to 'If NOT using WebEOC, then communicate information on the ENF verbally while making contact for transmission in Attachment 3, ENF Transmission'.

PRR 2329139

• Attachment 4 Section 1.1 Step 3: Changed 'is located in' to 'may be found in the'. Deleted 'Procedure file cabinet' (PRR 2311970) and added 'or on hard copies stocked within each sites' TSC and the EOF'.

• Attachment 5: For Lines 10 & 11 added bullet 'Projection period is not required when performing a URI Rapid Dose Assessment' (PRR 2163335). Changed 'Fax or Email' to 'Transmit'; changed 'notification' to 'ENF';

changed 'If completing a pre-printed or blank ENF, then use fax machine to send fax to the appropriate recipients' to 'If using a paper ENF, then transmit the ENF verbally as specified in Attachment 8, ENF Transmissions'. PRR 2329139

• Attachment 6: Under Step 5 changed 'Pre-printed ENF and Blank ENF' to 'Paper ENF'. Moved Old Step 7 to Step 8 and added EOF checkboxes. PRR 2231992

• Attachment 7 Changes (PRR 2318460): On Pages 2of 8 through 8 of 8 added 'The first page of this attachment is applicable to all sites. If any of the statements below are true, then a Release is occurring' prior to Step 1. Numbered items on these pages. Under BNP Step 2 added 'with no operational radiation monitor at the release point'. On Pages 3 of 8 through 8 of 8 Step 3 added 'is' before 'occurring' and deleted 'steam line' and 'with known release path to environment (e.g., stuck open steam line valve, steam line break)'. Under CNS added new Step 3.c; under HNP added new Step 3.b; under MNS in Step 3 changed 'Primary and Secondary' to 'Primary to Secondary' and added new Step 3.c; under ONS added new Step 3.b; under RNP added new Step 3.b.

• Attachment 8 Changes: Arranged ENF Transmissions in alphabetical order (BNP, CNS, HNP, MNS, ONS, RNP) versus the current order (MNS, CNS, ONS, BNP, HNP, RNP). PRR 2325215 Indented scripted text.

(PRR 2316401). Under Step 1 of each site's transmission, added 'Please standby' after 'A/an Unusual Event /

Alert / Site Area Emergency / General Emergency has been declared'. PRR 2317710

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 3 of 37 TABLE OF CONTENTS SECTION .......................................................................................................................... PAGE 1.0 PURPOSE ..................................................................................................................... 4 2.0 SCOPE .......................................................................................................................... 4 3.0 DEFINITIONS ................................................................................................................ 4 4.0 RESPONSIBILITIES ...................................................................................................... 5 5.0 INSTRUCTIONS ............................................................................................................ 6 5.1 General Instructions ...................................................................................................... 6 6.0 RECORDS..................................................................................................................... 6

7.0 REFERENCES

.............................................................................................................. 6 ATTACHMENTS 1 Emergency Notification Form (ENF) .............................................................................. 8 2 ENF Completion ............................................................................................................ 9 3 ENF Transmission ....................................................................................................... 13 4 Authentication Guideline .............................................................................................. 17 5 ENF Quick Reference .................................................................................................. 19 6 Offsite Communications Turnover Checklist ................................................................ 21 7 Determining Radiological Release Status.................................................................... 24 8 ENF Transmissions ..................................................................................................... 32

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 4 of 37 1.0 PURPOSE

1. This procedure describes the instructions for Initial and Follow-up Notifications to state and county response organizations in the event of a declared emergency at a Duke Energy nuclear site.

2.0 SCOPE

1. This procedure applies to all operating Duke Energy nuclear sites when an emergency is declared in accordance with site Emergency Plans.

3.0 DEFINITIONS

1. Authentication Code List: A controlled list of numbers and corresponding words provided by the state(s) to authenticate communications between various parties.

2. DEMNET: The primary communication method used by the licensee to communicate emergency information to offsite response organizations.

3. Emergency Notification Form (ENF): The document prepared by the licensee to communicate Initial and Follow-up Notifications to the offsite response organizations.

4. Emergency Release: An unplanned, quantifiable airborne radiological release to the environment attributed to the emergency event.

5. Follow-up Notifications: Periodic notifications to provide updated information to offsite response organizations following an Initial Notification.

6. Initial Notification: The first notification made to offsite response organizations upon declaration of any emergency classification, upgrade in classification (Alert, Site Area Emergency, or General Emergency), or change in Protective Action Recommendations (PARs).

7. Termination Notification: The last notification sent to offsite response organizations communicating termination of the emergency.

8. WebEOC: An electronic emergency response communication system used to provide information within the Duke Energy emergency response facilities and to offsite response organizations.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 5 of 37 4.0 RESPONSIBILITIES 4.1 Shift Manager, Emergency Coordinator, or EOF Director

1. Ensures required notifications are made when in Command and Control.

4.2 TSC Dose Assessor/Radiation Assessment Manager

1. Determines release levels and provides accurate and timely dose projections.

4.3 Emergency Coordinator/Accident Assessment Manager

1. Determines PARs.

4.4 Offsite Communicators

1. Complete and transmit ENFs as outlined in their position-specific checklists using the guidance provided in this procedure.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 6 of 37 5.0 INSTRUCTIONS 5.1 General Instructions

1. Follow instructions in the position-specific checklists and procedures provided for the Control Room, TSC and EOF to make required notifications to State and County agencies.

2. Use guidance provided in the following attachments, as appropriate:

• Attachment 1, Emergency Notification Form (ENF)

• Attachment 2, ENF Completion

• Attachment 3, ENF Transmission

• Attachment 4, Authentication Guideline

• Attachment 5, ENF Quick Reference

• Attachment 6, Offsite Communications Turnover Checklist

• Attachment 7, Determining Radiological Release Status

• Attachment 8, ENF Transmissions 6.0 RECORDS

1. Provide all checklists, forms and other documentation generated by this procedure for retention in the Drill, Exercise, or actual event record package, as necessary.

a. In case of an actual event, retain documentation generated by this procedure in the event record package in accordance with AD-EP-ALL-1000, Conduct of Emergency Preparedness, if required.

b. In case of a Drill or Exercise, retain documentation generated by this procedure in the Drill record package in accordance with AD-EP-ALL-0803, Evaluation and Critique of Drills and Exercises, if required.

7.0 REFERENCES

7.1 Commitments None

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 7 of 37 7.2 Procedures

1. [BNP] 0ERP, Radiological Emergency Response Plan (ERP)

2. AD-EP-ALL-0104, ERO Common Guideline and Forms

3. AD-EP-ALL-0406, Duke Emergency Management Network (DEMNET)

4. AD-EP-ALL-0803, Evaluation and Critique of Drills and Exercises

5. AD-EP-ALL-1000, Conduct of Emergency Preparedness

6. [RNP] PLP-007, Robinson Emergency Plan

7. [HNP] PLP-201, Emergency Plan 7.3 Miscellaneous Documents

1. 66 FR 5427, Consideration of Potassium Iodide in Emergency Plans

2. [CNS] Catawba Emergency Plan

3. CSD-EP-ALL-0104-01, Emergency Telephone Directory

4. [MNS] McGuire Emergency Plan

5. NRC Regulatory Issue Summary (RIS) 2007-02, Clarification of NRC Guidance for Emergency Notifications During Quickly Changing Events

6. [ONS] Oconee Emergency Plan

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 8 of 37 ATTACHMENT 1 Page 1 of 1

<< Emergency Notification Form (ENF) >>

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 9 of 37 ATTACHMENT 2 Page 1 of 4

<< ENF Completion >>

1.0 INSTRUCTIONS 1.1 Initial Notifications

1. Make the Initial Notification to the state(s) and counties within 15 minutes of the event declaration time or a change in Protective Action Recommendation (PAR)

(evacuation and shelter only) using the information contained in the ENF. The ENF is preferred to be approved to make notifications, however it is not required to make notifications of a declared event.

2. The Initial Notification for a General Emergency classification must include PARs.

3. If a higher Emergency Classification Level (ECL) is declared before the notification begins for the lesser ECL, then perform the following: [7.3.5]

a. If possible, then update the ENF to reflect the higher ECL and complete the notification within 15 minutes of the lesser ECL.

b. If it is not possible to update the ENF within 15 minutes of the lesser classification, then add a Line 12 remark that explains a change in classification is forthcoming AND continue notification for lesser ECL to meet the 15 minute requirement.

(1) Complete an Initial ENF for the higher ECL AND perform the notification within 15 minutes of declaration of the higher ECL.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 10 of 37 ATTACHMENT 2 Page 2 of 4

<< ENF Completion >>

1.2 Follow-up Notifications NOTES

• Examples of significant changes requiring a Follow-up Notification include: Dose Assessment Data characterizing a release or addition of Kl, change in release status, evacuation or relocation of site personnel, fires onsite, chemical spills, explosions, MERT activation or injured personnel transported offsite, and any event that would cause or require offsite agency response.

• Follow-up Notifications are to occur within approximately 60 minutes from the first contact of the previous notification until a new time period is agreed upon by all offsite agencies.

• A Termination Notification is a type of Follow-up Notification. Termination Notifications must occur within 60 minutes from the time the last notification was made.

• The purpose for timely turnover from the Shift Manager/EC to the TSC/EC is to relieve the Control Room crew from burdens and distractions that might delay plant stabilization and recovery.

The transfer of Command and Control is a priority over ENF follow-up notifications since the regulatory requirement for timely ERO activation (i.e., within 75 minutes of classification) takes precedence over follow-up.

Do not allow follow-up notification to delay Command and Control turnover, which is required to be completed prior to ERO facility activation.

• It is acceptable to perform an ENF follow-up early, event oversight permitting.

The Shift Manager can request the Offsite Communicator to contact the Offsite Response Organizations to alert the individuals that turnover is in progress, provide a status of the event, and inform the ORO the follow-up form will be sent imminently upon turnover completion.

1. If a significant change to plant conditions occurs, then perform a Follow-up Notification as soon as possible, with the expectation of completion of notification within 30 minutes.

2. An Initial General Emergency Notification should be followed by another Follow-up Notification to include Dose assessment and Meteorological data as soon as possible, with the expectation of completion of notification within 30 minutes.

3. Follow-up Notifications continue to be made throughout the event within approximately 60 minutes from the first contact of the previous notification in Attachment 8, Section 2, or as agreed upon by all offsite agencies receiving the ENF.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 11 of 37 ATTACHMENT 2 Page 3 of 4

<< ENF Completion >>

1.2 Follow-up Notifications (continued)

a. Documentation (log name of officials agreeing to new schedule) shall be maintained for any agreed-upon schedule change.

4. If a Follow-up Notification is due and an upgrade to a higher classification is declared, then do not complete the Follow-up ENF and complete the Initial Notification for the higher classification.

1.3 ENF Completion

1. If WebEOC is available, then access the WebEOC ENF.

2. If WebEOC is NOT available, then obtain a pre-printed or blank ENF.

a. Attachment 1, Emergency Notification Form (ENF), should be used as a blank ENF.

NOTE

• Attachment 5, Page 2, lists the positions responsible for providing information to complete the ENF.

• Only one ENF can be open at a time for the same event (e.g., opening an ENF in the TSC and then opening in the EOF will not allow the EOF to finalize the ENF).

• Peer check of the ENF is a best practice. Means for peer check include, but are not limited to, the following:

Control Room - Review by another person in the Control Room TSC or EOF - Using a video projector for all TSC or EOF personnel review EOF - EOF Offsite Communicator sharing their computer screen with the TSC Offsite Communicator for cross-facility review

3. Complete the ENF per Attachment 5, ENF Quick Reference.

4. Select the 'Approve' button on the WebEOC ENF to automatically open the WebEOC Emergency Notification Management panel with the recipient name list auto-populated.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 12 of 37 ATTACHMENT 2 Page 4 of 4

<< ENF Completion >>

1.4 Sending the ENF

1. If using WebEOC, then perform the following:

a. Access the Emergency Notification Management panel for the applicable ENF.

b. Select the 'Send ENF' button.

c. Select 'OK'.

(1) The 'Emergency Notification Management' panel will indicate it is sending the messages.

d. When 'Completed Sending Messages' appears, then select 'OK'.

2. If NOT using WebEOC, then communicate information on the ENF verbally while making contact for transmission in Attachment 3, ENF Transmission.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 13 of 37 ATTACHMENT 3 Page 1 of 4

<< ENF Transmission >>

1.0 INSTRUCTIONS 1.1 General Information NOTE

• Blast dial is a reverse conference call that calls recipients rather than the recipients calling in.

• Once initiated, the recipients will be called.

• Once the recipient answers, recipient will join the call automatically.

• Notification can then be made.

1. Duke Emergency Management Network (DEMNET) is the primary communication device.

a. Commercial telephone (blast dial) is the first back-up.

b. Commercial Telephone line (Individual Line) is the second back-up.

c. Satellite Phone is the third back-up.

2. Information regarding blast dial and back-up phone numbers is located in CSD-EP-ALL-0104-01, Emergency Telephone Directory.

3. DEMNET instructions are contained in ADEPALL0406, Duke Emergency Management Network (DEMNET).

4. The NRC requires that ALL state and county agencies be notified within 15 minutes of emergency declaration. Attachment 3, ENF Transmission, Step 7 meets the 15 minute notification time requirement.

1.2 Communicating the ENF using DEMNET Ethernet Phone Group Call

1. Verify that there is not another DEMNET call in progress that another Notify call would override by either method below:

• Verifying DEMNET icon status

• Contacting the Control Room, TSC, or EOF via landline

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 14 of 37 ATTACHMENT 3 Page 2 of 4

<< ENF Transmission >>

1.2 Communicating the ENF using DEMNET Ethernet Phone Group Call (continued)

2. Initiate a "Notify" call to the offsite agencies as follows:

a. Verify the appropriate screen for the affected nuclear site has been selected.

b. Select the orange oval group "Notify" button.

c. When the prompt appears on screen asking to connect the call, then select 'Yes'.

(1) Verify as the call is being connected that the 'Call in Progress' screen is displayed.

d. Press AND hold the push-to-talk (PTT) button whenever it is desired to talk to the agencies.

NOTE , ENF Transmissions, is used to perform and document communications with the offsite agencies for the appropriate site

3. When agencies start to answer the call, then state the plant name and the declaration of the emergency using Attachment 8, Section 1.

4. Note the time of the first contact on Attachment 8, Section 2. This is the start time for the next Follow-Up Notification.

5. Repeat Attachment 3 Section 1.2 Step 3 until it is believed that all agencies have answered the call.

NOTE Message authentication can be requested any time; however, authentication is only required if message transmittal is other than via DEMNET.

6. Refer to Attachment 4, Authentication Guideline as needed.

7. Once it is believed that all agencies have answered the notification call, state the reason for the notification using Attachment 8, Section 3.

8. Conduct and document a roll call using Attachment 8, Section 3 to verify all required agencies are on the line by stating each State or County agency and allowing time for a reply.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 15 of 37 ATTACHMENT 3 Page 3 of 4

<< ENF Transmission >>

1.2 Communicating the ENF using DEMNET Ethernet Phone Group Call (continued)

9. If an offsite agency does not answer, then contact the missing agency by any other means (i.e. commercial phone, cell phone, satellite phone, radio) while continuing with the DEMNET notification if possible:

a. If needed, then request another communicator contact the agency using other means (i.e. commercial phone, cell phone, satellite phone, radio) to complete the notification.

10. Record the time that all agencies were notified on Attachment 8, Section 4.

11. Verify each agency has received the ENF using Attachment 8, Section 5, and record the names of the person receiving the notification.

a. If the form was transmitted verbally, then there is no need to verify that the agency/agencies received the ENF by other means.

12. Determine if there are any agency questions and then conclude the message using Attachment 8, Section 6.

a. If a question applies to information on the ENF, then provide the information to the requesting agency.

b. If a question requires follow up, then document the questions and state that you will follow up with the requesting agency after the notification is complete.

13. Depress the "Hang up" button to end the DEMNET Call.

14. If using the WebEOC ENF, then perform the following:

a. Open the control panel.

b. Select 'EN Form' from the WebEOC control panel.

c. Select 'View' button in the Notification Management column for the applicable message.

d. Record recipient names in the Government Agencies Notified 'Received By' field and enter times and dates.

e. Select the 'Update' Button.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 16 of 37 ATTACHMENT 3 Page 4 of 4

<< ENF Transmission >>

1.2 Communicating the ENF using DEMNET Ethernet Phone Group Call (continued)

f. Enter the Time and Date that the first agency responded into the Notification Time and Date fields.

g. Verify or record the name of the Off Site Communicator making the notification call in the 'Notified By' field.

h. Select the 'Save' button to auto populate the ENF with the Notification Time and Date on Line 14.

15. If not using WebEOC, then:

a. If desired, then record offsite agency recipient names on the back of the ENF.

b. Document the notification time and date on Line 14 of the approved original ENF.

16. If an agency question requires follow up, then perform the following:

a. Document the questions in the Communicator's position log.

b. Document the name, agency, and contact information of the individual making the request.

c. Inform the individual you will contact them regarding the question.

d. Obtain the answer to the question from the appropriate ERO member and request the SM, Emergency Coordinator, or EOF Director to approve release of the information to the off-site agency.

e. Document the answer provided by the Shift Manager, Emergency Coordinator, or EOF Director in the Communicator's position log.

f. Contact requesting agency.

g. Provide the answer to the requesting agency.

h. Document the time the answer was provided to the requesting agency in the Communicator's position log.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 17 of 37 ATTACHMENT 4 Page 1 of 2

<< Authentication Guideline >>

1.0 INSTRUCTIONS 1.1 General Information

1. When using the DEMNET phone, then authentication is typically NOT required unless requested by an off-site agency.

2. The Authentication Code List is a controlled list of numbers and corresponding words provided by the state(s) to authenticate communications between the various parties.

a. Authentication provides assurance to the receiver that the information is valid.

b. Authentication may be performed anytime the receiver wishes to assure the information received from the transmitter is valid.

c. The receiver provides a number from the Authentication Code List.

d. The transmitter provides the word that corresponds to the number provided by the receiver.

3. The Authentication Code List may be found in the WebEOC Emergency Notification Management panel using 'Get Authentication Code' button or on hard copies stocked within each sites' TSC and the EOF.

1.2 Responding to a Request for Authentication

1. If using WebEOC, then perform the following:

a. Access the Emergency Notification Management panel for the appropriate message (ENF).

b. If Authentication is requested, then perform the following:

(1) Request the state or county representative to provide a number from the Authentication Code List.

(2) Enter the number provided by the Agency into the AUTHENTICATION # field.

(3) Select 'Get Authentication Code' (the Code Word(s) will appear).

(4) Provide code word(s) to the requestor.

(5) Select "OK" in the Pop up window to make the window disappear.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 18 of 37 ATTACHMENT 4 Page 2 of 2

<< Authentication Guideline >>

1.2 Responding to a Request for Authentication (continued)

(6) Select 'Save' to populate the ENF.

c. If Authentication is NOT requested, then perform the following:

(1) Enter N/A into the AUTHENTICATION # field.

(2) Select 'Save' to auto-populate the ENF.

2. If not using WebEOC, then perform the following:

a. If Authentication is requested, then request state or county representative to provide a number from the Authentication Code List.

(1) Provide code word(s) corresponding to number from the Authentication Code List.

(2) Document the number in the AUTHENTICATION # field located at the top of the ENF.

b. If Authentication is NOT requested, then enter N/A in the AUTHENTICATION # field located at the top of the ENF.

1.3 Receiving a Call

1. If receiving a call from an off-site agency and the identity of call is NOT known, then perform the following:

a. Tell the caller you'd like to authenticate the call.

b. Provide a number from Authentication Code List to caller.

c. Obtain code word(s) corresponding with number on the Authentication Code List from the caller.

d. If caller has questions pertaining to the event in progress, then perform Attachment 3 Section 1.2 Step 16.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 19 of 37 ATTACHMENT 5 Page 1 of 2

<< ENF Quick Reference >>

• Performance Indicator Accuracy Measure Above line 1 Select 'Initial' or 'Follow-up. Verify or record Message Number.

• Only lines 1-6 and line 13 are required for an Initial Notification.

• Only lines 1-6, 7-11 and 13 are required for a Follow-up Notification Line 1* Event - Select or ensure appropriate block for Drill, Actual Declaration, or Termination.

• Only lines 1, 2, 4 and 13 are required for a Termination Message.

Line 2* Verify, record, or select correct site.

Verify, record, or select appropriate Confirmation Phone#.

Line 3* Emergency Classification - Select or ensure correct classification.

Line 4*

• Verify, record, or select correct Emergency Action Level (EAL) # and corresponding EAL Description.

• If termination, then verify, select or record "N/A for EAL# and EAL Description.

• Select or enter Declaration or Termination Date and Time.

Line 5* Release to the environment - Select or verify appropriate block for None, Is Occurring, or Has Occurred.

(Refer to Attachment 7, Determining Radiological Release Status, for additional guidance)

Line 6* Protective Action Recommendations

• If Unusual Event, Alert, or Site Area Emergency, then verify, select or mark None.

• If General Emergency, then select or mark 'Evacuate' and/or 'Shelter' as appropriate. Verify, select or record appropriate zones. If circumstance warrant, then select or mark 'KI' or 'Other'.

• Once an evacuation PAR has been issued for a zone, it shall NOT be rescinded until recovery.

Line 7 Prognosis - If it is likely a higher emergency classification or a change in PARS will be required before the next follow-up, then select or mark 'Yes'. Otherwise mark 'No'.

Line 8 Site Unit(s) status

• Select or verify 'Yes' for the unit(s) affected with the highest classification or units with the same classification caused by the same event.

Complete for all Units

• If Unit(s) is (are) Shutdown, then record 0% power AND Shutdown Time and Date.

• If Unit(s) is (are) NOT Shutdown, then record % reactor power only.

Line 9 Meteorological Data - Verify, record or import Meteorological data including wind speed, direction, precipitation, and stability class.

Lines 10 & 11 Airborne Release Characterization and Dose Projection - Record or import radiological information. Lines 10 and 11 are only completed if Line 5 has Is Occurring or Has Occurred selected.

• Only BNP Vent Stack is an Elevated Release.

• All releases other than BNP Vent Stack are Ground Releases.

• Projection period is not required when performing a URI Rapid Dose Assessment.

Line 12 Remarks - Record any additional information using short narratives without acronyms.

Line 13 Approved By - Enter or record approvers name, title, and date and time.

Line 14 Notified By - If known, then enter the name of the person who will be notifying the State/Counties, OR if unknown, then leave blank and it will be filled out when the notification is complete.

Line 15 Received By - This field is only used by off-site agencies. This field will not be present on WebEOC.

Validate

• If using WebEOC, then select 'Validate' to identify issues for resolution.

• If completing a pre-printed or blank ENF, then review all data to identify and resolve issues.

Approve

• If using WebEOC, then obtain approval and select 'Approve'.

• If completing a pre-printed or blank ENF, then obtain approval by having approver sign the ENF Transmit If using WebEOC, after the form is approved, then the screen will advance to the notification management screen. Ensure correct recipients are specified and select Send ENF.

If using a paper ENF, then transmit the ENF verbally as specified in Attachment 8, ENF Transmissions.

Record Record the notification date, time, and notified by, and authentication (if performed) information Notification either in WebEOC or manually.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 20 of 37 ATTACHMENT 5 Page 2 of 2

<< ENF Quick Reference >>

ENF Completion Responsibilities Above Line 1 Off-Site Communicator Line 1 Off-Site Communicator Line 2 Off-Site Communicator Line 3 Shift Manager / Operations Manager / Accident Assessment Manager Line 4 Shift Manager / Operations Manager / Accident Assessment Manager Line 5 Shift Manager / Radiation Protection Manager / Radiological Assessment Manager Line 6 Shift Manager / Radiation Protection Manager / Radiological Assessment Manager Line 7 Shift Manager / Operations Manager / Accident Assessment Manager Line 8 Shift Manager / Operations Manager / Accident Assessment Manager Line 9 Shift Manager / Radiation Protection Manager / Radiological Assessment Manager Line 10 Shift Manager / Radiation Protection Manager / Radiological Assessment Manager Line 11 Shift Manager / Radiation Protection Manager / Radiological Assessment Manager Line 12 Anyone Line 13 Shift Manager / Emergency Coordinator / EOF Director Line 14 Off-Site Communicator

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 21 of 37 ATTACHMENT 6 Page 1 of 3

<< Offsite Communications Turnover Checklist >>

1. Affected Site(s):

Brunswick Nuclear Plant (BNP)

Catawba Nuclear Station (CNS)

Harris Nuclear Plant (HNP)

McGuire Nuclear Station (MNS)

Oconee Nuclear Station (ONS)

Robinson Nuclear Plant (RNP)

2. Obtain the most recent notification forms.

3. Emergency Classification (check):

UE Alert Site Area Emergency General Emergency Emergency Declaration (time): ___________

4. Last Emergency Notification Form Message #: ______

Notification (time): ________

5. Using: WebEOC, Paper ENF

6. Next Message Due at (time): ________

7. Communications Problems or Offsite agencies activated:

8. Alternate Facility Activated - TSC: Yes No OSC: Yes No EOF: Yes No

9. Site Assembly Status: N/A In progress Completed Time Site Assembly Initiated: _______

Number of persons unaccounted for: ________

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 22 of 37 ATTACHMENT 6 Page 2 of 3

<< Offsite Communications Turnover Checklist >>

10. Site Evacuation: Yes No Time Evacuation Initiated: _______

Approximate Number of persons being evacuated: ________

Site Evacuation Location (indicate relocation area):

BNP Yes No Technical Training Center (TTC)

Home CNS Yes No Plant Allen (Belmont, NC)

York Operations Center (York, SC)

Home HNP Yes No Administration Building Home MNS Yes No TTTC (Bldg. 7403)

Cowans Ford Dam Service Bay Mt. Holly Training Center McGuire Office Complex (MOC) Auditorium (Bldg. 7422)

Home ONS Yes No Daniel High School Keowee Elementary School Home RNP Yes No Unit 2 Administration Building Building 110 (Next to Lake Robinson)

Home

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 23 of 37 ATTACHMENT 6 Page 3 of 3

<< Offsite Communications Turnover Checklist >>

11. Other Pertinent Information (e.g., fires or explosions onsite, MERT activation, injured personnel transported offsite, chemical spills.)

12. Turnover Completed by: ____________________________

At (date/time): _______________

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 24 of 37 ATTACHMENT 7 Page 1 of 8

<< Determining Radiological Release Status >>

Use the following guidance in determining how to report radiological release status on ENF.

A release in progress must be:

• Quantifiable

• Airborne

• Attributed to the declared emergency event An increase on a radiation monitor is defined as a validated reading resulting from plant conditions (e.g., not attributable to instrument drift or electronic noise) above pre-emergency levels.

The following are release designations as listed on the Emergency Notification Form (ENF):

None - No release of quantifiable airborne radioactivity attributed to the emergency event.

Has Occurred - Any quantifiable airborne radioactivity released to the environment attributed to the emergency event, but has stopped.

Is Occurring - Any quantifiable airborne radioactivity release to the environment attributed to the emergency event, and is currently in progress as defined by the following criteria.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 25 of 37 ATTACHMENT 7 Page 2 of 8

<< Determining Radiological Release Status >>

BNP The first page of this attachment is applicable to all sites. If any of the statements below are true, then a Release is occurring.

1. Any gaseous radiation monitor below shows increase in activity:

a. Main Stack: D12-RM-23S

b. Reactor Building Vent Noble Gas: CAC-AQH-1264-3

c. Turbine Building Vent Rad: D12-RM-23

2. Any drywell radiation monitor below showing an increase in activity AND a known leak path to environment exists with no operational radiation monitor at the release point:

a. Drywell High Rad Monitor 30 ft elevation: D-22-RM-4195

b. Drywell High Rad Monitor 57 ft elevation: D-22-RM-4196

c. Drywell High Rad Monitor 23 ft elevation: D-22-RM-4197

d. Drywell High Rad Monitor 57 ft elevation: D-22-RM-4198

3. A known unmonitored release path exists AND a radioactive source exists (RCS or fuel damage).

4. Field Monitoring Team results of airborne radioactivity (other than naturally occurring) detected by survey or sampling.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 26 of 37 ATTACHMENT 7 Page 3 of 8

<< Determining Radiological Release Status >>

CNS The first page of this attachment is applicable to all sites. If any of the statements below are true, then a Release is occurring.

1. Any gaseous radiation monitor below that shows an increase in activity:

a. Unit Vent Low/High: 1/2 EMF-36 L/H

b. Unit Vent Extended: 1/2 EMF-54

2. Any containment radiation monitor below that shows an increase in activity AND known leak path to environment exists:

a. Containment High Range: 1/2 EMF-53 A/B

b. Containment Gas Low/High: 1/2 EMF-39 L/H

3. Any radiation monitor below that shows an increase in activity AND Primary to Secondary leakage is occurring:

a. Unit 1 Steam Line: 1 EMF-26/27/28/29

b. Unit 2 Steam Line: 2 EMF-10/11/12/13

c. Condenser Steam Air Ejector: 1/2 EMF-33 (not for use in dose assessment)

4. A known unmonitored release path exists AND a radioactive source exists (RCS or fuel damage).

5. Field Monitoring Team results of airborne radioactivity (other than naturally occurring) detected by survey or sampling.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 27 of 37 ATTACHMENT 7 Page 4 of 8

<< Determining Radiological Release Status >>

HNP The first page of this attachment is applicable to all sites. If any of the statements below are true, then a Release is occurring.

1. Any gaseous radiation monitor below that shows an increase in activity:

a. Plant Vent: RM-21AV-3509-1SA

b. Turbine Building: RM-1TV-3536-1

c. Waste Processing Building Vent 5: RM-1WV-3546-1

d. Waste Processing Building Vent 5A: RM-1WV-3547-1

2. Any containment radiation monitor below that shows an increase in activity AND known leak path to environment exists:

a. Containment High Range: RM-01CR-3589SA

b. Containment High Range: RM-01CR-3590SB

c. Containment Gas: REM-01LT-3502ASA

3. Any radiation monitor below that shows an increase in activity AND Primary to Secondary leakage is occurring:

a. Main Steam Line A/B/C: RM-01MS-3591/3592/3593

b. Turbine Building Vent Stack Wide Range Gas Monitor: RM-01TV-3536-1

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 28 of 37 ATTACHMENT 7 Page 5 of 8

<< Determining Radiological Release Status >>

HNP (continued)

4. Damage to irradiated fuel in conjunction with a valid high alarm on any Containment or Fuel Handling Building radiation monitor listed below:

a. Containment Ventilation Isolation: RM-1CR-3561 A/B/C/D

b. Spent Fuel Pool SW, SE, SW: RM-1FR-3564A-SA

c. Spent Fuel Pool SW, SE, SE: RM-1FR-3564B-SB

d. Spent Fuel Pool SW, SE, SW: RM-1FR-3565A-SA

e. Spent Fuel Pool SW, SE, SE: RM-1FR-3565B-SB

f. Spent Fuel Pool NE, NW, NE: RM-1FR-3566A-SA

g. Spent Fuel Pool NW, NE, NW: RM-1FR-3566B-SB

h. Spent Fuel Pool NW, NE, NW: RM-1FR-3567A-SA

i. Spent Fuel Pool NE, NW, NE: RM-1FR-3567B-SB

5. A known unmonitored release path exists AND a radioactive source exists (RCS or fuel damage).

6. Field Monitoring Team results of airborne radioactivity (other than naturally occurring) detected by survey or sampling.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 29 of 37 ATTACHMENT 7 Page 6 of 8

<< Determining Radiological Release Status >>

MNS The first page of this attachment is applicable to all sites. If any of the statements below are true, then a Release is occurring.

1. Any gaseous radiation monitor below that shows an increase in activity:

a. Unit Vent Low/High/High-High: 1/2 EMF-36 L/H/HH

2. Any Containment radiation monitor below that shows an increase in activity AND known leak path to environment exists:

a. Containment High Range: 1/2 EMF-51 A/B

b. Containment Gas Low/High: 1/2 EMF-39 L/H

3. Any radiation monitor below that shows an increase in activity AND Primary to Secondary leakage is occurring:

a. Unit 1 Steam Line: 1 EMF-24/25/26/27

b. Unit 2 Steam Line: 2 EMF-10/11/12/13

c. Condenser Steam Air Ejector: 1 & 2 EMF-33

4. A known unmonitored release path exists AND a radioactive source exists (RCS or fuel damage).

5. Field Monitoring Team results of airborne radioactivity (other than naturally occurring) detected by survey or sampling.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 30 of 37 ATTACHMENT 7 Page 7 of 8

<< Determining Radiological Release Status >>

ONS The first page of this attachment is applicable to all sites. If any of the statements below are true, then a Release is occurring.

1. Any gaseous radiation monitor below that shows an increase in activity:

a. Unit Vent Low: 1/2/3 RIA-45

b. Unit Vent High: 1/2/3 RIA-46

c. Unit Vent High Gross Gamma: 1/2/3 RIA-56

2. Any Containment radiation monitor below that shows an increase in activity AND known leak path to environment exists:

a. Containment High Range: 1/2/3 RIA-57

b. Containment High Range: 1/2/3 RIA-58

c. Containment Gas Low: 1/2/3 RIA-49

d. Containment Gas High: 1/2/3 RIA-49A

3. Any radiation monitor below that shows an increase in activity AND Primary to Secondary leakage is occurring:

a. Steam Line: 1/2/3 RIA-16/17

b. Air Ejector Off Gas: 1/2/3 RIA-40

4. A known unmonitored release path exists AND a radioactive source exists (RCS or fuel damage).

5. Field Monitoring Team results of airborne radioactivity (other than naturally occurring) detected by survey or sampling.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 31 of 37 ATTACHMENT 7 Page 8 of 8

<< Determining Radiological Release Status >>

RNP The first page of this attachment is applicable to all sites. If any of the statements below are true, then a Release is occurring.

1. Any gaseous radiation monitor below that shows an increase in activity:

a. Plant Vent Low/Mid/High: R-14 C/D/E

b. Fuel Handling Building Exhaust: R-20

c. Fuel Handling Building Exhaust High: R-30

2. Any Containment radiation monitor below that shows an increase in activity AND known leak path to environment exists:

a. Containment High Range: R-32 A/B

b. Containment Gas: R-12

3. Any radiation monitor below that shows an increase in activity AND Primary to Secondary leakage is occurring:

a. Steam Line: R-31 A/B/C

b. Condenser Air Ejector Gas: R-15

4. A known unmonitored release path exists AND a radioactive source exists (RCS or fuel damage).

5. Field Monitoring Team results of airborne radioactivity (other than naturally occurring) detected by survey or sampling.

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 32 of 37 ATTACHMENT 8 Page 1 of 6

<< ENF Transmissions >>

1. "This is the Brunswick Nuclear Plant ENF # ____ ENF # ____ ENF # ____

A/an Unusual Event / Alert / Site Area Emergency / General Initial / Follow-up Initial / Follow-up Initial / Follow-up Emergency has been declared. Please standby." UE / AL / SAE / GE UE / AL / SAE / GE UE / AL / SAE / GE OR "We have terminated from the Unusual Event / Alert / Site Area Emergency / General Emergency. Please standby."

2. Record time of first agency on the phone. Repeat the above until all agencies are on-line. Time: _________ Time: _________ Time: _________

3. "The Brunswick Nuclear Plant has declared a/an Brunswick County Verified Verified Verified Unusual Event / Alert / Site Area Emergency / General Emergency."

If Initial or Follow-up of GENERAL EMERGENCY, then state:

New Hanover "We recommend the following protective actions:" (read ENF LINE 6) Verified Verified Verified County "Im now going to conduct a roll call." (verify each agency is on the line)

OR North Carolina Verified Verified Verified "The Brunswick Nuclear Plant has Terminated from the Unusual Event / Alert / Site Area Emergency / General Emergency."

Coast Guard Verified Verified Verified "I need to confirm required agencies are on-line."

4. Record time all required agencies are notified. Time: _________ Time: _________ Time: _________

5. "A copy of message # _____ has been sent to you. When I call your Brunswick County agency, please state whether you have received the message and also New Hanover state your name." County Verify receipt of message and RECORD names.

North Carolina If any agency did not receive the ENF OR you cannot transmit the ENF, then request the agency to obtain a blank ENF and transmit the message verbally Coast Guard line by line

6. "Are there any questions?" Record questions per Attachment 3 Section 1.2 Step 16 Page ___ of ___

"This concludes the notification, my name is __________________________________________. Duke Energy clear."

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 33 of 37 ATTACHMENT 8 Page 2 of 6

<< ENF Transmissions >>

1. "This is the Catawba Nuclear Station ENF # ____ ENF # ____ ENF # ____

A/an Unusual Event / Alert / Site Area Emergency / General Initial / Follow-up Initial / Follow-up Initial / Follow-up Emergency has been declared. Please standby." UE / AL / SAE / GE UE / AL / SAE / GE UE / AL / SAE / GE OR "We have terminated from the Unusual Event / Alert / Site Area Emergency / General Emergency. Please standby."

2. Record time of first agency on the phone. Repeat the above until all agencies are on-line. Time: _________ Time: _________ Time: _________

3. "The Catawba Nuclear Station has declared a/an York County Verified Verified Verified Unusual Event / Alert / Site Area Emergency / General Emergency."

If Initial or Follow-up of GENERAL EMERGENCY, then state: Mecklenburg Co. Verified Verified Verified "We recommend the following protective actions:" (read ENF LINE 6)

"Im now going to conduct a roll call." (verify each agency is on the line) Gaston County Verified Verified Verified OR "The Catawba Nuclear Station has Terminated from the North Carolina Verified Verified Verified Unusual Event / Alert / Site Area Emergency / General Emergency."

South Carolina Verified Verified Verified "I need to confirm required agencies are on-line."

4. Record time all required agencies are notified. Time: _________ Time: _________ Time: _________

5. "A copy of message # _____ has been sent to you. When I call your York County agency, please state whether you have received the message and also Mecklenburg Co.

state your name."

Verify receipt of message and RECORD names. Gaston County If any agency did not receive the ENF OR you cannot transmit the ENF, then North Carolina request the agency to obtain a blank ENF and transmit the message verbally South Carolina line by line

6. "Are there any questions?" Record questions per Attachment 3 Section 1.2 Step 16 "This concludes the notification, my name is _____________________________________________. Duke Energy clear." Page ___ of ___

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 34 of 37 ATTACHMENT 8 Page 3 of 6

<< ENF Transmissions >>

1. "This is the Harris Nuclear Plant ENF # ____ ENF # ____ ENF # ____

A/an Unusual Event / Alert / Site Area Emergency / General Initial / Follow-up Initial / Follow-up Initial / Follow-up Emergency has been declared. Please standby." UE / AL / SAE / GE UE / AL / SAE / GE UE / AL / SAE / GE OR "We have terminated from the Unusual Event / Alert / Site Area Emergency / General Emergency. Please standby."

2. Record time of first agency on the phone. Repeat the above until all agencies are on-line. Time: _________ Time: _________ Time: _________

3. "The Harris Nuclear Plant has declared a/an Wake County Verified Verified Verified Unusual Event / Alert / Site Area Emergency / General Emergency."

If Initial or Follow-up of GENERAL EMERGENCY, then state: Chatham County Verified Verified Verified "We recommend the following protective actions:" (read ENF LINE 6)

"Im now going to conduct a roll call." (verify each agency is on the line) Harnett County Verified Verified Verified OR Lee County Verified Verified Verified "The Harris Nuclear Plant has Terminated from the Unusual Event / Alert / Site Area Emergency / General Emergency."

North Carolina Verified Verified Verified "I need to confirm required agencies are on-line."

4. Record time all required agencies are notified. Time: _________ Time: _________ Time: _________

5. "A copy of message # _____ has been sent to you. When I call your Wake County agency, please state whether you have received the message and also Chatham County state your name."

Verify receipt of message and RECORD names. Harnett County If any agency did not receive the ENF OR you cannot transmit the ENF, then Lee County request the agency to obtain a blank ENF and transmit the message verbally line by line North Carolina

6. "Are there any questions?" Record questions per Attachment 3 Section 1.2 Step 16 Page ___ of ___

"This concludes the notification, my name is _______________________________________________. Duke Energy clear."

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 35 of 37 ATTACHMENT 8 Page 4 of 6

<< ENF Transmissions >>

1. "This is the McGuire Nuclear Station ENF # ____ ENF # ____ ENF # ____

A/an Unusual Event / Alert / Site Area Emergency / General Initial / Follow-up Initial / Follow-up Initial / Follow-up Emergency has been declared. Please standby." UE / AL / SAE / GE UE / AL / SAE / GE UE / AL / SAE / GE OR "We have terminated from the Unusual Event / Alert / Site Area Emergency / General Emergency. Please standby."

2. Record time of first agency on the phone. Repeat the above until all agencies are on-line. Time: _________ Time: _________ Time: _________

3. "The McGuire Nuclear Station has declared a/an Gaston County Verified Verified Verified Unusual Event / Alert / Site Area Emergency / General Emergency." Lincoln County Verified Verified Verified If Initial or Follow-up of GENERAL EMERGENCY, then state:

"We recommend the following protective actions:" (read ENF LINE 6) Iredell County Verified Verified Verified "Im now going to conduct a roll call." (verify each agency is on the line) Mecklenburg Co. Verified Verified Verified OR Catawba County Verified Verified Verified "The McGuire Nuclear Station has Terminated from the Unusual Event / Alert / Site Area Emergency / General Emergency." Cabarrus County Verified Verified Verified "I need to confirm required agencies are on-line." North Carolina Verified Verified Verified

4. Record time all required agencies are notified. Time: _________ Time: _________ Time: _________

5. "A copy of message # _____ has been sent to you. When I call your Gaston County agency, please state whether you have received the message and also Lincoln County state your name."

Iredell County Verify receipt of message and RECORD names.

If any agency did not receive the ENF OR you cannot transmit the ENF, then Mecklenburg Co.

request the agency to obtain a blank ENF and transmit the message verbally Catawba County line by line. Cabarrus County North Carolina

6. "Are there any questions?" Record questions per Attachment 3 Section 1.2 Step 16 "This concludes the notification, my name is _____________________________________________. Duke Energy clear."

Page ___ of ___

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 36 of 37 ATTACHMENT 8 Page 5 of 6

<< ENF Transmissions >>

1. "This is the Oconee Nuclear Station ENF # ____ ENF # ____ ENF # ____

A/an Unusual Event / Alert / Site Area Emergency / General Initial / Follow-up Initial / Follow-up Initial / Follow-up Emergency has been declared. Please standby." UE / AL / SAE / GE UE / AL / SAE / GE UE / AL / SAE / GE OR "We have terminated from the Unusual Event / Alert / Site Area Emergency / General Emergency. Please standby."

2. Record time of first agency on the phone. Repeat the above until all agencies are on-line. Time: _________ Time: _________ Time: _________

3. "The Oconee Nuclear Station has declared a/an Unusual Event / Alert / Site Area Emergency / General Emergency." Oconee County Verified Verified Verified If Initial or Follow-up of GENERAL EMERGENCY, then state:

"We recommend the following protective actions:" (read ENF LINE 6)

Pickens County Verified Verified Verified "Im now going to conduct a roll call." (verify each agency is on the line)

OR "The Oconee Nuclear Station has Terminated from the Unusual Event / Alert / Site Area Emergency / General Emergency." South Carolina Verified Verified Verified "I need to confirm required agencies are on-line."

4. Record time all required agencies are notified. Time: _________ Time: _________ Time: _________

5. "A copy of message # _____ has been sent to you. When I call your Oconee County agency, please state whether you have received the message and also state your name."

Pickens County Verify receipt of message and RECORD names.

If any agency did not receive the ENF OR you cannot transmit the ENF, then request the agency to obtain a blank ENF and transmit the message verbally South Carolina line by line

6. "Are there any questions?" Record questions per Attachment 3 Section 1.2 Step 16 "This concludes the notification, my name is ______________________________________________. Duke Energy clear."

STATE AND COUNTY NOTIFICATIONS AD-EP-ALL-0304 Rev. 3 Page 37 of 37 ATTACHMENT 8 Page 6 of 6

<< ENF Transmissions >>

1. "This is the Robinson Nuclear Plant ENF # ____ ENF # ____ ENF # ____

A/an Unusual Event / Alert / Site Area Emergency / General Initial / Follow-up Initial / Follow-up Initial / Follow-up Emergency has been declared. Please standby." UE / AL / SAE / GE UE / AL / SAE / GE UE / AL / SAE / GE OR "We have terminated from the Unusual Event / Alert / Site Area Emergency / General Emergency. Please standby."

2. Record time of first agency on the phone. Repeat the above until all agencies are on-line. Time: _________ Time: _________ Time: _________

3. "The Robinson Nuclear Plant has declared a/an Darlington County Verified Verified Verified Unusual Event / Alert / Site Area Emergency / General Emergency."

If Initial or Follow-up of GENERAL EMERGENCY, then state:

Chesterfield "We recommend the following protective actions:" (read ENF LINE 6) Verified Verified Verified County "Im now going to conduct a roll call." (verify each agency is on the line)

OR Lee County Verified Verified Verified "The Robinson Nuclear Plant has Terminated from the Unusual Event / Alert / Site Area Emergency / General Emergency."

South Carolina Verified Verified Verified "I need to confirm required agencies are on-line."

4. Record time all required agencies are notified. Time: _________ Time: _________ Time: _________

5. "A copy of message # _____ has been sent to you. When I call your Darlington County agency, please state whether you have received the message and also Chesterfield state your name." County Verify receipt of message and RECORD names.

Lee County If any agency did not receive the ENF OR you cannot transmit the ENF, then request the agency to obtain a blank ENF and transmit the message verbally South Carolina line by line

6. "Are there any questions?" Record questions per Attachment 3 Section 1.2 Step 16 Page ___ of ___

"This concludes the notification, my name is _______________________________________________. Duke Energy clear."

NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM MESSAGE # ________ SIM:(803) 831-3807 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 SA1.1

4. EAL #______________ Declaration Date: ____/____/____ Time: ________

Termination Date: ____/____/____ Time: ________(mark "N/A" for EAL # & Description)

Loss of all but one AC power source to essential buses for 15 minutes or longer.

EAL DESCRIPTION: _________________________________________________________________________________

5. RELEASE TO THE ENVIRONMENT (caused by the emergency): 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):__________________________________________________________________________

13. APPROVED BY: _________________________TITLE: ___________________Date Emergency Coordinator ___/_____/____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) 9-1-803/329-1110 (date) (time)

2. Mecklenburg County WP/EOC (name) 9-704/336-2441 (WP) 9-704/432-4120 (EOC)

(date) (time)

3. Gaston County WP/EOC (name) 9-704/866-3300 (date) (time)

4. North Carolina EOC/WP (name) 9-1-919/733-3300 (Primary) 9-1-800/858-0368 (Alt.)

(date) (time)

5. North Carolina Alt. WP (name) 9-1-828/466-5500 9-1-828/466-5501 (date) (time)

6. North Carolina Alt. EOC (name) 9-1-919/733-3300 (Primary) 9-1-800-858-0368 (Alt.)

(date) (time)

7. South Carolina WP (name) 9-1-803/737-8500 (Primary) 9-1-800/811-8045 (Alt.)

(date) (time)

8. South Carolina Alt. WP (name) 9-1-803/896-9621 (date) (time)

9. South Carolina EOC (name) 9-1-803/737-8500 (Primary) 9-1-803-737-8724 (Alt.)

(date) (time)

EAL WALLCHARTS GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Release of gaseous radioactivity resulting in offsite dose greater Release of gaseous radioactivity resulting in offsite dose greater Release of gaseous or liquid radioactivity resulting in offsite dose Release of gaseous or liquid radioactivity greater than 2 times the than 1,000 mrem TEDE or 5,000 mrem thyroid CDE than 100 mrem TEDE or 500 mrem thyroid CDE greater than 10 mrem TEDE or 50 mrem thyroid CDE SLC/TS limits for 60 minutes or longer Loss of NCS inventory affecting fuel clad integrity with containment Loss of NCS inventory affecting core decay heat removal Loss of NCS inventory UNPLANNED loss of NCS inventory for 15 minutes or longer challenged capability 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 5 6 5 6 5 6 5 6 RG1.1 RS1.1 RA1.1 RU1.1 CG1.1 CS1.1 CA1.1 CU1.1 Reading on any Table R-1 effluent radiation monitor > column Reading on any Table R-1 effluent radiation monitor > column Reading on any Table R-1 effluent radiation monitor Reading on any Table R-1 effluent radiation monitor GE for 15 min. (Notes 1, 2, 3, 4) SAE for 15 min. (Notes 1, 2, 3, 4) > column ALERT for 15 min. (Notes 1, 2, 3, 4) > column UE for 60 min. (Notes 1, 2, 3) NCS level cannot be monitored for 30 min. (Note 1) UNPLANNED loss of NCS inventory as indicated by NCS UNPLANNED loss of NCS inventory results in NCS water NCS level cannot be monitored for 30 min. (Note 1)

AND water level < 6.5% (wide range) level less than a required lower limit for 15 min. (Note 1)

RG1.2 RS1.2 RA1.2 RU1.2 AND 1 Core uncovery is indicated by any of the following: Core uncovery is indicated by any of the following:

Dose assessment using actual meteorology indicates doses Dose assessment using actual meteorology indicates doses Dose assessment using actual meteorology indicates doses Sample analysis for a gaseous or liquid release indicates a - UNPLANNED increase in any Table C-6 sump or tank CA1.2 CU1.2

> 10 mrem TEDE or 50 mrem thyroid CDE at or beyond the - UNPLANNED increase in any Table C-6 sump or tank

> 1000 mrem TEDE or 5000 mrem thyroid CDE at or beyond > 100 mrem TEDE or 500 mrem thyroid CDE at or beyond concentration or release rate > 2 x SLC/TS limits for level due to a loss of NCS inventory level due to a loss of NCS inventory NCS water level cannot be monitored for 15 min. (Note 1) NCS water level cannot be monitored the SITE BOUNDARY (Notes 4) the SITE BOUNDARY (Notes 4) SITE BOUNDARY (Notes 4) 60 min. (Notes 1, 2) - Visual observation of UNISOLABLE NCS leakage 1 NCS - Visual observation of UNISOLABLE NCS leakage AND EITHER AND EITHER RG1.3 RS1.3 RA1.3 - Reactor Building Refueling Bridge Monitor 1EMF17 Level - Reactor Building Refueling Bridge Monitor 1EMF17 - UNPLANNED increase in any Table C-6 sump or tank - UNPLANNED increase in any Table C-6 sump or Analysis of a liquid effluent sample indicates a concentration (2EMF2) reading > 9,000 mR/hr (2EMF2) reading > 9,000 mR/hr level due to a loss of NCS inventory tank level due to a loss of NCS inventory Field survey results indicate EITHER of the following at or Field survey results indicate EITHER of the following at or or release rate that would result in doses > 10 mrem TEDE or - Erratic Source Range or Gamma Metric Monitor - Erratic Source Range or Gamma Metric Monitor - Visual observation of UNISOLABLE NCS leakage - Visual observation of UNISOLABLE NCS leakage Rad beyond the SITE BOUNDARY: beyond the SITE BOUNDARY:

50 mrem thyroid CDE at or beyond the SITE BOUNDARY for indication indication Effluent - Closed window dose rates > 1000 mR/hr expected to con- - Closed window dose rates > 100 mR/hr expected to con-60 min. of exposure (Notes 1, 2) AND tinue for 60 min. tinue for 60 min.

- Analyses of field survey samples indicate thyroid CDE - Analyses of field survey samples indicate thyroid CDE RA1.4 Any Containment Challenge indication, Table C-1

> 5000 mrem for 60 min. of inhalation. > 500 mrem for 60 min. of inhalation. Field survey results indicate EITHER of the following at or (Notes 1, 2) (Notes 1, 2) beyond the SITE BOUNDARY:

Loss of all offsite and all onsite AC power to essential buses for 15 Loss of all but one AC power source to essential buses for 15

- Closed window dose rates > 10 mR/hr expected to minutes or longer minutes or longer continue for 60 min.

5 6 DEF 5 6 DEF

- Analyses of field survey samples indicate thyroid CDE

> 50 mrem for 60 min. of inhalation.

2 CA2.1 R

CU2.1 (Notes 1, 2) AC power capability, Table C-2, to essential 4160V buses None None Loss of all offsite and all onsite AC power capability to Spent fuel pool level cannot be restored to at least the top of the Spent fuel pool level at the top of the fuel racks Significant lowering of water level above, or damage to, irradiated Unplanned loss of water level above irradiated fuel Loss of essential 4160V buses 1(2)ETA and 1(2)ETB for 15 min. 1(2)ETA and 1(2)ETB reduced to a single power source for fuel racks for 60 minutes or longer fuel (Note 1) 15 min. (Note 1)

Essential AND Abnorm. 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF AC Any additional single power source failure will result in loss of Rad RG2.1 RS2.1 RA2.1 RU2.1 Power all AC power to SAFETY SYSTEMS Levels Spent fuel pool level cannot be restored to at least 14.5 ft. Lowering of spent fuel pool level to 14.5 ft. (Level 3) on Uncovery of irradiated fuel in the REFUELING PATHWAY UNPLANNED water level drop in the REFUELING PATHWAY (Level 3) on 1(2)KFP5780 or 1(2)NVP8790 for 60 min. 1(2)KFP5780 or 1(2)NVP8790 as indicated by low water level alarm or indication

/ Rad 2

Inability to maintain plant in cold shutdown UNPLANNED increase in NCS temperature (Note 1) RA2.2 AND C

Effluent UNPLANNED rise in corresponding area radiation levels as Table R-1 Effluent Monitor Classification Thresholds Damage to irradiated fuel resulting in a release of radioactivity 5 6 5 6 indicated by any of the following radiation monitors:

Irradiated AND CA3.1 CU3.1

- 1EMF15 (2EMF4) Spent Fuel Building Refueling Bridge 3

Fuel Event Release Point Monitor GE SAE Alert UE A Trip 2 radiation alarm on any of the following radiation - 1EMF17 (2EMF2) Reactor Building Refueling Bridge monitor indications: UNPLANNED increase in NCS temperature to > 200°F for UNPLANNED increase in NCS temperature to > 200°F due Gaseous Unit Vent Noble Gas Low 1/2EMF36L -------- -------- 4.18E+6 cpm 5.75E+3 cpm - 1EMF15 (2EMF4) Spent Fuel Building Refueling Bridge > Table C-3 duration (Notes 1, 9) to loss of decay heat removal capability Cold SD/ None None

- 1EMF17 (2EMF2) Reactor Building Refueling Bridge OR

- 1EMF42 (2EMF42) Spent Fuel Pool Ventilation Refuel NCS UNPLANNED NCS pressure increase > 10 psig due to a loss CU3.2 Unit Vent Noble Gas High 1/2EMF36H 2.21E+4 cpm 2.22E+3 cpm 2.42E+2 cpm --------

- 1EMF39L (2EMF39L) Containment Noble Gas System Temp of NCS cooling (this does not apply during water-solid plant Loss of all NCS temperature and NCS level indication Malfunct. conditions) for 15 min. (Note 1)

RA2.3 Liquid Waste Effluent Line 0EMF49L -------- -------- -------- 4.50E+6 cpm Liquid Lowering of spent fuel pool level to 24.5 ft. (Level 2) on

---

-------- 1(2)KFP5780 or 1(2)NVP8790 Monitor Tank Discharge 0EMF57L -------- 4.97E+5 cpm Radiation levels that IMPEDE access to equipment necessary for CU4 Loss of Vital DC power for 15 minutes or longer 4

normal plant operations, cooldown or shutdown Table R-2 Safe Operation & Shutdown Rooms/Areas 5 6 1 2 3 4 5 6 DEF Bldg. Elevation Unit 1 Room/Area Unit 2 Room/Area Mode RA3.1 None None CU4.1 3

None Dose rates > 15 mR/hr in EITHER of the following areas: Loss of < 105 VDC bus voltage indications on Technical Specification Rm 478 (1EMXA) Rm 469 (2EMXA) 4 Control Room (EMF12) Vital DC required 125 VDC buses for 15 min. (Note 1)

Auxiliary Rm 496 (1ETA) Rm 486 (2ETA) 4 OR Power None 577' None Area Rad Rm 496 (1EMXS) Rm 486 (2EMXS) 4 Central Alarm Station (by survey)

Levels AB-577', JJ-57 (1MXK) AB-577', JJ-57 (2MXK) 4 Loss of all onsite or offsite communications capabilities Rm 330 (1EMXJ) Rm 320 (2EMXJ) 4 RA3.2 5 6 DEF An UNPLANNED event results in radiation levels that prohibit 5

Auxiliary 560' Rm 372 (1ETB) Rm 362 (2ETB) 4 or IMPEDE access to any Table R-2 rooms or areas (Note 5) CU5.1 Rm 372 (1EMXD) Rm 362 (2EMXD) 4 None None None Loss of all Table C-4 onsite communication methods OR HOSTILE ACTION within the PROTECTED AREA HOSTILE ACTION within the OWNER CONTROLLED AREA or Confirmed SECURITY CONDITION or threat Loss of airborne attack threat within 30 minutes Loss of all Table C-4 ORO communication methods Comm OR 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF Loss of all Table C-4 NRC communication methods HS1.1 HA1.1 HU1.1 A HOSTILE ACTION is occurring or has occurred within the A HOSTILE ACTION is occurring or has occurred within the A SECURITY CONDITION that does not involve a HOSTILE Hazardous event affecting a SAFETY SYSTEM needed for the PROTECTED AREA as reported by the Security Shift OWNER CONTROLLED AREA as reported by the Security ACTION as reported by the Security Shift Supervision current operating mode 1 None Supervision Shift Supervision HA1.2 HU1.2 Notification of a credible security threat directed at the site CA6.1 5 6 Security A validated notification from NRC of an aircraft attack threat within 30 min. of the site HU1.3 A validated notification from the NRC providing information 6 None None The occurrence of any Table C-5 hazardous event AND None of an aircraft threat Hazardous - Event damage has caused indications of degraded Event performance on one train of a SAFETY SYSTEM Affecting needed for the current operating mode Safety AND EITHER of the following:

NOTES Seismic event greater than OBE level Systems - Event damage has caused indications of degraded 2

performance to a second train of the SAFETY SYSTEM 1 2 3 4 5 6 DEF needed for the current operating mode.

Note 1: The Emergency Coordinator should declare the event promptly upon determining that time limit has been exceeded, or will likely be exceeded.

None None None HU2.1 - Event damage has resulted in VISIBLE DAMAGE to the Seismic event > OBE as indicated by OBE EXCEEDED second train of the SAFETY SYSTEM needed for the Seismic Note 2: If an ongoing release is detected and the release start time is unknown, assume that the release duration has exceeded the specified time limit. [Refer to EAL CA6.1 OR SA9.1 for escalation due to seismic event] alarm on 1AD-4, B/8 current operating mode Event (Note 11, 12)

Note 3: If the effluent flow past an effluent monitor is known to have stopped, indicating that the release path is isolated, the effluent monitor reading is no longer Hazardous event VALID for classification purposes.

1 2 3 4 5 6 DEF Note 4: The pre-calculated effluent monitor values presented in EALs RA1.1, RS1.1 and RG1.1 should be used for emergency classification assessments until HU3.1 the results from a dose assessment using actual meteorology are available. A tornado strike within the PROTECTED AREA Table C-1 Containment Challenge Indications Table C-2 AC Power Sources Table C-3 NCS Heat-up Duration Thresholds Table C-4 Communication Methods Note 5: If the equipment in the listed room or area was already inoperable or out- HU3.2 of-service before the event occurred, then no emergency classification is Internal room or area FLOODING of a magnitude sufficient System Onsite ORO NRC

- CONTAINMENT CLOSURE not established (Note 6) Containment Heat-up Offsite NCS Status 3

warranted.

to require manual or automatic electrical isolation of a Closure Status Duration SAFETY SYSTEM component needed for the current - Containment hydrogen concentration > 6% - ATC (Train A) Public Address X Note 6: If CONTAINMENT CLOSURE is re-established prior to exceeding the 30- Intact (but not reduced minute time limit, declaration of a General Emergency is not required. operating mode N/A 60 min.* Internal Telephones X None None None

- UNPLANNED rise in containment pressure

- SATA (Train A) (if already aligned) . inventory)

Natural or Note 7: This EAL does not apply to routine traffic impediments such as fog, snow, [Refer to EAL CA6.1 OR SA9.1 for escalation due to natural or HU3.3 - ATD (Train B) Not intact 20 min.* Onsite Radios X Tech. ice, or vehicle breakdowns or accidents. technological hazard]

established Hazard Movement of personnel within the PROTECTED AREA is OR DEMNET X

- SATB (Train B) (if already aligned)

IMPEDED due to an offsite event involving hazardous At reduced inventory 0 min.

Note 8: A manual trip action is any operator action, or set of actions, which causes not established the control rods to be rapidly inserted into the core, and does not include manually materials (e.g., an offsite chemical spill or toxic gas release) Onsite Commercial Telephones X X driving in control rods or implementation of boron injection strategies.

- D/G A (Train A)

• If an NCS heat removal system is in operation within this time frame and Satellite Phones X X Note 9: In the absence of reliable NCS temperature indication caused by the loss HU3.4 NCS temperature is being reduced, the EAL is not applicable of decay heat removal capability, classification should be based on time to boil A hazardous event that results in on-site conditions sufficient - D/G B (Train B) Cellular Phones X X data when in Mode 5 and 6. to prohibit the plant staff from accessing the site via personal vehicles (Note 7) NRC Emergency X X Note 10: If the loss of containment cooling threshold is exceeded due to loss of Telecommunications System (ETS) both trains of VX-CARF, this EAL only applies if at least one train of VX-CARF is not operating, per design, after the 10 minute actuation delay for greater than or FIRE potentially degrading the level of safety of the plant equal to 15 minutes.

[Refer to EAL CA6.1 OR SA9.1 for escalation due to FIRE] 1 2 3 4 5 6 DEF Note 11: If the affected SAFETY SYSTEM train was already inoperable or out of service before the hazardous event occurred, then this emergency classification is HU4.1 not warranted. Table C-5 Hazardous Events Table C-6 Sumps/Tanks A FIRE is not extinguished within 15 min. of any of the Note 12: If the hazardous event only resulted in VISIBLE DAMAGE, with no following FIRE detection indications (Note 1):

indications of degraded performance to at least one train of a SAFETY SYSTEM, - Report from the field (i.e., visual observation) - Seismic event (earthquake) - Containment Floor & Equipment Sump then this emergency classification is not warranted. - Receipt of multiple (more than 1) fire alarms or indications Table H-1 - Internal or external FLOODING event - Incore Sump (alarm)

- Field verification of a single fire alarm H

Fire Areas AND - High winds or tornado strike - ND/NS sump The FIRE is located within any Table H-1 area - NCDT

- Reactor Building (Containment) - FIRE HU4.2 - PRT

- EXPLOSION 4

- Auxiliary Building Receipt of a single fire alarm (i.e., no other indications of a Hazards None None - Diesel Generator Rooms FIRE) - Other events with similar hazard AND characteristics as determined by the

- RN Pump House Shift Manager Fire The fire alarm is indicating a FIRE within any Table H-1 area CNS

- Dog Houses AND The existence of a FIRE is not verified within 30 min. of

- Standby Shutdown Facility (SSF) alarm receipt (Note 1)

HU4.3 A FIRE within the plant PROTECTED AREA not extinguished within 60 min. of the initial report, alarm or indication (Note 1)

HU4.4 A FIRE within the plant PROTECTED AREA that requires NOTES Table H-2 Safe Operation & Shutdown Rooms/Areas firefighting support by an offsite fire response agency to extinguish Note 1: The Emergency Coordinator should declare the event promptly upon Bldg. Elevation Unit 1 Room/Area Unit 2 Room/Area Mode determining that time limit has been exceeded, or will likely be exceeded.

Gaseous release IMPEDING access to equipment necessary for Rm 478 (1EMXA) Rm 469 (2EMXA) 4 Note 2: If an ongoing release is detected and the release start time is unknown, normal plant operations, cooldown or shutdown assume that the release duration has exceeded the specified time limit.

5 Rm 496 (1ETA) Rm 486 (2ETA) 4 Auxiliary 577' 4 Rm 496 (1EMXS) Rm 486 (2EMXS) 4 Note 3: If the effluent flow past an effluent monitor is known to have stopped, AB-577', JJ-57 (1MXK) AB-577', JJ-57 (2MXK) 4 HA5.1 indicating that the release path is isolated, the effluent monitor reading is no longer Hazardous None Rm 330 (1EMXJ) Rm 320 (2EMXJ) 4 Release of a toxic, corrosive, asphyxiant or flammable gas None VALID for classification purposes. Date & Time of Shutdown Gases Auxiliary 560' Rm 372 (1ETB) Rm 362 (2ETB) 4 into any Table H-2 rooms or areas Note 4: The pre-calculated effluent monitor values presented in EALs RA1.1, Rm 372 (1EMXD) Rm 362 (2EMXD) 4 AND RS1.1 and RG1.1 should be used for emergency classification assessments until Entry into the room or area is prohibited or IMPEDED (Note 5) the results from a dose assessment using actual meteorology are available.

Date Time Inability to control a key safety function from outside the Control Note 5: If the equipment in the listed room or area was already inoperable or out-Control Room evacuation resulting in transfer of plant control to Room of-service before the event occurred, then no emergency classification is alternate locations warranted.

1 2 3 4 5 6 1 2 3 4 5 6 DEF HS6.1 Note 6: If CONTAINMENT CLOSURE is re-established prior to exceeding the 30-HA6.1 6

minute time limit, declaration of a General Emergency is not required.

An event has resulted in plant control being transferred from An event has resulted in plant control being transferred from the Control Room to the Auxiliary Shutdown Panels or the Control Room to the Auxiliary Shutdown Panels or Note 7: This EAL does not apply to routine traffic impediments such as fog, snow, None Standby Shutdown Facility Standby Shutdown Facility None ice, or vehicle breakdowns or accidents.

Control AND Room Note 8: A manual trip action is any operator action, or set of actions, which causes Control of any of the following key safety functions is not the control rods to be rapidly inserted into the core, and does not include manually Evacuation reestablished within 15 min. (Note 1): driving in control rods or implementation of boron injection strategies.

- Reactivity (Modes 1, 2 and 3 only)

CNS

- Core Cooling Note 9: In the absence of reliable NCS temperature indication caused by the loss

- NCS heat removal of decay heat removal capability, classification should be based on time to boil data when in Mode 5 and 6.

Other conditions exist which in the judgment of the Site Emergency Other conditions existing that in the judgment of the Site Emergency Other conditions exist that in the judgment of the Site Emergency Other conditions existing that in the judgment of the Site Emergency Note 10: If the loss of containment cooling threshold is exceeded due to loss of Coordinator warrant declaration of a General Emergency Coordinator warrant declaration of a Site Area Emergency Coordinator warrant declaration of an Alert Coordinator warrant declaration of a UE both trains of VX-CARF, this EAL only applies if at least one train of VX-CARF is not operating, per design, after the 10 minute actuation delay for greater than or 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF equal to 15 minutes.

HG7.1 HS7.1 HA7.1 HU7.1 Note 11: If the affected SAFETY SYSTEM train was already inoperable or out of Other conditions exist which in the judgment of the Other conditions exist which in the judgment of the Other conditions exist which, in the judgment of the Other conditions exist which in the judgment of the service before the hazardous event occurred, then this emergency classification is 7 Emergency Coordinator indicate that events are in progress or have occurred which involve actual or IMMINENT substantial core degradation or melting with potential for loss Emergency Coordinator indicate that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or Emergency Coordinator, indicate that events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a Emergency Coordinator indicate that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to not warranted.

Note 12: If the hazardous event only resulted in VISIBLE DAMAGE, with no indications of degraded performance to at least one train of a SAFETY SYSTEM, EC of containment integrity or HOSTILE ACTION that results in HOSTILE ACTION that results in intentional damage or security event that involves probable life threatening risk to facility protection has been initiated. No releases of then this emergency classification is not warranted.

Judgment an actual loss of physical control of the facility. Releases can malicious acts, (1) toward site personnel or equipment that site personnel or damage to site equipment because of radioactive material requiring offsite response or monitoring be reasonably expected to exceed EPA Protective Action could lead to the likely failure of or, (2) that prevent effective HOSTILE ACTION. Any releases are expected to be limited are expected unless further degradation of SAFETY Guideline exposure levels offsite for more than the access to equipment needed for the protection of the public. to small fractions of the EPA Protective Action Guideline SYSTEMS occurs.

immediate site area Any releases are not expected to result in exposure levels exposure levels.

which exceed EPA Protective Action Guideline exposure levels beyond the SITE BOUNDARY.

Damage to a loaded cask CONFINEMENT BOUNDARY EAL Identifier Table E-1 ISFSI Dose Limits 1 2 3 4 5 6 DEF XXX.X Prepared for Duke Energy by: Operations Support Services, Inc. - www.ossi-net.com (2/18/16)

NAC UMS NAC MAGNASTOR EU1.1 Category (R, H, E, C, S, F) Sequential number within subcategory/classification E

• 100 mrem/hr (neutron + gamma) on the side

• 240 mrem/hr gamma on the vertical surfaces Damage to a loaded canister CONFINEMENT BOUNDARY as indicated by an on-contact radiation reading on the Emergency classification (G, S, A, U) Subcategory number (1 if no subcategory)

• 100 mrem/hr (neutron + gamma) on the top

• 10 mrem/hr neutron on the vertical surfaces None None None surface of a loaded spent fuel cask > any Table E-1 dose ISFSI

• 200 mrem/hr (neutron + gamma) at the air

• 900 mrem/hr (neutron + gamma) on the top limit inlets or outlets Modes: 1 2 3 4 5 6 DEF Catawba Nuclear Station CSD-EP-CNS-0101-02 Rev 000 MODES 5, 6 & Defueled Power Operation Startup Hot Standby Hot Shutdown Cold Shutdown Refuel Defueled

GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT Release of gaseous radioactivity resulting in offsite dose greater Release of gaseous radioactivity resulting in offsite dose greater than Release of gaseous or liquid radioactivity resulting in offsite dose Release of gaseous or liquid radioactivity greater than 2 times the than 1,000 mrem TEDE or 5,000 mrem thyroid CDE 100 mrem TEDE or 500 mrem thyroid CDE greater than 10 mrem TEDE or 50 mrem thyroid CDE SLC/TS limits for 60 minutes or longer Prolonged loss of all offsite and all onsite AC power to essential Loss of all offsite and all onsite AC power to essential buses Loss of all but one AC power source to essential buses Loss of all offsite AC power capability to essential buses buses for 15 minutes or longer for 15 minutes or longer for 15 minutes or longer 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF RG1.1 RS1.1 RA1.1 RU1.1 1 2 3 4 1 2 3 4 1 2 3 4 1 2 3 4 Reading on any Table R-1 effluent radiation monitor > column Reading on any Table R-1 effluent radiation monitor > column Reading on any Table R-1 effluent radiation monitor Reading on any Table R-1 effluent radiation monitor SG1.1 SS1.1 SA1.1 SU1.1 GE for 15 min. (Notes 1, 2, 3, 4) SAE for 15 min. (Notes 1, 2, 3, 4) > column ALERT for 15 min. (Notes 1, 2, 3, 4) > column UE for 60 min. (Notes 1, 2, 3) Loss of all offsite and all onsite AC power capability to Loss of all offsite and all onsite AC power capability to AC power capability, Table S-1, to essential 4160V buses Loss of all offsite AC power capability, Table S-1, to 1

RG1.2 RS1.2 RA1.2 RU1.2 essential 4160V buses 1(2)ETA and 1(2)ETB essential 4160V buses 1(2)ETA and 1(2)ETB for 15 min. 1(2)ETA and 1(2)ETB reduced to a single power source essential 4160V buses 1(2)ETA and 1(2)ETB for 15 min.

Dose assessment using actual meteorology indicates doses Dose assessment using actual meteorology indicates doses Dose assessment using actual meteorology indicates doses Sample analysis for a gaseous or liquid release indicates a AND (Note 1) for 15 min. (Note 1) (Note 1)

> 1000 mrem TEDE or 5000 mrem thyroid CDE at or beyond > 100 mrem TEDE or 500 mrem thyroid CDE at or beyond > 10 mrem TEDE or 50 mrem thyroid CDE at or beyond the concentration or release rate > 2 x SLC/TS limits for SSF fails to supply NC pump seal injection AND the SITE BOUNDARY (Note 4) the SITE BOUNDARY (Note 4) SITE BOUNDARY (Note 4) Loss of OR Any additional single power source failure will result in loss of 60 min. (Notes 1, 2) 1 RG1.3 Field survey results indicate EITHER of the following at or RS1.3 Field survey results indicate EITHER of the following at or RA1.3 Analysis of a liquid effluent sample indicates a concentration Essential AC CA supply to SGs AND EITHER:

- Restoration of at least one essential bus in < 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is all AC power to SAFETY SYSTEMS beyond the SITE BOUNDARY: beyond the SITE BOUNDARY: or release rate that would result in doses > 10 mrem TEDE or Power not likely (Note 1) Table S-1 AC Power Sources Rad 50 mrem thyroid CDE at or beyond the SITE BOUNDARY for Effluent - Closed window dose rates > 1000 mR/hr expected to - Closed window dose rates > 100 mR/hr expected to - Core Cooling RED PATH conditions met 60 min. of exposure (Notes 1, 2) continue for 60 min. continue for 60 min.

Offsite

- Analyses of field survey samples indicate thyroid CDE - Analyses of field survey samples indicate thyroid CDE RA1.4

> 5000 mrem for 60 min. of inhalation. > 500 mrem for 60 min. of inhalation. Field survey results indicate EITHER of the following at or - ATC (Train A)

(Notes 1, 2) (Notes 1, 2) Loss of all essential AC and vital DC power sources for 15 beyond the SITE BOUNDARY: minutes or longer - SATA (Train A) (if already aligned)

- Closed window dose rates > 10 mR/hr expected to continue for 60 min. 1 2 3 4 - ATD (Train B)

- Analyses of field survey samples indicate thyroid CDE SG1.2 - SATB (Train B) (if already aligned) 2

> 50 mrem for 60 min. of inhalation. Loss of all vital DC power for 15 minutes or longer R

Loss of all offsite and all onsite AC power capability to (Notes 1, 2) Onsite essential 4160V buses 1(2)ETA and 1(2)ETB for 15 min. 1 2 3 4 Spent fuel pool level cannot be restored to at least the top of the Spent fuel pool level at the top of the fuel racks Significant lowering of water level above, or damage to, irradiated Unplanned loss of water level above irradiated fuel AND SS2.1 - D/G A (Train A) fuel racks for 60 minutes or longer fuel Loss of Loss of all 125 VDC power based on battery bus voltage None - D/G B (Train B)

Loss of all 125 VDC power based on battery bus voltage None Vital DC indications < 105 VDC on all vital DC buses EDA, EDC, EDB Abnorm. 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF indications < 105 VDC on all vital DC buses EDA, EDC, EDB Power and EDD for 15 min.

Rad RG2.1 RS2.1 RA2.1 RU2.1 (Note 1) and EDD for 15 min. (Note 1)

Levels Spent fuel pool level cannot be restored to at least 14.5 ft. Lowering of spent fuel pool level to 14.5 ft. (Level 3) on Uncovery of irradiated fuel in the REFUELING PATHWAY UNPLANNED water level drop in the REFUELING PATHWAY

/ Rad (Level 3) on 1(2)KFP5780 or 1(2)NVP8790 for 60 min. 1(2)KFP5780 or 1(2)NVP8790 as indicated by low water level alarm or indication UNPLANNED loss of Control Room indications for 15 minutes or 2

UNPLANNED loss of Control Room indications for 15 minutes or (Note 1) AND longer with a significant transient in progress longer Effluent RA2.2 Damage to irradiated fuel resulting in a release of radioactivity UNPLANNED rise in corresponding area radiation levels as 3

Table R-1 Effluent Monitor Classification Thresholds indicated by any of the following radiation monitors: 1 2 3 4 1 2 3 4 Irradiated AND

- 1EMF15 (2EMF4) Spent Fuel Building Refueling Bridge SA3.1 SU3.1 Fuel Event Release Point Monitor GE SAE Alert UE A Trip 2 radiation alarm on any of the following radiation None

- 1EMF17 (2EMF2) Reactor Building Refueling Bridge None An UNPLANNED event results in the inability to monitor one An UNPLANNED event results in the inability to monitor one monitor indications:

Gaseous Unit Vent Noble Gas Low 1/2EMF36L -------- -------- 4.18E+6 cpm 5.75E+3 cpm - 1EMF15 (2EMF4) Spent Fuel Building Refueling Bridge Loss of CR or more Table S-2 parameters from within the Control Room or more Table S-2 parameters from within the Control Room

- 1EMF17 (2EMF2) Reactor Building Refueling Bridge Indications for 15 min. (Note 1) for 15 min. (Note 1)

- 1EMF42 (2EMF42) Spent Fuel Pool Ventilation Table S-3 Significant Transients AND Unit Vent Noble Gas High 1/2EMF36H 2.21E+4 cpm 2.22E+3 cpm 2.42E+2 cpm -------- - 1EMF39L (2EMF39L) Containment Noble Gas Any significant transient is in progress, Table S-3 RA2.3 - Reactor trip Liquid Waste Effluent Line 0EMF49L -------- -------- -------- 4.50E+6 cpm NCS activity greater than Technical Specification allowable limits Liquid Monitor Tank Discharge 0EMF57L

---

4.97E+5 cpm Lowering of spent fuel pool level to 24.5 ft. (Level 2) on 1(2)KFP5780 or 1(2)NVP8790 4 None

- Runback > 25% thermal power

- Electrical load rejection > 25% electrical load None SU4.1 1 2 3 4 Radiation levels that IMPEDE access to equipment necessary for normal plant operations, cooldown or shutdown NCS - Safety injection actuation Table S-2 Safety System Parameters NCS activity > Technical Specification 3.4.16 limits or Facility Activity Operating License limits (151/159), whichever is more Table R-2 Safe Operation & Shutdown Rooms/Areas 1 2 3 4 5 6 DEF restrictive RA3.1 - Reactor power 3

Bldg. Elevation Unit 1 Room/Area Unit 2 Room/Area Mode NCS leakage for 15 minutes or longer Dose rates > 15 mR/hr in EITHER of the following areas: - NCS level Rm 478 (1EMXA) Rm 469 (2EMXA) 4 Control Room (EMF12) 1 2 3 4 OR - NCS pressure None Rm 496 (1ETA) Rm 486 (2ETA) 4 Area Rad Auxiliary 577' Central Alarm Station (by survey) None SU5.1 5

Rm 496 (1EMXS) Rm 486 (2EMXS) 4 - In-core T/C temperature S

Levels NCS unidentified or pressure boundary leakage AB-577', JJ-57 (1MXK) AB-577', JJ-57 (2MXK) 4 RA3.2 - Level in at least one S/G Rm 330 (1EMXJ) Rm 320 (2EMXJ) 4 None > 10 gpm for 15 min.

An UNPLANNED event results in radiation levels that prohibit None NCS - Auxiliary or emergency feed flow in at least OR Auxiliary 560' Rm 372 (1ETB) Rm 362 (2ETB) 4 or IMPEDE access to any Table R-2 rooms or areas (Note 5)

Rm 372 (1EMXD) Rm 362 (2EMXD) 4 Leakage one S/G NCS identified leakage > 25 gpm for 15 min.

System OR HOSTILE ACTION within the PROTECTED AREA HOSTILE ACTION within the OWNER CONTROLLED AREA or Confirmed SECURITY CONDITION or threat Malfunct. Leakage from the NCS to a location outside containment airborne attack threat within 30 minutes > 25 gpm for 15 min.

1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF (Note 1)

HS1.1 HA1.1 HU1.1 Inability to shut down the reactor causing a challenge to core cooling Automatic or manual trip fails to shut down the reactor and Automatic or manual trip fails to shut down the reactor A HOSTILE ACTION is occurring or has occurred within the A HOSTILE ACTION is occurring or has occurred within the A SECURITY CONDITION that does not involve a HOSTILE or NCS heat removal subsequent manual actions taken at the reactor control consoles are PROTECTED AREA as reported by the Security Shift OWNER CONTROLLED AREA as reported by the Security ACTION as reported by the Security Shift Supervision not successful in shutting down the reactor 1 Supervision Shift Supervision HA1.2 HU1.2 Notification of a credible security threat directed at the site SS6.1 1

SA6.1 1

SU6.1 1

An automatic or manual trip fails to shut down the reactor as An automatic or manual trip fails to shut down the reactor as An automatic trip did not shut down the reactor as Security None A validated notification from NRC of an aircraft attack threat HU1.3 indicated by reactor power > 5% indicated by reactor power > 5% indicated by reactor power > 5% after any RPS setpoint within 30 min. of the site A validated notification from the NRC providing information AND AND is exceeded 6

of an aircraft threat All actions to shut down the reactor are not successful as Manual trip actions taken at the reactor control console AND indicated by reactor power > 5% (manual reactor trip switches or turbine manual trip) are not A subsequent automatic trip or manual trip action taken AND EITHER: successful in shutting down the reactor as indicated by reactor at the reactor control console (manual reactor trip None - Core Cooling RED PATH conditions met power > 5% (Note 8) switches or turbine manual trip) is successful in shutting RPS Seismic event greater than OBE level - Heat Sink RED PATH conditions met down the reactor as indicated by reactor power < 5%

Failure 2

(Note 8) 1 2 3 4 5 6 DEF HU2.1 SU6.2 None NOTES None None NOTES A manual trip did not shut down the reactor as indicated by Seismic event > OBE as indicated by OBE EXCEEDED Seismic [Refer to EAL CA6.1 OR SA9.1 for escalation due to seismic event] alarm on 1AD-4, B/8 reactor power > 5% after any manual trip action was initiated Event Note 1: The Emergency Coordinator should declare the event promptly upon Note 1: The Emergency Coordinator should declare the event promptly upon AND determining that time limit has been exceeded, or will likely be exceeded. determining that time limit has been exceeded, or will likely be exceeded. A subsequent automatic trip or manual trip action taken at the Note 2: If an ongoing release is detected and the release start time is unknown, Hazardous event Note 2: If an ongoing release is detected and the release start time is unknown, reactor control console (manual reactor trip switches or assume that the release duration has exceeded the specified time limit.

1 2 3 4 5 6 DEF assume that the release duration has exceeded the specified time limit. turbine manual trip) is successful in shutting down the reactor as indicated by reactor power < 5% (Note 8)

Note 3: If the effluent flow past an effluent monitor is known to have stopped, HU3.1 Note 3: If the effluent flow past an effluent monitor is known to have stopped, indicating that the release path is isolated, the effluent monitor reading is no longer VALID for classification purposes. A tornado strike within the PROTECTED AREA indicating that the release path is isolated, the effluent monitor reading is no longer Loss of all onsite or offsite communications capabilities VALID for classification purposes.

Note 4: The pre-calculated effluent monitor values presented in EALs RA1.1, HU3.2 Note 4: The pre-calculated effluent monitor values presented in EALs RA1.1, 1 2 3 4 RS1.1 and RG1.1 should be used for emergency classification assessments until Internal room or area FLOODING of a magnitude sufficient 7

RS1.1 and RG1.1 should be used for emergency classification assessments until 3

the results from a dose assessment using actual meteorology are available. to require manual or automatic electrical isolation of a the results from a dose assessment using actual meteorology are available. Table S-4 Communication Methods SU7.1 SAFETY SYSTEM component needed for the current None Loss of all Table S-4 onsite communication methods Note 5: If the equipment in the listed room or area was already inoperable or out- Loss of of-service before the event occurred, then no emergency classification is operating mode Note 5: If the equipment in the listed room or area was already inoperable or out- System Onsite ORO NRC OR None None None warranted.

Comm of-service before the event occurred, then no emergency classification is Loss of all Table S-4 ORO communication methods Natural or warranted.

Tech.

[Refer to EAL CA6.1 OR SA9.1 for escalation due to natural or HU3.3 Public Address X OR Note 6: If CONTAINMENT CLOSURE is re-established prior to exceeding the 30- technological hazard] Movement of personnel within the PROTECTED AREA is Hazard Note 6: If CONTAINMENT CLOSURE is re-established prior to exceeding the 30- Loss of all Table S-4 NRC communication methods minute time limit, declaration of a General Emergency is not required. IMPEDED due to an offsite event involving hazardous Internal Telephones X minute time limit, declaration of a General Emergency is not required.

Note 7: This EAL does not apply to routine traffic impediments such as fog, snow, materials (e.g., an offsite chemical spill or toxic gas release) Onsite Radios X Failure to isolate containment or loss of containment pressure control Note 7: This EAL does not apply to routine traffic impediments such as fog, snow, ice, or vehicle breakdowns or accidents. ice, or vehicle breakdowns or accidents.

HU3.4 DEMNET X 1 2 3 4 Note 8: A manual trip action is any operator action, or set of actions, which causes A hazardous event that results in on-site conditions sufficient Commercial Telephones X X SU8.1 8

Note 8: A manual trip action is any operator action, or set of actions, which causes the control rods to be rapidly inserted into the core, and does not include manually driving in control rods or implementation of boron injection strategies. to prohibit the plant staff from accessing the site via personal the control rods to be rapidly inserted into the core, and does not include manually EITHER:

vehicles (Note 7) driving in control rods or implementation None of boron injection strategies. Satellite Phones X None X Any penetration is not isolated within 15 min. of a VALID Note 9: In the absence of reliable NCS temperature indication caused by the loss CMT Note 9: In the absence of reliable NCS temperature indication caused by the loss Cellular Phones X X containment isolation signal (Note 1) of decay heat removal capability, classification should be based on time to boil FIRE potentially degrading the level of safety of the plant Failure of decay heat removal capability, classification should be based on time to boil OR data when in Mode 5 and 6. data when in Mode 5 and 6. NRC Emergency X X Telecommunications System (ETS) Containment pressure > 3 psig with < one full train of Note 10: If the loss of containment cooling threshold is exceeded due to loss of [Refer to EAL CA6.1 OR SA9.1 for escalation due to FIRE] 1 2 3 4 5 6 DEF Note 10: If the loss of containment cooling threshold is exceeded due to loss of containment cooling operating per design for > 15 min.

both trains of VX-CARF, this EAL only applies if at least one train of VX-CARF is both trains of VX-CARF, this EAL only applies if at least one train of VX-CARF is (Notes 1, 10) not operating, per design, after the 10 minute actuation delay for greater than or HU4.1 not operating, per design, after the 10 minute actuation delay for greater than or equal to 15 minutes. SA9 Hazardous event affecting a SAFETY SYSTEM needed for the A FIRE is not extinguished within 15 min. of any of the equal to 15 minutes.

current operating mode Note 11: If the affected SAFETY SYSTEM train was already inoperable or out of following FIRE detection indications (Note 1): Table S-5 Hazardous Events service before the hazardous event occurred, then this emergency classification is - Report from the field (i.e., visual observation) Note 11: If the affected SAFETY SYSTEM train was already inoperable or out of 1 2 3 4 CNS 9

service before the hazardous event occurred, then this emergency classification is SA9.1 not warranted. - Receipt of multiple (more than 1) fire alarms or indications not warranted.

- Field verification of a single fire alarm - Seismic event (earthquake) The occurrence of any Table S-5 hazardous event Table H-1 H

Note 12: If the hazardous event only resulted in VISIBLE DAMAGE, with no AND Note 12: If the hazardous event only resulted in VISIBLE DAMAGE, with no AND indications of degraded performance to at least one train of a SAFETY SYSTEM, Fire Areas - Internal or external FLOODING event - Event damage has caused indications of degraded The FIRE is located within any Table H-1 area Hazardous indications of degraded performance to at least one train of a SAFETY SYSTEM, then this emergency classification is not warranted. None is not warranted.

then this emergency classification - High winds or tornado strike performance on one train of a SAFETY SYSTEM HU4.2 Event

- Reactor Building (Containment) needed for the current operating mode None Affecting 4 Receipt of a single fire alarm (i.e., no other indications of a - FIRE AND EITHER of the following:

- Auxiliary Building Safety Hazards None None FIRE)

Systems - EXPLOSION - Event damage has caused indications of degraded

- Diesel Generator Rooms AND performance to a second train of the SAFETY SYSTEM Fire The fire alarm is indicating a FIRE within any Table H-1 area - Other events with similar hazard needed for the current operating mode.

- RN Pump House characteristics as determined by the AND - Event damage has resulted in VISIBLE DAMAGE to the

- Dog Houses Shift Manager second train of the SAFETY SYSTEM needed for the Table F-2 Containment Radiation - R/hr (EMF53A/B)

The existence of a FIRE is not verified within 30 min. of alarm receipt (Note 1) current operating mode

- Standby Shutdown Facility (SSF) CMT Potential Table H-2 Safe Operation & Shutdown Rooms/Areas (Note 11, 12) Time After S/D FC Loss NCS Loss HU4.3 Loss F

FG1.1 1 2 3 4 FS1.1 1 2 3 4 FA1.1 1 2 3 4 Bldg. Elevation Unit 1 Room/Area Unit 2 Room/Area Mode A FIRE within the plant PROTECTED AREA not extinguished 0-1 550 8.8 5500 within 60 min. of the initial report, alarm or indication (Note 1) Loss of any two barriers Loss or potential loss of any two barriers (Table F-1) Any loss or any potential loss of either Fuel Clad or NCS Rm 478 (1EMXA) Rm 469 (2EMXA) 4 1-2 400 8.4 4000 HU4.4 AND (Table F-1)

Auxiliary 577' Rm 496 (1ETA) Rm 486 (2ETA) 4 Fission Loss or potential loss of third barrier (Table F-1) 2-8 160 7.0 1600 Rm 496 (1EMXS) Rm 486 (2EMXS) 4 A FIRE within the plant PROTECTED AREA that requires Product AB-577', JJ-57 (1MXK) AB-577', JJ-57 (2MXK) 4 firefighting support by an offsite fire response agency to >8 100 6.2 1000 extinguish Barriers Rm 330 (1EMXJ) Rm 320 (2EMXJ) 4 Auxiliary 560' Rm 372 (1ETB) Rm 362 (2ETB) 4 Gaseous release IMPEDING access to equipment necessary for Rm 372 (1EMXD) Rm 362 (2EMXD) 4 normal plant operations, cooldown or shutdown Table F-1 Fission Product Barrier Threshold Matrix 5 None None HA5.1 4

Hazardous Release of a toxic, corrosive, asphyxiant or flammable gas None Fuel Clad (FC) Barrier Reactor Coolant System (NCS) Barrier Containment (CMT) Barrier Gases into any Table H-2 rooms or areas AND Entry into the room or area is prohibited or IMPEDED (Note 5)

Loss Potential Loss Loss Potential Loss Loss Potential Loss A. NCS or SG 1. An automatic or manual ECCS (SI) 1. CSFST Integrity-RED PATH 1. A leaking or RUPTURED SG is Inability to control a key safety function from outside the Control Control Room evacuation resulting in transfer of plant control to actuation required by EITHER:

Tube conditions met FAULTED outside of containment Room alternate locations Leakage

• UNISOLABLE NCS leakage 1 2 3 4 5 6 1 2 3 4 5 6 DEF None None

• SG tube RUPTURE None CNS HS6.1 HA6.1 6 None An event has resulted in plant control being transferred from the Control Room to the Auxiliary Shutdown Panels or Standby Shutdown Facility An event has resulted in plant control being transferred from the Control Room to the Auxiliary Shutdown Panels or Standby Shutdown Facility None Control AND B. Inadequate 1. CSFST Core Cooling-RED PATH 1. CSFST Core Cooling-ORANGE 1. CSFST Heat Sink-RED PATH 1. CSFST Core Cooling-RED PATH Room Control of any of the following key safety functions is not Heat conditions met PATH conditions met conditions met conditions met Evacuation reestablished within 15 min. (Note 1): Removal AND AND

- Reactivity (Modes 1, 2 and 3 only) 2. CSFST Heat Sink-RED PATH Heat sink is required None Restoration procedures not conditions met None

- Core Cooling effective within 15 min. (Note 1)

- NCS heat removal AND Heat sink is required Other conditions exist which in the judgment of the Site Emergency Other conditions existing that in the judgment of the Site Emergency Other conditions exist that in the judgment of the Site Emergency Other conditions existing that in the judgment of the Site Emergency Coordinator warrant declaration of a General Emergency Coordinator warrant declaration of a Site Area Emergency Coordinator warrant declaration of an Alert Coordinator warrant declaration of a UE C. CMT 1. EMF53A/B > Table F-2 column 1. EMF53A/B > Table F-2 column 1. EMF53A/B > Table F-2 column 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF 1 2 3 4 5 6 DEF Radiation / FC Loss None NCS Loss None None CMT Potential Loss NCS Activity 2. Dose equivalent I-131 coolant HG7.1 HS7.1 HA7.1 HU7.1 activity > 300 µCi/gm Other conditions exist which in the judgment of the Other conditions exist which in the judgment of the Other conditions exist which, in the judgment of the Other conditions exist which in the judgment of the 7 Emergency Coordinator indicate that events are in progress or have occurred which involve actual or IMMINENT substantial core degradation or melting with potential for loss Emergency Coordinator indicate that events are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public or Emergency Coordinator, indicate that events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a Emergency Coordinator indicate that events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to D. CMT Integrity or

1. Containment isolation is required AND EITHER

• Containment integrity has been lost

1. CSFST Containment-RED PATH conditions met Bypass EC of containment integrity or HOSTILE ACTION that results in HOSTILE ACTION that results in intentional damage or security event that involves probable life threatening risk to facility protection has been initiated. No releases of based on Emergency Coordinator 2. Containment hydrogen concentration > 6%

Judgment an actual loss of physical control of the facility. Releases can malicious acts, (1) toward site personnel or equipment that site personnel or damage to site equipment because of radioactive material requiring offsite response or monitoring judgment be reasonably expected to exceed EPA Protective Action could lead to the likely failure of or, (2) that prevent effective HOSTILE ACTION. Any releases are expected to be limited are expected unless further degradation of SAFETY None None 3. Containment pressure > 3 psig with < one None None

• UNISOLABLE pathway from Guideline exposure levels offsite for more than the access to equipment needed for the protection of the public. to small fractions of the EPA Protective Action Guideline SYSTEMS occurs. Containment to the environment exists full train of containment cooling operating immediate site area Any releases are not expected to result in exposure levels exposure levels. per design for > 15 min. (Notes 1, 10) which exceed EPA Protective Action Guideline exposure 2. Indications of NCS leakage outside of levels beyond the SITE BOUNDARY. containment Damage to a loaded cask CONFINEMENT BOUNDARY E. EC 1. Any condition in the opinion of the 1. Any condition in the opinion of 1. Any condition in the opinion of the 1. Any condition in the opinion of the 1. Any condition in the opinion of the 1. Any condition in the opinion of the Judgment Emergency Coordinator that the Emergency Coordinator that Emergency Coordinator that Emergency Coordinator that Emergency Coordinator that indicates loss of Emergency Coordinator that indicates Table E-1 ISFSI Dose Limits 1 2 3 4 5 6 DEF indicates loss of the Fuel Clad indicates potential loss of the indicates loss of the NCS barrier indicates potential loss of the NCS the Containment barrier potential loss of the Containment barrier Prepared for Duke Energy by: Operations Support Services, Inc. - www.ossi-net.com (2/18/16) barrier Fuel Clad barrier barrier NAC UMS NAC MAGNASTOR EU1.1 E

• 100 mrem/hr (neutron + gamma) on the side

• 240 mrem/hr gamma on the vertical surfaces Damage to a loaded canister CONFINEMENT BOUNDARY None

• 100 mrem/hr (neutron + gamma) on the top None

• 10 mrem/hr neutron on the vertical surfaces None as indicated by an on-contact radiation reading on the surface of a loaded spent fuel cask > any Table E-1 dose EAL Identifier ISFSI limit

• 200 mrem/hr (neutron + gamma) at the air inlets or outlets

• 900 mrem/hr (neutron + gamma) on the top XXX.X Category (R, H, E, C, S, F) Sequential number within subcategory/classification Emergency classification (G, S, A, U) Subcategory number (1 if no subcategory)

Catawba Nuclear Station Modes: 1 Power Operation Startup 2 3 Hot Standby 4

Hot Shutdown 5

Cold Shutdown 6

Refuel DEF Defueled CSD-EP-CNS-0101-02 Rev 000 MODES 1, 2, 3 & 4