ML23206A050

2A, Exam Final Items (Hatch 2021-301)

ML23206A050
Person / Time
Site:	Hatch
Issue date:	07/25/2023
From:	NRC/RGN-II
To:	Southern Nuclear Operating Co
References
Download: ML23206A050 (1)

Text

ML23206A050 Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 13-1 Op-Test No.: 2021-301 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at 58% RTP. RFPT 2A is reset and windmilling awaiting fuse replacement of 2C32-R601A, RFP A M/A Station, next shift. 2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written. RCIC is inoperable, RAS written.

Turnover: IAW 34SO-E51-001-2, un-isolate RCIC and place in standby. 34SV-E51-001-2, RCIC Pump Operability, will be performed at the end of the next shift. After RCIC is placed in standby, raise Reactor power to 62% RTP using Recirc.

Event Event Event Malf. No.

No. Type* Description IAW 34SO-E51-001-2, un-isolate RCIC and place in standby, 1 N/A N (BOP) starting at step 4.1.1.36.

mfE51_250 RCIC Steam Line breaks in the Reactor Building. RCIC isolation C (ATC) 2 svoE51074 valves fail to auto close. Manual isolation is required.

svoE51075 TS (SRO)

(Critical Task)

Feedwater pump 2B cooling water controller failure requiring 3 mfN21_88B I (BOP) manual control to restore temperature. TC repair & return to Automatic.

mfP41_292 mfP41_67B C (ATC) PSW Pump 2B sheared shaft, Standby PSW pump 2D fails to auto 4 loP41-C001BA3 loP41-C001BG1 TS (SRO) start and must be manually started.

loP41-C001BR2 C (BOP) Instrument Bus 2B breaker trips open, reclose breaker to return to service.

5 mfR25_186 TS (SRO) mf65702209 Earthquake with a loss of Unit 1 SAT 1D. Reduce reactor power to 6 mf65702227 R (ATC) mf65321987 between 40% & 50% due to earthquake.

svoT48140(70/.75) svoT48142(50/10) Earthquake requiring an Emergency Depress prior to Torus level 7 svoT48143(50/10) M (ALL) svoT48147(50/10) reaches 98 inches. (Critical Task) svoT48148(50/10)

RPS Manual pushbuttons & Reactor Mode Switch fail requiring 8 mfC71_60B C (ATC) manual initiation of ARI.

diN21_C001A diN21_C001B diN21_C001C Small leak in Drywell with a loss of all Condensate pumps which mfG31_242 requires transition to CS for RWL control since HPCI, RCIC &

9 C (BOP) mfE11_42A RHR have failed. CS injection valve must be manually open.

mfE11_42B (Critical Task) rfE21_168 diE41A-S20

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 1 Page 2 of 32 Event

Description:

IAW 34SO-E51-001-2, un-isolate RCIC and place in standby, starting at step 4.1.1.36.

Time Position Applicant's Actions or Behavior Directs BOP to un-isolate RCIC and place in standby IAW 34SO-E51-001-2, 10 Min SRO RCIC System, starting at step 4.1.1.36.

NOTE: The RCIC Steam Line can be warmed and pressurized by performing either step 4.1.1.36.a (2E51-F007)

OR 4.1.1.36.b (2E51-F008).

If the BOP chooses step 4.1.1.36.a, (2E51-F007), then the following steps are applicable.

Pressurizing RCIC steam supply with 2E51-F007:

Ensures CLOSED 2E51-F007, Steam Supply Isol Valve.

Ensures OPEN 2E51-F008 Steam Supply Line Isol Valve.

Ensures OPEN 2E51-F054 Steam Line Drain Valve.

Slowly throttles OPEN 2E51-F007 Steam Supply Isol Valve.

FULLY OPENS 2E51-F007 when turbine steam inlet pressure (2E51-R602) is within 50 psig of reactor pressure on 2B21-R623A or B (P601 panel).

Confirms RCIC ISOLATION VLV F007/F008 NOT FULLY OPEN, (602-336) alarm clears.

BOP Ensures CLOSE 2E51-F054, Steam Line Drain Valve, when alarm, RCIC TURBINE INLET DRAIN POT LEVEL HIGH, (602-308),

clears.

Ensures OPEN 2E51-F008, Outbd Steam Isol Valve.

(keylock switch in STOP)

Ensures OPEN 2E51-F007, Inbd Steam Isol Valve.

(keylock switch in STOP)

NOTE: Alarm 602-308 is not expected to be in alarm due to RCIC out of service time.

Completes Attachment 1 and notifies SRO to be verified.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 1 Page 3 of 32 Event

Description:

IAW 34SO-E51-001-2, un-isolate RCIC and place in standby, starting at step 4.1.1.36.

Time Position Applicant's Actions or Behavior BOP Notifies SSS to complete verification of Attachment 1.

NOTE: The RCIC Steam Line can be warmed and pressurized by performing either step 4.1.1.36.a (2E51-F007)

OR BOP 4.1.1.36.b (2E51-F008).

If the BOP chooses step 4.1.1.36.b, (2E51-F008), then the following steps are applicable.

Pressurizing RCIC steam supply with 2E51-F008:

Ensures CLOSED 2E51-F008, Steam Supply Isol Valve.

Ensures OPEN 2E51-F007 Steam Supply Line Isol Valve.

Ensures OPEN 2E51-F054 Steam Line Drain Valve.

Slowly throttles OPEN 2E51-F008 Steam Supply Isol Valve.

FULLY OPENS 2E51-F008 when turbine steam inlet pressure (2E51-R602) is within 50 psig of reactor pressure on 2B21-R623A or B (P601 panel).

Confirms RCIC ISOLATION VLV F007/F008 NOT FULLY OPEN, (602-336) alarm clears.

Ensures CLOSE 2E51-F054, Steam Line Drain Valve, when alarm, RCIC TURBINE INLET DRAIN POT LEVEL HIGH, (602-308),

clears.

Ensures OPEN 2E51-F008, Outbd Steam Isol Valve.

(keylock switch in STOP)

Ensures OPEN 2E51-F007, Inbd Steam Isol Valve.

(keylock switch in STOP)

NOTE: Alarm 602-308 is not expected to be in alarm due to RCIC out of service time.

Completes Attachment 1 and notifies SRO to be verified.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 1 Page 4 of 32 Event

Description:

IAW 34SO-E51-001-2, un-isolate RCIC and place in standby, starting at step 4.1.1.36.

Time Position Applicant's Actions or Behavior SRO May notify SSS to complete verification of Attachment 1.

SIMULATOR OPERATOR proceeds to the next event at the Chief Examiners direction

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 2 Page 5 of 32 Event

Description:

RCIC steam line break with failure to auto close, manual works.

(Critical Task)

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, ENTER (RB-2), then call the BOP and request 2C Main Fuel Oil Storage tank level:

15 mfE51_250 RCIC Leak (final: 100, rate:7)

Min.

svoE51074 F007 stuck open svoE51075 F008 stuck open NOTE: It takes approximately 2 minutes for the following alarms to be received.

NOTE: The ATC may diagnose RCIC steam inlet pressure lowering prior to alarms being received and take actions to isolate RCIC.

Recognize and respond to the following alarms:

ALL LEAK DET DIF TEMP HIGH, 601-321 Recognize and respond to the following alarms:

RCIC STEAM LINE DIFF PRESS HIGH, 602-302 ALL RCIC TURBINE TRIP, 602-301 RCIC ISOLATION SIGNAL LOGIC A, 602-307 RCIC ISOLATION SIGNAL LOGIC B, 602-313 ATC may direct BOP to address at panel 2H11-P614, which area is producing alarm using Temperature Recorder on 2G31-R604 OR 2G31-R608:

ATC/BOP Determines TORUS ROOM AREA temperatures are increasing Determines MSL TUNNEL AREA temperatures are increasing Enters the SC EOP Flowchart on differential temperature above Max Normal.

SRO Directs an operator monitor Secondary Containment temperatures Directs operators to monitor systems for source of the leak Enters 34AB-T22-001-2, Primary Coolant System Pipe Break - Reactor BOP Building & 34AB-T22-003-2, Secondary Containment Control.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 2 Page 6 of 32 Event

Description:

RCIC steam line break with failure to auto close, manual works.

(Critical Task)

Time Position Applicant's Actions or Behavior Excerpt from 34AB-T22-003-2, Secondary Containment Control, Attachment 9 MAX MAX SECONDARY CONTAINMENT TEMP RDG RDG RDG NORMAL SAFE NORM on 2H11-P614, 2G31-R604 1 2 3

°F °F TORUS ROOM AREA 115 Torus vent air DIFF 42 98 9 (2E51-N027B/2E51-N026B) 116 Torus vent air DIFF 42 98 9 (2E51-N027D/2E51-N026D)

MAX MAX SECONDARY CONTAINMENT TEMP RDG RDG RDG NORMAL SAFE NORM on 2H11-P614, 2G31-R608 1 2 3

°F °F TORUS ROOM AREA 117 Torus vent air DIFF 42 98 8 (2E51-N027A/2E51-N026A) 118 Torus vent air DIFF 42 98 9 (2E51-N027C/2E51-N026C)

NOTE: Critical task is met when 2E51-F007 is manually closed prior to any area exceeding Max Safe Operating Temperature. Max Safe Operating Temperature is 98°F as read on 2H11-P614 panel, 2G31-R604 & R608 Point 115/116 & Point 117/118 respectively. It takes ~10 minutes to EXCEED MAX SAFE.

ENSURE Event Trigger EGE51-7 deletes svoE51074 when 2E51-F007 control switch is placed to close.

Responds to failure of RCIC Isolation:

Places 2E51- F008 control switch to CLOSE.

ATC Places 2E51- F007 control switch to CLOSE. (Critical Task)

Informs SRO of failure of 2E51-F008 to close.

Dispatches SO/Maintenance to investigate the leak.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 2 Page 7 of 32 Event

Description:

RCIC steam line break with failure to auto close, manual works.

(Critical Task)

Time Position Applicant's Actions or Behavior Address Tech Specs:

LCO 3.6.1.3, PCIVs Condition A (2E51-F008 is INOP)

SRO Isolate the flow path and deactivate 2E51-F007 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> AND verify the affected penetration flow path is isolated once every 31 days NOTE: RCIC was INOPERABLE at the beginning of the scenario.

SIMULATOR OPERATOR, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 3 Page 8 of 32 Event

Description:

2B RFPT Cooling water controller failure. TC repair & return to Automatic.

Time Position Applicant's Actions or Behavior At the Chief Examiners direction, SIMULATOR OPERATOR, INSTRUCT the ATC operator by phone to stay on the line until told to hang up, THEN 8 Min ENTER: (RB-3) mfN21_88B, Feedwater Pump Lube Oil Cooling System Failure.

The following alarms will annunciate:

RFPT 2B BRG OIL TEMP HIGH, (650-315).

RFPT 2B BRG TEMP HIGH, (650-333).

ALL RFP/COND BRG METAL TEMP HIGH, (650-112), (approximately 1 minute later if 2B RFPT PSW TCV is NOT opened in a timely manner).

NOTE: The BOP may immediately place the controller in manual IAW NMP-OS-007-001, Conduct of Operations Standards and Expectations, responding to a failed controller.

Addresses the high temp annunciator, pulling the ARP and confirms temperatures:

Dispatches BOP to panel 2H11-P655, checks all temperature indicators on BOP 2N32-R616 to determine actual oil temperatures.

Confirms that RFPT 2B Oil Temp controller, 2P41-R606, on panel 2H11-P650 is adjusted for 110 to 130°F.

Recognizes the automatic function of the controller has failed, closing the cooling water valve.

BOP Places the controller in manual, depresses the open/increase pushbutton, opening the valve. Oil temperatures begin decreasing and the alarm extinguishes.

Notifies maintenance of the 2P41-R606, RFPT temperature controller, SRO problem.

SIMULATOR OPERATOR, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 4 Page 9 of 32 Event

Description:

PSW Pump 2B shaft shears, PSW pump 2D fails to auto start and must be manually started.

Time Position Applicant's Actions or Behavior NOTE: Event 4 can be run simultaneously with Event 3 when the BOP is around the back panel, with the Chief Examiners direction, SIMULATOR OPERATOR, when the BOP is around the back panel, ENTER: (RB-4) mfP41_292 8 Min mfP41_67B, loP41_C001BR2 (ON),

loP41_C001BG1 (OFF),

loP41_C001BA3 (OFF) mf65013433 (OFF) mf65023482 (OFF)

When PSW pump 2B fails, responds to the following alarm:

ATC PSW MAIN HDR DIV II PRESS LOW, (650-156)

Acknowledges 650-156 alarm and informs the SRO that the PSW system pressure is low and that the PSW 2D pump did NOT auto start. (PSW ATC pump 2D may be started manually prior to recognizing failure to auto start.

There is NOT an obvious reason for the pressure being low.

Manually starts the PSW pump 2D IAW 34AR-650-156-2 or 34AB-P41-001-2, Loss of PSW. (May NOT pull procedures until after the pump has been started.)

ATC Monitors for increasing system pressure (>90psig).

Dispatches SO/Maintenance to investigate the cause of the PSW Low system pressure.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 4 Page 10 of 32 Event

Description:

PSW Pump 2B shaft shears, PSW pump 2D fails to auto start and must be manually started.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR:

ENSURE PSW TRIGGER EGP41-1 is ACTIVATED, THEN After 2 minutes of being sent to investigate the PSW system low pressure AND after the ATC has started PSW pump 2D, report that the PSW pump 2B motor is running, but the pump shaft is NOT turning.

SIMULATOR OPERATOR, As Maintenance, reports (with Time Compression) that only the Low-Pressure Auto Start Switch had a dirty contact that has now been cleaned and functioning properly.

Confirms/sends SO/Maintenance to investigate PSW Low system pressure.

Directs the operator to place the PSW Pump 2B to PTL off.

Reviews TS 3.7.2, Plant Service Water (PSW) System and Ultimate Heat SRO Sink (UHS),

Condition A.1 and determines PSW Pump 2B must be restored to OPERABLE status within 30 days.

Places 2P41-C001B control switch to PTL OFF position and reports this to ATC the SRO.

SIMULATOR OPERATOR, PROCEEDS to the next event at the Chief Examiners direction.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 5 Page 11 of 32 Event

Description:

Instrument Bus 2B breaker trips open, reclose breaker to return to service.

Time Position Applicant's Actions or Behavior 15 SIMULATOR OPERATOR, at direction of the lead examiner, ACTIVATE:

Mins (RB-5) malfunction mfR25_186, Loss Of Instrument Bus 2B.

ALL Various alarms indicating Instrument Bus 2B has lost power.

Directs BOP to enter 34AB-R25-002-2, Loss Of Instrument Buses, for loss of SRO Instrument Bus 2B.

Enters 34AB-R25-002-2, Loss of Instrument Buses, and performs the following at Panel 2H11-P654, May place 2B SBGT Fan control switch to OFF IAW 34SO-T46-001-2.

Dispatches SO to confirm CLOSE Instrument Bus 2B supply breaker 28 on 2R25-S037, Essential Cabinet 2B by dispatching a SO locally.

BOP Dispatches SO to confirm Essential Cabinet 2B 2R25-S037 is energized by NO other alarms illuminated at 2H11-P651.

Per step 4.4, dispatches Maintenance to check fuses R25F209 F01, R25F210 F02, and R25F211 F03, in fuse panel 2R20N P002 located next to Essential Cabinet 2B (power supply to 2R25 S065, Instrument Bus 2B 6).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 5 Page 12 of 32 Event

Description:

Instrument Bus 2B breaker trips open, reclose breaker to return to service.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, Once Tech Specs have been addressed, Call the control room, as an Electrician, and report that Instrument Bus 2B supply breaker 28 on 2R25-S037, Essential Cabinet 2B, is open. As the Electrical Supervisor, Electricians have investigated breaker 28 and find no reason to leave this breaker in the open position. We recommend closing breaker 28 and a SO is standing by to reclose breaker 28.

SIMULATOR OPERATOR, when directed, DELETE mfR25_186, THEN NOTIFIES SRO that breaker 28 on Essential Cabinet 2B is closed.

Addresses TS 3.8.7, Distribution Systems - Operating and determines that Condition C exists requiring Instrument Bus 2B returned to operable status in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SRO Addresses TS 3.4.5. Condition B, requiring grab samples of primary containment atmosphere once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and restore within 30 days.

After report on local actions, directs the BOP to re-energize Instrument Bus 2B by closing breaker 28 to Instrument Bus 2A.

NOTE: The following steps may be performed out of order, AFTER placing Group Isolation Reset Switch to the Group 1 and Group 2/5 positions, on P601.

Directs SO to crosstie Instrument Buses per step 4.5.

Once Instrument Bus 2B is energized, continues at step 4.7 and performs the following:

Following confirmation of any group isolation(s),

RESET isolation(s) by placing Group Isolation Reset Switch to the BOP Group 1 and Group 2/5 positions, on P601.

Opens the following Fission Product Monitoring isolation valves, panel P700:

2D11-F052 2D11-F053 2D11-F072 Opens 2B31-F020, Rx Wtr Sample Otbd Isol AOV, on P601.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 5 Page 13 of 32 Event

Description:

Instrument Bus 2B breaker trips open, reclose breaker to return to service.

Time Position Applicant's Actions or Behavior IT IS NOT INTENDED FOR THE CREW TO RESTORE ALL OF THE LOADS ASSOCIATED WITH INSTRUMENT BUS 2B.

AFTER THE OPERATOR RESTORES 2D11-F052, F053 & F072, AT THE CHIEF EXAMINERS DIRECTION, SIMULATOR OPERATOR PROCEEDS TO THE NEXT EVENT.

Resets and return Rx Bldg. Ventilation to normal per 34SO-T41-005-2.

Resets and return R/F Ventilation to normal per 34SO-T41-006-2 Secures Standby Gas Treatment System and place in standby per 34SO-T46-001-2.

BOP Restores Drywell Equipment and Floor Drain Sumps per 34SO-G11-009-2.

Returns Steam Packing Exhauster to service per 34SO-N33-001-2.

Notifies Unit 1 NPO to restore Control Room ventilation to the desired mode of operation per 34SO-Z41-001-1.

At SRO direction returns Rx Water Level Control to 3 element control per 34AR-603-132-2, Feedwater Control System Trouble.

Restores the Drywell Cooling Fans to normal alignment per 34SO-T47-001-2.

Alarm 650-204, Drywell/Torus RCDR R627 Temp High, may be received if Drywell Cooling Fans are not restored to a pre-event lineup.

It is NOT intended for the crew to restore all of the loads associated with INSTRUMENT BUS 2B.

AFTER the operator restores 2D11-F052, F053 & F072, SIMULATOR OPERATOR, PROCEEDS to the next event at the Chief Examiners direction.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 6 Page 14 of 32 Event

Description:

Earthquake with a loss of Unit 1 SAT 1D. Reduce reactor power to between 40% & 50% due to earthquake.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, at Chief Examiners direction, ACTIVATE (RB-6)

(Earthquake - malfunctions to (ON):

10 mf65702209 Window 30 SEISMIC PEAK SHOCK RECORDER HIGH G Min LEVEL & mf65702227 Window 48 SEISMIC INSTRUMENTATION TRIGGERED.

SIMULATOR OPERATOR, ENSURE Event Triggers EGS40-440 &

EGS40-450 trip open PCBs 179440 & 179450 de-energizing SAT 1D.

The following annunciators are received:

2H11-P657 SYSTEM TROUBLE, (650-224).

ALL SEISMIC PEAK SHOCK RECORDER HIGH G LEVEL, (657-030).

SEISMIC INSTRUMENTATION TRIGGERED, (657-048).

230 KV BREAKER TRIP, (653-218).

2H11-P657 SYSTEM TROUBLE, (650-224), alarm on 2H11-P650 panel.

BOP 230 KV BREAKER TRIP, (653-218) on 2H11-P653 panel.

Communicates both alarms to the SRO.

SRO Dispatches the BOP to Panel 2H11-P653 and 2H11-P657.

Enters 230 KV BREAKER TRIP, 653-218, on 2H11-P653 panel and informs the SRO that PCBs 179440 & 179450 supplying power to BOP SAT 1D have tripped open.

As time permits, may notify GCC of tripped PCBs.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 6 Page 15 of 32 Event

Description:

Earthquake with a loss of Unit 1 SAT 1D. Reduce reactor power to between 40% & 50% due to earthquake.

Time Position Applicant's Actions or Behavior Informs the SRO of the Seismic alarms and enters ARPs:

34AR-657-030-2 and 34AR-657-048-2 to perform the following actions:

BOP NOTE: Actions for both ARPs are the same, except for checking the power supply.

Dispatches Unit 1 RO to panel 1H11-P701 to check for further indication of a seismic event by monitoring Peak Shock Annunciator, 1L51-R620, for 12.7 Hz amber lights (> 0.08g, OBE) and 12.7 Hz red lights (> 0.15g, DBE).

SIMULATOR OPERATOR, after one minute, NOTIFIES Unit 2 Control Room that you were in the Reactor Building and felt the floor vibrating.

May have the Unit 1 RO check the following:

Peak Shock Annunciator, 1L51-VDC-R620, plugged in on panel 1H11-P701.

BRKR 3 on 120/208V Essential AC Cab., 1R25-S065.

BOP May have I & C refer to Seismic Instrumentation Earthquake Response Manual, SX-18271, for guidance in analyzing seismic data.

Enters 34AB-Y22-002-0, Naturally occurring Phenomenon.

May inform the Shift Manager to evaluate an Emergency Classification.

Directs the BOP to enter 34AB-Y22-002-0, Naturally occurring Phenomenon, SRO if not already entered.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 6 Page 16 of 32 Event

Description:

Earthquake with a loss of Unit 1 SAT 1D. Reduce reactor power to between 40% & 50% due to earthquake.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, Immediately after being dispatched to check the Shock recorder on 1H11-P701 panel, inform the team that the following lights are illuminated:

12.7 Hz Amber lights (> 0.08g, OBE)

AND 12.7 Hz Red lights (> 0.15g, DBE)

(Immediately is appropriate since this indicator is on Unit 1, but right next to the Unit 2 SRO desk. It is NOT simulated in the Simulator since it is a Unit 1 only instrument.)

NOTE: With SAT 1D de-energized, 34GO-OPS-013-2, Normal Plant Shutdown, should NOT be entered.

Determines that all electrical power is NOT available.

Directs the crew to reduce reactor power to between 40% and 50% RTP per 34GO-OPS-005-2, Power Changes.

Contacts switchyard maintenance to assist in switchyard damage assessment .

Contacts Maintenance to inspect Independent Spent Fuel Storage Installation (ISFSI) for damage.

SRO Within one hour, dispatches personnel to locally close or confirmed closed the following valves (if not performed by the BOP):

1P11-F167, CST Sump to Radwaste Drain.

1P11-F3002, Condensate Transfer Pumps and Sample Sink Drain Line to Yard.

2P11-F051, Retaining Wall Drain.

2P11-F100, Transfer Pump Wall Drain.

Dispatches personnel to inspect the plant for damage.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 6 Page 17 of 32 Event

Description:

Earthquake with a loss of Unit 1 SAT 1D. Reduce reactor power to between 40% & 50% due to earthquake.

Time Position Applicant's Actions or Behavior NOTE: These actions are redundant to the SROs and either can perform.

Enters 34AB-Y22-002-0 and performs the following actions:

Determines that all electrical power is available.

Informs SRO of the requirement to enter 34GO-OPS-005-2, Power Changes, and reduce reactor power to between 40% and 50% RTP per 34GO-OPS-005-2, Power Changes.

Contacts switchyard maintenance to assist in switchyard damage assessment.

Contacts Maintenance to inspect Independent Spent Fuel Storage BOP Installation (ISFSI) for damage.

Within one hour, dispatches personnel to locally close or confirmed closed the following valves (if not performed by the SRO):

1P11-F167, CST Sump to Radwaste Drain.

1P11-F3002, Condensate Transfer Pumps and Sample Sink Drain Line to Yard.

2P11-F051, Retaining Wall Drain.

2P11-F100, Transfer Pump Wall Drain.

Dispatches personnel to inspect the plant for damage.

Directs ATC to decrease reactor power to 40% to 50% by decreasing Recirc flow and/or inserting control rods. Power decreases should be SRO made as recommended by the STA/Reactor Engineering at a rate exceeding 10 MWe/min.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 6 Page 18 of 32 Event

Description:

Earthquake with a loss of Unit 1 SAT 1D. Reduce reactor power to between 40% & 50% due to earthquake.

Time Position Applicant's Actions or Behavior NOTE: May get the RBM UPSCALE, (603-202) and ROD OUT BLOCK, (603-238) alarm, if a peripheral control rod is not selected. This is expected and the operator may select a peripheral rod at this time.

May also get Alarm HEATER TROUBLE, 650-135 alarm. This is expected at this power level.

IAW 34SO-B31-001-2 (step 7.1.5) & 34GO-OPS-005-2, the ATC decreases Recirc pump speed, exceeding 10 MWE per minute by depressing the LOWER SLOW, LOWER MEDIUM or LOWER FAST pushbuttons on the Master (P603 panel) or Individual controls (P602 panel) until reactor power is 40 - 50%.

ATC If using Individual Controls, pump speed decreases will alternate between the A & B Recirc pumps to prevent excessive flow mismatches.

Monitors power decrease by observing APRM and generator output indications.

Notifies SRO of attaining 40% to 50% reactor power.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 7 Page 19 of 32 Event

Description:

Earthquake requiring an Emergency Depress prior to Torus level reaches 98 inches. (Critical Task)

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, after reactor power is reduced between 40-50%

RTP and at Chief Examiners direction, ACTIVATE (RB-7)

Torus leak at (3/4) 0.75/min) svoT48140 (70/.75), svoT48142 (50/10), svoT48143 (50/10), svoT48147 (50/10), svoT48148 (50/100)

LOOK ahead, this leak will be modified at 142 inches in the Torus (EGT48-1).

SIMULATOR OPERATOR: After one minute, Notifies Unit 2 Control Room that you were in the Reactor Building and felt the floor vibrating.

The following annunciators are received:

650-224, PANEL 2H11-P657 SYSTEM TROUBLE.

657-086, TORUS S-W AREA INSTR SUMP LVL HIGH.

657-087, TORUS N-W AREA INSTR SUMP LVL HIGH.

657-088, TORUS N-E AREA INSTR SUMP LVL HIGH.

657-089, TORUS S-E AREA INSTR SUMP LVL HIGH.

657-104, TORUS S-W AREA INSTR SUMP LVL HIGH-HIGH.

ALL 657-105, TORUS N-W AREA INSTR SUMP LVL HIGH-HIGH.

657-106, TORUS N-E AREA INSTR SUMP LVL HIGH-HIGH.

657-107, TORUS S-E AREA INSTR SUMP LVL HIGH-HIGH.

657-013, TORUS N-E AREA INSTR SUMP LVL HIGH-HIGH-HIGH.

657-031, TORUS S-E AREA INSTR SUMP LVL HIGH-HIGH-HIGH.

657-049, TORUS N-W AREA INSTR SUMP LVL HIGH-HIGH-HIGH.

657-067, TORUS S-W AREA INSTR SUMP LVL HIGH-HIGH-HIGH.

Reports multiple alarms to SRO indicating a break in the Reactor Building.

BOP Directs SO/Maintenance to investigate the leak.

Directs BOP to 2H11-P657 panel.

SRO When above alarms are reported, directs operator to monitor Torus water level and then if lowering, enter 34AB-T23-004-2, Torus Water Level.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 7 Page 20 of 32 Event

Description:

Earthquake requiring an Emergency Depress prior to Torus level reaches 98 inches. (Critical Task)

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR: Three (3) minutes after being dispatched to check for leaks in the Torus section of the Reactor Building, report to the crew:

A leak has been identified on the 2A RHR line between the Torus and the first RHR isolation valve.

602-235, TORUS WATER LEVEL HIGH/LOW, annunciates ALL Recognizes that Torus level is decreasing.

Dispatches personnel to determine the location of the Torus leak.

If not already directed, directs NPO to enter 34AB-T23-004-2, Torus Water Level, and to monitor Torus water level.

Enters the PC EOP Flowchart when Torus level decreases to SRO 146 inches.

May determine that water will not be added to the Torus until the cause of the low Torus level is identified and controlled.

Enter SC EOP flowchart for SC area water levels being high.

If NOT already performed, dispatches personnel to the Torus area AND BOP the Reactor Building diagonals to determine the source of the water loss (if the leak location has not already been reported).

NOTE: Once the leak has been identified on the 2A RHR line, the operators may stop isolating other systems in an attempt to isolate valve.

Enters 34AB-T23-004-2, Torus Water Level, and performs the following:

Dispatches personnel to the Torus to determine source of leakage Notifies SRO of ECCS TS requirements when closing valves.

ATC Closes 2E21-F019B, Torus Suction Vlv.

Closes 2E11-F065B, Torus Suction Vlv.

Closes 2E11-F065D, Torus Suction Vlv.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 7 Page 21 of 32 Event

Description:

Earthquake requiring an Emergency Depress prior to Torus level reaches 98 inches. (Critical Task)

Time Position Applicant's Actions or Behavior Checks Torus water level and determines the Torus level is continuing to decrease with the above valves closed ATC Closes 2E41-F051, HPCI Torus Suction Vlv.

Opens 2E21-F019B, Torus Suction Vlv.

Opens 2E11-F065B, Torus Suction Vlv.

Opens 2E11-F065D, Torus Suction Vlv.

Enters 34AB-T23-001-2, Loss of Primary Containment Integrity, AND 34AB-T22-003-2, Secondary Containment Control.

Checks Torus water level and determines the Torus level is continuing to ATC decrease, and performs the following valves:

Opens 2E41-F051, HPCI Torus Suction Vlv.

Closes 2E51-F003, RCIC Torus Suction Vlv.

Checks Torus water level and determines the Torus level is continuing to decrease, and performs the following valves:

ATC Opens 2E51-F003, RCIC Torus Suction Vlv.

Closes 2E21-F019A, Torus Suction Vlv.

Closes 2E11-F065A, Torus Suction Vlv.

Closes 2E11-F065C, Torus Suction Vlv.

Checks Torus water level and determines the Torus level is continuing to decrease, and opens the following valves:

ATC 2E21-F019A, Torus Suction Vlv.

2E11-F065A, Torus Suction Vlv.

2E11-F065C, Torus Suction Vlv.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 7 Page 22 of 32 Event

Description:

Earthquake requiring an Emergency Depress prior to Torus level reaches 98 inches. (Critical Task)

Time Position Applicant's Actions or Behavior IAW the PC flowchart, prior to water level reaching 98 inches, determines that the reactor is required to be shutdown and enters the RC flowchart at point A.

Assigns the ATC to perform RC-1.

SRO Assigns the BOP operator to perform RC-2 and RC-3.

Enters 31EO-EOP-010-2, RC EOP flow chart if RWL decreases below 3 inches.

Directs RWL Band of 3 to 50 inches.

NOTE: GO TO EVENT 8 FOR RC-1 ACTIONS Performs RC-2 actions consisting of:

Confirms proper Level Control response:

Checks ECCS Injection Systems.

Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value (will not due to low power).

Set down does not auto function (low power), manually reduces FW Master Controller setpoint to approximately 9 inches.

BOP When feed flow is less than the capacity of the S/U level control valve

( 1.5 mlbm/hr), then:

Opens 2N21-F125.

Places 2C32-R619, FW S/U level control valve controller, in Auto, set at approximately 9 inches.

Closes 2N21-F110.

Will control RWL and with SRO permission will raise RWL to 32 to 42 inches.

Performs RC-3 consisting of:

Monitor RPV pressure.

Confirm proper operation of pressure control system (TBV, LLS, etc.).

BOP If necessary, allow RPV pressure to exceed 1074 psig then cycle any SRV to initiate LLS.

Maintain RPV pressure between 1074 and 800 psig.

Notify SRO of pressure control system operation.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 7 Page 23 of 32 Event

Description:

Earthquake requiring an Emergency Depress prior to Torus level reaches 98 inches. (Critical Task)

Time Position Applicant's Actions or Behavior If the need to Emergency Depressurize is recognized in time, then Anticipates Emergency Depressurization.

SRO Assign an operator to fully open all Main Turbine Bypass Valves.

Directs ATC/BOP to place HPCI in Pull To Lock prior to 110 inches Torus level.

On the DEHC panel Selects the Control > Bypass Valve screen.

Inserts a ramp rate of 100, then presses OK.

Inserts a bypass valve position of 100, then presses OK.

Checks that the Bypass Valve Jack status is active.

ATC/BOP Recognizes that 3 Bypass Valves open.

Reports to the SRO 3 Bypass Valves are open.

Places HPCI Aux Oil pump in the Pull To Lock position on 2H11-P601 panel.

ATC Provides periodic updates on Torus level to the SRO.

Transitions to CP-1 and orders 7 ADS valves open for Emergency SRO Depress.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 7 Page 24 of 32 Event

Description:

Earthquake requiring an Emergency Depress prior to Torus level reaches 98 inches. (Critical Task)

Time Position Applicant's Actions or Behavior Places the switches for 7 ADS valves in the open position.

(Critical Task)

(Critical Task - Open 7 SRVs prior to Torus water level reaches 98 inches. Critical task is met when 5 SRVs have been opened).

(Approximately 25 minutes to reach 98 inches in Torus)

The amber lights for the SRVs will not illuminate if pressure has been reduced to below approximately 300 psig. In this case the operator ATC/BOP must use 2H11-P614 recorder indication to monitor tail pipe temperatures for the SRVs to verify the valves actually opened (Recorder 2B21-R614).

Depending on RWL prior to opening ADS valves, RWL may swell to above 60 inches, requiring the operator to enter 34AB-C32-001-2, Reactor Water Level Above 60 inches.

Operator secures all injection other than CRD.

NOTE:

GO TO EVENT 9 FOR RWL CONTROL FOR CORE SPRAY ACTIONS Depending on Reactor Water Level prior to opening ADS valves, RWL may swell to above 60 inches, requiring the operator to enter ATC/BOP 34AB-C32-001-2, Reactor Water Level Above 60 inches.

Operator secures all injection other than CRD.

SIMULATOR OPERATOR, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 8 Page 25 of 32 Event

Description:

RPS Manual pushbuttons & Reactor Mode Switch fail requiring ARI initiation.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, malfunction mfC71_60B, Reac Prot System Fails to Scram Complete, has been inserted from the beginning.

Performs RC-1 consisting of:

Inserts a manual scram Places the mode switch to SHUTDOWN Confirms BLUE Scram Lights are NOT ILLUMINATED Manually initiates ARI by rotating both ARI collars and then depressing both ARI pushbuttons Confirms BLUE Scram Lights are ILLUMINATED If NOT tripped, places the Recirc pumps at minimum speed 5 Mins ATC Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display Notifies SRO of rod position check Inserts SRMs and IRMs Places SDV isolation valve switch to "isolate" & confirms closed Shifts recorders to read IRMS, when required Ranges IRMS to bring reading on scale Notifies the SRO when the above actions are complete.

SIMULATOR OPERATOR, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 9 Page 26 of 32 Event

Description:

Small leak in Drywell with a loss of all Condensate pumps which requires transition to CS for RWL control since HPCI, RCIC & RHR have failed.

CS injection valve must be manually open. (Critical Task)

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, ENSURES Event Trigger EGC71-21, 5 Min ACTIVATES: malfunctions mfG31_242 RWCU Non-Isol Leak, diN21_C001A, diN21_C001B, and diN21_C001C, Spurious Loss of All Condensate Pumps, five minutes after the Mode switch is placed to SHUTDOWN.

ALL Recognizes that ALL Condensate Pumps have tripped.

Recognizes increasing Containment Pressure from the following alarms:

PRIMARY CNMT HIGH PRESSURE TRIP, (603-106)

ALL PRIMARY CNMT PRESSURE HIGH, (603-115)

DRYWELL PRESSURE HIGH, (602-210)

Informs SS of status of Condensate system and intentions of transitioning to BOP HPCI for RWL control Per the PC flowchart, verifies Torus level is <285 inches and directs an SRO operator to place Torus Sprays in service.

Sprays the Torus per 34SO-E11-010-2 placard on the 2H11-P601 Panel as follows:

Places Cnmt Spray Vlv Cntl switch in the MANUAL position.

ATC Starts RHR pump(s) in loop A/B, if NOT already running.

Opens 2E11-F028A/B.

Throttles Open 2E11-F027A/B.

Notifies SRO that RHR is in Torus Sprays.

NOTE: Only one loop of RHR will be placed in Torus Sprays. The flow is only 700 gpm.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 9 Page 27 of 32 Event

Description:

Small leak in Drywell with a loss of all Condensate pumps which requires transition to CS for RWL control since HPCI, RCIC & RHR have failed.

CS injection valve must be manually open. (Critical Task)

Time Position Applicant's Actions or Behavior As time allows, may spray the DW when Torus pressure exceeds 11 psig, verifying that Torus Level is <215 inches, and in the safe area of Graph 8 SRO (DWSIL) and directs an operator to:

Place all DW cooling fans to OFF.

Place both Recirc pumps to PTL OFF.

Places both Recirc pumps to PTL OFF on panel 2H11-P602.

Places the following DW cooling fans control switches to OFF on panels 2H11-P654 & P657:

2T47-B007B, Drywell Cooling Top Head Area Unit.

2T47-B008B, Drywell Cooling Pedestal/Annular Area Unit.

2T47-B009B, Drywell Cooling Recirc Pump Area Unit.

2T47-C001B, Drywell Cooling Return Air Fan.

ATC 2T47-C002B, Drywell Cooling Return Air Fan.

2T47-B010B, Drywell Cooling EL 114 Unit.

2T47-B007A, Drywell Cooling Top Head Area Unit.

2T47-B008A, Drywell Cooling Pedestal/Annular Area Unit.

2T47-B009A ,Drywell Cooling Recirc Pump Area Unit.

2T47-C001A, Drywell Cooling Return Air Fan.

2T27-C002A, Drywell Cooling Return Air Fan.

2T47-B010A, Drywell Cooling EL 114 Unit.

When all DW cooling fans are OFF AND both Recirc pumps are PTL OFF:

SRO Directs an operator to spray the Drywell.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 9 Page 28 of 32 Event

Description:

Small leak in Drywell with a loss of all Condensate pumps which requires transition to CS for RWL control since HPCI, RCIC & RHR have failed.

CS injection valve must be manually open. (Critical Task)

Time Position Applicant's Actions or Behavior Sprays the Drywell per 34SO-E11-010-2 placard on the 2H11-P601 Panel as follows:

Places Cnmt Spray Vlv Cntl switch in the Manual position.

Starts RHR pump(s) in loop A (B), if NOT already running.

Opens 2E11-F021A or B.

Opens 2E11-F016A or B (ONE WILL NOT OPEN AND OPERATOR ATC TRANSITIONS TO THE OTHER LOOP).

Informs SRO that the 2E11-F016A (or B) will NOT Open.

Opens 2E11-F021A or B.

Throttles Open 2E11-F016A(B) to >5000 gpm.

Confirms Drywell pressure is reducing.

Notifies SRO that RHR is in Drywell Sprays.

If HPCI is started for RWL control performs the following at 2H11-P601 panel:

Opens/confirms open 2E41-F059, Lube Oil Cooling Wtr Vlv.

Starts/confirms started 2E41-C002-2, Barometric Condenser Vacuum Pump.

BOP Opens/confirms open 2E41-F001, Turbine Steam Supply Vlv.

Places 2E41-C002-3, Aux Oil Pump, control switch to the START position.

Realizes 2E41-C002-3, will not start As time allows, notifies Maintenance of 2E41-C002-3 failure Informs SRO of 2E41-C002-3 failure NOTE: RHR & Core Spray valve failures were inserted from the beginning.

At panel 2H11-P601, Confirms the 4 RHR pumps and 2 Core Spray pumps did start BOP and notifies SRO

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-1 Event No.: 9 Page 29 of 32 Event

Description:

Small leak in Drywell with a loss of all Condensate pumps which requires transition to CS for RWL control since HPCI, RCIC & RHR have failed.

CS injection valve must be manually open. (Critical Task)

Time Position Applicant's Actions or Behavior Operates Core Spray for level control by performing the following at 2H11-P601 panel:

Confirms 2E21-C001A, CS pump 2A, running Confirms 2E21-C001B, CS pump 2B, running After RPV pressure is below the 425 psig:

BOP Opens 2E21-F005A, Injection Valve Opens 2E21-F005B, Injection Valve Throttles 2E21-F005A and\or F005B to restore RWL to +5 to 50 inches.

(Critical Task)

(Critical Task is met if at least one Core Spray injection valve is manually open prior to transitioning to Steam Cooling on CP-1)

With Chief Examiners Permission the Scenario will be terminated when the RPV has been Emergency Depressurized and RWL is in band of 5 inches to 50 inches or approaching.

Page 30 of 32 Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 13-1 Op-Test No.: 2021-301 Examiners: Operators: SRO RO BOP Initiating Conditions: Unit 2 is operating at 58% RTP. RFPT 2A is reset and windmilling awaiting fuse replacement of 2C32-R601A, RFP A M/A Station, next shift. 2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written. RCIC is inoperable, RAS written.

Turnover IAW 34SO-E51-001-2, un-isolate RCIC and place in standby. 34SV-E51-001-2, RCIC Pump Operability, will be performed at the end of the next shift. After RCIC is placed in standby, raise Reactor power to 62% RTP using Recirc.

Summary:

Event 1: Normal; IAW 34SO-E51-001-2, un-isolate RCIC and place in standby, starting at step 4.1.1.36.

Event 2: Component/TS; A RCIC steam line will break outside of Primary Containment. The outboard isolation valve is failed open and cannot be closed. Both isolation valves fail to automatically close on an automatic isolation signal and must be manually closed. (Critical Task) The SRO addresses Tech Specs for inoperable Primary Containment Isolation Valve.

Event 3: Instrument; Feedwater pump 2B cooling water controller will fail requiring the BOP to maintain cooling water manually. Time Compression repair & return the controller to automatic.

Event 4: Component/TS; PSW Pump 2B will experience a sheared shaft and the standby PSW pump will NOT automatically start. The operator will manually start the standby PSW pump 2D to restore system flow/pressure to normal. LCO 3.7.2 Required Action.

Event 5: Component/TS; Instrument Bus 2B supply breaker from Essential 2B will trip open de-energizing subsequent loads. Once investigated, Essential 2B breaker will be reclosed to restore Instrument Bus 2B to service. The BOP will return loads to service.

Event 6: Reactivity; Earthquake, the ATC will lower Reactor power to between 40% to 50%

RTP due to earthquake.

Event 7: Major; Emergency Depress prior to 98 inches in the Torus. (Critical Task)

Event 8: Component; RPS Manual pushbuttons & Reactor Mode Switch fail requiring ARI initiation.

Event 9: Component; Small leak in Drywell with a loss of all Condensate pumps which requires transition to CS for RWL control since HPCI, RCIC & RHR have failed. CS injection valve must be manually open. (Critical Task)

Page 31 of 32 Critical Tasks NRC FINAL Facility: E. I Hatch Scenario No.: 13-1 Op-Test No.: 2021-301 Critical Tasks With a RCIC steam line break discharging into the Reactor Building; manually isolate RCIC prior to any area exceeding Max Safe Operating Temperature (~ 7 minutes). (Event 2)

Emergency Depress prior to Torus level reaches 98 inches. (Event 7)

Small leak in Drywell with a loss of all Condensate pumps which requires transition to CS for RWL control since HPCI, RCIC & RHR have failed. CS injection valve must be manually open prior to transitioning to Steam Cooling on CP-1. (Event 9)

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 7 1. RCIC isolation, manual works (Event 2)

2. RFP 2B cooling water controller fails (Event 3)

3. PSW 2B sheared shaft, start PSW 2D (Event 4)

4. Instrument Bus 2B breaker fails (Event 5)

5. Earthquake (Event 6)

6. RPS failure with manual ARI (Event 8)

7. CP, HPCI & RHR fails, use CS (Event 9)

2. Malfunctions After 1-2 2 1. RPS failure with manual ARI (Event 8)

EOP Entry 2. CP, HPCI & RHR fails, use CS (Event 9)

3. Abnormal Events 2-4 3 1. RCIC isolation, manual works (Event 2)

2. PSW 2B sheared shaft, start PSW 2D (Event 4)

3. Earthquake (Event 6)

4. Major Transients 1-2 1 1. Emergency Depress (Event 7)

5. EOPs entered, 1-2 2 1. RC-(Non-ATWS) (Event 7) requiring substantive 2. PC (Event 7) actions

6. EOPs contingencies 0-2 1 1. CP-1 entered with substantive actions

7. Preidentified >2 3 1. RCIC steam line break (Event 2)

Critical Tasks 2. Emergency Depress prior to 98 inches in Torus (Event 7)

3. CS injection valve open (Event 9)

ILT-13 NRC FINAL Scenario 1 SHIFT TURNOVER Safety Focus UNIT 1 STATUS Plant Conditions: Unit 1 is operating at 100% RTP.

Unit 2 is operating at 58% RTP.

RFPT 2A is reset and windmilling awaiting fuse replacement of 2C32-R601A, RFP A M/A Station, next shift.

Plant Conditions:

2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written.

2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Protected Train: EOOS:

Division I Green Orange Division II Yellow Red Scheduled evolutions: IAW 34SO-E51-001-2, un-isolate RCIC and place in standby starting at step 4.1.1.36. 34SV-E51-001-2, RCIC Pump Operability, will be performed at the end of the next shift.

After RCIC is placed in standby, raise Reactor power to 62% RTP using Recirc.

Surveillances due this NONE shift:

Inop Equipment: 2D11-K615B, Off gas Post Treatment Radiation monitor has failed Downscale.

IAW TS/TRM, I&C has placed 2D11-K615B in the trip condition while maintaining the function of 601-405, Post Treatment O/G Radiation Hi-Hi-Hi/Inop. A Caution Tag is attached to 2D11-K615B switch.

2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

RCIC Active tagouts: NONE Rod Configuration: See RWM Step 24

Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 13-2 Op-Test No.: 2021-301 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at 92% RTP. 2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Turnover: Restore 2C32-R601B to normal alignment IAW 34AB-N21-002-2, Feedwater/Reactor Water Level Control Issues, Section 4.2. After 2C32-R601B is restored to normal alignment, raise reactor power to 95% RTP using Recirc flow.

Event Event Event Malf. No.

No. Type* Description RFPT 2B MA Controller has lost power/repaired & ready to be 1 mfC32_137B N (BOP) returned to service.

2 N/A R (ATC) Raise Reactor power to 95% using Recirc.

mf70022416 (ON) C (BOP)

Instrument Air System Prefilter Diff Press High. Place the standby 3 Prefilter in service.

Recirc Pump 2A High Vibration requiring reducing reactor power in 4 mfB31_41A C (ATC) an attempt to clear alarm. Alarm will clear when Recirc 2A speed is reduced prior to entering the Region of Potential Instabilities.

I (BOP) 5 mfE41_103 HPCI Inadvertent Initiation.

TS (SRO)

I (ATC) SRV 2F (LLS) cycles open/close until fuses are pulled.

6 mfB21_130F TS (SRO) (Critical Task) mfC71_59 Spurious Reactor scram/ATWS. Insert control rods/SBLC/Lower 7 M (ALL) RWL (Critical Task) mfC11_211 mfG31_207A 2G31-F004, RWCU Isolation valve, fails to close when SBLC pump 8 C (ALL) mfG31_207B is started.

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 1 Page 2 of 25 Event

Description:

RFPT 2B MA Controller has lost power/repaired & ready to be returned to service.

Time Position Applicant's Actions or Behavior 15 Directs the BOP to restore 2C32-R601B to normal alignment IAW 34AB-N21-SRO Mins 002-2, Feedwater/Reactor Water Level Control Issues, Section 4.2.2.7.

Enters 34AB-N21-002-2, Section 4.2, RFPT Recovery From Loss of Signal From M/A Station to TMR (Step 4.2.2.7)

Since TWO RFPTs are operating, THEN momentarily places RFPT 2B BOP Speed Setter switch to:

RAISE to INCREASE speed OR LOWER to DECREASE speed as necessary to correct large mismatches in RFPT speed.

Ensures RFPT 2B speed is > 2100 rpm as indicated on 2N32-R603B AND the M/A Station Permissive 2B White light is ILLUMINATED, 2H11-P650.

BOP Ensures the following, 2H11-P603:

Annunciator, RFPT CONTROLLER TROUBLE (603-150), is CLEAR.

RFP B M/A Station output signal is tracking actual RFPT 2B speed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 1 Page 3 of 25 Event

Description:

RFPT 2B MA Controller has lost power/repaired & ready to be returned to service.

Time Position Applicant's Actions or Behavior Transfers the RFPT 2B TMR Mode Switch to M/A AND confirms M/A STATION Green light is ILLUMINATED, 2H11-P650.

Since TWO RFPT's are operating, performs the following, 2H11-P603:

Slowly raises or lowers RFPT 2B speed, UNTIL the incoming RFP AND running RFP speed MATCH.

Compares the input AND the output of Pump B M/A Station by performing the following:

Depressing the PF key AND reading the controller output (PF lamp BOP LIT).

THEN depresses the PF key so the input to the controller is displayed (PF lamp is OFF), 2H11-P603.

Carefully adjusts the manual output lever, UNTIL the input AND output are MATCHED.

Places RFP B M/A Station in automatic by depressing the 'A' pushbutton UNTIL it ILLUMINATES.

As required, adjusts RFP A OR RFP B Speed Control Bias SETTING to maintain RFPT 2A AND RFPT 2B speed WITHIN 100 rpm.

SIMULATOR OPERATOR, after Event 2 PROCEED to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 2 Page 4 of 25 Event

Description:

Raise Reactor power to 95% using Recirc.

Time Position Applicant's Actions or Behavior Directs ATC to increase reactor power to 95% by increasing Recirc flow.

10 Min SRO Power increases are not to exceed 10 MWe/min.

NOTE: May get the RBM UPSCALE, (603-202) and ROD OUT BLOCK, (603-238) alarm, if a peripheral control rod is not selected. This is expected and the operator may select a peripheral rod at this time.

May also get Alarm HEATER TROUBLE, (650-135), alarm. This is expected at this power level.

May receive Alarm LPRM UPSCALE, (603-237), alarm.

IAW 34SO-B31-001-2 (step 7.1.5) & 34GO-OPS-005-2, the ATC increases Recirc pump speed, not to exceed 10 MWE per minute by depressing the RAISE SLOW or RAISE MEDIUM pushbuttons on the Master (P603 panel) or Individual controls (P602 panel) until reactor power is 95%.

ATC If using Individual Controls, pump speed increases will alternate between the A & B Recirc pumps to prevent excessive flow mismatches.

Monitors power increase by observing APRM and generator output indications.

Complies with 34SO-B31-001-2 , Limitation 5.2.15, which states:

WHEN changing Recirc pumps speed while in Two Loop operation maintain pump speeds to limit recirculation loop jet pump mismatch within the following limits:

ATC

<10% of rated core flow (7.7 E6 lbm/hr) WHEN operating

< 70% of rated core flow; AND

<5% of rated core flow (3.85 E6 lbm/hr) WHEN operating at

>70% of rated core flow.

ATC Notifies the SRO that reactor power has been increased to 95%.

SIMULATOR OPERATOR, at the Chief Examiners request, proceeds to the next event.

3ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 3 Page 5 of 25 Event

Description:

Instrument Air System Prefilter dP Hi - swap Prefilters.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, at the Chief Examiners direction, ACTIVATE 7

(RB-3)

Mins mf70022416, Instr Air Prefltr D103A Diff Press High (On)

Recognize and respond to the following alarms:

ALL PANEL 2H11-P700 SYSTEM TROUBLE, (650-225)

INSTR AIR PREFLTR D103A DIFF PRESS HIGH, (700-225)

Enters ARP 34AR-700-225-2:

Dispatches a SO locally to confirm Prefilter dP on 2P52-dPIS-N301A BOP IF filter P is high, notify Maintenance to replace the filter cartridge and initiate a Condition Report Dispatches a SO to inspect system for leak downstream of 2P52-D103A SIMULATOR OPERATOR, two (2) minutes after being dispatched to check Prefilter dP, inform the BOP that 2P52-dpis-N301A indicates 6 psid and that no air leaks exist.

If necessary, notifies Maintenance to change out the prefilter cartridge and SRO initiates a condition report.

Directs the BOP to swap Prefilters IAW 34AR-700-225-2.

SIMULATOR OPERATOR, WHEN the BOP swaps Prefilters, ENSURES EVENT TRIGGER EGP52-1 & EGP52-2 ACTIVATES: deleting malfunction mf70022416 - INSTRU AIR PREFLTR D103A DIFF PRESS HIGH (ANNUNCIATOR ON) and simulates correct light arrangement.

At panel 2H11-P700, places the standby filter in service:

Places control switch to ON for Turb Bldg Inst Air PreFltr/Afterfilter 2P52-D103B/2P52-D102B Inlet Isol, 2P52-F002B/2P52-F011B.

Places control switch to OFF for Turb Bldg Inst Air PreFltr/Afterfilter BOP 2P52-D103A/2P52-D102A Inlet Isol, 2P52-F002A/2P52-F011A.

Notifies Maintenance to replace the filter cartridge and initiate a condition report Notifies the SRO that the standby filter in service has been placed in service.

SIMULATOR OPERATOR, WHEN the BOP is at the P700 panel swapping the pre/afterfilters, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 4 Page 6 of 25 Event

Description:

Recirc Pump 2A High Vibration requiring reducing reactor power to clear alarm.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, when the BOP is at the P700 panel swapping the 18 pre/after filters, at the Chief Examiners direction, DEPRESS (RB-4) to Min ACTIVATE mfB31_41A, Recirc Pump A High Vibration.

ALL Receives RECIRC PUMP A HIGH VIBRATION, (602-104), alarm.

Enters 602-104 and performs the following:

Depresses the Hi vibration reset pushbutton and determines that the alarm does not clear.

ATC Notifies the SRO that the vibration alarm did not clear.

Notifies the SRO that the ARP requires reducing Recirc flow and attempting to reset the alarm again.

Directs the operator to reduce Rx power with Recirc per 34GO-OPS-005 and 34SO-B31-001-2, section 7.1.6, Two Loop Operation From Rated To Minimum Speed, exceeding 10 MWE/minute if necessary.

SRO Reminds the operator that entry into the Immediate Exit Region of the Power to Flow map is allowed.

Notifies Plant Management, Load Dispatcher, and Engineering of the Recirc Pump 2A high vibration condition.

IAW 34SO-B31-001-2 (step 7.1.6) & 34GO-OPS-005-2, the ATC decreases Recirc pump speed by depressing the Slow, Medium or Fast ATC LOWER pushbuttons. (may exceed 10 MWE per minute)

Monitors power decrease by observing APRM and generator output indications.

SIMULATOR OPERATOR, AFTER Recirc 2A Speed has been reduced to approximately 83% Speed, ENSURES Event Trigger EGB31-14, DELETES mfB31_41A, Recirc Pump A High Vibration.

Stops power reduction periodically and depresses the High vibration reset ATC pushbutton.

Notifies SRO that the vibration alarm is clear.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 4 Page 7 of 25 Event

Description:

Recirc Pump 2A High Vibration requiring reducing reactor power to clear alarm.

Time Position Applicant's Actions or Behavior NOTE: NOT expected to EXCEED 15% RTP.

NOTE: A 15% power change may occur if the ATC reduces Recirc speed significantly before depressing the Vibration Reset pushbutton.

If a 15% power change occurs, notification is required IAW limitation 5.2.13, 34GO-OPS-005-2.

If necessary, notifies chemistry of 15% power change in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> BOP/ATC IAW 34GO-OPS-005-2, Power Changes, Step 5.2.13.

NOTE: HEATER TROUBLE ALARM, (650-135), may alarm due to plant conditions.

SRO Directs the ATC operator to stop the power reduction.

Directs the operator determine the operating point on the Power to Flow SRO Map.

Notifies the SRO that operation is in the Analyzed Region of the Power to ATC Flow Map was entered.

SIMULATOR OPERATOR, at the Chief Examiners request, proceeds to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 5 Page 8 of 25 Event

Description:

HPCI Inadvertent Initiation.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR; WAIT UNTIL THE ATC OPERATOR IS AWAY (I.E. AWAY FROM HPCI) BEFORE ENTERING THIS MALFUNCTION OR 15 Mins NOTIFY ATC OPERATOR BY PHONE AND INFORM, AS I&C, THAT THE SIGNAL FOR RECIRC PUMP 2A VIBRATION COMING FROM THE DRYWELL WAS AN ACCURATE SIGNAL.

SIMULATOR OPERATOR, at Chief Examiner's direction, ENTERS (RB-5) malfunction mfE41_103, HPCI auto start.

ALL Recognize and report HPCI has started from an invalid initiation signal.

Verifies RWL and Drywell Pressure are normal.

BOP Enters 34AB-E10-001-2, Inadvertent Initiation of ECCS/RCIC.

Secures HPCI as follows:

Either, places HPCI Controller in Manual and lowers output to prevent injection and then performs the following:

OR:

Depresses and holds the HPCI Turbine Trip push-button.

Receives the following:

BOP HPCI TURBINE TRIP, (601-103)

HPCI TURBINE TRIP SOLENOID ENERGIZED, (601-109)

HPCI PUMP DISCHARGE FLOW LOW, (601-231)

When HPCI turbine has stopped, places the HPCI Aux Oil Pump in Pull To Lock off.

Receives HPCI TURBINE BRG OIL PRESS LOW, (601-112)

When HPCI TURBINE BRG OIL PRESS LOW, (601-112) alarm is received, releases the HPCI Turbine Trip push-button.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 5 Page 9 of 25 Event

Description:

HPCI Inadvertent Initiation.

Time Position Applicant's Actions or Behavior HPCI TURBINE TRIP SOLENOID ENERGIZED, (601-109),

clears.

IF injection occurs from HPCI, the following alarms occur:

FEEDWATER CONTROL SYSTEM TROUBLE, (603-132)

After HPCI is shutdown, returns Feedwater Control Mode select switch to 3-ELEM.

ATC/BOP RBM UPSCALE OR INOPERABLE, (603-202), APRM Upscale, (603-219), ROD OUT BLOCK, (603-238), and REACTOR VESSEL WATER LEVEL HIGH/LOW, (603-141) may come in and then clear.

SIMULATOR OPERATOR -

AFTER SRO declares HPCI inop per TS 3.5.1.C, as I & C Tech called to resolve the HPCI problem, inform the SRO that the HPCI initiation logic appears to be causing the inadvertent start signal and that you will be investigating the problem further.

Reviews TS 3.5.1, ECCS/RCIC.

IAW TS 3.5.1 Condition C, Declares HPCI inoperable, Must verify within one hour that RCIC is operable by administrative SRO means Must restore HPCI to operable status within 14 days Contacts Maintenance (if ATC has not done this) to investigate inadvertent HPCI start.

SIMULATOR OPERATOR proceeds to the next event at the Chief Examiners direction.

3ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 6 Page 10 of 25 Event

Description:

SRV 2F (LLS) cycles open/close until fuses are pulled. (Critical Task)

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR: At the Chief Examiners direction, INFORM the BOP operator by phone, that further investigation is needed for the HPCI initiation logic to determine the failure, then ENTER 10 Min (RB-6) mfB21_130F, Main Steam Relief Valve Fails Open.

ENSURE Event Trigger EGB21-12 ACTIVATES. This SRV will cycle such that it is open for 15 seconds, then stays closed for 45 seconds, then repeats this cycle for 5 minutes or until fuses for SRV 2F are removed. After 5 minutes, the SRV will fail open if fuses are not pulled.

Receive alarms:

ALL SAFETY/BLOWDOWN VALVE LEAKING, (603-122)

SAFETY BLOWDOWN PRESSURE HIGH, (602-311)

Directs operator to enter 34AB-B21-003-2, Failure of Safety/Relief Valves Enters a RAS for TS LCO 3.6.1.6, Condition A, for 2 or more LLS valves inop, which requires the unit to be in mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and SRO mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

If Torus water level exceeds 150 inches, enters RAS for TS LCO 3.6.2.2 Condition A, for Torus water level above 150 inches, which requires Torus water level to be restored in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Enters 34AB-B21-003-2, Failure of Safety/Relief Valves; Determines SRV 2F is cycling open then close.

Cycles the SRV 2F Control Switch several times.

May depress the ADS Logic A Timer Reset pushbutton (2B21-S2A).

May depress the ADS Logic B Timer Reset pushbutton (2B21-S2B).

ATC Depresses the LLS Channel A / C Reset pushbutton (2B21-S15A).

Depresses the LLS Channel B / D Reset pushbutton (2B21-S15B).

Informs SRO that SRV 2F is cycling and the fuses will have to be removed for the valve.

Notifies the SSS to remove the fuses for SRV 2F. (Critical Task)

(Critical Task is met if performed prior to entering the BIIT Curve, 110°F Torus Temperature, approximately 10 Minutes).

3ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 6 Page 11 of 25 Event

Description:

SRV 2F (LLS) cycles open/close until fuses are pulled. (Critical Task)

Time Position Applicant's Actions or Behavior Receives DRYWELL/TORUS RCDR R627 TEMP HIGH, (650-204) alarm ATC Determines Torus Water Temp (Point 2) is high at 98°F When the SRV is closed Point 2 starts decreasing.

SIMULATOR OPERATOR, if requested to remove fuses for SRV 2F, wait 4 minutes, then DELETE mfB21_130F, 2F LLS Valve and/or Scenario EGB21-12, then ENTER (RB-1), rfB21_305, to simulate removing the fuses for SRV 2F.

Then, NOTIFIES the crew that the fuses have been removed for SRV 2F.

Confirms that SRV 2F is closed by monitoring one or more of the following:

SRV tailpipe temperature decreasing (Panel 2H11-P614).

Torus water level increase has stopped.

Torus temperature increase has stopped.

Reactor and Generator power return to the pre-event level.

ATC Resets the SRV leak detection by placing the Leak Detection Logic A Reset keylock switch and Leak Detection Logic B Reset keylock switch to Reset position and back to Normal position.

Confirms that the Amber SRV indicating lights have Extinguished.

SAFETY BLOWDOWN PRESSURE HIGH, (602-311), clears.

Informs the SRO that SRV 2F is closed.

Informs the crew that operability of the suppression chamber-drywell vacuum breakers must be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per 34SV-T48-002-2, Suppression Chamber To Drywell Vacuum Breaker System Operability.

SRO/

Notifies Chemistry and initiates a CR to initiate increased monitoring of vessel ATC moisture content carryover per 64CH-SAM-025-0.

Notifies the Shift Manager to make appropriate notifications for the failed SRV.

3ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 6 Page 12 of 25 Event

Description:

SRV 2F (LLS) cycles open/close until fuses are pulled. (Critical Task)

Time Position Applicant's Actions or Behavior NOTE:

If Torus temperature exceeds 95°F, then the following steps will be done to place Torus Cooling in service.

At this time, Torus temperature will still be below 95°F, therefore RHR is NOT required to be placed into Torus Cooling. The SRO may elect to place Torus Cooling in service, since steam was admitted to the Torus.

The following steps are written IF the SRO elects to place Torus Cooling in service.

NOTE: The operator may place torus cooling in service by using the Placard that's available or using the appropriate section of the procedure.

These steps assume the Placard is used. The A or B loop of RHR may be used. The following steps are written assuming "B" loop and "B" pump is used. If "A" loop is used, substitute "A" for "B" for valves and if "B" pump is not used substitute "A", "C", or "D" for "B" pump.

Enters 34SO-E11-010-2, Residual Heat Removal Places RHRSW in service Overrides 2E11-F068B Low Discharge Pressure Interlock.

Positions 2E11-F068B to 45% OPEN.

BOP Starts RHRSW pump B.

Places 2E11-F068B Low Discharge Pressure Interlock switch to normal position.

Positions 2E11-F068B to obtain < 4400 gpm AND < 450 psig.

IF desired to start a SECOND RHRSW pump, Throttles 2E11-F068B to achieve max flow rate (not to exceed 4400 GPM).

BOP Opens 2E11-F068B an additional 5%.

Starts second RHRSW Pump.

Positions 2E11-F068B to obtain < 8800 gpm AND < 450 psig.

3ppendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 6 Page 13 of 25 Event

Description:

SRV 2F (LLS) cycles open/close until fuses are pulled. (Critical Task)

Time Position Applicant's Actions or Behavior Places RHR B Loop in Torus cooling per the placard by performing the following steps:

Opens 2E11-F048B.

Closes 2E11-F047B.

Opens 2E11-F003B.

Starts RHR Loop B pump Receives alarm, RHR LOW FLOW, (601-222).

Opens 2E11-F028B.

Receives alarm, AUTO BLOWDOWN CS OR RHR PRESS BOP PERMISSIVE, (602-312).

Receives alarm, SEC SYSTEM AUTO INITIATION SIGNAL PRESENT, (650-234).

Throttles OPEN 2E11-F024B.

Alarm, RHR LOW FLOW, (601-222), clears.

Opens 2E11-F047B.

Ensures RHR flow is < 11,500 GPM, THEN Closes 2E11-F048B.

Notifies the SRO that RHR "B" loop is in service.

May place the second pump in service.

SIMULATOR OPERATOR, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 7 Page 14 of 25 Event

Description:

Spurious Reactor scram/ATWS. Insert control rods/SBLC/Lower RWL (Critical Task)

Time Position Applicant's Actions or Behavior 10 SIMULATOR OPERATOR, at the Chief Examiners direction, ACTIVATE:

Min (RB-7) malfunction mfC71_59, Spurious Reactor Scram.

SIMULATOR OPERATOR, to prevent control rod motion when the manual scram is repeated, THEN following the Reactor Scram, ENSURE Event Trigger EGC71-15 modifies malfunction mfC11_211, SDV ATWS (Var), to a Final Value of 100 & inserts aiC11-R607-1, f:25 r:1000 & deletes mfC71_59.

A Spurious Reactor Scram occurs:

Enters RC or RC-A EOP Flowcharts Directs ATC to perform RC-1 placard Directs BOP to perform RC-2 and RC-3 placards SRO If time allows assigns TC-1 to be performed Enters the RCA EOP flow chart, 31EO-EOP-011-2, for a scram condition and reactor power above 5%.

Enters CP-3 EOP flow chart, 31EO-EOP-017-2, for ATWS level control.

Directs ATC to (or may observe):

Confirm the reactor Mode Switch in SHUTDOWN.

SRO Confirm ARI Initiation.

Confirm Recirc runback to minimum/tripped.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 7 Page 15 of 25 Event

Description:

Spurious Reactor scram/ATWS. Insert control rods/SBLC/Lower RWL (Critical Task)

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, when both Recirc Pumps are secured ENSURE Event Trigger EGB31-26 INSERTS AFTER 5 minutes mfC51_253, Region Independent LPRM Oscillations f:10 r:10 d:0.

Performs actions of placard RC-1 after Reactor SCRAM.

Manually SCRAMs the Reactor using the SCRAM pushbuttons.

Places Rx Mode Switch in SHUTDOWN.

If Scram blue lights are NOT illuminated, initiates Alternate Rod Insertion (ARI) by rotating the button collars and depressing both ARI pushbuttons at the same time.

If NOT tripped, places Recirc to minimum speed (if power is above 5%,

Uses the Full Core Display and Rod Worth Minimizer to determine that all control rods are NOT inserted past position 02.

Informs the SRO that all rods are NOT fully inserted.

ATC Reactor power is ~ 16% , performing ATWS ACTIONS.

(Placard) Performs ATWS ACTIONS since reactor power is above 5%:

Manually initiates ARI Trips the Recirc Pumps Inhibit ADS Injects SBLC (power is above 5%)

NOTE: See Event 8 for SBLC injection.

Notifies SRO, RC-1 ATWS ACTIONS complete Inserts IRMs and SRMs.

Places SDV Isol Vlv Switch to ISOL and ensures closed.

Shifts recorders to read IRMS, when required.

Ranges IRMS to bring reading on scale.

Notifies SRO when above actions are complete.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 7 Page 16 of 25 Event

Description:

Spurious Reactor scram/ATWS. Insert control rods/SBLC/Lower RWL (Critical Task)

Time Position Applicant's Actions or Behavior Performs actions of placards RC-2 and RC-3 after Reactor SCRAM.

BOP Performs RC-2 actions consisting of:

Confirms proper Level Control response:

Checks ECCS Injection Systems Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value BOP When feed flow is less than the capacity of the S/U level control valve (Placard) ( 1.5 mlbm/hr), then:

Ensures Open 2N21-F125.

Ensures 2C32-R619, FW S/U level control valve controller, in Auto, set at approximately 9 inches.

Closes 2N21-F110.

Secures one RFPT IF two are operating.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 7 Page 17 of 25 Event

Description:

Spurious Reactor scram/ATWS. Insert control rods/SBLC/Lower RWL (Critical Task)

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR; WHEN RWL is being lowered below 0 inches, DELETES EGB31-26 Scenario (mfC51_272).

Performs RC-2 ATWS ACTIONS; Terminates injection to lower RWL to -60 inches. (Critical Task)

(Critical Task is met if injection into the RPV is stopped within 5 minutes of Recirculation pumps being tripped).

Manually controls the RFPT(s) to maintain discharge pressure below reactor pressure per 34AB-N21-002-2, attachment 4.

Controls HPCI by performing the following actions as necessary If operating, places HPCI Flow controller in Manual and lowers output to achieve a lowering RWL trend or trips HPCI.

If NOT operating, place aux oil pump in PTL Off If required, places RCIC Flow controller in Manual and lowers BOP output to achieve a lowering RWL trend.

WHEN RWL reaches -60 inches, performs the following to maintain RWL -60 inches to -90 inches; Re-establishes injection with Condensate/Feedwater per 34AB-N21-002-2, Attachment 4, as required to support RWL Control actions.

Re-establishes injection with HPCI per 34SO-E41-001-2, as required to support RWL Control actions.

WHEN RWL is controlled between -60 in and -90 in, informs SRO, RWL is value controlling RWL with RFPT and/or HPCI.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 7 Page 18 of 25 Event

Description:

Spurious Reactor scram/ATWS. Insert control rods/SBLC/Lower RWL (Critical Task)

Time Position Applicant's Actions or Behavior Performs RC-3 consisting of:

Monitor RPV pressure.

Confirm proper operation of pressure control system (TBV, LLS, etc.).

BOP If necessary, allow RPV pressure to exceed 1074 psig then cycles any (Placard)

SRV to initiate LLS.

Maintain RPV pressure between 1074 and 800 psig.

Notify SRO of pressure control system operation.

Directs ATC or STA to report reactor power or observes reactor power on SRO SPDS.

Directs ATC to Reset ARI and insert control rods IAW 31EO-EOP-103-2.

NOTE: If asked, STA will direct the ATC to start in the center of the core and spiral out in a black and white pattern.

ATC Reports power level to the SRO.

Enters 31EO-EOP-103-2, EOP Control Rod Insertion Methods, section 3.7, Driving Control Rods at panel 2H11-P603.

Confirms ARI initiation signals are clear and Then depresses ARI Reset pushbutton OR dispatches an operator to place ARI System Test switch, to TEST, on panel 2C11-P001 Check annunciator ARI INITIATED,603-304, clear Attempts to drive rods by:

Places Reactor Mode switch to REFUEL.

Places Rod Worth Minimizer bypass switch to BYPASS.

Obtain recommendations from STA Verifies adequate CRD drive water pressure for driving rods and may operate 2C11-R600, CRD Flow Control, to achieve higher drive water DP.

May start second CRD pump Drives rods to at least 02 using the Emerg In or IN

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 7 Page 19 of 25 Event

Description:

Spurious Reactor scram/ATWS. Insert control rods/SBLC/Lower RWL (Critical Task)

Time Position Applicant's Actions or Behavior ATC Enters 31EO-EOP-103-2, EOP Control Rod Insertion Methods, section 3.3, Repeating Manual Scram at panel 2H11-P603.

Bypasses scram discharge volume high level trip at 2H11-P603.

Dispatches operator to install jumpers to override all automatic scram signals.

Places Discharge Volume Isolation Test switch to Norm at 2H11-P603.

Resets Scram when notified that jumpers have been installed.

Confirm all SDV Vent and Drain Valves are open.

NOTE: 2C11-R607, Press Control Vlv F127, controller is failed to allow only ~25% valve position. A valve position of 25% will NOT allow control rods to insert from Cooling Water DP.

Enters 31EO-EOP-103-2, EOP Control Rod Insertion Methods, section 3.8, Increasing CRD Cooling Water Dp at panel 2H11-P603.

Places 2C11-R607, Press Control Vlv F127 Controller, in MAN Increases output of 2C11-R607 to 100% at 2H11-P603 Confirms open OR fully opens 2C11-F003 Places 2C11-R600, CRD Flow Control, in MANUAL Increases output of 2C11-R600 to 100%

Closes 2C11-F005, Return To Vessel Flow Control Directs SSS to bypass MSIV Low Water Level isolation SRO IAW 31EO-EOP-100-2.

Directs BOP to override 2P41-F316A-D, PSW Isolation valves

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 7 Page 20 of 25 Event

Description:

Spurious Reactor scram/ATWS. Insert control rods/SBLC/Lower RWL (Critical Task)

Time Position Applicant's Actions or Behavior When RPV level is below -60 inches, directs BOP to control RPV level within a level band.

Any band between -60 inches and -180 inches is acceptable.

SRO (Typically -60 to -100 to maintain RPV level above -101)

If RWL increases to >-60 inches and Rx power is >5%, the override will be re-addressed to once again, lower level to < -60.

As time allows, and when generator load goes below 80 MWe, the crew performs TC-1 to trip the Main Turbine.

Manually Trip the Turbine.

Confirm TSVs, TCVs, and CIVs have properly closed.

Confirm the generator PCBs and EX2100 Control Tripped/Stopped.

Confirms/Opens PCB 179740 Confirms/Opens PCB 179750 BOP/ATC Confirms the 4160 VAC station service busses have transferred to their alternate supply.

Confirms/Places TGM in auto.

Start TG Oil Pump Motor Suction Pump Lift Pumps Confirms Steam Seal & Condenser Vacuum systems proper operation.

Closes the RSSVs (2N11-F004A and F004B).

Notifies the SRO that TC-1 is complete.

If time allows, directs BOP operator to stabilize reactor pressure to <845 psig SRO (at approximately 841 psig with Bypass valves)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 7 Page 21 of 25 Event

Description:

Spurious Reactor scram/ATWS. Insert control rods/SBLC/Lower RWL (Critical Task)

Time Position Applicant's Actions or Behavior If directed, lowers pressure setpoint to <845 psig using the DEHC system as BOP described on the following graphic.

SIMULATOR OPERATOR, at the direction of the Chief Examiner, PROCEEDS to next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-2 Event No.: 8 Page 22 of 25 Event

Description:

2G31-F004, RWCU Isolation valve, fails to close when a SBLC pump is started.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, mfG31_207A & 207B, 2G31-F001 AND F004 FAIL TO CLOSE ON A GROUP 5 SIGNAL, were inserted at the beginning of the scenario.

Injects SBLC (power >5%)

Unlocks and places SBLC pump select switch in Start Sys A or Start Sys B position.

Confirms Squib Valve Ready Lights are extinguished.

Confirms SBLC Loss of Continuity to Squib Valve annunciator is alarmed.

Confirms the selected SBLC pump started.

5 Mins ATC Recognizes 2G31-F004, RWCU Isolation Valve, did NOT close.

Closes 2G31-F004, RWCU Isolation Valve Notifies SRO that SBLC is injecting and 2G31-F004 failed to automatically close and was manually closed.

If RWL lowers to <-35 inches, may also inform SRO that 2G32-F001, RWCU Isolation Valve, failed to automatically close on Group 5 signal and was manually closed.

SIMULATOR OPERATOR, when the following conditions exist:

1. Scram is RESET,

2. RWL is controlled between -60 and -90 inches,

3. Reactor power is <5% RTP.

WITH CHIEF EXAMINERS DIRECTION, the scenario may be terminated.

Page 23 of 25 Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 13-2 Op-Test No.: 2021-301 Examiners: Operators: SRO RO BOP Initiating Conditions: Unit 2 is operating at 92% RTP. 2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Turnover Restore 2C32-R601B to normal alignment IAW 34AB-N21-002-2, Feedwater/Reactor Water Level Control Issues, Section 4.2.

After 2C32-R601B is restored to normal alignment, raise reactor power to 95%

RTP using Recirc flow.

Summary:

Event 1: Normal; The RFPT 2B MA Controller has lost power/repaired & ready to be returned to service.

Event 2: Reactivity; The ATC will raise Reactor power to ~95% RTP.

Event 3: Component; Instrument Air System Prefilter dP Hi - swap Prefilters.

The operator will dispatch a SO locally to determine dP. Report back will require BOP swapping Prefilters to restore normal system flow/pressure. (OE)

Event 4: Recirc Pump 2A will experience high vibration requiring reducing reactor power in an attempt to clear the alarm. Alarm will clear when 2A Recirc speed is reduced to ~ 45% Speed Event 5: Component/TS; The HPCI system will experience an inadvertent start. The operator takes manual control to secure HPCI.

Event 6: Instrument; SRV 2F (LLS) cycles open and close until fuses are removed.

(Critical Task)

Event 7: Major; A Spurious Turbine trip will cause a Reactor scram and subsequent ATWS.

The SRO will direct/ensure the BOP stops injection to lower RWL within 5 minutes of securing both Recirc Pumps. (Critical Task)

Event 8: Component; 2G31-F004, RWCU Isolation valve, fails to automatically close when a SBLC pump is started. Manual actions are required to isolate valve.

3age 24 of 25 Critical Tasks NRC FINAL Facility: E. I Hatch Scenario No.: 13-2 Op-Test No.: 2021-301 Critical Tasks SRV 2F (LLS) valve cycles open/close and then remains open until the fuses are removed which will preclude a failure that will result in challenging Primary Containment integrity if manual action is not taken in a timely manner (prior to exceeding the BIIT curve) or challenge exceeding the Tech Spec cooldown rate limit. (Event 6)

Lowers injection into the RPV to obtain -60 inches to -90 inches within 5 minutes of Recirculation pumps being tripped. (Event 7)

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 6 1. Instrument Air Prefilter dP Hi (Event 3)

2. Recirc Pump 2A High Vibration (Event 4)

3. HPCI inadvertent start (Event 5)

4. SRV 2F cycles open and closed (Event 6)

5. Spurious Reactor scram (Event 7)

6. 2G31-F004 failure (Event 8)

2. Malfunctions After 1-2 1 1. 2G31-F004 failure (Event 8)

EOP Entry

3. Abnormal Events 2-4 3 1. Instrument Air Prefilter dP Hi (Event 3)

2. HPCI inadvertent start (Event 5)

3. SRV 2F cycles open and closed (Event 6)

4. Major Transients 1-2 1 1. Spurious Reactor scram (Event 7)

5. EOPs entered, 1-2 2 1. RCA requiring substantive 2. PC actions

6. EOPs contingencies 0-2 1 1. CP-3 entered with substantive actions

7. Preidentified >2 2 1. SRV 2F cycles open and closed (Event 6)

Critical Tasks 2. Spurious Reactor scram/lower RWL (Event 7)

ILT-13 NRC FINAL Scenario 2 SHIFT TURNOVER Safety Focus UNIT 1 STATUS Plant Conditions: Unit 1 is operating at 100% RTP.

Unit 2 is operating at 92% RTP.

2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, Plant Conditions:

RAS written.

2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Protected Train: EOOS:

Division I Green Orange Division II Yellow Red Scheduled evolutions: Restore 2C32-R601B to normal alignment IAW 34AB-N21-002-2, Feedwater/Reactor Water Level Control Issues, Section 4.2 step 4.2.2.7.

After 2C32-R601B is restored to normal alignment, raise reactor power to 95% RTP using Recirc flow.

Surveillances due this NONE shift:

Inop Equipment: 2D11-K615B, Off gas Post Treatment Radiation monitor has failed Downscale. IAW TS/TRM, I&C has placed 2D11-K615B in the trip condition while maintaining the function of 601-405, Post Treatment O/G Radiation Hi-Hi-Hi/Inop. A Caution Tag is attached to 2D11-K615B switch.

2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Active tagouts: 2D11-K615B, Off gas Post Treatment Radiation monitor Rod Configuration: See RWM Step 27

Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 13-3 Op-Test No.: 2021-301 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at ~5% RTP. 2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Turnover: After turnover restore to Normal Hydrogen Seal Oil System Lineup starting at step 7.3.3.2.5 of 34SO-N42-001-2. Once Hydrogen Seal Oil is returned to Normal lineup, continue with the Startup IAW 34GO-OPS-001-2 at step 4.4.4.

Event Event Event Malf. No.

No. Type* Description Restoration To Normal Hydrogen Seal Oil System Lineup starting at 1 N/A N (BOP) step 7.3.3.2.5 of 34SO-N42-001-2 2 N/A R (ATC) Withdraw Control Rods to increase power.

C (ATC) Control Rod 30-47 double notches and must be restored 3 mfC12_138_30-47 TS (SRO) IAW 34GO-OPS-065-0.

C (BOP) HPCI B005A Low Flow, secure & Standby HPCI B005B cooler 4 mf65021497 started.

TS (SRO) mfG31_207B RWCU line breaks outside of Primary Containment. Must be C (ATC) 5 svoG31071 manually isolated (Critical Task), with failure of outboard isolation TS (SRO) mfG31_46 valve to close.

mfP64_193C C (BOP) 6 Loss of Drywell Chillers, vent the Drywell.

mfP64_193D TS (SRO) 7 mfS11_161 M (ALL) Loss of Offsite Power mfR43_49A One (1) minute after LOSP, ALL EDGs trip and EDG 2A must be 8 mfR43_49B C (ATC) manually reset with pushbutton & manually started with start switch.

mfR43_49C (Critical Task)

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 1 Page 2 of 22 Event

Description:

Restoration To Normal Hydrogen Seal Oil System Lineup starting at step 7.3.3.2.5 of 34SO-N42-001-2.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, IF contacted as SO, report the following:

Seal Oil Vacuum Pump Separator Tank oil level is between the High AND Low Oil Level on 2N42-LG-R306, Separator Tank Sight Glass 10 2N42-F042, Vacuum Tank Inlet Valve, open Mins Oil level in the Vacuum Tank is above the bottom of the lower observation window Seal Oil Vacuum Pump shaft has been manually rotated.

Enters Restoration To Normal Hydrogen Seal Oil System Lineup at step 7.3.3.2.5 Starts 2N42-C001, H2 Seal Oil Vacuum Pump, (2H11-P651).

SIMULATOR OPERATOR, WHEN contacted as SO, 2N42-R302, Vacuum Tank Pressure, is 26.5 in. Hg and steady.

Confirms 2N42-R302, Vacuum Tank Pressure, stabilizes above 26 in. Hg. by contacting SO locally.

BOP Starts 2N42-C003, Recirc H2 Seal Oil Pump.

Starts 2N42-C004, Main H2 Seal Oil Pump.

Secure 2N42-C002, Emergency Seal Oil Pump, as follows:

Holds control switch for ESOP in OFF Pull To Lock position until pump stops as indicated by its extinguished red AND green lights Alarm EMERG SEAL OIL PUMP RUNNING, (651-216) will clear after the SO resets the local panel.

AFTER pump stops, releases control switch.

Confirm its green light is illuminated.

SIMULATOR OPERATOR, when contacted as SO, report the following:

2N42-R300, Seal Oil Pump Disch Press, is 105 psig 2N42-R301, Seal Oil / Machine Gas dP, pressure, is 8 psig above generator gas pressure.

If asked, inform BOP the Emergency Seal Oil Pump shaft has stopped rotating.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 1 Page 3 of 22 Event

Description:

Restoration To Normal Hydrogen Seal Oil System Lineup starting at step 7.3.3.2.5 of 34SO-N42-001-2.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, when contacted as SO, report the following:

DELETE mf65121574, EMERGENCY SEAL OIL PUMP RUNNING (ANNUNCIATOR ON)

REPORT Local alarm, EMERG SEAL OIL PUMP RUNNING, (N43-105) has been reset Confirms the following by contacting SO locally:

2N42-R300, Seal Oil Pump Disch Press, is 100 - 110 psig.

BOP 2N42-R301, Seal Oil / Machine Gas dP, pressure, is being maintained 7

- 9 psig above generator gas pressure.

SIMULATOR OPERATOR, at the Chief Examiners request, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 2 Page 4 of 22 Event

Description:

Withdraw control rods to ~9% power and transfer the Reactor Mode Switch to Run.

Time Position Applicant's Actions or Behavior 12 SRO Directs ATC to continue rod withdrawal (46-23) to approximately 9% power Min Starting at RWM Step 15, withdraws all control rods within step to the withdraw limit IAW 34GO-OPS-065-0 & provided control rod movement sheets.

Initials for control rod withdrawal.

ATC Dates for control rod withdrawal.

SEE EVENT 3 FOR CONTROL ROD DOUBLE NOTCH EVENT Notifies SRO that reactor power is approximately 9%.

Directs:

SRO ATC confirm all APRMs indicate between 7% AND 10%.

BOP confirm operable APRM DOWNSCALE trips are clear.

ATC Reports all APRMs indicate between 7% AND 10%.

Confirms operable APRM DOWNSCALE trips are clear by performing the following at the APRM ODAs at 2H11-P608:

Depress the ETC key.

BOP UNTIL TRIP STATUS option ILLUMINATES.

Depress TRIP STATUS key, THEN confirm APRM FLUX DOWNSCALE ALARM is NOT active.

SRO Directs BOP or ATC to confirm all IRMs are NOT Upscale.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 2 Page 5 of 22 Event

Description:

Withdraw control rods to ~9% power and transfer the Reactor Mode Switch to Run.

Time Position Applicant's Actions or Behavior Confirms no IRMs are UPSCALE by observing:

2H11-P606 upscale lights not illuminated OR BOP/ATC 2H11-P603 upscale lights not illuminated OR 2H11-P603 annunciator 603-221, IRM UPSCALE, NOT illuminated.

Confirms APRM/OPRM Operability:

at least three APRM channels per RPS Trip System are OPERABLE.

AND SRO at least 2 "APRM TWO-OUT-OF-FOUR-VOTER-CHANNELS" per RPS Trip System are OPERABLE.

AND at least 3 OPRM channels per RPS Trip System are OPERABLE.

NOTE: APRM status can be confirmed by the turnover sheet or by directing STA to confirm operability.

SIMULATOR OPERATOR: If contacted for APRM status, inform the SRO all APRMs are operable.

Directs the ATC (or observes) the following annunciators are CLEAR:

SRO MAIN STEAM LINE PRESS A LOW, 603-232, MAIN STEAM LINE PRESS B LOW, 603-233 ATC If directed, reports annunciators 603-232 and 603-233 are clear.

NOTE TO EXAMINER:

DO NOT ALLOW THE Reactor Mode Switch to be placed to the RUN position due to Major Event. PROCEED to next event before Reactor Mode Switch is positioned.

SIMULATOR OPERATOR, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 3 Page 6 of 22 Event

Description:

Control Rod 30-47 double notches and must be restored IAW 34GO-OPS-065-0.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, ENSURE Event Trigger EGC12-9 inserts 10 Min malfunction mfC12_138_30-47, 5 seconds after control rod 30-47 is selected and the Settle light is illuminated.

Withdraws control rod 30-47 to position 12 and determines control rod 30-47 has double notched at 2H11-P603.

Notifies the SRO Enters 34GO-OPS-065-0, Control Rod Movement, Section 7.5 to restore control rod 30-47 and performs the following:

ATC Inserts control rod 30-47 to position 12 Informs SRO & STA of control rod 30-47 double notching and the need to write a Condition Report on control rod 30-47.

Enters Section 7.9 and performs the following:

Informs SRO to notify the Operations Duty Manager Documents double notch in Plant Narrative Log SIMULATOR OPERATOR, If Reactor Engineering is notified for guidance, EITHER reply with what the SRO wants to proceed with or ask for a recommendation of what to do and then agree with them.

Notifies the Operations Duty Manager SRO Enters TS LCO 3.1.6 Condition A to restore control rod within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or declare the control rod inop within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SIMULATOR OPERATOR, PROCEEDS to the next event at the Chief Examiners request.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 4 Page 7 of 22 Event

Description:

HPCI B005A Low Flow, secure & Standby HPCI B005B cooler started.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, At the Chief Examiners direction, NOTIFY ATC as Chemistry, and request Off Gas flow to the Main Stack, WHILE on the phone, ENTERS (RB-4) to activate the following:

10 Min mf65021497, SEC SYSTEM CLR 5A OR 5B FLOW LOW (ANNUNCIATOR ON)

ONCE BOP is addressing the ARP, hang up with ATC.

ALL Alarm, SEC SYSTEM CLR 5A OR 5B FLOW LOW, (650-235), is received.

SRO Directs an operator to enter 34AR-650-235-2.

SIMULATOR OPERATOR, ENSURE Event Trigger EGE41-8 removes B005A low flow alarm when B005A green light is ON & INSERTS EGE41-9 which will insert B005A low flow alarm when B005A red light is ON.

Enters SEC SYSTEM CLR 5A OR 5B FLOW LOW, (650-235);

Places the control switch for 2T41-B005A in the OFF position Places the control switch for 2T41-B005B in the RUN position Dispatches a SO to confirm the return air inlet for 2T41-B005A is NOT obstructed BOP Confirms SEC SYSTEM CLR 5A OR 5B FLOW LOW, (650-235) clears Notifies SRO of the following TS (found in Section 8.0 of ARP);

T3.7.2, ECCS and RCIC Room Coolers- Operating T3.7.3, ECCS and RCIC Room Coolers- Shutdown SIMULATOR OPERATOR, if dispatched to investigate, WAIT 3 minutes and then NOTIFY the control room that 2T41-B005A fan has very little flow coming out and the return air inlet for 2T41-B005A is NOT obstructed. If the crew secures the fan prior to report, then report that B005A was not running when you got there.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 4 Page 8 of 22 Event

Description:

HPCI B005A Low Flow, secure & Standby HPCI B005B cooler started.

Time Position Applicant's Actions or Behavior NOTE: Chief Examiner, if SRO evaluates a different TS call, provide follow-up question on TS determination.

Enters TRM T3.7.2, ECCS and RCIC Room Coolers- Operating, Condition C.1 to restore room cooler to FUNCTIONAL status within 30 days SRO OR Condition C.2 Obtain Corporate Nuclear Engineering and Licensing Department evaluation justifying extended Completion Time within 30 days.

SIMULATOR OPERATOR; At Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 5 Page 9 of 22 Event

Description:

RWCU line will break outside of Primary Containment. Manual actions required to isolate the leak. (Critical Task)

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR: At the direction of the Chief Examiner, Call the 10 BOP and request the value for Off Gas flow. When the BOP is at 2N62-P600, Mins ENTER malfunction mfG31_46, final: 2.5398, ramp: 0.15 (RB-5).

Recognizes the following alarms:

RX BLDG RADIATION HIGH, (601-306) (~1.0 minutes)

TIP MACHINE AREA RADIATION HIGH, (601-323)

ALL approximately 3.0 minutes later indicating ~ 20 mr/hr LEAK DET AMBIENT TEMP HIGH, (601-327) approximately 8.0 minutes NOTE: If 2G31-F001 is closed in a timely manner, the failure of the auto isolation may NOT be recognized.

Responds to RX BLDG RADIATION HIGH, (601-306) annunciator

• Determines radiation levels are approximately 25 mr/hr on the following ARMs:

• RB 158 AREA S-E, 2D21-K601B

• RB 158' area N-E, 2D21-K601C

• RB 158' area N-W, 2D21-K601D

• Decant pump and equipment room area 158', 2D21-K601L

• Determines that a RWCU isolation is required and performs the following:

• Confirms automatic actions by:

ATC

• Tripping RWCU Pump 2B

• Places control switch for 2G31-F004 to close (will NOT Manual or Auto close)

• Places control switch 2G31-F001 to the close (Critical Task)

Critical Task is met if 2G31-F001 is closed prior to any area exceeding the Maximum Safe Operating Levels (215F in 11 minutes).

• Enters 34AB-G31-001-2, RWCU System Isolation.

• Notifies SRO of conductivity monitoring requirements of TRM T3.4.1.

• Notifies SRO of possible SC-Secondary Containment Control Entry.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 5 Page 10 of 22 Event

Description:

RWCU line will break outside of Primary Containment. Manual actions required to isolate the leak. (Critical Task)

Time Position Applicant's Actions or Behavior BOP Responds to RWCU DISCH PRESS HIGH/LOW, 602-409 alarm.

Since RWCU System has isolated, may stop blowdown operations by closing the following valves on 2H11-P602, IAW 34SO-G31-003-2:

2G31-F033 2G31-F034 2G31-F031 Makes a Page Announcement to evacuate the Unit 2 Reactor Building due to high radiation, if NOT performed by the BOP.

Notifies SRO the failure of 2G31-F004 to close.

ATC Suspects a leak has occurred and enters 34AB-T22-001-2, Primary Coolant System Pipe Break Reactor Building.

Informs ATC to monitor level and power.

Dispatches SO to determine RWCU leak location.

Enters SC/RR EOP flowchart and directs the ATC to trip and isolate the RWCU System.

SRO Dispatches SO/Maintenance to determine why 2G31-F004 did NOT manually close.

May request SSS to draft a Danger Tagout for 2G31-F004.

Enters TS for 2G31-F004.

Determines that LCO 3.6.1.3.A.1 and A.2 applies and the RWCU Line must be isolated & de-activated (breaker open) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and verified closed every 31 days.

SRO May review TRM T 3.4.1 RCS Chemistry, TSR 3.4.1.1 for continuous conductivity monitoring and determines that with the Recorder 2G31-R601 Select switch in the Reactor Water position on 2H11-P602, a TRACKING RAS exists.

SIMULATOR OPERATOR, at the direction of the Chief Examiner, PROCEEDS to next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 6 Page 11 of 22 Event

Description:

Loss of Drywell Chillers.

Time Position Applicant's Actions or Behavior At the Chief Examiners direction, SIMULATOR OPERATOR enters (RB-6),

(mfP64_193C, Drywell Chiller Compressor A Safety System Shutdown) and 10 Min ENSURES Event Trigger EGP64-2 enters malfunction mfP64_193D, Drywell Chiller Compressor B Safety System Shutdown, 15 seconds after Drywell Chiller B red light is illuminated.

The following alarms will be received:

650-204, DRYWELL/TORUS RCDR R627 TEMP HIGH 700-105, DRWL CHILLED WTR B006A SAFETY S/D ALL 657-025, MULTIPOINT TEMP RCDR 2T47-R626 TEMP HIGH 654-004, MULTIPOINT TEMP RCDR 2T47-R620 TEMP HIGH 650-214, PANEL 2H11-P654 SYSTEM TROUBLE 650-224, PANEL 2H11-P657 SYSTEM TROUBLE NOTE: With the loss of both DW chillers, the BOP/SS may address 34AB-T47-001-2, Loss of DW Coolers, first.

SRO When venting is required; Directs Operator to vent the drywell.

Enters 34SO-T46-001-2, Standby Gas Treatment System procedure or uses placard at the 2H11-P657/P654 panel to start SBGT 2A or 2B.

Opens 2T46-F001 (A or B) or 2T46-F003 (A or B) for the subsequent train.

BOP Places SBGT Fan (2A or 2B) control switch to RUN.

(Placard)

Receives alarm 2B (or 2A) SBGT Switch Not In Auto (654-076) (or 657-091)

Confirms 2T46-F002 (A or B) OPENS Confirms SBGT Heater red light illuminates.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 6 Page 12 of 22 Event

Description:

Loss of Drywell Chillers.

Time Position Applicant's Actions or Behavior Enters 34SO-T48-002-2, Containment Atmosphere Dilution System or uses placard to vent the Drywell.

Opens 2T48-F334A or 2T48-F334B (both valves may be opened)

Receives alarm DW Vent Exh Bypass Vlv Open (654-002)

BOP or (657-008)

(Placard)

Receives alarm DRWL/Torus N2 M/U 2 Inch Isol Valves Open (654-035) or (657-042)

Opens 2T48-F335A or 2T48-F335B(both valves may be opened)

Opens 2T48-F336A or 2T48-F336B. (both valves may be opened)

Monitors DW pressure NOTE: Caution in 34SO-T48-002-2 states 2 inch valves will be used first prior to the 18 inch valves.

Only if Drywell pressure cannot be controlled with the 2 inch valves, may SRO direct the operator to fast vent the Drywell IAW 34SO-T48-002-2.

Dispatches Maintenance to investigate.

Receives DRYWELL PRESS HIGH, 602-210, alarm.

Confirms that none of the following alarms are illuminated:

SBGT/DRYWELL AND TORUS RADIATION HIGH (601-402)

FISSION PRODUCT PARTIC RADN HIGH/INOP (602-406)

BOP FISSION PRODUCT IODINE RADN HIGH/INOP (602-412)

FISSION PRODUCT GAS HIGH/INOP (602-418)

CONTAINMENT RADIATION HIGH/INOP (602-436)

Opens 2T48-F319, Drywell Vent Vlv (2H11-P602).

Opens 2T48-F320, Drywell Vent Vlv (2H11-P601).

WHEN Drywell pressure is < 0.5 PSIG on 2T48-R607A OR 2T48-R607B, closes 2T48-F320, Drywell Vent Vlv.

Closes 2T48-F319, Drywell Vent Vlv.

SIMULATOR OPERATOR, at the Chief Examiners direction, PROCEEDS to the next event when Drywell pressure is under operator control.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 6 Page 13 of 22 Event

Description:

Loss of Drywell Chillers.

Time Position Applicant's Actions or Behavior Enters 34AB-T47-001-2, Loss of DW Coolers Monitors Drywell pressure and temperature Corrects RWL indications as necessary for high Drywell temperatures per 34AB-B21-002-2, RPV Water Level Corrections Reminds SRO of PC EOP Flow chart entry conditions ATC Monitors for any peak Drywell temperatures per Attachment 1 on SPDS panel and if exceeded for 30 minutes, enters 34GO-OPS-014-2, Fast Reactor Shutdown May request to crosstie Rx Bldg Chilled Water to the Drywell Chilled Water System per section 7.3.2, Cross Connecting The 2P64 and 2P65 Systems of 34SO-P64-001-2.

If Drywell temperature exceeds 150°F, performs the following:

Enters 31EO-EOP-012-2, Primary Containment flow chart SRO Enters TS LCO 3.6.1.5 Drywell Average Air Temperature, Condition A to restore Drywell Average Air Temperature <150°F within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Directs H2/O2 Analyzers placed in service IAW 34SO-P33-001-2 Places H2/O2 Analyzers in service IAW 34SO-P33-001-2 Depresses Channel A and Channel B Reset pushbuttons on 2H11-P700 BOP panel.

Confirms analyzers are running.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 7 Page 14 of 22 Event

Description:

Loss of Offsite Power.

Time Position Applicant's Actions or Behavior 15 SIMULATOR OPERATOR: At the direction of the Chief Examiner, Mins ACTIVATE (RB-7), mfS11_161, Loss of Offsite Power.

ALL Recognizes a Loss Of Offsite Power.

NOTE: With a Loss of Offsite Power, the pertinent operator RC-2 actions are limited to checking ECCS.

Calls for maintenance support in restoring all emergency 4160 VAC buses.

SRO Enters the RC EOP flowchart and directs a RWL band of +3 - +50 inches.

May enter 34AB-R22-003-2, Station Blackout, until the appropriate EDGs are ATC supplying power to emergency buses.

NOTE: The SRO may assign one operator to perform Scram procedure placards RC-1, RC-2 and RC-3.

Assigns the ATC to perform RC-1.

Assigns the BOP operator to perform RC-2 and RC-3.

If time allows assigns TC-1 to be performed.

SRO Enters the RC EOP flow chart, 31EO-EOP-010-2, once reactor water level decreases to 3 inches or reactor pressure increases to 1074 psig.

Directs EOP RC level control band of +3 inches to +50 inches

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 7 Page 15 of 22 Event

Description:

Loss of Offsite Power.

Time Position Applicant's Actions or Behavior Performs RC-1 consisting of:

Manually SCRAMs the Reactor using the SCRAM pushbuttons.

Places Rx Mode Switch in SHUTDOWN.

If Scram blue lights are NOT illuminated, initiates Alternate Rod Insertion (ARI) by rotating the button collars and depressing both ARI pushbuttons at the same time.

Uses the Full Core Display and Rod Worth Minimizer to determine that ATC all control rods are inserted past position 02.

Informs the SRO that all rods are fully inserted.

Inserts IRMs and SRMs.

Places SDV Isol Vlv Switch to ISOL and ensures closed.

Shifts recorders to read IRMS, when required.

Ranges IRMS to bring reading on scale.

Notifies SRO when above actions are complete.

NOTE: With a Loss of Offsite Power, the pertinent operator RC-2 actions are limited to checking ECCS.

Checks ECCS Injection Systems and verifies no initiation signal present.

Starts RCIC for level control by performing the following:

Depresses RCIC Manual Initiation P/B.

Confirms Open 2E51-F046.

BOP Confirms Start of Barom Cndsr Vac Pmp.

Confirms Open 2E51-F045.

Confirms Open 2E51-F013.

Adjusts RCIC flow controller to maintain RWL.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 7 Page 16 of 22 Event

Description:

Loss of Offsite Power.

Time Position Applicant's Actions or Behavior If necessary, starts HPCI for level control by performing the following at 2H11-P602 panel:

If required, depresses High Water Level Reset P/B.

Opens 2E41-F059, Lube Oil Cooling Wtr Vlv Starts 2E41-C002-2, Barometric Condenser Vacuum Pump Opens 2E41-F001, Turbine Steam Supply Vlv BOP Starts 2E41-C002-3, Aux Oil Pump Opens 2E41-F006, Pump Discharge Valve Confirms TCV.

and Confirms/Closes 2E41-F012 at flow > 790 gpm.

Adjusts controller for desired flow and with SRO permission will raise RWL to 32 to 42 inches.

Performs RC-3 consisting of:

Monitor RPV pressure.

Confirm proper operation of pressure control system (LLS and SRVs).

BOP If necessary, allows RPV pressure to exceed 1074 psig then cycles any SRV to initiate LLS.

Maintain RPV pressure between 1074 and 800 psig.

Notify SRO that LLS is the pressure control system.

SIMULATOR OPERATOR, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 8 Page 17 of 22 Event

Description:

One (1) minute after LOSP, ALL EDGs trip and EDG 2A must be manually reset with pushbutton & manually started with start switch.

(Critical Task)

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, ENSURE Event Trigger EGR43-10 INSERTS the following 60 seconds after EDG 2A starts:

mfR43_49A f:1 d:0, mfR43_49B f:1 d:0, mfR43_49C f:1 d:0, &

Inserts Event Trigger EGR43-11 [(Deletes EDG 2A Shutdown (mfR43_49A)

& inserts mfR43_62A f:1 d:0 (Manual start switch required to start EDG 2A)]

10 Reviews DG 2A annunciators and determines a LUBE OIL PRESS LOW, ATC Min (652-111) and EMERGENCY ENGINE SHUTDOWN, (652-129).

• IAW 34AB-R43-001-2, Diesel Generator Recovery, for DG 2A:

• Determines the DG is NOT running.

• Determines the Auto Start System Operative Light is NOT lit.

• Depresses the Shutdown Relay Pushbutton.

• After 100 second time delay, determines DG 2A DID NOT start and places DG 2A start switch to START to energize 4160VAC Emergency Bus 2E. (Critical Task)

(Critical Task is not met if emergency bus 2E is de-energized after 15 minutes due to complicating the degraded emergency power capacity by not restoring emergency core cooling systems requiring a change to the event mitigation strategy when an EAL classification change would be required)

• Notifies SRO that 4160VAC Emergency Bus 2E is energized.

Reviews DG 1B annunciators and determines a LUBE OIL PRESS LOW, ATC (652-211) and EMERGENCY ENGINE SHUTDOWN, (652-229).

IAW 34AB-R43-001-2, Diesel Generator Recovery, for EDG 1B:

Determines the EDG is NOT running Determines the Auto Start System Operative Light is NOT lit Depresses the Shutdown Relay Pushbutton Determines the EDG restarted but tripped again Sends a SO/Maintenance to investigate EDG 1B failure

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 8 Page 18 of 22 Event

Description:

One (1) minute after LOSP, ALL EDGs trip and EDG 2A must be manually reset with pushbutton & manually started with start switch.

(Critical Task)

Time Position Applicant's Actions or Behavior Reviews DG 2C annunciators and determines a LUBE OIL PRESS LOW, ATC (652-311) and EMERGENCY ENGINE SHUTDOWN, (652-329).

IAW 34AB-R43-001-2, Diesel Generator Recovery, for EDG 2C:

Determines the EDG is NOT running Determines the Auto Start System Operative Light is NOT lit ATC Depresses the Shutdown Relay Pushbutton Determines the EDG 2C restarted but tripped again Sends a SO/Maintenance to investigate EDG 2Cfailure SIMULATOR OPERATOR:

When called to investigate the EDGs, as the SO, wait two minutes and report as Maintenance:

IF EDG 2A has NOT been RESTARTED, report that no trip condition exists.

EDG 1B has a break on the oil pump discharge line EDG 2C has a trip signal in its Shutdown circuit.

The following can be performed in any order.

As time allows, directs the SSS to perform the following:

RPS MG Set 2A - restarted RPS Alternate Supply from 2A Essential Cabinet - restarted 2A SSAC local breaker - reclosed Division I Station Service Battery Chargers (may depress pushbuttons on P664 panel)

ATC/BOP Vital AC Alternate supply returned to service Restores RBCCW as follows:

Directs SO to close discharge valve 2P42-F005A, or F005C Places RBCCW pump control switch to off and then to auto Directs SO to slowly open discharge valve 2P42-F005A, or F005C Starts second pump by taking control switch to off and then to run

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-3 Event No.: 8 Page 19 of 22 Event

Description:

One (1) minute after LOSP, ALL EDGs trip and EDG 2A must be manually reset with pushbutton & manually started with start switch.

(Critical Task)

Time Position Applicant's Actions or Behavior The following can be performed in any order. 34AB-R22-003-2, Station Blackout, will not be exited since ONLY one (1) 4160VAC Emergency Bus is energized.

Enters 34AB-R22-003-2, Station Blackout, and performs Attachment 3, 4160VAC 2E Emergency Bus Restoration:

1. Confirms Running/Starts 2P41-C001A, 2A PSW Pump

2. Closes 2P41-F316A, Division I Turbine Building PSW Isolation Valve

3. Since RCIC will control RWL, directs BOP to secure HPCI

4. Trips the following equipment control switches:

2C11-C001A, CRD Pump 2A, panel 2H11-P603 (Norm) 2E21-C001A, Core Spray Pump 2A, panel 2H11-P601 (Norm) 2P64-B006A, Drywell Chiller 2A, panel 2H11-P700 (Off)

5. At panel 2H11-P652, resets the 600VAC Bus 2C Nonessential Load ATC lockout pushbutton

6. Restore Division l Station Service Battery Chargers per the following:

Depresses 2R42-S026, Battery Charger 2A pushbutton, panel 2H11-P664 Depresses 2R42-S027, Battery Charger 2B pushbutton, panel 2H11-P664 Depresses 2R42-S028, Battery Charger 2C pushbutton, panel 2H11-P664

7. Starts 2Z41-C014, Station Service Battery Room 2A Exhaust Fan, panel 2H11-P657.

The scenario will be terminated when EDG 2A is restarted with 125/250 Division 1 Battery Chargers back in service, RWL in band with RCIC OR at Chief Examiners direction.

Page 20 of 22 Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 13-3 Op-Test No.: 2021-301 Examiners: Operators: SRO RO BOP Initiating Conditions: Unit 2 is operating at ~5% RTP. 2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Turnover Hydrogen Seal Oil System is currently aligned with the Emergency Seal Oil pump in service. After turnover restore to Normal Hydrogen Seal Oil System Lineup starting at step 7.3.3.2.5 of 34SO-N42-001-2. Once Hydrogen Seal Oil is returned to Normal lineup, continue with the Startup IAW 34GO-OPS-001-2 at step 4.4.4.

Summary:

Event 1: Normal; The BOP will return Hydrogen Seal Oil to a Normal lineup IAW the system operating procedure.

Event 2: Reactivity; Withdraw control rods to ~9% power.

Event 3: Component/ TS; Control Rod 30-47 double notches and must be restored IAW 34GO-OPS-065-0.

Event 4: Component/TS; The HPCI B005A Cooler experiences a low flow condition requiring it to be secured & Standby HPCI B005B cooler started.

Event 5: Component/TS; A RWCU line will break outside of Primary Containment. The inboard and outboard isolation valves fail to close automatically. The operator will take manual actions to isolate the leaking RWCU line. (Critical Task) The SRO addresses Tech Specs for inoperable Primary Containment Isolation Valves.

Event 6: Component/TS; Loss of DW Chillers requiring the Drywell to be vented. The SRO addresses Tech Specs for Drywell Average Air Temperature >150°F.

Event 7: Major; The plant will experience a Loss of Offsite Power.

Event 8: Component; One (1) minute after LOSP, ALL EDGs trip and EDG 2A must be manually reset with pushbutton & manually started with start switch. (Critical Task)

Page 21 of 22 Critical Tasks Facility: E. I Hatch NRC FINAL Scenario No.: 13-3 Op-Test No.: 2021-301 Critical Tasks

• Closes 2G31-F001 prior to exceeding Maximum Safe Secondary Containment Control EOP parameters (Temperatures, Radiation levels or SC water levels). (Event 5)

• Manually reset EDG 2A emergency shutdown and start switch within 15 minutes based on forcing the plant into a higher level of EAL classification when not required. (Critical Task is not met if emergency bus 2E is de-energized after 15 minutes due to complicating the degraded emergency power capacity by not restoring emergency core cooling systems requiring a change to the event mitigation strategy when an EAL classification change would be required) (Event 8)

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 6 1. Control rod double notch (Event 3)

2. HPCI B005A Low Flow (Event 4)

3. RWCU line break (Event 5)

4. Loss of DW Chillers (Event 6)

5. Loss of Offsite Power (Event 7)

6. All EDGs trip after start (Event 8)

2. Malfunctions After 1-2 1 1. All EDGs trip after start (Event 8)

EOP Entry

3. Abnormal Events 2-4 2 1. RWCU line break (Event 5)

2. Loss of DW Chillers (Event 6)

4. Major Transients 1-2 1 1. Loss of Offsite Power (Event 7)

5. EOPs entered, 1-2 2 1. RC (Non-ATWS) requiring substantive 2. PC actions

6. EOPs contingencies 0-2 1 1. 34AB-R22-003-2, Station Blackout entered with substantive actions

7. Preidentified >2 2 1. RWCU line break (Event 5)

Critical Tasks 2. All EDGs trip after start (Event 8)

ILT-13 NRC FINAL Scenario 3 SHIFT TURNOVER Safety Focus UNIT 1 STATUS Plant Conditions: Unit 1 is operating at 100% power.

UNIT 2 STATUS Unit 2 is operating at ~5% RTP.

2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written.

2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Plant Conditions:

RWCU is in service rejecting to the Main Condenser.

RFPT 2A is in service.

CRD pump 2A is in service.

APRM Gains have been adjusted.

Protected Train: EOOS:

Division I Green Orange Division II Yellow Red Scheduled evolutions: Hydrogen Seal Oil System is currently aligned with the Emergency Seal Oil pump in service. After turnover restore to Normal Hydrogen Seal Oil System Lineup starting at step 7.3.3.2.5 of 34SO-N42-001-2.

Once Hydrogen Seal Oil is returned to Normal lineup, continue with the Startup IAW 34GO-OPS-001-2 at step 4.4.4.

Surveillances due this NONE shift:

Inop Equipment: 2D11-K615B, Off gas Post Treatment Radiation monitor has failed Downscale. IAW TS/TRM, I&C has placed 2D11-K615B in the trip condition while maintaining the function of 601-405, Post Treatment O/G Radiation Hi-Hi-Hi/Inop. A Caution Tag is attached to 2D11-K615B switch.

2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Active tagouts: 2D11-K615B, Off gas Post Treatment Radiation monitor Rod Configuration: See RWM Step 15

Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 13-4 Op-Test No.: 2021-301 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at 97% RTP. 2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Turnover: IAW 34SO-T41-006-2, Refueling Floor Ventilation System, section 4.3.3, remove RF Vent Filter, 2T41-D007, From Service. After RF Vent Filter, 2T41-D007, is removed from service, raise reactor power to 100% RTP using Recirc.

Event Event Event Malf. No.

No. Type* Description IAW 34SO-T41-006-2, Refueling Floor Ventilation System, section 1 N/A N (BOP) 4.3.3, remove RF Vent Filter, 2T41-D007, From Service.

mf60131136 C (BOP) 2B Loop of Core Spray experiences high discharge pressure (valve 2

aoE21R600B TS (SRO) leakage). Perform ARP & restore.

CRD 2A pump experiences an Overload condition requiring 3 mf60311325 C (ATC) swapping to standby pump.

I (BOP) 4 mfB21_131 ADS Inadvertent initiation/Inhibit used. (Critical Task)

TS (SRO)

Recirc Pump A & B runback to Speed Limiter #1 resulting in the mfB31_268A 5 mfB31_268B R (ATC) plant operating in the Region of Potential Instabilities of the Power-to-Flow Map.

mfC12_22_10-35 While exiting the Immediate Exit Region of the Power to Flow Map, 6 mfC12_22_34-19 C (ATC) Control Rod 34-11/34-19 sticks, requiring Drive Water dP to be mfC11_280 increased to insert Control Rod 34-11/34-19.(Critical Task-see below)

Unisolable Steam leak in Steam Chase. Team should attempt to mfB21_224 isolate leak source given a report of loud noise in steam tunnel. One 7 M (ALL) mfB21_225 path of MSIVs will not close with CS. (Critical Task) RCIC isolates.

HPCI flow controller output fails low requiring manual increase to 8 mfE41_106 C (BOP) obtain injection.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Event 6: Administered post-scenario Critical Task created (affects Day 2 Crew 1):

- Critical Task is met if a manual reactor scram is not inserted during crew mitigation of a stuck control rod (reference ES-D-2, page 12)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 1 Page 2 of 24 Event

Description:

IAW 34SO-T41-006-2, Refueling Floor Ventilation System, section 4.3.3, remove RF Vent Filter, 2T41-D007, From Service.

Time Position Applicant's Actions or Behavior Directs the BOP to remove RF Vent Filter, 2T41-D007, From Service IAW 10 Min SRO 34SO-T41-006-2, Refueling Floor Ventilation System, section 4.3.3.

The following switches are located on the 2H11-P657 panel.

Confirms 2T41-C005A, Refuel Flr Vent Exh Fan, is RUNNING Places 2T41-C005A, Refuel Flr Vent Exh Fan, control switch, in OFF Checks 2T41-C005B, Refuel Flr Vent Exh Fan, STARTS BOP Places 2T41-C005B, Refuel Flr Vent Exh Fan, control switch, in RUN Dispatches a SO to adjust 2T41-R032 and 2T41-R037, Flow Controller, to obtain approximately 15 KCFM through 2T41-C002A or 2T41-C002B, Refueling Floor Supply Fan AND 2T41-C005B, Refueling Floor Exhaust Fan.

SIMULATOR OPERATOR, when dispatched, DEPRESS RB-1, which modifies RF Supply flow indication, aoT41-R618P4 f:16 r:1000, THEN waits approximately 2 minutes and reports to the BOP, as a SO, that you have adjusted 2T41-R032 and 2T41-R037, to approximately 15 KCFM.

Checks 0.25 inches water negative pressure on the Refueling Floor as indicated on2T46-R604A AND 2T46-R604B, Sec Cnmt Diff Press A&B, BOP on 2H11-P700.

Closes 2T41-F041A, Refuel Flr Vent Filter D007 Inlet Damper.

Notifies SRO Vent Filter D007 is out of service.

SIMULATOR OPERATOR - Continue with the next event at the Chief Examiners request.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 2 Page 3 of 24 Event

Description:

2B Loop of Core Spray experiences high discharge pressure (valve leakage).

When ARP is performed, system pressure is restored.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR; at the Chief Examiners direction, 10 ENTER (RB-2):

Mins mf60111061, Core Spray B Disch Pipe Press High (ON) aoE21-R600B to 465 psig Enters ARP 34AR-601-125-2:

Confirm validity of alarm using Disch Press indicator, 2E21-R600B

(~465 psig)

Confirm the following valves are CLOSED 2E21-F037B, Testable Check Bypass Vlv.

BOP 2E21-F005B, Inbd Discharge Vlv.

Closes 2E21-F004B, Outbd Discharge Vlv.

Opens 2E21-F005B Closes 2E21-F005B Opens 2E21-F004B Reviews TS 3.5.1, ECCS and Enters Condition A since 2E21-F004B is closed.

SRO TS 3.5.1.A requires the ECCS pump to restored to operable status in 7 days.

NOTE: If addressed, 2E21-F004B is NOT a PCIV and TS 3.6.1 is for PCIVs.

SIMULATOR OPERATOR; ENSURE Event Trigger EGE21-6 activates when 2E21-F015B is placed to open position. This will clear CS B DISCH PRESS HIGH alarm & return 2E21-R600B to normal.

IAW ARP 601-125, may perform the following:

Slightly opens 2E21-F015B to lower CS Discharge pressure Confirms alarm 601-125 clears When pressure is approximately 100 psig, closes 2E21-F015B.

BOP If CORE SPRAY B JOCKEY PUMP SYS WATER LEVEL LOW, 601-114, is received, directs a SO to vent Loop B of Core Spray IAW 34SV-SUV-017-2.

Monitors Core Spray B Loop pressure for subsequent increases.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 2 Page 4 of 24 Event

Description:

2B Loop of Core Spray experiences high discharge pressure (valve leakage).

When ARP is performed, system pressure is restored.

Time Position Applicant's Actions or Behavior NOTE: If pressure is NOT relieved, then a follow-up question on PCIV leakage TS 3.6.1.3.D may be appropriate.

NOTE: If pressure IS relieved on Core Spray Loop B, and pressure is NOT monitored, then a follow-up question on a high pressure condition of the inner system piping may be appropriate.

SIMULATOR OPERATOR, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 3 Page 5 of 24 Event

Description:

CRD 2A pump experiences an Overload condition requiring swapping to standby pump.

Time Position Applicant's Actions or Behavior At the Chief Examiners direction, SIMULATOR OPERATOR ENTERS 10 Min (RB-3) mf60311325, CRD Pump A Overload, alarm.

Receives CRD PUMP A OVERLOAD, 603-137, alarm.

Determines that the CRD 2A pump is still in service.

Dispatches SO locally to Bus 2R22-S005, Frame 8, to check the ATC following:

Overcurrent relay targets tripped Amperage reading on all three phases SIMULATOR OPERATOR, AFTER 2 minutes from being dispatched, report to the SRO/ATC, as a SO, that one (1) Overcurrent relay target is tripped AND the HIGHEST Amperage reading is 45 amperes.

Dispatches Maintenance to investigate CRD pump 2A overload condition.

SRO After SO report, directs ATC to shift CRD pumps IAW 34SO-C11-005-2.

NOTE: The ATC may direct the CRD pump room coolers to be swapped or may elect to leave the 2T41-B001B cooler in service. Both are acceptable.

IAW 34SO-C11-005-2, 4.1.3, Shifting CRD Pumps, performs the following:

Dispatches SO to confirm cooling water valves listed in step 4.1.3.1.b are open.

Confirms a CRD Room Cooler is in operation per 34SO-T41-002-2, CRD Pump Room Ventilation System by performing the following:

Confirms 2T41-B001B is in Run (may direct BOP to confirm)

ATC OR Places control switch for 2T41-B001A, in Run (P657) (may direct BOP to perform).

Places 2T41-B001B, CRD Pump Room Cooler, in Off (P654)

(may direct BOP to perform).

Places 2T41-B001B, CRD Pump Room Cooler, in Auto (P654)

(may direct BOP to perform).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 3 Page 6 of 24 Event

Description:

CRD 2A pump experiences an Overload condition requiring swapping to standby pump.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, when dispatched to vent the CRD pump 2B, WAIT 2 minutes and NOTIFY the ATC the CRD pump 2B has been vented and the vent valves are closed.

Also ENSURE Event Trigger EGC11-3 DELETES CRD 2A Overload alarm when CRD pump 2A is secured and INSERTS EGC11-7 which INSERTS CRD 2A Overload alarm if CRD pump 2A is re-started.

Dispatches SO to confirm open the following valves and to vent the 2B CRD pump:

2C11-F118B, CRD Pump 2B Suction Valve 2C11-F114B, Suction Filter 2B Outlet Isolation 2C11-F115B, Suction Filter 2B Inlet Isolation Starts 2C11-C001B, CRD Pump 2B, at P603.

ATC Confirms flow control valve responds properly by controlling system flow between 30 gpm to 50 gpm.

Stops 2C11-C001A, CRD Pump 2A, at P603.

Dispatches SO to confirm closed 2C11-F117, CRD Suction Crosstie.

Confirms system parameters are in their normal ranges per NOTE in System Startup section of 34SO-C11-005-2.

SIMULATOR OPERATOR enters the next event at the Chief Examiners request.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 4 Page 7 of 24 Event

Description:

ADS Inadvertent initiation/Inhibit used. (Critical Task)

Time Position Applicant's Actions or Behavior At the Chief Examiners direction, SIMULATOR OPERATOR, phone the ATC 10 and inform that CRD pump 2B is operating properly, THEN enters (RB-4)

Mins malfunction mfB21_131 Inadvertent ADS Initiation.

Identifies ADS is about to initiate and observe the following alarms:

ALL AUTO BLOW DOWN TIMERS INITIATED, (602-306)

AUTO BLOW DOWN RELAYS ENERGIZED, (602-318)

BOP Acknowledges the alarms and reports them to the SRO.

May observe the ADS timer on SPDS begin counting down.

Directs ATC to enter the following:

SRO AUTO BLOW DOWN TIMERS INITIATED, (602-306)

AUTO BLOW DOWN RELAYS ENERGIZED, (602-318) 34AB-E10-001-2, Inadvertent Initiation of ECCS/RCIC May direct ATC to inhibit ADS NOTE: The SRO may direct the ATC to inhibit ADS prior to pulling the 34AB-E10-001-2, Inadvertent Initiation of ECCS/RCIC.

Enters 34AB-E10-001-2 Monitors plant parameters to determine extent of ECCS/RCIC actuations.

BOP Inhibits ADS using 2B21C-S7A & S7B, ADS Auto Logic Inhibit Switches, on 2H11-P602.

(Critical Task)

(Critical task is met when BOTH ADS Inhibit switches are in INHIBIT prior to the ADS valves opening.)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 4 Page 8 of 24 Event

Description:

ADS Inadvertent initiation/Inhibit used. (Critical Task)

Time Position Applicant's Actions or Behavior If ADS Timer on SPDS is approaching Zero (0), the ATC may depress BOP the ADS Logic Timer pushbuttons prior to inhibiting ADS.

SRO Dispatches Maintenance to determine problem with ADS logic.

SIMULATOR OPERATOR, when dispatched using Time Compression, REPORT to the SRO that the ADS Instrumentation logic for Trip System A has failed. ALL of the functional units of ADS Trip System A have failed.

NOTE: The SRO enters TS 3.3.5.1. F & G and declare all ADS valves inoperable if the ADS instrumentation is NOT repaired in one hour.

Without more information on failed instruments, a follow-up question to the SRO may be required to determine this TS call.

Enters TS 3.5.1.F and declares ALL ADS valves inop immediately.

With all ADS valves inop, be in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and

<150 psig RPV press in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Once information of instrument failures is made, enters TS 3.3.5.1 ADS Instrumentation, Condition F & G, SRO Required Action F.1 - declares Automatic Depressurization System (ADS) valves inoperable 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of ADS initiation capability in both trip systems.

Required Action F.2 - places Channel in trip 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> from discovery of inoperable channel concurrent with HPCI or Reactor Core Isolation Cooling (RCIC) inoperable AND 8 days SIMULATOR OPERATOR, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 5 Page 9 of 24 Event

Description:

Recirc Pump A & B runback to Speed Limiter #1 resulting in the plant operating in the Region of Potential Instabilities of the Power-to-Flow Map. Insert control rods to exit the RPI.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR; At Chief Examiners direction, press (RB-5) to 5 Mins ACTIVATE mfB31_268A & mfB31_268B, Recirc Pump A & B Runback To #1 Limiter (22%).

Receives the following alarms:

ALL RECIRC A FLOW LIMIT, 602-134 RECIRC B FLOW LIMIT, 602-234 Confirms Recirc pump A & B speed has runback using:

2B31-R661A, Recirc pump % Speed Demand meter/Recirc pump %

speed meter, or 2B31-R660A, Recirc A RPM, panel 2H11-P602 2B31-R661B, Recirc pump % Speed Demand meter/Recirc pump %

speed meter, or 2B31-R660B, Recirc B RPM, panel 2H11-P602 Determine which speed limiter is enforcing ATC Check APRM, and process computer to determine IF a 15% power change has occurred.

IF a 15% power change has occurred, THEN take actions per 34GO-OPS-005-2, Power Changes.

IF the OPRM System is inop, enter 34AB-C51-001-2.

IF the Region of Potential Instabilities is entered, take actions to exit per Shift Supervisors direction Notifies Plant Management, Load Dispatcher, and Engineering of Recirc Pump SRO A & B Runback to #1 Speed Limiter.

SIMULATOR OPERATOR; When the crew determines the plant is in the Region Of Potential Instabilities of the Power to Flow map, WAIT FIVE (5) MINUTES AND IF THE CREW HAS NOT STARTED INSERTING CONTROL RODS, THEN DEPRESS RB-9, mfC51_253 f:10 r:10, Region Independent LPRM Oscillations.

Oscillations will start building and exceed 5% peak-to-peak.

Determines that the plant is in the Region Of Potential Instabilities of the ATC Power to Flow map.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 5 Page 10 of 24 Event

Description:

Recirc Pump A & B runback to Speed Limiter #1 resulting in the plant operating in the Region of Potential Instabilities of the Power-to-Flow Map. Insert control rods to exit the RPI.

Time Position Applicant's Actions or Behavior NOTE: Heater Trouble Alarm (650-135) may alarm due to plant conditions.

NOTE: IF the crew makes the decision to SCRAM the Reactor, at the Chief Examiners direction, PROCEED to the MAJOR EVENT.

EXAMINER NOTE: Log time when Region of Potential Instabilities has been ENTERED. Time: _________

NOTE: IAW 34GO-OPS-005-2, Power Changes, Limitation 5.2.3.1:

If the Region Of Potential Instabilities (RPI) is entered, IMMEDIATELY initiate actions to exit the (RPI), to return operation to the Analyzed Region of the Power/Flow Map outside of the RPI.

If the Immediate Exit Region is entered, within 5 minutes the operators are to initiate control rod movement to return to the Analyzed Region.

Operation within the Analyzed Region AND outside of the RPI must be restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Directs ATC operator to insert rods to exit the RPI and Immediate Exit Region SRO to return operation to the Analyzed Region of the Power/Flow Map.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 5 Page 11 of 24 Event

Description:

Recirc Pump A & B runback to Speed Limiter #1 resulting in the plant operating in the Region of Potential Instabilities of the Power-to-Flow Map. Insert control rods to exit the RPI.

Time Position Applicant's Actions or Behavior NOTE: RBM Downscale alarm may alarm during this movement due to the significant rod worth of these rods. The RBM Downscale and Rod Out Block alarms may be flagged.

SIMULATOR OPERATOR; When the crew starts inserting Control rods, DELETE RB-9, mfC51_253 f:4 r:10, Region Independent LPRM Oscillations, IF it was inserted previously.

NOTE: If control rods are inserted using the Rx Management plan, the 1st control rod to be inserted is Step 24 42-35.

NOTE: If control rods are inserted using REVERSE order, then the 1st control rod to be inserted is Step 38 control rod 26-27.

Either is acceptable.

Inserts control rods per 34GO-OPS-065-0, Control Rod Movement:

Inserts control rods per the Reactivity Briefing Sheet and rod pull sheets.

Selects first Rod to be inserted Group 24 42-35 or Group 38 26-27.

Places Control Rod movement switch to the IN position.

Verifies Rod moves using Rod display information and Rx and Generator power decreasing.

ATC Releases Rod movement switch so that the control rod stops 1 position before the insert limit, unless the insert limit is 00.

Initials Rod movement Sheet.

Verifier, if available, Initials Rod movement sheet.

GO TO EVENT 6 FOR STUCK CONTROL ROD SIMULATOR OPERATOR, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 6 Page 12 of 24 Event

Description:

While exiting the Immediate Exit Region of the Power to Flow Map, Control Rod 34-11/34-19 sticks, requiring Drive Water dP to be increased to insert Control Rod 34-11/34-19.

Time Position Applicant's Actions or Behavior NOTE: Malfunctions mfC12_22_34-11 & 34-19, Stuck Control Rod &

mfC11_280, Stuck Control Rod (Malfunction 22) Unsticks At High dP, were both inserted at the beginning of the scenario.

NOTE: RBM Downscale alarm may alarm during this movement due to the significant rod worth of these rods. The RBM Downscale and Rod Out Block alarms may be flagged.

Continues inserting control rods per 34GO-OPS-065-0, Control Rod Movement:

ATC Selects next Rod to be inserted Group 25/36 34-11/34-19.

Places Control Rod movement switch to the IN position Notifies the SRO that Control Rod 10-35/34-19 will not insert and enters 34AB-C11-003-2, Inability To Move A Control Rod, Control Rod Immovable flowchart and performs the following:

Confirms Control Rod 34-11/34-19 is NOT at position 00 Confirms drive water dP is less than 600 psid ATC Momentarily closes 2C11-F003, Drive water press control valve, to increase drive water dP by 50 psid Places Control Rod movement switch to the IN position and determines Control Rod 34-11/34-19 does NOT move using Rod display information.

Confirms drive water dP is less than 600 psid Momentarily closes 2C11-F003, Drive water press control valve, to increase drive water dP by 50 psid Places Control Rod movement switch to the IN position and determines ATC Control Rod 34-11/34-19 does move using Rod display information.

Momentarily opens 2C11-F003, Drive water press control valve, to return drive water dP to approximately 230 psid.

Initials Rod movement Sheet.

Verifier, if available, Initials Rod movement sheet.

Event 6: Administered post-scenario Critical Task created (affects Day 2 Crew 1):

- Critical Task is met if a manual reactor scram is not inserted during crew mitigation of a stuck control rod Safety Significance- unnecessary RPS actuation Initiating Cue- inappropriate interpretation of APRM alarm Measurable Performance Std- invoke a manual reactor scram as opposed to addressing stuck rod Performance Feedback- stuck rod mitigation strategy was event success path

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 6 Page 13 of 24 Event

Description:

While exiting the Immediate Exit Region of the Power to Flow Map, Control Rod 34-11/34-19 sticks, requiring Drive Water dP to be increased to insert Control Rod 34-11/34-19.

Time Position Applicant's Actions or Behavior Exits 34AB-C11-003-2 and notifies SRO that a Condition Report needs to be generated for Control Rod 10-35/34-19.

Continues inserting control rods to exit the RPI Verifies Rod moves using Rod display information and Rx and Generator power decreasing.

ATC Releases Rod movement switch so that the control rod stops 1 position before the insert limit, unless the insert limit is 00.

Initials Rod movement Sheet.

Verifier, if available, Initials Rod movement sheet.

Notifies the SRO when they are out of the RPI.

If required, adjust 2C11-F003 to get 220 - 280 psid drive water dp EXAMINER NOTE:

Excerpt from 34AB-C51-001-2, Entry Into The Region Of Potential Instabilities (RPI) Or Reactor Operations With Inoperable OPRM System 4.1 IF at any time while operating in the Region of Potential Instabilities (RPI), any of the following conditions exist, enter 34AB-C71-001-2, Scram Procedure, AND SCRAM the Reactor:

o Any APRM is observed to have bandwidth oscillations > 5% peak to peak oscillations AND INCREASING.

OR o Two OR more LPRMS are observed to have bandwidth oscillations

> 5% peak to peak oscillations AND INCREASING.

OR o Any APRM upscale OR downscale alarm cycling on and off with a period of <3 seconds on the ODAs OR two OR more LPRM upscale OR downscale alarms on the ODAs BARGRAPH screen are cycling on and off with a period of <3 seconds.

EXAMINER NOTE: Log time when Region of Potential Instabilities has been EXITED (~40% RTP). Time: _________

SIMULATOR OPERATOR; PROCEEDS to the next Event after Chief Examiner approval.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 7 Page 14 of 24 Event

Description:

Unisolable Steam leak in Steam Chase (Reactor Building). (Critical Task)

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR; at Chief Examiners direction, ENTER (RB-7) 15 Mins mfB21_224, Main Steam Line Leak Between MSIVS Outside Containment &

mfB21_225, B21-F022A Fails to Completely Close On Isolation Signal.

Responds to annunciator, 601-321, LEAK DET DIFF TEMP HIGH (~85 secs)

Responds to annunciator, 601-327, LEAK DET AMBIENT TEMP HIGH

(~125 secs)

Responds to annunciator, ALL 603-208, GROUP 1 SYSTEM A TRIP, (~160 secs)

Responds to annunciator, 603-221, STEAM TUNNEL TEMPERATURE A HIGH, (~160 secs)

Responds to annunciator, 603-209, GROUP 1 SYSTEM B TRIP, (~180 secs)

Responds to annunciator, 603-222, STEAM TUNNEL TEMPERATURE B HIGH, (~180 secs)

Orders BOP to evaluate leak detection alarms on 2H11-P601.

SRO Orders BOP to evacuate the Reactor Building Addresses 2G31-R604 OR 2G31-R608 on 2H11-P614.

Identifies point 119, Main Steam Line Tunnel (2B21-N014), on R608 is BOP

~225°F.

Reports temperatures to the SRO.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 7 Page 15 of 24 Event

Description:

Unisolable Steam leak in Steam Chase (Reactor Building). (Critical Task)

Time Position Applicant's Actions or Behavior Enters the SC flow chart.

Progresses down each path.

Proceeds down the SC/T path, directing:

All available area coolers are operated.

SRO Operate the Refueling Floor ventilation.

Operate the Reactor Building ventilation.

Isolate all systems discharging into the area except those needed for ACC, shutdown the reactor, suppress a fire, maintain primary containment.

Excerpt from 34AB-T22-003-2, Secondary Containment Control, Attachment 9 MAX MAX SECONDARY CONTAINMENT TEMP RDG RDG RDG NORMAL SAFE NORM on 2H11-P614, 2G31-R604 1 2 3

°F °F TORUS ROOM AREA 115 Torus vent air DIFF 42 98 9 (2E51-N027B/2E51-N026B) 116 Torus vent air DIFF 42 98 9 (2E51-N027D/2E51-N026D)

MAX MAX SECONDARY CONTAINMENT TEMP RDG RDG RDG NORMAL SAFE NORM on 2H11-P614, 2G31-R608 1 2 3

°F °F TORUS ROOM AREA 117 Torus vent air DIFF 42 98 8 (2E51-N027A/2E51-N026A) 118 Torus vent air DIFF 42 98 9 (2E51-N027C/2E51-N026C)

MAIN STEAM LINE TUNNEL AREA 119 Main Steam Tunnel (2B21-N014) 192.5 310 132 120 Main Steam Tunnel DIFF 70 150 24 (2B21-N016B/2B21-N016A)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 7 Page 16 of 24 Event

Description:

Unisolable Steam leak in Steam Chase (Reactor Building). (Critical Task)

Time Position Applicant's Actions or Behavior Orders the reactor shutdown prior to any area exceeding Max Safe Operating Temperatures or Delta Temps since a primary system (Main SRO Steam) is discharging into Secondary Containment. (May direct this prior to Max Safe received).

Assigns the ATC to perform RC-1.

Assigns the BOP operator to perform RC-2 and RC-3.

SRO Enters 31EO-EOP-010-2, RC EOP flow chart if RWL decreases below 3 inches.

Directs RWL Band of 3 to 50 inches.

SIMULATOR OPERATOR, Ensures Event Trigger EGC71-5 DELETES malfunctions mfC12_22_34-11 & mfC12_22_34-19, Stuck Control Rods, when the reactor mode switch is placed to SHUTDOWN.

Performs RC-1 consisting of:

Inserts a manual scram. Critical Task (Critical Task is met when a manual scram is inserted prior to exceeding a Max Safe Operating temperature. Approximately 7 minutes to exceed Max Safe).

Places the mode switch to SHUTDOWN.

If NOT tripped, places the Recirc pumps at minimum speed.

ATC Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display.

Notifies SRO of rod position check.

Inserts SRMs and IRMs.

Places SDV isolation valve switch to "isolate" & confirms closed.

Shifts recorders to read IRMS, when required.

Ranges IRMS to bring reading on scale.

Notifies the SRO when the above actions are complete.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 7 Page 17 of 24 Event

Description:

Unisolable Steam leak in Steam Chase (Reactor Building). (Critical Task)

Time Position Applicant's Actions or Behavior Performs RC-2 actions consisting of:

Confirms proper Level Control response:

Checks ECCS Injection Systems (will NOT be in service if RWL >-35 inches).

Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.

If Set down does NOT auto function, manually reduces FW Master Controller setpoint to approximately 9 inches.

BOP When feed flow is less than the capacity of the S/U level control valve

( 1.5 mlbm/hr), then:

Ensures /Opens 2N21-F125.

Ensures /places 2C32-R619, FW S/U level control valve controller, in Auto, set at approximately 9 inches.

Closes 2N21-F110.

If RFPTs are no longer available, will transition to HPCI to control RWL.

SIMULATOR OPERATOR, Event Trigger EGC71-5 INSERTS mfE51_113A

& mfE51_113B, RCIC Auto Isolation after one (1) minute.

The following ARPs are received:

RCIC TURBINE TRIP, (602-301).

ATC RCIC ISOLATION SIGNAL LOGIC A, (602-307).

RCIC ISOLATION SIGNAL LOGIC B, (602-313).

IAW 602-307 & 602-313 confirms the following:

Confirms CLOSED 2E51-F008, Steam Supply Line Isol Vlv.

ATC Confirms CLOSED 2E51-F007, Steam Supply Isol Vlv.

Informs SRO RCIC has isolated

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 7 Page 18 of 24 Event

Description:

Unisolable Steam leak in Steam Chase (Reactor Building). (Critical Task)

Time Position Applicant's Actions or Behavior Performs RC-3 consisting of:

Monitoring RPV pressure.

Confirms proper operation of pressure control system (TBV, LLS, etc.), at 2H11-P650 panel, by confirming TBVs are responding to control reactor pressure at the desired pressure setpoint.

Maintains RPV pressure between 1074 and 800 psig until a different band is directed.

Notifies SRO of pressure control system operation.

Verifies the inboard MSIVs have failed to close (2B21-F022A-D) and places control switches to close.

BOP Identifies 2B21-F022A has failed to fully close.

Verifies the outboard MSIVs have failed to close (2B21-F028A-D) and places control switches to close.

Verifies the remaining 4 Group 1 valves have failed to close and places the control switches for 2B31-F019, 2B31-F020, 2B21-F016 and 2B21-F019 to the close position (P602 and P601 panel).

Reports to the SRO the Group 1 signal failure and 2B21-F022A failing to fully close (double indication). All other Group 1 valves are closed.

If directed to lower the driving head of the leak, opens SRVs to maintain RPV pressure in band.

May order a lower Reactor pressure band to reduce the driving head IAW RC/P Path of the RC (Non-ATWS) flowchart.

SRO May direct an operator to perform Rx Power, Level, and Pressure control, so that the other operator can address Secondary Containment parameters.

SRO May order a lower Reactor pressure band to reduce the driving head.

Provides periodic updates on temperature readings and delta temp readings to the SRO.

ATC Reports R604 point 115 and R608 point 116 are NOT above Max Safe.

(WILL NOT EXCEED 2ND MAX SAFE)

Reports R608 point 120 is above Max Safe.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 7 Page 19 of 24 Event

Description:

Unisolable Steam leak in Steam Chase (Reactor Building). (Critical Task)

Time Position Applicant's Actions or Behavior Provides periodic updates on temperature readings and delta temp readings to ATC the SRO.

Enters Primary Containment Control (PC) EOP flow chart.

If required, (Torus temperature >95°F) IAW PC/T path directs Torus SRO Cooling to be placed into service. If Torus temperature is <100°F only one loop of RHR will be placed in Torus Cooling. If Torus temperature is

>100°F both loops of RHR will be placed in Torus Cooling.

NOTE: The operator may place torus cooling in service by using the Placard that's available or using the appropriate section of the procedure.

These steps assume the Placard is used. The A and/or B loop of RHR may be used depending on Torus temperature. The following steps are written assuming "B" loop and "B" pump is used. If/When "A" loop is used, substitute "A" for "B" for valves and if "B" pump is NOT used substitute "A", "C", or "D" for "B" pump.

Enters 34SO-E11-010-2, Residual Heat Removal, AND places RHRSW in service IAW Placard; Overrides 2E11-F068B Low Discharge Pressure Interlock.

Positions 2E11-F068B to 45% OPEN.

ATC Starts RHRSW pump B.

Places 2E11-F068B Low Discharge Pressure Interlock switch to normal position.

Positions 2E11-F068B to obtain < 4400 gpm AND < 450 psig.

IF desired to start a SECOND RHRSW pump, Throttles 2E11-F068B to achieve max flow rate (NOT to exceed 4400 GPM).

ATC Opens 2E11-F068B an additional 5%.

Starts second RHRSW Pump.

Positions 2E11-F068B to obtain < 8800 gpm AND < 450 psig.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 7 Page 20 of 24 Event

Description:

Unisolable Steam leak in Steam Chase (Reactor Building). (Critical Task)

Time Position Applicant's Actions or Behavior IAW 34SO-E11-010-2, Placard; IF RWL <2/3 core height, (-193 inches), PLACE the Cnmt Spray Vlv.

Cntl 2/3 Core Ht Permis keylock in the MANUAL OVERRD. (NOT needed)

IF required by EOPs AND LOCA signal present, PLACE Cnmt Spray ATC Vlv. Cntl switch in the MANUAL position. (NOT needed)

Opens 2E11-F048A (2E11-F048B).

IF SPC is NOT required per the EOPs, CLOSE 2E11-F047A (2E11-F047B). (NOT needed)

Opens 2E11-F003A (2E11-F003B).

IF power is being provided by EDG, CHECK EDG loading prior to start of RHR pump(s).

Starts RHR Loop A(B) pump(s).

Opens 2E11-F028A (2E11-F028B.

Throttles Open 2E11-F024A (2E11-F024B).

Open 2E11-F047A (2E11-F047B).

ATC IF it is desired to provide cooling of the Torus rather than mixing, ensure RHR flow is < 11,500 GPM, then closes 2E11-F048A (2E11-F048B).

Throttles 2E11-F068A OR 2E11-F068B to maintain 20 PSID Hx A(B) dp.

Refers to 34SO-E11-010-2.

SIMULATOR OPERATOR, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-4 Event No.: 8 Page 21 of 24 Event

Description:

HPCI flow controller output fails low requiring manual increase to obtain injection.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR; ENSURE Event Trigger EGE41-1 ACTIVATES malfunction mfE41_106, HPCI Flow Controller Fails Low, 5 Min with HPCI speed >3800 rpm.

NOTE TO EXAMINER: Prolonged operation with HPCI <2000 RPMs is to be avoided.

Starts HPCI for level control by performing the following at 2H11-P602 panel:

If required, depresses High Water Level Reset P/B.

Opens 2E41-F059, Lube Oil Cooling Wtr Vlv.

Starts 2E41-C002-2, Barometric Condenser Vacuum Pump Opens 2E41-F001, Turbine Steam Supply Vlv.

Starts 2E41-C002-3, Aux Oil Pump Opens 2E41-F006, Pump Discharge Valve Confirms the following valves OPENED:

BOP Turbine Control Vlv.

Turbine Stop Vlv..

Confirms the Turbine does NOT come up to proper speed.

Recognizes that HPCI flow controller has failed and places 2E41-R612, Flow Controller, in MANUAL and adjusts output to maintain RWL When flow increases to 790 GPM, confirms 2E41-F012, Min Flow Vlv., closed.

Adjusts controller for desired flow and with SRO permission will raise RWL to 32 to 42 inches.

At Chief Examiners direction, the scenario should be terminated when RWL is being restored with RWL is +5 to +50 inches or approaching OR at Chief Examiners direction.

Page 22 of 24 Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 13-4 Op-Test No.: 2021-301 Examiners: Operators: SRO RO BOP Initiating Conditions: 2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Turnover IAW 34SO-T41-006-2, Refueling Floor Ventilation System, section 4.3.3, remove RF Vent Filter, 2T41-D007, From Service. After RF Vent Filter, 2T41-D007, is removed from service, raise reactor power to 100% RTP using Recirc.

Summary:

Event 1: Normal; The BOP will remove RF Vent Filter, 2T41-D007, From Service IAW 34SO-T41-006-2, Refueling Floor Ventilation System, section 4.3.3. The crew should complete this with no problems.

Event 2: Component/TS; 2B Loop of Core Spray experiences high discharge pressure (valve leakage). When ARP is performed, system pressure is restored.

Event 3: Component: CRD 2A pump experiences an Overload condition requiring swapping to standby pump IAW System Operating procedure.

Event 4: Instrument/TS; The ADS System will experience an inadvertent initiation which will require the BOP to place the ADS Inhibit switches to INHIBIT prior to the valves opening to prevent exceeding 100°F/hr cooldown rate or 110°F Torus water temperature. (Critical Task)

The SRO will declare ADS INOPERABLE.

Event 5: Reactivity; Recirc Pump A & B runback to Speed Limiter #1 resulting in the plant operating in the Region of Potential Instabilities of the Power-to-Flow Map. Insert control rods to exit the RPI.

Event 6: Component; The plant will be operating in the Region of Potential Instabilities of the Power-to-Flow map with Control Rod 34-11/34-19 is stuck, requiring Drive Water dP to be increased to insert Control Rod 34-11/34-19.

Event 7: Unisolable Steam leak in Steam Chase (Reactor Building). Team should attempt to isolate leak source given a report of loud noise in steam tunnel. One path of MSIVs will not close with CS. (Critical Task)

Event 8: HPCI flow controller output fails low requiring the BOP to manually increase speed to obtain HPCI injection.

Page 23 of 24 Critical Tasks NRC FINAL Facility: E. I Hatch Scenario No.: 13-4 Op-Test No.: 2021-301 Critical Tasks The ADS System will experience an inadvertent initiation which will require the BOP to place the ADS Inhibit switches to INHIBIT prior to the valves opening to prevent exceeding >100°F cooldown rate. (Event 4)

Manually scram the reactor prior to exceeding one area Max Safe Temperature. (Event 7)

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 7 1. Core Spray 2B high pressure (Event 2)

2. High amps on CRD pump 2A (Event 3)

3. ADS System inadvertent initiation (Event 4)

4. Recirc Pumps runback to SL #1 (Event 5)

5. Stuck control rod (Event 6)

6. Unisolable Steam leak (Event 7)

7. HPCI flow controller fails. (Event 8)

2. Malfunctions After 1-2 1 1. HPCI flow controller fails. (Event 8)

EOP Entry

3. Abnormal Events 2-4 3 1. ADS System inadvertent initiation (Event 4)

2. Recirc Pumps runback to SL #1 (Event 5)

3. Stuck control rod (Event 6)

4. Major Transients 1-2 1 1. Unisolable Steam leak (Event 7)

5. EOPs entered, 1-2 2 1. RC (Non-ATWS) requiring substantive 2. SC actions

6. EOPs contingencies 0-2 0 1. NONE entered with substantive actions

7. Preidentified >2 2 1. ADS System inadvertent initiation (Event 4)

Critical Tasks 2. Unisolable Steam leak (Event 7)

ILT-13 NRC FINAL Scenario 4 SHIFT TURNOVER Safety Focus UNIT 1 STATUS Unit 1 is operating at 100% power Plant Conditions:

Activities in progress: Maintaining Rated Thermal Power Unit 2 is operating at 97% RTP preparing to remove RF Vent Filter, 2T41-D007, From Service IAW 34SO-T41-006-2, Refueling Floor Ventilation System, section 4.3.3.

Plant Conditions:

2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written.

2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Protected Train: EOOS:

Division I Green Orange Division II Yellow Red Scheduled evolutions: Remove RF Vent Filter, 2T41-D007, From Service IAW 34SO-T41-006-2, Refueling Floor Ventilation System, section 4.3.3.

After RF Vent Filter, 2T41-D007, is removed from service, raise reactor power to 100% RTP using Recirc.

Surveillances due this NONE shift:

Inop Equipment: 2D11-K615B, Off gas Post Treatment Radiation monitor has failed Downscale. IAW TS/TRM, I&C has placed 2D11-K615B in the trip condition while maintaining the function of 601-405, Post Treatment O/G Radiation Hi-Hi-Hi/Inop. A Caution Tag is attached to 2D11-K615B switch.

2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Active tagouts: 2D11-K615B, Off gas Post Treatment Radiation monitor Rod Configuration: See RWM Step 38

Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 13-6 Op-Test No.: 2021-301 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at 63% RTP preparing to remove 2A RFPT from service. 2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Turnover: Reduce reactor power using Recirc to 60% RTP for RFPT 2A removal. Leave RFPT 2A windmilling until Maintenance requests a Danger tag out.

Event Event Event Malf. No.

No. Type* Description 1 N/A R (ATC) Reduce reactor power using Recirc to 60% for RFPT 2A removal.

2 N/A N (BOP) Remove 2A RFPT from service and leave wind milling.

mfE51_114 C (ATC) 3 RCIC Inadvertent start with Trip pushbutton failure.

diE51A-S17 TS (SRO) 4 mfD11_190 C (BOP) Leak in RBCCW System. Isolate RWCU.

mfP51_222C loP51-C001BGl SSAC 2C Trips - 2B fails unloaded, 2A must be manually started.

5 C (ATC) (Critical Task) loP51-C001BR2 diP51-C001B C (BOP) 6 mfG31_242 Small leak in the DW requiring SBGT to vent DW. (Critical Task)

TS (SRO) 7 mfN21_87B M (ALL) RFPTs trip with only 1 in service.

HPCI 2E41-F001 stuck closed, RCIC must be manually restarted to 8 mfE41_107 C (BOP) inject prior to RWL reaching -180 inches. (Critical Task)

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 1 Page 2 of 24 Event

Description:

Reduce reactor power using Recirc to ~60% to achieve a Feedwater flow

<7 mlbm/hr for RFPT 2A removal.

Time Position Applicant's Actions or Behavior Directs ATC to reduce reactor power using Recirc to 60% to achieve a Feedwater flow <7 mlbm/hr for RFPT removal.

15 SRO Mins Power decreases should be made as recommended by the STA/Reactor Engineering at a rate NOT to exceed 10 MWe/min.

IAW 34SO-B31-001-2, the ATC decreases Recirc pump speed, NOT to exceed 10 MWE per minute by depressing the LOWER SLOW or LOWER MEDIUM pushbuttons on the Master or Individual controls until reactor power is 60%. Monitors power decrease by observing ATC APRM and generator output indications.

Monitors Total Feedwater flow to achieve Feedwater flow <7 mlbm/hr on 2C32-R604A, 2C32-R604B, and 2C32-R607.

Notifies SRO when Feedwater flow is <7 mlbm/hr.

Complies with 34SO-B31-001-2 , Limitation 5.2.15, which states:

WHEN changing Recirc pumps speed while in Two Loop operation maintain pump speeds to limit recirculation loop jet pump mismatch within the following limits:

ATC

<10% of rated core flow (7.7 E6 lbm/hr) WHEN operating

< 70% of rated core flow; AND

<5% of rated core flow (3.85 E6 lbm/hr) WHEN operating at

> 70% of rated core flow.

NOTE: May get the RBM UPSCALE, (603-202) and ROD OUT BLOCK, (603-238) alarm, if a peripheral control rod is NOT selected. This is expected, and the operator may select a peripheral rod at this time.

May also get Alarm HEATER TROUBLE, 650-135 alarm. This is expected at this power level.

SIMULATOR OPERATOR; at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 2 Page 3 of 24 Event

Description:

Remove 2A RFPT from service and leave wind milling.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR; Event 2 and Event 3 can be run simultaneously.

PROCEED to Event 3 when RFPT 2B is controlling RWL.

10 Directs the BOP to remove the 2A RFPT from service IAW SRO Mins 34SO-N21-007-2, Section 7.2.1.1.

Ensures Feedwater Flow is less than 7 Mlbm / hr.

Ensures RFPT 2A AND RFPT 2B are in Automatic control on 2C32-R600, Master Controller.

Depresses setpoint increase button on 2C32-R600, Master Controller and raises RWL setpoint to 39 inches.

Places 2C32-R601A, RFP A M/A Station, in Manual, by depressing the

'M' pushbutton until it illuminates, panel 2H11-P603.

Slowly lowers RFPT 2A speed until RFP 2B is controlling reactor vessel level. (See Event 3)

RFP C005A DISCH LOW FLOW, (656-039) will alarm and is expected.

RFPT CONTROLLER TROUBLE, (603-150) will alarm and is expected.

BOP Depresses setpoint decrease button on 2C32-R600, Master Controller and lowers RWL setpoint to 37 inches.

Slowly decreases RFPT 2A speed until no speed decrease is observed and places RFPT A TMR switch to SS and confirms SPEED SETTER yellow light illuminates.

Slowly lowers RFPT 2A Speed Setter switch until RFPT speed is at 1000 rpm, at 2H11-P650.

Dispatches SO to ensure open OR open RFPT 2A drain valves on Local panel 2H21-P244 (steps 7.2.1.1.9).

Slowly lowers RFPT 2A Speed Setter switch to MINIMUM to allow the RFPT to windmill (~130 rpm), at 2H11-P650.

SIMULATOR OPERATOR; at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 3 Page 4 of 24 Event

Description:

RCIC Inadvertent start with Trip pushbutton failure.

Time Position Applicant's Actions or Behavior At the Chief Examiners direction, SIMULATOR OPERATOR; if dispatched to confirm RFPT 2A drains, NOTIFY BOP and report all drain valves per step 7.2.1.1.9 are open, 6 Mins OTHERWISE.

Contact BOP and request EDG 1A Main Fuel Oil Storage tank level, AND ACTIVATE: (RB-3) to ENTER mfE51_114 and diE51A-S17 to off.

Recognizes that RCIC has started.

ALL Receives SEC SYSTEM AUTO INITIATION SIGNAL PRESENT, (650-234), is received.

ATC Determines RCIC has auto started and that RWL is normal.

May tell ATC that RWL is normal.

SRO Directs operator to trip RCIC.

Attempts to Trip RCIC by depressing the RCIC Trip pushbutton and recognizes that the Trip pushbutton is failed.

Notifies the SRO that the RCIC trip pushbutton has failed and Trips RCIC by ONE of the following methods:

Closes the Trip and Throttle valve, 2E51-F524.

ATC OR Places controller 2E51-R612 to Manual and reduces output to lower RCIC discharge pressure to below reactor pressure.

Receives RCIC TURBINE BRG OIL PRESS LOW, (602-304) &

RCIC PUMP DISCHARGE FLOW LOW, (602-322).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 3 Page 5 of 24 Event

Description:

RCIC Inadvertent start with Trip pushbutton failure.

Time Position Applicant's Actions or Behavior Enters 34AB-E10-001-2, Inadvertent Initiation of ECCS/RCIC.

Enters 34SO-E51-001-2, RCIC System.

Dispatches RO/Maintenance to determine cause of initiation signal and the ATC cause of the Trip pushbutton failure.

May attempt to reset the Initiation signal.

Will close 2E51-F524, Trip and Throttle Vlv, if not already closed.

Notifies SRO that RCIC is shutdown.

May have the operator run the Trip and Throttle Valve down to in case RCIC is needed later.

SRO Enters TS RAS for RCIC 3.5.3 Condition A, which requires verifying HPCI is operable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and restoring RCIC in 14 days.

NOTE: It is intended that RCIC is left in its current condition and not returned to standby.

SIMULATOR OPERATOR; at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 4 Page 6 of 24 Event

Description:

Leak in RBCCW System. Isolate RWCU.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, at the Chief Examiners direction, ENTERS (RB-4) mfD11_190, High Radiation in RBCCW f:5 r:10 8 Min AND THEN NOTIFIES the ATC by phone that RCIC inadvertent start is still being investigated and we will update you as reports come available.

Recognize and respond to the following alarms:

ALL RBCCW RADIATION HIGH, (601-413) approximately 60 seconds RBCCW SURGE TK LEVEL, (650-258)

Enters the APR 34AR-650-258-2:

Dispatches a SO to perform the following:

At 2P42-A001, RBCCW Surge Tank, confirm the level is greater than 30 inches above the tank centerline Confirm CLOSED 2P42-F055, Level Control Valve Bypass IF annunciator RBCCW RADIATION HIGH (601-413) is ALARMING, enters 34AR-601-413-2 IF 2P42-F054, Level Control Valve, is malfunctioning, BOP CLOSE 2P42-F027, Level Control Valve Isolation, AND control level using 2P42-F055.

IF level continues to increase, PLACE the standby RBCCW Heat Exchanger in service per 34SO-P42-001-2, RBCCW System, AND ISOLATE service water to the original in-service heat exchanger by closing the applicable 2P41-F439A or 2P41-F439B IF level increase is due to system in leakage, notify chemistry AND ensure compliance with 64CH-OPS-010, THEN throttle OPEN 2P42-F032, RBCCW Surge Tank Drain Valve, as needed to lower surge tank level.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 4 Page 7 of 24 Event

Description:

Leak in RBCCW System. Isolate RWCU.

Time Position Applicant's Actions or Behavior Enters the ARP 34AR-601-413-2:

Confirms high radiation levels on 2D11-R604, RBCCW/PSW Rad Monitor, panel 2H11-P600 BOP Requests Chemistry to sample RBCCW Monitor 2P42-A001, RBCCW Surge Tank, level locally IF possible, isolate radioactive RBCCW loads one at a time to determine the source of in leakage.

SIMULATOR OPERATOR, At Chief Examiner permission, REPORT as Chemistry: The sample of RBCCW indicates higher than normal levels of radiation.

NOTE: The Reactor water sample point remains in service if the switch on the P602 panel remains in the REACTOR WATER position.

Directs the ATC to isolate RWCU IAW 34SO-G31-003-2 SRO May address with RWCU out of service, TSR 3.4.1.1 for continuous monitoring of Rx coolant conductivity (TRACKING RAS with switch on P602 in the REACTOR WATER position)

NOTE: When RWCU is isolated, RBCCW radiation levels will slowly decrease.

Isolates RWCU IAW 34SO-G31-003-2:

Secures the running RWCU pump BOP Closes 2G31-F001 on panel 2H11-P602 Closes 2G31-F004 on panel 2H11-P601 Enters 34AB-G31-001-2, RWCU System Isolation SIMULATOR OPERATOR, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 5 Page 8 of 24 Event

Description:

SSAC 2C Trips - 2B fails unloaded, 2A must be manually started.

(Critical Task)

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, at direction of the Chief Examiner, NOTIFIES the Control Room by phone and request, as Chemistry, RBCCW radiation monitor reading, then ACTIVATES: (RB-5) malfunction mfP51_222C. ENSURE Event Trigger EGP51-3 ACTIVATES the following when the "B" air compressor red light is on:

loP51-C001BG1 to OFF, loP51-C001BR2 to ON, mfP51_222B, 7 Min EGP51-4 EGP52-5.

ONCE SSAC 2B is placed in PTL, ENSURE Event Trigger EGP51-4 DELETES: loP51-C001BG1, loP51-C001BR2, and mfP51_222B.

WHEN Control Air pressure reaches approximately 50 psig, ENSURE Event Trigger EGP52-5 inserts a Remote Function, rfP52_199, which will close the backup Nitrogen valve and turn off lights.

The following annunciators are received:

ALL PANEL 2H11-P700 SYSTEM TROUBLE, (650-225)

AIR CMPSR 2C TRIPPED/SHUTDOWN, (700-233)

Acknowledges 2H11-P700 panel alarm on 2H11-P650 Acknowledges AIR CMPSR 2C TRIPPED/SHUTDOWN, (700-233), on 2H11-P700 and notifies the SRO of the alarm Confirms/starts SSAC 2B on P650 panel Determines air pressure is continuing to decrease.

Starts SSAC 2A on P650 panel IAW (700-233) or 34AB-P51-001-2 ATC (Critical Task)

Critical Task is met if SSAC 2A is started prior to the Outboard MSIVs closing. (approximately 10 minutes).

Dispatches SO/Maintenance locally to investigate SSAC 2C tripping and SSAC 2B not maintaining air pressure As time allows, contacts Radiation Protection after starting Standby SSACs

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 5 Page 9 of 24 Event

Description:

SSAC 2C Trips - 2B fails unloaded, 2A must be manually started.

(Critical Task)

Time Position Applicant's Actions or Behavior May receive CONTROL BLG SERVICE AIR PRESS LOW, (700-222)

May direct ATC/BOP into 34AB-P51-001-2, Loss of Instrument and Service SRO Air System or Water Intrusion into the Service Air System SIMULATOR OPERATOR, 2 minutes after being dispatched to investigate SSAC 2C tripping and SSAC 2B not maintaining air pressure (unless SSAC 2A was started), and with Lead Examiners permission, INFORM the BOP; SSAC 2C has a low oil pressure shutdown indication AND IF SSAC 2B IS STILL RUNNING that SSAC 2B is running unloaded and you cannot locally get it to LOAD.

OR IF SSAC 2B IS NOT RUNNING that SSAC 2B is off and NOT in automatic mode locally (auto light not lit).

SIMULATOR OPERATOR: If requested to crosstie air, REPORT Unit 1 crosstie is not available.

IF dispatched locally as Maintenance, if SSAC 2B IS RUNNING, as Maintenance, request SSAC 2B Shutdown for troubleshooting.

Notifies SO/Maintenance (if BOP has not) to investigate SSAC 2C tripping and SSAC 2B not maintaining air pressure and initiates a condition report.

SRO Directs the BOP to start the SSAC 2A IAW AIR CMPSR 2C TRIPPED/SHUTDOWN, (700-233).

Directs the BOP to start the SSAC 2B.

May request to crosstie air with Unit 1.

Places SSAC 2B switch to PTL on P650 panel.

ATC As time allows, dispatches SO to perform step 7.5.1.6 of 34SO-P51-001-2.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 5 Page 10 of 24 Event

Description:

SSAC 2C Trips - 2B fails unloaded, 2A must be manually started.

(Critical Task)

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR PROCEEDS to the next event at the Chief Examiners direction.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 6 Page 11 of 24 Event

Description:

Small leak in the DW requiring SBGT to vent DW. (Critical Task)

Time Position Applicant's Actions or Behavior 10 SIMULATOR OPERATOR; at the direction of the Chief Examiner, ENTERS:

Mins (RB-6) malfunction mfG31_242 f:0.06 and ramp of 1000.

Receives Annunciators:

PRIMARY CNMT PRESSURE HIGH, (603-115)

ALL MULTIPOINT TEMPERATURE RCDR 2T47-R626 TEMP HIGH, (657-025)

Directs the BOP to:

Enter 657-025 ARP.

Monitor Drywell pressure.

SRO Vent the DW with SBGT, when DW pressure approaches 0.65 psig.

Enter 34AB-T23-002-2; Small Pipe Break Inside Primary Containment (may give this to the ATC since BOP will be at back panel).

Directs Operator Check DW Leakage per 34SV-SUV-019-2.

NOTE: The BOP will use either (A or B) train of SBGT per 34SO-T46-001-2 SBGT System procedure or uses placard.

Opens 2T46-F001 (A or B) or 2T46-F003 (A or B) for the subsequent train.

BOP Places SBGT Fan (2A or 2B) control switch to RUN.

(Placard)

Receives (2B or 2A) SBGT SWITCH NOT IN AUTO, (657-091 or Back 654-076), alarm Panels Confirms 2T46-F002 (A or B) OPENS Confirms SBGT Heater red light illuminates.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 6 Page 12 of 24 Event

Description:

Small leak in the DW requiring SBGT to vent DW. (Critical Task)

Time Position Applicant's Actions or Behavior Opens 2T48-F334A or 2T48-F334B (both valves may be opened)

Receives alarm DW VENT EXH BYPASS VLV OPEN, (657-008) or (654-002)

Receives alarm DRWL/TORUS N2 M/U 2 INCH ISOL VALVES BOP OPEN, (657-042) or (654-035)

(Placard) Opens 2T48-F335A or 2T48-F335B (both valves may be opened)

Back Opens 2T48-F336A or 2T48-F336B (both valves may be opened)

Panels (Critical Task)

(Critical task is met if DW venting is placed in service prior to a Reactor SCRAM on high DW pressure.)

Monitors DW pressure Notifies SRO that venting of the Drywell is in progress.

If directed, enters 34SO-T48-002-2, to Fast Vent and confirms the BOP/ATC following alarms are NOT illuminated:

SBGT/DRYWELL AND TORUS RADIATION HIGH (601-402)

FISSION PRODUCT PARTIC RADN HIGH/INOP (602-406)

FISSION PRODUCT IODINE RADN HIGH/INOP (602-412)

FISSION PRODUCT GAS HIGH/INOP (602-418)

CONTAINMENT RADIATION HIGH/INOP (602-436)

Opens 2T48-F319, Drywell Vent Vlv (2H11-P602).

Opens 2T48-F320, Drywell Vent Vlv (2H11-P601).

When Drywell pressure is < 0.5 psig on 2T48-R607A OR 2T48-R607B, close 2T48-F320, Drywell Vent Vlv.

Closes 2T48-F319, Drywell Vent Vlv.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 6 Page 13 of 24 Event

Description:

Small leak in the DW requiring SBGT to vent DW. (Critical Task)

Time Position Applicant's Actions or Behavior Enters 34AB-T23-002-2 and attempts to identify the location of the pipe break including:

Instrumentation lines RWCU (may remove from service and isolate by, if not previously done:)

ATC/BOP Recirc Pump seals HPCI RCIC SRV Tailpipe Vacuum Breakers malfunctioning Feedwater line break indication Notifies SSS to perform 34SV-SUV-019-2, DW Leakage check.

SIMULATOR OPERATOR; WAIT 3 minutes from being dispatched to perform DW leakage check, As the operator checking DW leakage, report:

DW Equipment drain leakage is stable at 1.7 gpm DW Floor drain leakage has increased from 0.8 gpm to 6.1 gpm Enters Tech Specs:

3.4.4 RCS Operational Leakage Condition: 3.4.4.A, Unidentified leakage not within limit OR total leakage not within limit.

SRO Required Action: Reduce leakage to within limits.

Completion time: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Condition 3.4.4.B, Unidentified leakage increase not within limit.

Required Action: Reduce leakage increase to within limits.

Completion time: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SIMULATOR OPERATOR; at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 7 Page 14 of 24 Event

Description:

RFPTs trip with only 1 in service.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR; at the Chief Examiners ACTIVATE: (RB-7) malfunctions mfN21_87A, Feedwater Pump A trip, mfN21_87B, Feedwater 5 Min Pump B trip, & mfE41_107, F001 Stuck. Event Trigger EGC71-7, Modifies mfG31_242 to f:2.0 r:100 & INSERTS Overrides mfC11_30A & mfC11_30B when Reactor Mode Switch is placed to SHUTDOWN .

ALL Notices that RFPT 2B has tripped.

Assigns the ATC to perform RC-1.

Assigns the BOP operator to perform RC-2 and RC-3.

Enters 31EO-EOP-010-2, RC EOP flow chart if RWL decreases below 3 SRO inches.

Directs RWL Band of 3 to 50 inches.

May direct Maximize CRD flow IAW 34SO-C11-005-2.

Performs RC-1 consisting of:

Inserts a manual scram.

Places the mode switch to SHUTDOWN.

Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display.

Notifies SRO of rod position check.

ATC Places SDV isolation valve switch to "isolate" & confirms closed.

If not tripped, places the Recirc pumps at minimum speed.

Inserts SRMs and IRMs.

Shifts recorders to read IRMS, when required.

Ranges IRMS to bring reading on scale.

Notifies the SRO when the above actions are complete.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 7 Page 15 of 24 Event

Description:

RFPTs trip with only 1 in service.

Time Position Applicant's Actions or Behavior Performs RC-2 actions consisting of:

Confirms proper Level Control response:

Checks ECCS Injection Systems (will not be in service if RWL >-35 inches)

Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value If Set down does not auto function, manually reduces FW Master Controller setpoint to approximately 9 inches.

BOP May not complete RC-2 since both RFPTs are tripped.

As time allows, confirms/Opens 2N21-F125.

As time allows, confirms/places 2C32-R619, FW S/U level control valve controller, in Auto, set at approximately 9 inches.

As time allows, confirms/closes 2N21-F110.

Informs SRO of loss of both RFPTs.

GO TO EVENT 8 HPCI/RCIC OPERATION Performs RC-3 consisting of:

Monitor RPV pressure.

Confirm proper operation of pressure control system (LLS and SRVs).

BOP If necessary, allows RPV pressure to exceed 1074 psig then cycles any SRV to initiate LLS.

Maintain RPV pressure between 1074 and 800 psig.

Notify SRO that LLS is the pressure control system.

Re-opens 2P41-F316A-D per 34AB-P41-001-2, Loss of PSW, Placard Places the A and B Isolation Override switches on the 2H11-P652 panel to OVERRIDE ATC Fully opens 2P41-F316A or C and 2P41-F316B or D Throttles 2P41-F316C or A and 2P41-F316D or B to open while monitoring PSW Division 1 and 2 pressures on 2H11-P650 panel ensuring that PSW pressure remains above 80 psig

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 7 Page 16 of 24 Event

Description:

RFPTs trip with only 1 in service.

Time Position Applicant's Actions or Behavior NOTE: The SRO may select an RPV pressure band which will lower the driving head of the leak while maintaining <100°F/hr RPV cool down (typically between 500 psig & 920 psig).

As time allows, may; Direct the ATC to decrease reactor pressure to reduce the driving head of the leak using SRVs.

SRO Enters the PC EOP flow chart May direct operator to restart Drywell Chillers and Cooling Fans IAW EOP-100.

Per the PC flowchart, as directed by Primary Containment Pressure, verifies Torus level is <285 inches and directs an operator to place Torus Sprays in service.

SRO May direct operator to place Torus Cooling in service if Torus temperature exceeds 95°F.

Sprays the Torus per 34SO-E11-010-2 placard on the 2H11-P601 Panel as follows:

Places Cnmt Spray Vlv Cntl switch in the MANUAL position.

Confirms/Starts RHR pump in loop A(B), if NOT already running ATC Opens 2E11-F028A(B)

Opens 2E11-F027A(B)

Throttles Open 2E11-F027A(B)

Notifies SRO that RHR is in Torus Sprays

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 7 Page 17 of 24 Event

Description:

RFPTs trip with only 1 in service.

Time Position Applicant's Actions or Behavior NOTE: The operator may place Torus Cooling in service by using the Placard that's available or using the appropriate section of the procedure. These steps assume the Placard is used. The A loop of RHR will be used.

Enters 34SO-E11-010-2, Residual Heat Removal Places RHRSW in service Overrides 2E11-F068A(B) Low Discharge Pressure Interlock Positions 2E11-F068A(B) to 45% OPEN Receives alarm, RHR HX A(B) DIFF PRESS LOW, (601-BOP 313)(601-215)

Starts RHRSW pump A(B)

Places 2E11-F068A(B) Low Discharge Pressure Interlock switch to normal position.

Positions 2E11-F068A(B) to obtain < 4400 gpm AND < 450 psig Places RHR A(B)Loop in Torus cooling per the placard by performing the following steps:

Opens 2E11-F048A(B)

Opens 2E11-F047A(B).

Opens 2E11-F003A(B).

Confirms/Starts RHR pump in loop A(B), if NOT already running Receives alarm, RHR LOW FLOW, (601-222)

Opens 2E11-F028A(B)

BOP Receives alarm, AUTO BLOWDOWN CS OR RHR PRESS PERMISSIVE, (602-312)

Receives alarm, SEC SYSTEM AUTO INITIATION SIGNAL PRESENT, (650-234)

Throttles OPEN 2E11-F024A(B)

Alarm, RHR LOW FLOW, (601-222), clears Ensures RHR flow is < 11,500 GPM, THEN Closes 2E11-F048A(B)

Notifies the SRO that RHR "A(B)" loop is in service.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 7 Page 18 of 24 Event

Description:

RFPTs trip with only 1 in service.

Time Position Applicant's Actions or Behavior As time allows, directs an operator to perform 31EO-EOP-114-2 for RHR SRO

& CS If time allows, directs H2/O2 Analyzers placed in service IAW SRO 34SO-P33-001-2.

Places H2/O2 Analyzers in service IAW 34SO-P33-001-2 Depresses Channel A and Channel B Reset pushbuttons on 2H11-P700 ATC panel.

Confirms Analyzers are running.

Notifies SRO H2/O2 Analyzers are in service.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 7 Page 19 of 24 Event

Description:

RFPTs trip with only 1 in service.

Time Position Applicant's Actions or Behavior NOTE: If crew addresses restoring DW Chillers they will NOT be able to due to Drywell temperature above 250°F.

If directed, restores drywell chillers per 31EO-EOP-100-2 section 3.7 by:

Verifies chilled water expansion tank is within normal level, (NO high/low alarms on 2H11-P700 panel or verify locally).

Verifies D/W temperature is <250°F, in the vicinity of 2T47-B007A /

2T47-B007B. SPDS points N001A and N010 can be used for 2T47-B007A and N001K and N002 can be used for 2T47-B007B. These points can be read directly from the SPDS Diagnostic Screen for Drywell temperature.

Notifies SSS to place switch for 2P64-C008A, Chilled Water pump, to ATC RUN & then verify Chilled Water return temperature is <100°F.

Place 2P64-S3, LOCA Override Switch, to BYPASS on panel 2H11-P700.

Notifies SSS to:

Open link, Lower TB4-12 in 2R22-S005 Fr. 6, for 2P64-B006A.

Reset 86 lockout relays on drywell chiller breaker on 4160V bus 2E (2R22-S005 Fr. 11).

Reset the POR relay for chiller.

Monitors for chiller start by observing the red light on 2H11-P700 or input from the SSS.

If directed, restores the drywell coolers per 31EO-EOP-100-2 section 3.6 by:

Verifies chilled water expansion tank is within normal level, (NO high/low alarms on 2H11-P700 panel or verify locally)

Verifies D/W temperature is <250°F, in the vicinity of 2T47-B007A / 2T47-B007B.

Notifies SSS to place switch for 2P64-C008A, Chilled Water pump, to ATC RUN & then verify Chilled Water return temperature is <100°F.

Places drywell cooling fans system A key-lock LOCA override switch to BYPASS on 2H11-P657.

Places drywell cooling fans system B key-lock LOCA override switch to BYPASS on 2H11-P654.

Observes the drywell cooler fans start by observing their red lights illuminating on 2H11-P654 and panel P657.

SIMULATOR OPERATOR; at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 8 Page 20 of 24 Event

Description:

HPCI 2E41-F001 stuck closed, RCIC must be manually restarted to inject prior to RWL reaching -180 inches. (Critical Task)

Time Position Applicant's Actions or Behavior NOTE: The malfunction for this event was in at the beginning of the scenario (mfE41_107 F001 STUCK). The operator may start RCIC OR HPCI first; either is acceptable, however 2E41-F001 is stuck closed, making HPCI unavailable.

NOTE: The RCIC Initiation Signal can NOT be RESET; therefore, the operator will enter section 7.1.4.3 of 34SO-E51-001-2 to restart RCIC.

Enters 34SO-E51-001-2 to restart RCIC per Section 7.1.4, RCIC Recovery From An Isolation Signal / Turbine Trip For Vessel Injection and performs the following:

Transfers 2E51-R612, Turbine Controller, to MANUAL AND adjusts output to 50%

May NOT dispatch SO for Mechanical overspeed device RESET (Was not tripped on overspeed),

Confirms close 2E51-F524, Trip & Throttle Valve Confirms open 2E51-F045, Stm to Turb Valve Confirms open 2E51-F046, Turb Clg Water Valve Confirms operating or start 2E51-C002-2, Barom Cndsr Vac Pump Slowly throttles open 2E51-F524, Trip & Throttle Valve, AND concurrently BOP confirms open OR opens 2E51-F013, Pump Discharge Valve Confirms 2E51-F019, Min Flow Valve, opens, AND subsequently closes Fully opens 2E51-F524, Trip & Throttle Valve Increases 2E51-R612, Turbine Controller, output to achieve 3000 to 4000 rpm Transfers 2E51-R612, Turbine Controller, to AUTO AND adjust to desired injection flowrate OR MANUALLY adjusts controller to maintain RWL above TAF (Critical Task)

(Critical Task will be met when RCIC is returned to service to maintain RWL

>-180 inches OR an Emergency Depressurization (at least 5 SRVs open) is performed prior to RWL <-180 inches.) Approximately 15 minutes to TAF &

18.75 minutes to -180.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-6 Event No.: 8 Page 21 of 24 Event

Description:

HPCI 2E41-F001 stuck closed, RCIC must be manually restarted to inject prior to RWL reaching -180 inches. (Critical Task)

Time Position Applicant's Actions or Behavior Starts HPCI for level control by performing the following at 2H11-P602 panel:

Opens 2E41-F059, Lube Oil Cooling Wtr Vlv.

Starts 2E41-C002-2, Barometric Condenser Vacuum Pump.

Realizes 2E41-F001, Turbine Steam Supply Vlv, will not open.

BOP Takes 2E41-C002-3, Aux Oil Pump, control switch to the START position.

(May place switch in Pull To Lock Off)

As time allows, notifies Maintenance of 2E41-F001 failure.

Informs SRO of 2E41-F001 failure.

With Chief Examiners Permission, the Scenario will be terminated when RWL is controlled in band or approaching or as directed by the Chief Examiner.

Page 22 of 24 Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 13-6 Op-Test No.: 2021-301 Examiners: Operators: SRO RO BOP Initiating Conditions: Unit 2 is operating at 63% RTP preparing to remove 2A RFPT from service for maintenance activities. 2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Turnover Reduce reactor power to 60% RTP for RFPT 2A removal. Leave RFPT 2A operating at ~1000 RPM until Maintenance requests a Danger tag out.

Summary:

Event 1: Reactivity: The ATC will reduce reactor power to ~60% RTP via Recirc to achieve

<7 mlbm/hr for 2A RFPT removal from service.

Event 2: Normal; After reactor power is reduced, the BOP will remove the 2A RFPT from service and leave windmilling.

Event 3: Component/TS; RCIC will experience an inadvertent start with Trip pushbutton failing to trip RCIC. Operator will shutdown RCIC by either; closing T&TV or placing flow controller in manual and lowering speed to prevent injection.

Event 4: Component; Leak in RBCCW System. Isolate RWCU.

Event 5: Component; SSAC 2C Trips - 2B fails unloaded, 2A manually started. The "2C" Station Service Air Compressor (SSAC) trips due to an equipment malfunction. "2B" SSAC auto starts but does not supply any air to the system because its loader system is malfunctioning.

The crew will manually start "2A" SSAC, which does return the air system to normal pressures.

(Critical Task)

Event 6: Component/TS; Small leak causes DW pressure to increase. The BOP will start Standby Gas Treatment (SBGT) and DW venting will be aligned prior to a reactor scram on high DW pressure. (Critical Task) The SRO will declare a TS Required Action Statement.

Event 7: Major; RFPTs trip with only 1 in service.

Event 8: HPCI 2E41-F001 stuck closed, RCIC must be manually restarted to inject prior to RWL reaching -180 inches. (Critical Task)

Page 23 of 24 Critical Tasks NRC FINAL Facility: E. I Hatch Scenario No.: 13-6 Op-Test No.: 2021-301 Critical Tasks SSAC 2C Trips - 2B fails unloaded, 2A must be manually started. (Event 5)

DW venting is placed in service prior to a Reactor SCRAM on high DW pressure. (Event 6)

HPCI 2E41-F001 stuck closed, RCIC must be manually restarted to inject prior to RWL reaching

-180 inches OR an Emergency Depressurization (at least 5 SRVs open) is performed prior to RWL

<-180 inches. (Event 8)

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 6 1. RCIC inadvertent start (Event 3)

2. Leak in RBCCW System (Event 4)

3. SSAC 2C trips (Event 5)

4. DW leak/start SBGT (Event 6)

5. Only operating RFPT trips (Event 7)

6. HPCI 2E41-F001 stuck closed (Event 8)

2. Malfunctions After 1-2 1 1. HPCI 2E41-F001 stuck closed (Event 8)

EOP Entry

3. Abnormal Events 2-4 4 1. RCIC inadvertent start (Event 3)

2. Leak in RBCCW System (Event 4)

3. SSAC 2C trips (Event 5)

4. DW leak/start SBGT (Event 6)

4. Major Transients 1-2 1 1. Only operating RFPT trips (Event 7)

5. EOPs entered, 1-2 2 1. RC-(Non-ATWS) requiring substantive 2. PC actions

6. EOPs contingencies 0-2 1 1. RC-L Path of RC-(Non-ATWS) entered with substantive actions

7. Preidentified >2 3 1. SSAC 2C trips (Event 5)

Critical Tasks 2. DW leak/start SBGT (Event 6)

3. HPCI 2E41-F001 stuck closed (Event 8)

ILT-13 NRC FINAL Scenario 6 SHIFT TURNOVER Safety Focus UNIT 1 STATUS Unit 1 is operating at 100% power Plant Conditions:

Activities in progress: Maintaining Rated Thermal Power Unit 2 is operating at 63% RTP preparing to remove 2A RFPT from service for maintenance activities.

Plant Conditions: 2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written.

2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Protected Train: EOOS:

Division I Green Orange Division II Yellow Red Scheduled evolutions: Reduce reactor power using Recirc to 60% RTP for RFPT 2A removal.

Starting at step 7.2.1.1 of 34SO-N21-007-2 ,Condensate & Feedwater System, remove RFPT 2A from service and leave windmilling until Maintenance requests a Danger tag out.

Surveillances due this NONE shift:

Inop Equipment: 2D11-K615B, Off gas Post Treatment Radiation monitor has failed Downscale. IAW TS/TRM, I&C has placed 2D11-K615B in the trip condition while maintaining the function of 601-405, Post Treatment O/G Radiation Hi-Hi-Hi/Inop. A Caution Tag is attached to 2D11-K615B switch.

2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Active tagouts: 2D11-K615B, Off gas Post Treatment Radiation monitor Rod Configuration: See RWM Step 24

Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 13-7 Op-Test No.: 2021-301 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at 70% RTP. 2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Turnover: Perform 34IT-T45-001-2, Reactor Building Instrument Sumps Isolation Valve Exercise.

After complete, raise reactor power via Recirc flow to 80% RTP.

Event Event Event Malf. No.

No. Type* Description Perform 34IT-T45-001-2, Reactor Building Instrument Sumps 1 N/A N (BOP)

Isolation Valve Exercise.

mfC11_30A CRD pump trips due to low suction pressure instrument failure. Must 2 I (ATC) mf60311334 start standby pump to restore system flow & pressure.

mfE41_213 loE41_F004G1 I (BOP) HPCI Torus Level Sensor Fails High; with failure of CST valve in 3 loE41_F004R2 TS (SRO) open position (Valve overload).

mf60111047 aoE41-R606 C (ATC) Recirc Pump 2B trips resulting in the plant operating in the Region of 4 mfB31_37B TS (SRO) Potential Instabilities of the Power-to-Flow map 5 N/A R (ATC) Insert Control rods to exit the Region of Potential Instabilities.

The Backup SDV valves will close due to a small air leak on 2C11-6 rfC11_141 TS (SRO) F040 requiring the SRO declare a TS Required Action Statement.

Stator Cooling Pump 2B Trips mfN43_148A 7 C (BOP) Standby Stator Cooling pump 2A fails to start (manually started) mfN43_158B (Critical Task) 8 mfG31_242 M (ALL) Leak in Drywell causes High Drywell pressure scram.

diE11-F016A RHR 2E11-F016A/B stuck closed requiring swapping to other loop 9 C (ATC) diE11-F016B of DW spray (Critical Task)

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 1 Page 2 of 26 Event

Description:

Perform 34IT-T45-001-2, Reactor Building Instrument Sumps Isolation Valve Exercise.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR; Inform the SRO you will provide an extra operator to perform the restoration section of the procedure when it's required.

10 min SRO Directs the BOP to perform 34IT-T45-001-2, Reactor Building Instrument Sumps Isolation Valve Exercise.

The following switches are located on the 2H11-P654 panel.

Obtains SROs permission to perform test starting at section 7.2 Confirms Sump Isol switch for 2T45-F005, 2T45-F003, and 2T45-F001 (below indication for 2T45-F001) is in CLOSED Confirms the following valves are CLOSED:

2T45-F005, RHR N-E Inbd Sump Isol 2T45-F003, Torus N-E & S-E Inbd Sump Isol BOP 2T45-F001, HPCI Sump Isol Places the Sump Isol switch for 2T45-F005, 2T45-F003, and 2T45-F001, in AUTO, AND confirms the following valves OPEN:

2T45-F005 2T45-F003 2T45-F001 Places the Sump Isol switch for 2T45-F005, 2T45-F003, and 2T45-F001 in CLOSE, AND confirms the following valves CLOSE:

BOP 2T45-F005, RHR N-E Inbd Sump Isol.

2T45-F003, Torus N-E & S-E Inbd Sump Isol.

2T45-F001, HPCI Sump Isol.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 1 Page 3 of 26 Event

Description:

Perform 34IT-T45-001-2, Reactor Building Instrument Sumps Isolation Valve Exercise.

Time Position Applicant's Actions or Behavior Per Section 7.3, confirms the Sump Isol switch for 2T45-F007 and 2T45-F006 (below indication for 2T45-F006) is in CLOSED Confirms the following valves are CLOSED:

2T45-F007, Torus N-W & S-W Inbd Sump Isol.

2T45-F006, RCIC Sump Isol.

Places the Sump Isol switch for 2T45-F007 and 2T45-F006 in AUTO, BOP AND confirms the following valves OPEN:

2T45-F007 2T45-F006 Places the Sump Isol switch for 2T45-F007 and 2T45-F006 in CLOSE, AND confirms the following valves CLOSE:

2T45-F007, Torus N-W & S-W Inbd Sump Isol.

2T45-F006, RCIC Sump Isol.

Per Section 7.4, confirms the Sump Isol switch for 2T45-F004 and 2T45-F002, (below indication for 2T45-F002) is in CLOSED Confirms the following valves are CLOSED:

2T45-F004, RHR N-E Outbd Sump Isol.

BOP 2T45-F002, Torus N-E & S-E Outbd Sump Isol.

Places the Sump Isol switch for 2T45-F004 and 2T45-F002 in AUTO, AND confirms the following valves OPEN:

2T45-F004 2T45-F002 Places the Sump Isol switch for 2T45-F004 and 2T45-F002 in CLOSE, AND confirms the following valves CLOSE:

2T45-F004, RHR N-E Outbd Sump Isol.

BOP 2T45-F002, Torus N-E & S-E Outbd Sump Isol Notifies SRO the surveillance is complete and needs to be independently verified.

SIMULATOR OPERATOR; Continue with the next event at the Chief Examiners request.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 2 Page 4 of 26 Event

Description:

CRD pump trips due to low suction pressure instrument failure. Must start standby pump to restore system flow & pressure.

Time Position Applicant's Actions or Behavior At the Chief Examiners direction, SIMULATOR OPERATOR ENTERS (RB-2) malfunction mf60311334 CRD A Suction Pressure Low alarm.

10 Mins ENSURE Event Trigger EGC11-2 ACTIVATES when CRD A Suction Pressure Low alarms.

Recognizes the following occurs:

CRD PUMP A SUCTION PRESSURE LOW, (603-146) alarms CRD PUMP 2A BREAKER TRIP, (603-128) alarms ATC CRD pump 2A is tripped CRD HYD TEMP HIGH, (603-140) alarms CRD ACCUMULATOR PRESS LOW OR HIGH, (603-148) alarms ~

1.5 minutes later (will NOT alarm if CRD 2B is started expeditiously).

Dispatches SO/Maintenance to determine the cause of the low suction SRO/ATC pressure condition for CRD pump 2A.

Directs the ATC to enter 34AB-C11-001-2, Loss of CRD, and start CRD SRO pump 2B.

NOTE: The Abnormal procedure requires charging water header to be restored within 20 minutes.

Enters 34AB-C11-001-2, Loss of CRD Places 2C11-R600, CRD Flow Control, in Manual Decreases 2C11-R600 output to zero Manually starts CRD pump 2B CHARGING WATER PRESSURE HIGH, (603-139) may come in and ATC then clear on pump start Increases system flow to ~50 gpm Transfers 2C11-R600 to Automatic Notifies SRO CRD pump 2B is in service May place CRD pump 2A switch to stop, which clears CRD PUMP 2A BREAKER TRIP, (603-128) alarm.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 2 Page 5 of 26 Event

Description:

CRD pump trips due to low suction pressure instrument failure. Must start standby pump to restore system flow & pressure.

Time Position Applicant's Actions or Behavior Dispatches a SO to check CRD temperatures and Accumulator pressures SRO/ATC locally.

SIMULATOR OPERATOR, if dispatched to check Accumulator pressures, wait until after CRD pump 2B is started AND ALL Accumulator alarms are clear, THEN report all accumulator pressure are > 980 psig.

May review TS 3.1.5 for inop accumulators and since all accumulator SRO pressures are > 980 psig, does NOT declare any accumulators inop.

SIMULATOR OPERATOR reports that:

If the CRD High Temp Alarm is still lit, report that 1 CRD drive (26-35) is 270°F If the CRD High Temp Alarm is NOT lit, report that all temps are < 250°F Suction pressure for CRD pump 2A is 22 psig and there is no apparent problem with the suction line-up or suction filter.

SIMULATOR OPERATOR, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 3 Page 6 of 26 Event

Description:

HPCI Torus Level Sensor Fails High; with failure of CST valve in open position (Valve overload).

Time Position Applicant's Actions or Behavior At the Chief Examiners direction, SIMULATOR OPERATOR ENTERS:

15 Min (RB-3) mfE41_213, loE41-F004R2 f:1 AND loE41-F004G1 f:0.

ALL TORUS LEVEL HIGH, (601-127) alarm is received on P601.

SRO Directs an operator to enter 34AR-601-127-2 SIMULATOR OPERATOR ENSURE Event Trigger EGE41-23 inserts the following WHEN 2E41-F004 control switch is placed to close:

loE41-F004R2 f:0, loE41-F004G1 f:0, mf60111047, HPCI VALVES MOTOR OVERLOAD (ANNUNCIATOR ON) svoT48140 f:160 r: 0.1, Torus Level, &

EGE41-24, E41-F004 green light ON deletes alarm (mf60111047)

Enters TORUS LEVEL HIGH, (601-127);

Determines that HPCI Suction has aligned to the Torus Ensures 2E41-F051, 2E41-F041 and 2E41-F042 are open.

Ensures that 2E41-F004 is closed. Valve is still open Closes 2E41-F004 (Cannot perform this step because when control switch placed to CLOSE, 2E41-F004 light indication de-energizes)

HPCI VALVES OVERLOAD, (601-111) alarm is received on P601 BOP Determines that Torus level is NOT high but is slowly going up.

Determines that HPCI should NOT have auto swapped to the Torus.

Notifies SRO that HPCI suction valve, 2E41-F004, has no light indication.

Notifies SRO of the following TS (found in Section 8.0 of ARP);

3.6.2.2, Suppression Pool Water Level 3.3.5.1, Emergency Core Cooling System (ECCS) Instrumentation 3.5.1, ECCS Operating Enters 601-111 Determines that 2E41-F004 has NO lights illuminated.

BOP Dispatches operator/Maintenance to reset the thermal overload for 2E41-F004, HPCI CST Suction MOV, (Frame 3B on 2R24-S022)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 3 Page 7 of 26 Event

Description:

HPCI Torus Level Sensor Fails High; with failure of CST valve in open position (Valve overload).

Time Position Applicant's Actions or Behavior Dispatches operator/Maintenance to reset the thermal overload for 2E41-SRO F004 (Frame 3B on 2R24-S022) (ATC may do this also)

Directs operator to monitor suction pressure on HPCI.

SIMULATOR OPERATOR, if dispatched to ATTS panels, report all Torus level indicators are slowly rising.

Also, 3 minutes after Maintenance is sent to investigate, NOTIFY the control room that local level switch, 2E41-LS-N062B, has failed high.

BOP Reports to the SRO that 2E41-LS-N062B has failed.

NOTE: Chief Examiner, if SRO evaluates a different TS call, provide follow-up question on TS determination.

Enters Tech Specs 3.3.5.1, HPCI System Instrumentation, Condition A.1 to enter Condition referenced in Table 3.3.5.1-1 (Condition D)

Condition D.2.1 or D.2.2, to place the channel in trip or align HPCI SRO suction to the Suppression pool within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

If Torus water level exceeds 150 inches, performs the following:

Enters TS 3.6.2.2 Condition A.1 to restore Torus water level in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Enters 31EO-EOP-012-2, PC flowchart and directs operator to lower Torus water level IAW 34SO-E11-010-2.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 3 Page 8 of 26 Event

Description:

HPCI Torus Level Sensor Fails High; with failure of CST valve in open position (Valve overload).

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, after 2 minutes from being dispatched to the breaker, DELETE override loE41-F004G1 AND ENSURE Event Trigger EGE41-24 PERFORMS the following:

MODIFIES svoT48140 rate to 0 DELETES: loE41-F004R2 and mf60111047, HPCI Motor Overload, alarm SIMULATOR OPERATOR; NOTIFIES the control room that the breaker for 2E41-F004 has been reset.

Confirms 2E41-F004 has traveled full closed.

Informs SRO that 2E41-F004 is full closed.

BOP Alarm HPCI VALVES MOTOR OVERLOAD, (601-111), clears.

Torus level has stopped rising.

SIMULATOR OPERATOR; At Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 4 Page 9 of 26 Event

Description:

Recirc Pump 2B trips resulting in the plant operating in the Region of Potential Instabilities of the Power-to-Flow map.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR; 10 Min At Chief Examiners direction, press (RB-4) to ACTIVATE mfB31_37B, Recirc Pump B ASD MV Input Breaker Trip.

Acknowledges the following annunciators:

602-201 ASD B TRIP WARNING ALL 602-202 ASD B FATAL FAULT 602-208 ASD B TROUBLE 602-227 RECIRC LOOP B OUT OF SERVICE Notifies Plant Management, Load Dispatcher, and Engineering of Recirc SRO Pump 2B Trip condition NOTE: Heater Trouble Alarm (650-135) may alarm due to plant conditions.

Enters 34AB-B31-001-2, Reactor Recirculation Pump(s) Trip, Recirc Loops ATC Flow Mismatch, Or ASD Cell Bypass for single Recirc pump trip.

Closes 2B31-F031B, Pump Disch Valve.

Time:

After 4-5 minutes, throttles 2B31-F031B, Pump Disch Valve OPEN Time:

ATC Acknowledges the following annunciators:

602-201 ASD B TRIP WARNING 602-202 ASD B FATAL FAULT 602-208 ASD B TROUBLE 602-227 RECIRC LOOP B OUT OF SERVICE

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 4 Page 10 of 26 Event

Description:

Recirc Pump 2B trips resulting in the plant operating in the Region of Potential Instabilities of the Power-to-Flow map.

Time Position Applicant's Actions or Behavior NOTE: IAW 34AB-B31-001-2 During single loop operation, WHEN the speed of the running pump decreases below approximately 35% speed, positive flow through the idle pump loop due to natural circulation overcomes the negative flow due to reverse flow. The total core flow summing circuitry will continue to subtract this positive idle loop flow from the running loop flow AND give a misleading LOW core flow indication. Total core flow can be calculated by adding the JET PUMP LOOP "A" AND the JET PUMP LOOP "B" flows.

Has the operator determine if the plant is in the Region of Potential Instabilities of the Power to Flow Map.

Directs entry into 34AB-C51-001-2, Entry Into The Region Of Potential SRO Instabilities (RPI) Or Reactor Operations With Inoperable OPRM System.

Go to Event 5 for exiting the RPI.

NOTE: IAW 34GO-OPS-005-2, Power Changes, Limitation 5.2.3.1:

If the Region Of Potential Instabilities (RPI) is entered, IMMEDIATELY initiate actions to exit the (RPI), to return operation to the Analyzed Region of the Power/Flow Map outside of the RPI.

If the Immediate Exit Region is entered, within 5 minutes the operators are to initiate control rod movement to return to the Analyzed Region.

Operation within the Analyzed Region AND outside of the RPI must be restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Based on the operating point on the Power to Flow Map, may direct the operator to insert the rods to the insert limit IAW Control Rod Movement SRO sheets Enters Tech Spec 3.4.1.A.1 and has 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to meet requirements for Single Loop Operation SIMULATOR OPERATOR, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 5 Page 11 of 26 Event

Description:

Insert Control rods to exit the Region of Potential Instabilities.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR; When the crew determines the plant is in the Region Of Potential Instabilities 10 Min of the Power to Flow map, WAIT FIVE (5) MINUTES, THEN DEPRESS RB-9, mfC51_253 f:10 r:10, Region Independent LPRM Oscillations.

Oscillations will start building and exceed 5% peak-to-peak.

NOTE: RBM Downscale alarm may alarm during this movement due to the significant rod worth of these rods. It is allowed to flag the RBM Downscale and Rod Block alarm.

SIMULATOR OPERATOR; When the crew starts inserting Control rods, DELETE RB-9, mfC51_253 f:4 r:10, Region Independent LPRM Oscillations, IF it was inserted previously.

Determines that the plant is in the Region of Potential Instabilities (RPI) of the Power to Flow map.

If received, acknowledges APRM UPSCALE, (603-219) and ROD OUT BLOCK (603-238) annunciators IAW Control Rod Movement sheets and 34GO-OPS-065-0, inserts Control rods to exit the RPI starting with Step 24 Rod 42-35 Selects Rod Places Control Rod movement switch to the IN position.

ATC Verifies Rod moves using Rod display information and Rx and Generator power decreasing.

Releases Rod movement switch so that the control rod stops 1 position before the insert limit unless the insert limit is 00.

Initials Rod Movement Sheet.

Verifier, if available, Initials Rod movement sheet.

Continues Control Rod movement until the RPI is exited Notifies the SRO when the RPI is exited As time allows, enters 34AB-C51-001-2, Entry Into The Region Of ATC Potential Instabilities (RPI) Or Reactor Operations With Inoperable OPRM System, to confirm actions.

SIMULATOR OPERATOR, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 6 Page 12 of 26 Event

Description:

The Backup SDV valves will close due to a small air leak on 2C11-F040 requiring the SRO declare a TS Required Action Statement.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, at the Chief Examiners direction, ENTERS (RB-6) rfC11_141, SDV Outboard Valves close 10 Min AND 3 minutes later ENSURES Event Trigger EGC11-4 ACTIVATES mf60311307, SDV Not Drained, alarm.

When the SDV NOT DRAINED, (603-119), alarm is received, recognizes ALL that the SDV Outboard Valves have closed.

(May recognize prior to alarm by scanning the control boards).

Enters 603-119 and performs the following:

Determines that 2C11-F035A, 2C11-F035B and 2C11-F037 have closed.

Determines status of all Scram Valves (blue lights are NOT lit) on P603 display.

Determines status of SCRAM VLV PILOT AIR HDR PRESS HIGH/LOW, (603-131), (NOT LIT)

Determines if any Rod Drift lights on P603 (None).

ATC Confirms Scram Disch Vol Isol Test Switch in Normal.

Dispatches SO to the CRD drives to check for leaking Scram Outlet Valves.

May discuss the monitoring of the White Rod Out permissive light for the upcoming rod block to quantify when a reactor scram would occur.

Dispatches SO/Maintenance to determine if an air leak exists on the SDV valve piping.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 6 Page 13 of 26 Event

Description:

The Backup SDV valves will close due to a small air leak on 2C11-F040 requiring the SRO declare a TS Required Action Statement.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, when dispatched to investigate, wait 2 minutes and report there is a small air leak on 2C11-F040, SDV Outboard Isolation Solenoid Valve and will have to be repaired. It will take approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to repair.

Enters Tech Spec 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, SRO Condition A which requires the SDV line to be isolated within 7 days.

May inform Maintenance to correct the associated air leak.

SIMULATOR OPERATOR, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 7 Page 14 of 26 Event

Description:

Stator Cooling Pump 2B Trips, Standby Stator Cooling pump 2A fails to start (manually started) (Critical Task)

Time Position Applicant's Actions or Behavior At the Chief Examiners direction, SIMULATOR OPERATOR, WHILE the 8 Min ATC is AWAY from 2H11-P651; THEN ENTER: (RB-7) to ACTIVATE:

mfN43_158B & mfN43_148A.

When Stator Water Cooling pump 2B is tripped, responds to the following alarms:

GENERATOR INLET FLOW LOW, 651-201 GENERATOR INLET PRESS LOW, 651-202 GENERATOR OUTLET TEMP HIGH, 651-204 BOP STATOR CLG TANK WATER LEVEL HIGH/LOW, 651-205 GENERATOR PROTECTION CIRCUIT ENERGIZED, 651-206 MAIN GENERATOR TEMPERATURE, 651-161 TURBINE TROUBLE, 650-105 600V STA SVC FDR BRKR TRIP, 650-138 Acknowledges the alarms and informs the SRO that the Stator Cooling system pressure and flow is low and that Stator Cooling pump 2A did NOT auto start.

BOP (Stator Cooling 2A may be started manually prior to recognizing failure to auto start.)

The ATC may enter the following ARPs in any order:

Enters GENERATOR INLET FLOW LOW, 651-201, and performs the following:

Dispatches SO locally to 2N43-R303, Flow Indicator at 2N43-P001 Manually starts Stator Cooling pump 2A (May NOT pull procedure until after the pump has been started.)

BOP Critical Task; Critical Task is met if 2A Stator Cooling pump is started prior to Main Turbine Bypass valves opening.

Monitors for increasing system flow by 651-201 clearing Dispatches SO/Maintenance to investigate the cause of Generator Inlet Flow Low

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 7 Page 15 of 26 Event

Description:

Stator Cooling Pump 2B Trips, Standby Stator Cooling pump 2A fails to start (manually started) (Critical Task)

Time Position Applicant's Actions or Behavior The BOP may NOT enter the following once the standby pump is started.

Enters GENERATOR INLET PRESS LOW, 651-202, and performs the following:

Dispatches SO locally to 2N43-R301, Pressure Indicator at 2N43-P001 Manually starts the Stator Cooling pump 2A BOP (May NOT pull procedure until after the pump has been started.)

Monitors for increasing system pressure by 651-202 clearing.

Dispatches SO/Maint to investigate the cause of Generator Inlet Pressure Low.

The BOP may NOT enter the following once the standby pump is started.

Enters GENERATOR OUTLET TEMP HIGH, 651-204, and performs the following:

Monitors Stator Cooling Outlet temp on EHC Control System monitor BOP on 2H11-P650 panel Dispatches SO/Maintenance to investigate GENERATOR OUTLET TEMP HIGH alarm.

The ATC may NOT enter the following once the standby pump is started.

Enters STATOR CLG TANK WATER LEVEL HIGH/LOW, 651-205, and BOP dispatches a SO locally to determine Tank level.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 7 Page 16 of 26 Event

Description:

Stator Cooling Pump 2B Trips, Standby Stator Cooling pump 2A fails to start (manually started) (Critical Task)

Time Position Applicant's Actions or Behavior The BOP may NOT enter the following once the standby pump is started.

Enters GENERATOR PROTECTION CIRCUIT ENERGIZED, 651-206, and performs the following:

Starts Stator Cooling pump 2A BOP IF a Main Turbine Bypass Valve begins opening, enters 34AB-C71-001-2, Scram Procedure, and SCRAM the reactor.

(NOT expected to be required)

SRO Directs the operator to place the Stator Cooling Pump 2B pump to Trip.

SIMULATOR OPERATOR, After being dispatched, as a SO, REPORT that Stator Cooling pump 2B motor is extremely hot and Maintenance is investigating.

May place 2N43-C001B control switch to Trip position upon Maintenance BOP request, and then reports this to the SRO.

SIMULATOR OPERATOR, at Chief Examiners direction, starts the Major event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 8 Page 17 of 26 Event

Description:

Leak in Drywell causes High Drywell pressure scram.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, at the Chief Examiners direction, ENTER: (RB-8) 10 to ACTIVATE mfG31_242, RWCU Non-Isol Leak in Drywell:

Min Final 0.5 Ramp 1000 Recognizes increasing Containment Pressure from the following alarms:

PRIMARY CNMT HIGH PRESSURE TRIP, (603-106).

ALL PRIMARY CNMT PRESSURE HIGH, (603-115).

DRYWELL PRESSURE HIGH, (602-210).

NOTE: The SRO may direct the BOP to vent the Drywell, but there will NOT be time to complete the task before the LOCA signal is received.

With Drywell pressure increasing and alarms PRIMARY CNMT PRESSURE HIGH, (603-115) and DRYWELL PRESSURE HIGH, (602-210), alarms being received, directs the ATC enter 34AB-C71-001-2, Scram Procedure, and Scram the reactor.

SRO Assigns the ATC to perform RC-1.

Assigns the BOP operator to perform RC-2 and RC-3.

Enters 31EO-EOP-010-2, RC (Non ATWS) & 31EO-EOP-012-2, PC Control, EOP flow charts.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 8 Page 18 of 26 Event

Description:

Leak in Drywell causes High Drywell pressure scram.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, WHEN the reactor is scrammed, ENSURES EVENT TRIGGER EGC71-12 MODIFIES mfG31_242 Final to 1.5 with a ramp of 1000 AFTER 180 seconds.

Performs RC-1 consisting of:

Inserts a manual scram.

Places the mode switch to SHUTDOWN.

Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display.

Notifies SRO of rod position check.

ATC Places SDV isolation valve switch to "isolate" & confirms closed.

If NOT tripped, places the Recirc pumps at minimum speed.

Inserts SRMs and IRMs.

Shifts recorders to read IRMS, when required.

Ranges IRMS to bring reading on scale.

Notifies the SRO when the above actions are complete.

Performs RC-2 actions consisting of:

Confirms proper Level Control response:

Checks ECCS Injection Systems and secure as necessary.

BOP Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.

IF set down does NOT auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 8 Page 19 of 26 Event

Description:

Leak in Drywell causes High Drywell pressure scram.

Time Position Applicant's Actions or Behavior Controls HPCI operation for level control by performing one or more of the following:

Adjusts 2E41-R612, HPCI Flow Control, to the desired injection rate.

Transfers the flow controller to manual and adjust its speed demand output to obtain the desired pump flow.

BOP Shutdown HPCI by:

Depresses and holds the HPCI Turbine Trip pushbutton.

When HPCI turbine has stopped, places 2E41-C002-3, HPCI Aux Oil Pump, in Pull-To-Lock.

When HPCI TURBINE BRG OIL PRESS LOW alarm is received, releases the HPCI Turbine Trip push-button..

When feed flow is less than the capacity of the S/U level control valve (

1.5 mlbm/hr), then:

Opens 2N21-F125.

Confirms 2C32-R619, FW S/U level control valve controller, in Auto, set at approximately 9 inches.

BOP Closes 2N21-F110.

May attempt to restart the CRD pumps.

May attempt maximize CRD flow IAW 34SO-C11-005-2.

Controls RWL with the HPCI/FW System.

Notifies SRO if RWL gets outside assigned band.

NOTE to EXAMINER: SRVs actuate in LLS at 1120 psig and then control pressure between 850 - 990 psig.

Performs RC-3 consisting of:

Monitors RPV pressure.

If necessary, allows RPV pressure to exceed 1074 psig then cycles any BOP SRV to initiate LLS.

If necessary, verifies LLS actuates at 1120 psig Maintains RPV Pressure between 1074 and 800 psig.

Notifies SRO of pressure control system operation.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 8 Page 20 of 26 Event

Description:

Leak in Drywell causes High Drywell pressure scram.

Time Position Applicant's Actions or Behavior NOTE: The SRO may select an RPV pressure band which will lower the driving head of the leak while maintaining <100°F/hr RPV cool down (typically between 500 psig & 920 psig).

As time allows, may; Direct the ATC to decrease reactor pressure to reduce the driving head of SRO the leak using EHC pressure set.

Remove RWCU from service IAW 34AB-T23-002-2, Small Pipe Break in Primary Containment.

Enters Attachment 11 of 34SO-N30-001-2, Main Turbine, or 34GO-OPS-013-2, Normal Plant Shutdown, and at the DEHC panel computer, performs ONE of the following:

1. Throttle Pressure Set Selects the Control psi- load screen.

Selects the *Ramp Rate* button.

ATC Enters a ramp rate.

Selects the *Pressure* button.

Enters desired target pressure.

2. Bypass Valve Jack Positioning.

Control BPV position by intermittently using the *Raise* /

• Lower* buttons until BYPASS VALVE JACK STATUS changes to *ACTIVE* AND desired cooldown rate is established.

ATC Notifies the SRO that RPV Pressure is at the target psig.

SIMULATOR OPERATOR; PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 9 Page 21 of 26 Event

Description:

RHR 2E11-F016A/B stuck closed requiring swapping to other loop of DW spray Time Position Applicant's Actions or Behavior Per the PC flowchart, verifies Torus level is <285 inches and directs an SRO operator to place Torus Sprays in service.

Sprays the Torus per 34SO-E11-010-2 placard on the 2H11-P601 Panel as follows:

Places Cnmt Spray Vlv Cntl switch in the MANUAL position.

ATC Starts RHR pump(s) in loop A/B, if NOT already running.

Opens 2E11-F028A/B.

Throttles Open 2E11-F027A/B.

Notifies SRO that RHR is in Torus Sprays.

NOTE: Only one loop of RHR will be placed in Torus Sprays. The flow is only 700 gpm.

SIMULATOR OPERATOR, ENSURE Event Triggers EGE11-4 & EGE11-5 is ACTIVATED when the operator positions 2E11-F016A or B to open.

When Torus pressure exceeds 11 psig, verifies that Torus Level is <215 inches, in the safe area of Graph 8 (DWSIL) and directs an operator to:

SRO Place all DW cooling fans to OFF.

Place both Recirc pumps to PTL OFF.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 9 Page 22 of 26 Event

Description:

RHR 2E11-F016A/B stuck closed requiring swapping to other loop of DW spray Time Position Applicant's Actions or Behavior Places both Recirc pumps to PTL OFF on panel 2H11-P602.

Places the following DW cooling fans control switches to OFF on panels 2H11-P654 & P657:

2T47-B007B, Drywell Cooling Top Head Area Unit.

2T47-B008B, Drywell Cooling Pedestal/Annular Area Unit.

2T47-B009B, Drywell Cooling Recirc Pump Area Unit.

2T47-C001B, Drywell Cooling Return Air Fan.

ATC 2T47-C002B, Drywell Cooling Return Air Fan.

2T47-B010B, Drywell Cooling EL 114 Unit.

2T47-B007A, Drywell Cooling Top Head Area Unit.

2T47-B008A, Drywell Cooling Pedestal/Annular Area Unit.

2T47-B009A ,Drywell Cooling Recirc Pump Area Unit.

2T47-C001A, Drywell Cooling Return Air Fan.

2T27-C002A, Drywell Cooling Return Air Fan.

2T47-B010A, Drywell Cooling EL 114 Unit.

When all DW cooling fans are OFF AND both Recirc pumps are PTL OFF:

SRO Directs an operator to spray the Drywell.

Sprays the Drywell per 34SO-E11-010-2 placard on the 2H11-P601 Panel as follows:

Places Cnmt Spray Vlv Cntl switch in the Manual position.

Starts RHR pump(s) in loop A (B), if NOT already running.

Opens 2E11-F021A or B.

Opens 2E11-F016A or B (ONE WILL NOT OPEN AND OPERATOR TRANSITIONS TO THE OTHER LOOP).

Informs SRO that the 2E11-F016A (or B) will NOT Open.

ATC Opens 2E11-F021A or B.

Throttles Open 2E11-F016A(B) to >5000 gpm. (Critical Task)

Critical Task is met if Drywell Sprays are placed in service while in the safe region of the Drywell Spray Initiation Limit (DSIL), prior to exceeding 340°F. (Approximately 20 minutes to 340°F)

Confirms Drywell pressure is reducing.

Notifies SRO that RHR is in Drywell Sprays.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2021-301 Scenario No.: 13-7 Event No.: 9 Page 23 of 26 Event

Description:

RHR 2E11-F016A/B stuck closed requiring swapping to other loop of DW spray Time Position Applicant's Actions or Behavior Notifies the SSS to perform actions for RHR per 31EO-EOP-114-2.

IAW 31EO-EOP-114-2, the operator performs the following:

CLOSES RHR OUTBD INJ VLV, 2E11-F017A.

CLOSES RHR OUTBD INJ VLV, 2E11-F017B.

Notifies SSS to OPEN links & INSTALL jumpers for 2E11-F017A.

Notifies SSS to OPEN links & INSTALL jumpers for 2E11-F017B.

BOP Confirms/CLOSES RHR OUTBD INJ VLV, 2E11-F017A.

Confirms/CLOSES RHR OUTBD INJ VLV, 2E11-F017B.

Confirms/CLOSES INBD DISCHARGE VLV, 2E21-F005A.

Confirms/CLOSES INBD DISCHARGE VLV, 2E21-F005B.

Trips Core Spray Pump A, 2E21-C001A.

Trips Core Spray Pump A, 2E21-C001B.

Notifies SRO 31EO-EOP-114-2 actions for RHR & CS are complete.

As time allows, directs H2/O2 Analyzers placed in service IAW SRO 34SO-P33-001-2.

If directed, places H2/O2 Analyzers in service IAW 34SO-P33-001-2 or Placard by performing the following at 2H11-P700 panel:

Confirms closed 2P33-F605.

Places 2P33-S16, LOCA Override to Bypass.

Places 2P33-S17, LOCA Override to Bypass.

ATC Confirms analyzers are running by either red analyzer lights illuminated, or values indicated on the Primary Display of SPDS.

If analyzers red light is off, depresses Channel A and Channel B Reset pushbuttons on 2H11-P700 panel.

Notifies SRO H2/O2 Analyzers are running.

With Chief Examiners Permission, the scenario should be terminated when the crew has sprayed the Drywell with the other Loop of RHR.

Page 24 of 26 Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 13-7 Op-Test No.: 2021-301 Examiners: Operators: SRO RO BOP Initiating Conditions: Unit 2 is operating at 70% RTP. 2D11-K615B, Off gas Post treatment radiation monitor, failed Downscale, RAS written. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Turnover Perform 34IT-T45-001-2, Reactor Building Instrument Sumps Isolation Valve Exercise. After complete, raise reactor power via Recirc flow to 80% RTP.

Summary:

Event 1: Normal; The BOP will perform 34IT-T45-001-2, Reactor Bldg. Instrument Sump Isolation Valve Exercise surveillance. The surveillance consists of several isolation valves being cycled to ensure they can operate. The crew should complete the surveillance with no problems.

Event 2: Instrument; The 2A CRD pump will trip due to a low suction pressure instrument failure. The ATC will be required to manually start the standby CRD pump to restore system flow & pressure.

Event 3: Instrument/TS; The HPCI Torus Level Sensor Fails High; with failure of CST valve to auto close. When BOP attempts to close the CST valve, the breaker trips (Valve overload). The breaker must be reset to allow the CST valve to close. The SRO will address the TS instrument.

Event 4: Component/TS; Recirc Pump 2B trips. The SRO addresses TS for an inoperable Recirc pump. The plant will be operating in the Region of Potential Instabilities of the Power-to-Flow map.

Event 5: Reactivity; The ATC will insert Control rods to exit the Region of Potential Instabilities.

Event 6: TS; The Backup SDV valves will close due to a small air leak on 2C11-F040 requiring the SRO declare a TS Required Action Statement.

Event 7: Component; Stator Cooling Pump 2B trips and the standby Stator Cooling pump will NOT automatically start. The operator will manually start the standby Stator Cooling pump to restore system flow/pressure to normal. (Critical Task)

Event 8: Major; Pipe leak in Drywell causing a High Drywell pressure scram.

Event 9: Component; When Torus pressure exceeds 11 psig, the operator will attempt to spray the Drywell but one RHR DW spray valve will NOT open. The other loop of RHR will be used to spray the Drywell. The first DW spray valve attempted will NOT open but the other loop of RHR DW spray valve will work. (Critical Task)

Page 25 of 26 Critical Tasks NRC FINAL Facility: E. I Hatch Scenario No.: 13-7 Op-Test No.: 2021-301 Critical Tasks Manually start the standby Stator Cooling pump to restore system flow/pressure to normal prior to Main Turbine Bypass valves opening. (Event 7)

RHR 2E11-F016A (B) is stuck closed requiring the operator to swap to other loop of RHR to spray the Drywell while in the safe region of the Drywell Spray Initiation Limit (DSIL), prior to exceeding 340°F. (Event 8)

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 6 1. CRD pump trips (Event 2)

2. HPCI Torus Level Sensor Fails (Event 3)

3. Recirc Pump 2B trips (Event 4)

4. SWC 2B trips/STBY fails auto (Event 7)

5. RWCU pipe break LOCA (Event 8)

6. 2E11-F016A(B) fails to open (Event 9)

2. Malfunctions After 1-2 1 1. 2E11-F016A(B) fails to open (Event 9)

EOP Entry

3. Abnormal Events 2-4 3 1. CRD pump trips (Event 2)

2. Recirc Pump 2B trips (Event 4)

3. SWC 2B trips/STBY fails auto (Event 7)

4. Major Transients 1-2 1 1. RWCU pipe break LOCA (Event 8)

5. EOPs entered, 1-2 2 1. RC (Non-ATWS) requiring substantive 2. PC actions

6. EOPs contingencies 0-2 0 1. NONE entered with substantive actions

7. Preidentified >2 2 1. SWC 2B trips/STBY fails auto (Event 7)

Critical Tasks 2. 2E11-F016A(B) fails to open (Event 9)

ILT-13 NRC FINAL Scenario 7 SHIFT TURNOVER Safety Focus UNIT 1 STATUS Unit 1 is operating at 100% power Plant Conditions:

Activities in progress: Maintaining Rated Thermal Power Unit 2 is operating at 70% RTP.

2D11-K615B, Off gas Post treatment radiation monitor, failed Plant Conditions:

Downscale, RAS written.

2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Protected Train: EOOS:

Division I Green Orange Division II Yellow Red Scheduled evolutions: Perform 34IT-T45-001-2, Reactor Building Instrument Sumps Isolation Valve Exercise.

After complete, raise reactor power via Recirc flow to 80% RTP.

Surveillances due this NONE shift:

Inop Equipment: 2D11-K615B, Off gas Post Treatment Radiation monitor has failed Downscale. IAW TS/TRM, I&C has placed 2D11-K615B in the trip condition while maintaining the function of 602-405, Post Treatment O/G Radiation Hi-Hi-Hi/Inop. A Caution Tag is attached to 2D11-K615B switch.

2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Active tagouts: NONE Rod Configuration: See RWM Step 25

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 1 (ALL)

Title START A RECIRC ADJUSTABLE SPEED DRIVE (ASD) FROM THE CONTROL ROOM (ALTERNATE PATH)

Author: Media Number: Time Anthony Ball 2021-301 CR-SIM 1 15.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

Reviewed by Instructional Technologist or designee Date Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 CR-SIM 1 Page 2 of 12 Course Number Program Name Media Number OPERATIONS TRAINING 2021-301 CR-SIM 1 Ver. No. Date Reason for Revision Author Print Peer Review Initials/Name Print Initials/Name 21.3 2/9/2021 Updated for ILT-13 NRC Exam 2021-301. ARB JDW

2021-301 CR-SIM 1 Page 3 of 12 UNIT 1 () UNIT 2 (X)

TASK TITLE: START A RECIRC ADJUSTABLE SPEED DRIVE (ASD) FROM THE CONTROL ROOM (ALTERNATE PATH)

JPM NUMBER: 2021-301 CR-SIM 1 TASK STANDARD: This task shall be successfully completed when all of the JPM Critical Steps corresponding to 34SO-B31-001-2, Section 4.15, have been correctly performed to start Recirc Pump 2A and then secured.

TASK NUMBER: 004.002 OBJECTIVE NUMBER: 004.002.A, 004.002.E PLANT HATCH JTA IMPORTANCE RATING:

RO 3.50 SRO 3.22 K/A CATALOG NUMBER: 202001K6.02 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.1 SRO 3.2 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 2 34SO-B31-001-2 (Ver. 47.2) 34AB-B31-001-2 (current version)

REQUIRED MATERIALS: Unit 2 34SO-B31-001-2 (Ver. 47.2) marked up to step 4.1.5.10 APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

2021-301 CR-SIM 1 Page 4 of 12 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to IC #102 or Snap 611 and leave in FREEZE.

2. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS OR RUN SCENARIO FILE and EVENT TRIGGER (current rev) 2021-301 CR-SIM 1:

A. Secure both Recirc Pumps and Close their Discharge valves B. Raise RWL to >47 inches as indicated on GEMAC.

C. Use rfB31_29 and open Seal purge valve B31-F016A.

D. Open Reactor Recirc Pump Suction Valves, 2B31-F023A and 2B31-F023B.

E. Start up the 2A Recirc ASD up to step 4.1.5.10, with the breaker closed for the ASD, the ASD START pushbutton lit, and RWL > 32.

F. Have a Marked up copy of 34SO-B31-001-2, Recirc system, marked up to step 4.1.5.10.

G. TURN OFF THE SPDS SCREENS.

H. Acknowledge/Reset annunciators

3. INSERT the following Event Trigger:

ET # Description EGB31-1 Inserts the following alarms when F031A is fully open (GREEN light goes out):

ASD A - Cooling Normal (White Light Off)

ASD A Cooling System Pump 1 Trip ASD A Cooling System Pump 2 Trip Event Trigger Contents:

(ET portion of ET)

Activate ET B31-1 when 2A Recirc pump discharge valve is full open (GREEN light out) loB31-F031AG1.algToPanel =0

THEN (SCN Portion of ET)

+10 IOR loB31-DS42AW1 f:0 d:0; IMF mfB31_166A f:1 d:0,

+10 IMF mfB31_166C f:1 d:0

4. PLACE the Simulator in FREEZE until the INITIATING CUE is given.

5. ESTIMATED Simulator SETUP TIME: 15 Minutes

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is in cold shutdown

2. SPDS is Out of Service and being worked.

3. A Recirc Pump is required for forced circulation.

4. CRD seal purge is in service with 1.9 gpm flow to the A seals.

5. Maintenance has performed all applicable sections for venting/purging of the A Recirc Pump seals IAW 52CM-B31-003-0.

6. A Systems Operator is in the field to monitor startup of ASD A

7. 34SO-B31-001-2, Recirc system, is complete up to step 4.1.5.10.

8. 34SO-B31-001-2 Attachment 5 Recirc Pump Startup Prerequisites, was just completed and is SAT for a start of the A Recirc Pump.

9. Visual checks of step 4.1.5.14 are SAT.

INITIATING CUES:

Start 2A Recirc Pump IAW 34SO-B31-001-2, Reactor Recirculation System, Section 4.1.5, starting at step 4.1.5.10.

2021-301 CR-SIM 1 Page 6 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

START TIME:__________

NOTE: Unless otherwise indicated, all actions are carried out at Panel 2H11-P601.

PROMPT: PROVIDE the applicant with a copy of 34SO-B31-001-2, Recirc system, marked up to step 4.1.5.10.

1. Operator obtains procedure and Operator has obtained 34SO-B31-reviews the procedures precautions 001-2 and reviewed the and limitations. precautions and limitations.

NOTE: RWL indication on 2H11-P603 is not corrected. The operator must subtract 15 inches from the indicated RWL. Therefore, RWL is required to be above 47 inches (32 + 15 = 47).

2. Check RWL is greater than +32 At panel 2H11-P603, the inches. (step 4.1.5.10) Operator CHECKS that RWL is greater than +32 inches actual level (> 47 inches indicated).

(** Indicates critical step)

2021-301 CR-SIM 1 Page 7 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

PROMPT: IF asked by the Operator about completion of Attachment 5, INFORM the Operator to refer to your Initial Conditions.

3. Check Closed Reactor Recirc Pump Operator checks PUMP DISCH Discharge Valve, 2B31-F031A. VLV 2B31-F031A is CLOSED, (step 4.1.5.12) GREEN light illuminated.

4. Check ASD A START pushbutton Operator checks ASD A START indicating lamp is illuminated. pushbutton indicating lamp is (step 4.1.5.13) illuminated.

5. Visually Check the ASD A startup Operator checks the ASD A temperature limits are still acceptable. startup temperature limits are still (step 4.1.5.14) acceptable by observing temperatures on 2B31-R601 at Panel 2H11-P614.

PROMPT: WHEN the operator states checking Attachment 5 (checking startup temperatures), INFORM the applicant to refer to your Initial Conditions.

• • 6. DEPRESS the ASD A START Operator depresses ASD A pushbutton. (step 4.1.5.14) START PUSH BUTTON.

7. Check the following: Operator checks the following:

The ASD A STARTING light The ASD A STARTING light illuminates. (step 4.1.5.14.a) illuminates.

The ASD A START light The ASD A START light extinguishes. (step 4.1.5.14.b) extinguishes.

2B31-F031A, Recirc Pump A 2B31-F031A, Recirc Pump A Disch Vlv, starts to JOG OPEN 2 Disch Vlv, starts to JOG seconds after the ASD A OPEN 2 seconds after the STARTING light illuminates. ASD A STARTING light (step 4.1.5.14.c) illuminates.

(** Indicates critical step)

2021-301 CR-SIM 1 Page 8 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

The ASD A speed increases to The ASD A speed increases to

~370 RPM on 2B31-R660A and ~370 RPM on 2B31-R660A

~22% on 2B31-R661A in about 4 and ~22% on 2B31-R661A in seconds. (step 4.1.5.14.d) about 4 seconds.

The ASD A RUNNING light The ASD A RUNNING light illuminates. (step 4.1.5.14.e) illuminates.

The ASD A STARTING light The ASD A STARTING light extinguishes. (step 4.1.5.14.f) extinguishes.

2B31-F031A, Recirc Pump A 2B31-F031A, Recirc Pump A Disch Vlv, is FULL OPEN <96 Disch Vlv, is FULL OPEN seconds after the Recirc ASD A <96 seconds after the Recirc STARTING light illuminates. ASD A STARTING light (step 4.1.5.14.g) illuminates.

Recirc A Flow, indicates 11,000 - Recirc A Flow, indicates 13,000 GPM on 2B31-R617. 11,000 - 13,000 GPM on (step 4.1.5.14.h) 2B31-R617.

Acknowledge expected alarms Acknowledges expected alarm 602-227, Recirc Loop B Out Of Service PROMPT: WHEN the operator addresses Attachment 5, INFORM the operator that another operator will complete Attachment 5.

NOTE: This step may not be done due to the cooling and fault alarms coming in on the ASD.

8. Complete remainder of Attachment 5. Operator has verified Attachment (step 4.1.5.15) 5 will be completed.

THE ALTERNATE PATH WILL START HERE SIMULATOR OPERATOR: Confirm Event Trigger EGB31-1 ACTIVATES when the GREEN light extinguishes on 2B31-F031A.

NOTE: The following cooling fault automatically occurs based on 2B31-F031A being full open.

(** Indicates critical step)

2021-301 CR-SIM 1 Page 9 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

9. Respond to annunciators: Operator enters associated ARP.

ASD A TRIP WARNING, 602-101 Operator contacts local SO to check for proper operation of the ASD A TROUBLE, 602-108 ASD A Cooling System.

ASD A COOLING TROUBLE, 602-125 SIMULATOR OPERATOR AFTER one minute, INFORM the operator that ASD A cooling water pumps are off and cannot be started.

SIMULATOR OPERATOR AFTER one minute, INFORM the operator that ASD A Transformer Overtemp High and ASD A Transformer Overtemp Very High annunciators are alarmed NOTE: The Operators may enter 34SO-B31-001-2, Section 4.2.3 early and place ASD A control switch 2B31-S002A in the PULL TO LOCK, position on 2H11-P602 as a conservative action.

(** Indicates critical step)

2021-301 CR-SIM 1 Page 10 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

10. ASD A TRIP WARNING, Operator enters associated ARP.

602-101

• • 11. ASD A TRIP WARNING, Enters 34SO-B31-001-2, Section 602-101 (continued) (step 5.2) 4.2.3 and performs one or both of OR the following:

ASD A COOLING FAULT 4.2.3.1.a 602-126 places ASD A control switch 2B31-S002A to the STOP/PULL TO LOCK, position 4.2.3.2.a depresses ASD A Shutdown pushbutton on 2H11-P602.

PROMPT: WHEN the operator addresses entering 34AB-B31-001-2, INFORM the operator that another operator will take the actions.

END TIME:__________

NOTE: The terminating cue shall be given to the Operator when:

Operator completes step 11 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator has tripped or shutdown ASD A.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

2021-301 CR-SIM 1 Page 11 of 12 Summary of JPM Attributes JPM 2021-301 CR-SIM 1:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical At least 2 2 Steps Step 6 Depress ASD start push button Starts ASD.

Step 11 ASD control switch to Pull to Lock Shuts down ASD to protect from loss of cooling OR ASD A Shutdown pushbutton Number of JPM Steps

<30 11 Time to Perform JPM <45 min 15 min Normal / Faulted /

Alternate Path Alternate Path Once ASD Cooling Trouble and ASD Cooling Fault alarms initiates directing an ASD shutdown IAW 34SO-B31-001-2.

Setting (administered)

Simulator Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is in cold shutdown

2. SPDS is Out of Service and being worked.

3. A Recirc Pump is required for forced circulation.

4. CRD seal purge is in service with 1.9 gpm flow to the A seals.

5. Maintenance has performed all applicable sections for venting/purging of the A Recirc Pump seals IAW 52CM-B31-003-0.

6. A Systems Operator is in the field to monitor startup of ASD A

7. 34SO-B31-001-2, Recirc system, is complete up to step 4.1.5.10.

8. 34SO-B31-001-2 Attachment 5 Recirc Pump Startup Prerequisites was just completed and is SAT for a start of the A Recirc Pump.

9. Visual checks of step 4.1.5.14 are SAT.

INITIATING CUES:

Start 2A Recirc Pump IAW 34SO-B31-001-2, Reactor Recirculation System, Section 4.1.5, starting at step 4.1.5.10.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 2 (ALL)

Title:

Perform a Manual RCIC Startup, Failed Controller High (Alternate Path)

Author: Media Number: Time:

Anthony Ball 2021-301 CR-SIM 2 9 Minutes Line Review By (Print) Date:

N/A N/A Reviewed by Instructional Technologist or designee (Print) Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 CR-SIM 2 Page 2 of 11 Course Number Program Name Media Number N/A OPERATIONS TRAINING 2021-301 CR-SIM 2 Ver. No. Date Reason for Revision Author Print Peer Review Initials/Name Print Initials/Name Updated JPM to latest version of references & use 1.0 2/9/2021 ARB JDW on ILT-13 NRC Exam.

2021-301 CR-SIM 2 Page 3 of 11 UNIT 1 () UNIT 2 (X)

TASK TITLE: Perform a Manual RCIC Startup, Failed Controller High (Alternate Path)

JPM NUMBER: 2021-301 CR-SIM 2 TASK STANDARD: The task shall be completed when the RCIC system is manually started and the flow controller is taken to manual to control injection. RCIC injection must be controlled to maintain RWL below the elevation of the MSLs (+111 inches).

TASK NUMBER: 039.002 OBJECTIVE NUMBER: 039.002.A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.36 SRO 2.93 K/A CATALOG NUMBER: 217000A4.01 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.9 SRO 3.9 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 Unit 2 NA 34SO-E51-001-2, Ver 28.1 REQUIRED MATERIALS: Unit 1 Unit 2 NA 34SO-E51-001-2 (current version)

APPROXIMATE COMPLETION TIME: 9 Minutes SIMULATOR SETUP: Refer to simulator setup sheet on the following page.

2021-301 CR-SIM 2 Page 4 of 11 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to IC# 113 (100% RTP) and leave in FREEZE.

2. ACTIVATE the following EVENT TRIGGERS:

Trigger # Description Conditions Expert Command

+10 IMF mfE51_111 EGE51-14 Runs when 2E51-F013 > 50% OPEN. rcv013>0.50 f:1 d:10 r:500

3. INSERT the following MALFUNCTIONS:

Activator MALF # TITLE FINAL RAMP VALUE RATE ST-0 mfB21_132 ADS Failure to Initate ST 0 mfC11_30A CRD Pump 2A trip ST 0 mfC11_30B CRD Pump 2B trip ST 0 mfE41_107 HPCI Failure to Start ST 0 mfE51_109 RCIC Failure to Auto Start ST 0 mfN21_87A Feedwater Pump A Trip ST 0 mfN21_87B Feedwater Pump B Trip

4. INSERT the following REMOTE FUNCTIONS:

Activator REM # Description Status ST 0 rfE51154 RCIC High Water Level Bypass BYPASS ST 0 rfE51155 RCIC Torus Suction Bypass BYPASS

5. INSERT the following ORS OVERRIDES:

Activator TAG # DESCRIPTION STATUS ST 0 diE51-S33 S RCIC Manual Initiation OFF

2021-301 CR-SIM 2 Page 5 of 11

6. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS OR RUN SCENARIO FILE and EVENT TRIGGER (current rev) 2021-301 CR-SIM 2:

A. Place MSIV control switches in close.

B. Allow simulator to run until RWL as indicated on 2B21-R623A and B is approximately -2 inches.

C. Ensure the RCIC flow controller is showing actual flow and NOT the setpoint.

D. Acknowledge annunciators.

7. PLACE the Simulator in FREEZE until the INITIATING CUE is given.

8. ESTIMATED Simulator SETUP TIME: 10 Minutes

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. The RCIC System is in a Standby Lineup.

2. RWL is lowering and RCIC is required for RWL control.

3. 31EO-EOP-010-2 (RC) is in progress and the Torus high level suction transfer logic has been defeated.

4. You are RC-2 and RC-3.

5. Pre-Job Brief is NOT required.

INITIATING CUES:

Start RCIC manually and inject to the Reactor to restore and maintain RWL between +3 to +50 inches.

2021-301 CR-SIM 2 Page 7 of 11 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

Start Time:_________

NOTE: The JPM steps are written based on the RCIC Startup Placard. The student may elect to use the body of 34SO-E51-001-2 which is acceptable.

1. Depress RCIC Manual Initiation At 2H11-P602, the Operator P/B. DEPRESSES the RCIC MANUAL INITIATION push-button. (NO response)

(Attachment 5, step 1)

2. ENSURE OPEN 2E51-F046. At 2H11-P602, the Operator OPENS Turb Cool Water Vlv (Attachment 5, step 2) 2E51-F046, red light illuminated.

3. ENSURE OPERATING / START At 2H11-P602, the Operator Barom Cndsr Vac Pmp. STARTS the Barom Cndsr Vac Pump, 2E51-C002-2, red light (Attachment 5, step 3) illuminated.

• • 4. ENSURE OPEN 2E51-F045. At 2H11-P602, the Operator OPENS 2E51-F045, Steam To (Attachment 5, step 4) Turb Vlv, red light illuminated.

(** Indicates critical step)

2021-301 CR-SIM 2 Page 8 of 11 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

5. ENSURE OPEN 2E51-F019. At 2H11-P602, the Operator ENSURES Min Flow Vlv 2E51-(Attachment 5, step 5) F019 is open, red light illuminated.

• • 6. ENSURE OPEN 2E51-F013. At 2H11-P602, the Operator OPENS Pump Discharge Valve, (Attachment 5, step 6) 2E51-F013, red light illuminated.

7. ENSURE CLOSE 2E51-F019 at flow At 2H11-P602, the Operator

> 79.3 gpm. ENSURES Min Flow Vlv 2E51-(Attachment 5, step 7) F019, is closed, green light illuminated.

ALTERNATE PATH starts here (recognize Flow Controller failure - speed above rated).

• • 8. ADJUST controller for desired flow. At 2H11-P602, the Operator RECOGNIZES 2E51-R612 has failed upscale allowing RCIC to (Attachment 5, step 8) operate beyond rated flow and PLACES controller in Manual.

• • 9. ADJUST controller for desired flow. At 2H11-P602, the Operator LOWERS 2E51-R612 output to (Attachment 5, step 8) control RWL between +3 and

+111 inches.

NOTE: SRV cycling may cause RWL momentarily being outside the desired band.

PROMPT: AFTER the Operator is controlling RCIC in Manual and RWL is within +3 and +50 inches, THE EVALUATOR MAY end the JPM by telling the Operator, Well Stop Here.

PROMPT: IF the Operator addresses 34SO-E51-001-2, INFORM the Operator that another operator will address this procedure.

PROMPT: IF the Operator addresses shifting from RWL control to pressure control, as the Shift Supervisor, INFORM the Operator this is not desired at this time.

(** Indicates critical step)

2021-301 CR-SIM 2 Page 9 of 11 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

PROMPT: IF the Operator addresses posting High Radiation Areas, as the Shift Supervisor, INFORM the Operator that Radiation Protection is posting the areas.

END TIME: _________

NOTE: The terminating cue shall be given to the operator when any of the following conditions exist:

Operator completes step 9 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

2021-301 CR-SIM 2 Page 10 of 11 Summary of JPM Attributes JPM: 2021-301 CR-SIM 2

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 4 Step 4 Opens 2E51-F045 Operator opens 2E51-F045 to supply steam to RCIC.

Step 6 Opens 2E51-F013 Operator opens 2E51-F013 to allow injection to the RPV.

Step 8 Controller in manual Operator places Controller in MANUAL to control RCIC flow.

Step 9 Lower RCIC flow Operator manually lowers Controller output to reduce RCIC flow to maintain RWL in band and not above the Main Steam Lines.

Number of JPM Steps <30 9 Time to Perform JPM <45 min 9 min Normal / Faulted /

Alternate Path Alternate Path RCIC does not start with the manual initiation pushbutton and requires manual Operator action to start. Once started, the RCIC flow controller fails requiring the Operator to place the controller in manual and adjust flow.

Setting (administered)

Simulator Is LOD 1 or 5 NO NO Page 10 of 11

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. The RCIC System is in a Standby Lineup.

2. RWL is lowering and RCIC is required for RWL control.

3. 31EO-EOP-010-2 (RC) is in progress and the Shift Support Supervisor has defeated the Torus high level suction transfer logic.

4. You are RC-2 and RC-3.

5. Pre-Job Brief is NOT required.

INITIATING CUES:

Start RCIC manually and inject to the Reactor to restore and maintain RWL between +3 to +50 inches.

Page 11 of 11

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 3 (ALL)

Title Reactor Pressure Control Within Band With BPVs & SRVs Author: Media Number Times Anthony Ball 2021-301 CR-SIM 3 10.0 Minutes Line Review By: Date N/A N/A Reviewed by Instructional Technologist or designee: Date N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 CR-SIM 3 Page 2 of 12 Course Number Program Name Media Number N/A OPERATIONS TRAINING 2021-301 CR-SIM 3 Author Print Peer Review Ver. No. Date Reason for Revision Initials/Name Print Initials/Name 00 5/26/11 Initial development for use on 2011-301 NRC Exam. ARB CME Updated JPM to latest version of references & use on 0.1 2/9/2021 ILT-13 NRC Exam, added EGN32-7 which replaces ARB JDW RB-1 & 2.

UNIT 1 () UNIT 2 (X)

TASK TITLE: Reactor Pressure Control Within Band With BPVs &

SRVs JPM NUMBER: 2021-301 CR-SIM 3 TASK STANDARD: The operator is controlling Reactor pressure in a band (without exceeding 100°F cooldown rate) using SRVs/BPVs per 34SO-B21-001-2.

TASK NUMBER: 200.034 OBJECTIVE NUMBER: 200.034.C PLANT HATCH JTA IMPORTANCE RATING:

RO SRO K/A CATALOG NUMBER: 239002A4.01 K/A CATALOG JTA IMPORTANCE RATING:

RO 4.4 SRO 3.20 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 2 34SO-N30-001-2 (current version) 34SO-B21-001-2 (current version)

REQUIRED MATERIALS: Unit 2 34SO-N30-001-2 (current version) 34SO-B21-001-2 (current version)

APPROXIMATE COMPLETION TIME: 10.0 Minutes SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

2021-301 CR-SIM 3 Page 4 of 10 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to IC #113 or Snap 613 and leave in FREEZE.

2. INSERT the following MALFUNCTIONS and OVERRIDES:

KEY MALF # DESCRIPTION FINAL RAMP DELAY ST-0 mfB21_129A SRV A Fails Stuck 0000 ST-0 mfB21_129B SRV B Fails Stuck 0000 ST-0 mfB21_129C SRV C Fails Stuck 0000 ST-0 mfB21_129D SRV D Fails Stuck 0000 ST-0 mfB21_129E SRV E Fails Stuck 0000 ST-0 mfB21_129F SRV F Fails Stuck 0000 ST-0 mfB21_129G SRV G Fails Stuck 0000 ST-0 mfB21_129H SRV H Fails Stuck 0000 ST-0 mfB21_129K SRV K Fails Stuck 0000 ST-0 mfB21_129L SRV L Fails Stuck 0000 ST-0 mfB21_129M SRV M Fails Stuck 0000 ST-0 mfE41_104 HPCI Turbine Trip 0000 ST-0 mfE51_110 RCIC Turbine Trip 0000 ST-0 mfN21_87A Feedwater Pump A Trip 0000 ST-0 mfB21_226A Low-Low Set A Fails Inop 0000 ST-0 mfB21_226B Low-Low Set B Fails Inop 0000 ST-0 mf60131129 Leak Det Diff Temp Hi 0000 ST-0 mf60131135 Leak Ambient Temp Hi 0000

2021-301 CR-SIM 3 Page 5 of 10

3. INSERT the following SIMULATOR VALUE OVERRIDES (SVO):

FINAL RAMP Activator SVO # DESCRIPTION DELAY VALUE RATE ST-0 svoB21053 PT-N127A SRV Electrical open 1000 1000 0000 ST-0 svoB21054 PT-N127B SRV Electrical open 1000 1000 0000 ST-0 svoB21055 PT-N127C SRV Electrical open 1000 1000 0000 ST-0 svoB21056 PT-N127D SRV Electrical open 1000 1000 0000

4. INSERT the following EVENT TRIGGERS:

Trigger # DESCRIPTION CONDITIONS Expert Command EGB21-21 SRV B Stuck, opens when control switch is in OPEN EGB21-22 SRV G Stuck, opens when control switch is in OPEN EGB21-23 SRV F Stuck, opens when control switch is in OPEN EGB21-24 SRV D Stuck, opens when control switch is in OPEN EGN32-7 ~797 psig, inserts mfN37_134, ALL BPVs fail closed,

+20 inserts diN32-C001A & C001B, BOTH EHC pumps fail

5. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS OR RUN SCENARIO FILE and EVENT TRIGGER (current rev) 2021-301 CR-SIM 3:

A. Perform RC-1 and RC-2 actions such that the 2N21-F110 is closed and the SULCV is in auto and set at +20.

B. Perform TC-1; ensuring 2N11-F004A and B are closed.

C. Lower Pressure Set to 825 psig.

D. Ensure Reactor pressure stabilizes at ~825 psig.

E. Ensure Bypass Valve screen and Speed screen is called up.

F. Place Pressure in the P603 plasma display.

G. Ensure Ramp rate is set at 10.

5. PLACE the Simulator in FREEZE until the INITIATING CUE is given.

6. ESTIMATED Simulator SETUP TIME: 15 minutes

2021-301 CR-SIM 3 Page 6 of 12 EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 Reactor has been scrammed.

2. Other operators are performing scram actions.

3. A Reactor pressure reduction is required due to an unisolable steam leak in the Reactor Building.

4. You are assigned Reactor Pressure control.

INITIATING CUES:

LOWER AND THEN MAINTAIN Reactor pressure between 700 and 800 psig using the Bypass Valves.

2021-301 CR-SIM 3 Page 7 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

START TIME:__________

1. Operator identifies the procedure Operator has obtained procedure needed to perform the task. 34GO-OPS-013-2, step 7.5.5 or uses Placard at Turbine Panel.

NOTE: For Steps 2 through 8 all indication will be on panel 2H11-P650 using HMI Screens 2N32-K4001A or B.

2. Selects *Control* / *psi-load* The operator has SELECTED the screen *Control* screen and also has SELECTED the *psi-load*

button on 2N32-K4001A or B.

3. Selects *Ramp Rate* button The operator has SELECTED the

• Ramp Rate* button on 2N32-K4001A or B.

NOTE: An acceptable Ramp Rate results in a cooldown rate NOT exceeding 100ºF/hr OR RWL exceeding 100 inches.

• • 4. Enters a ramp rate The operator has ENTERED a ramp rate >0 and <100 displayed on 2N32-K4001A or B.

• • 5. Selects *Pressure* button The operator has SELECTED the

• Pressure* button on 2N32-K4001A or B.

• • 6. Enters desired target pressure The operator has ENTERED a target pressure between 700 and 800 psig on 2N32-K4001A or B.

(** Indicates critical step)

2021-301 CR-SIM 3 Page 8 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 7. Adjusts *Ramp Rate* AND/OR the The operator has VARIED the

• Pressure* setpoints to maintain ramp rate/pressure to maintain a pressure/cooldown rate. cooldown rate 100° F/Hr OR RWL exceeding 100 inches change on 2N32-K4001A or B.

ALTERNATE PATH STARTS HERE NOTE: SIMULATOR OPERATOR, WHEN the operator has successfully opened Bypass Valves (BPVs) and RPV pressure is being reduced

(~797 psig), ENSURE Event Trigger, EGN32-7, inserts malfunctions which FULLY CLOSES ALL Bypass Valves & 20 seconds later TRIPS BOTH EHC Pumps.

8. The failure of ALL BPVs is Operator identifies all BPVs recognized. closed on 2N32-K4001A or B.

EXAMINER NOTE: IF the operator addresses using other systems to control Reactor pressure, INFORM the operator to use SRVs.

PROMPT: IF the operator reports the failure of the BPVs, INFORM the operator that you will get Maintenance to investigate, and to continue control Reactor pressure in the band.

PROMPT: IF the operator addresses the failure of EHC Pumps, INFORM the operator that you will get Maintenance to investigate, and to continue control Reactor pressure in the band.

PROMPT: IF alarm 650-124, Max Combined Flow Limit Limiting, is received, INFORM the operator that another operator will address the ARP.

NOTE: The operator can use any of the following procedures to control reactor pressure:

Placard on 2H11-P602 panel 34SO-B21-001-2, Automatic Depressurization (ADS) And Low-Low Set (LLS) Systems

(** Indicates critical step)

2021-301 CR-SIM 3 Page 9 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

9. Operator identifies applicable Operator has IDENTIFIED the procedures to perform the task. correct procedure as:

Placard on 2H11-P602 panel 34SO-B21-001-2, step 7.4.1.

PROMPT: IF the operator addresses using the Placard sequence for opening the SRVs, DIRECT the operator to follow the procedure.

NOTE: ALL SRVs, EXCEPT LLS SRVs, fail to open with the switch.

10. Attempts to OPEN SRV At Panel 2H11-P602, the operator 2B21-F013M. has PLACED the control switch for 2B21-F013M into the OPEN position, red light ILLUMINATES.

11. The failure of the 2B21-F013M to At 2H11-P602, the operator has open is recognized. RECOGNIZED the failure of the 2B31-F013M to OPEN, amber light remains EXTINGUISHED.

PROMPT: IF the operator reports the failure of the 2B21-F013M to open, INFORM the operator that you will get Maintenance to investigate, and to continue control Reactor pressure in the band.

NOTE: LLS will NOT arm with Reactor pressure >1074 psig.

• • 12. OPEN SRV 2B21-F013B At Panel 2H11-P602, the operator has PLACED the control switch for 2B21-F013B into the OPEN position prior to 1250 psig, red light ILLUMINATED.

PROMPT: IF the operator addresses checking SRV tailpipe temperature on recorder 2B21-R614, at Panel 2H11-P614, INFORM the operator that another operator will check the recorder for proper SRV operation.

(** Indicates critical step)

2021-301 CR-SIM 3 Page 10 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 13. Reactor pressure in band: The operator CONTROLS 700 to 800 psig pressure in band:

700 to 800 psig (50 psig)

• • 14. Before Reactor lowers below 700 At panel 2H11-P602, the operator psig, CLOSE SRV 2B21-F013B. has PLACED the control switch for 2B21-F013B into the CLOSE position PRIOR to Reactor pressure lowering to the point of exceeding >100°F cooldown rate, green light ILLUMINATED.

NOTE: AFTER the operator has demonstrated proper control of Reactor pressure, INFORM the operator that another operator will continue maintaining Reactor pressure in band.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when any one of the following is met:

After JPM step #14 is complete.

With no reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR - PICK UP the Initiating Cue sheet.

(** Indicates critical step)

2021-301 CR-SIM 3 Page 11 of 12 Summary of JPM Attributes JPM 2021-301 CR-SIM 3:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 6 Step 4 Enters a ramp rate Sets pressure reduction rate Step 5 Selects *Pressure* button Selects controlled parameter Step 6 Enters desired target pressure Selects target pressure Step 7 Adjusts *Ramp Rate* and/or the *Pressure* Control cooldown rate < 100°F Step 12 Open SRV 2B21-F013B Begins pressure reduction Step 14 Close SRV 2B21-F013B Stops pressure reduction PRIOR to Reactor pressure lowering to the point of exceeding

>100°F cooldown rate Number of JPM Steps <30 14 Time to Perform JPM <45 min 20 min Normal / Faulted /

Alternate Path Alternate Path The operator has successfully opened Bypass Valves (BPVs) and reactor pressure is being reduced, ALL Bypass Valves FULLY CLOSES requiring controlling pressure via SRVs.

Setting (administered)

Simulator Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 Reactor has been scrammed.

2. Other operators are performing scram actions.

3. A Reactor pressure reduction is required due to an unisolable steam leak in the Reactor Building.

4. You are assigned Reactor Pressure control.

INITIATING CUES:

LOWER AND THEN MAINTAIN Reactor pressure between 700 and 800 psig using the Bypass Valves.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 4 (ALL)

Title SDC Temperature Adjustment - Manual Initiation Of LPCI From SDC (ALT Path)

Author: Media Number Times Anthony Ball 2021-301 CR-SIM 4 15.0 Minutes Line Review By: Date N/A N/A Reviewed by Instructional Technologist or designee: Date N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 CR-SIM 4 Page 2 of 11 SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 1 of 1 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code: OPERATIONS TRAINING Media Number: 2021-301 CR-SIM 4 Author Print Peer Review Ver. No. Date Reason for Revision Initials/Name Print Initials/Name 1.0 2/9/2021 New JPM for 2021-301 CR-SIM 4 for ILT-13 NRC ARB JDW Exam.

2021-301 CR-SIM 4 Page 1 of 12 UNIT 1 ( ) UNIT 2 (X)

TASK TITLE: SDC Temperature Adjustment - Manual Initiation Of LPCI From SDC (ALT Path)

JPM NUMBER: 2021-301 CR-SIM 4 TASK STANDARD: The task shall be completed when RPV coolant temperature starts lowering and then the RHR loop previously in the shutdown cooling mode is aligned for LPCI, with both pumps running and injecting to the Reactor at approximately 17,000 gpm, as indicated on 2E11-R603A, per 34SO-E11-010.

TASK NUMBER: 006.008 OBJECTIVE NUMBER: 006.008.O PLANT HATCH JTA IMPORTANCE RATING:

RO 4.33 SRO 3.76 K/A CATALOG NUMBER: 203000A405 K/A CATALOG JTA IMPORTANCE RATING:

RO 4.30 SRO 4.10 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)/Senior Reactor Operator (SRO)

GENERAL

REFERENCES:

Unit 2 34SO-E11-010-2 (current version)

REQUIRED MATERIALS: Unit 2 34SO-E11-010-2 (current version)

APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

2021-301 CR-SIM 4 Page 2 of 12 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to SNAP 614 OR IC #102 and leave in FREEZE.

2. INSERT the following MALFUNCTIONS:

KEY MALF # DESCRIPTION FINAL RAMP DELAY ST-0 mfE11_115B RHR Pump B Trip 0000 ST-0 mfE11_115D RHR Pump D Trip 0000 ST-0 mfE11_202B RHR LOCA Signal Failure ST-0 mfE21_202A LOCA Signal Failure ST-0 mf60131129 Leak Det Diff Temp Hi 0000 ST-0 mf60131135 Leak Ambient Temp Hi 0000 EGE11-30 mfB31_210B Recirc Loop B Suction Rupture 1.0 100 9999

3. INSERT the following ORS OVERRIDES:

KEY# TAG # P/L DESCRIPTION STATUS ST-0 diE21-C001A P Core Spray Pmp 1A STOP ST-0 diE21-C001B P Core Spray Pmp B STOP ST-0 diE11-F007A P Min Flow Bypass Valve CLOSE ST-0 diE11-F028A P RHR A Torus Spray/Test Vlv CLOSE ST-0 diE11-F016A P Contmt Spray Outboard Drywell CLOSE ST-0 loE11-F007AG1 L Min Flow Bypass Valve OFF ST-0 loE11-F007AR2 L Min Flow Bypass Valve OFF ST-0 loE11-F028AG1 L RHR A Torus Spray/Test Vlv OFF ST-0 loE11-F028AR2 L RHR A Torus Spray/Test Vlv OFF ST-0 loE11-F016AG1 L Contmt Spray Outboard Drywell OFF ST-0 loE11-F016AR2 L Contmt Spray Outboard Drywell OFF

(** Indicates critical step)

2021-301 CR-SIM 4 Page 3 of 12

4. INSERT the following REMOTE FUNCTIONS:

REM # DESCRIPTION STATUS rfE11_22 2E11-F015A/B Override Jumper And Links Override

5. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS OR RUN SCENARIO FILE and EVENT TRIGGER (current rev) 2021-301 CR-SIM 4:

A. Place RHR Loop A into Shutdown Cooling.

B. Stabilize RPV pressure at 100 PSIG.

C. Acknowledge annunciators.

6. PLACE the Simulator in FREEZE until the crew assumes the shift.

7. PLACE STATUS TAGS on the following equipment:

MPL # COMPONENT TAGGED POSITION 2E11-F007A Min Flow Bypass Valve CLOSED 2E11-F028A Torus Spray Or Test Vlv CLOSED 2E11-F016A Cmt Spray Outboard Vlv CLOSED

8. ESTIMATED Simulator SETUP TIME: 20 Minutes

(** Indicates critical step)

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is shutdown.

2. RPV pressure is 100 PSIG and slowly rising.

3. RHR loop 2A is in the Shutdown Cooling mode with RHR Pump 2A in service.

4. Both Core Spray System Pumps are inoperable.

5. HPCI and RCIC are isolated.

6. RHR Pumps 2B and 2D are inoperable.

INITIATING CUES:

IAW 34SO-E11-010-2, RHR System, Section 4.2.3, step 82, lower and maintain RPV pressure between 80 PSIG to 90 PSIG.

2021-301 CR-SIM 4 Page 5 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

START TIME:__________

NOTE: JPM Steps 1 - 3 may be performed in any order and the operator may perform more one of the following as needed to reduce RPV coolant temperature.

• • 1. WHILE maintaining RHR Loop A At panel 2H11-P601, the flow rate of 6200 to 8200 GPM, following valve is throttled in the establish a rise OR reduction in the OPEN direction, cooling rate as required to obtain/maintain the desired coolant AND/OR RPV temperature(s) as (2E11-F003A), Hx Outlet Vlv.

specified by Shift Supervisor, by manipulating one OR a combination of the following MOVs:

2E11-F003A, Hx Outlet Vlv.

(OPEN to raise cooling; CLOSE to reduce cooling).

34SO-E11-010-2, (4.2.3.82.a).

(** Indicates critical step)

2021-301 CR-SIM 4 Page 6 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 2. WHILE maintaining RHR Loop A At panel 2H11-P601, the flow rate of 6200 to 8200 GPM, following valve is throttled in the establish a rise OR reduction in the CLOSE direction, cooling rate as required to obtain/maintain the desired coolant AND/OR RPV temperature(s) as 2E11-F048A, Hx Bypass Vlv.

specified by Shift Supervisor, by manipulating one OR a combination of the following MOVs:

2E11-F048A,Hx Bypass Vlv, (CLOSE to raise cooling; OPEN to reduce cooling).

34SO-E11-010-2, (4.2.3.82.b).

• • 3. WHILE maintaining RHR Loop A At panel 2H11-P601, the flow rate of 6200 to 8200 GPM, following valve is throttled in the establish a rise OR reduction in the OPEN direction, cooling rate as required to obtain/maintain the desired coolant AND/OR RPV temperature(s) as 2E11-F068A, Hx A RHRSW specified by Shift Supervisor, by Disch Vlv.

manipulating one OR a combination of the following MOVs:

2E11-F068A, Hx A RHRSW Disch Vlv.

(OPEN to raise cooling; CLOSE to reduce cooling).

34SO-E11-010-2, (4.2.3.82.c).

ALTERNATE PATH STARTS HERE (Step 4)

NOTE: SIMULATOR OPERATOR, ENSURE Event Trigger EGE11-30 INSERTS the DW leak malfunction WHEN Reactor pressure is ~99 psig.

(** Indicates critical step)

2021-301 CR-SIM 4 Page 7 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

4. Enters 34AB-E11-001-2, Loss OF 34AB-E11-001-2, Loss OF Shutdown Cooling. Shutdown Cooling, is entered.

5. Recognizes Drywell pressure has The operator transitions to exceeded the LOCA signal and Section 4.4.9, Manual LPCI transitions to Section 4.4.9, Manual Initiation While In Shutdown LPCI Initiation While In Shutdown Cooling.

Cooling, 34AB-E11-001-2, (Step 4.2).

6. If running, trip RHRSW pumps, At panel 2H11-P601, the operator places SERVICE WATER PUMP, 2E11-C001A to TRIP, 34SO-E11-010-2, (Step 4.4.9.2). green light illuminated.

7. If running, trip RHR pumps, At panel 2H11-P601, the following pumps are TRIPPED, neither green nor red lights are 34SO-E11-010-2, (Step 4.4.9.4.a). illuminated: RHR PUMPS, 2E11-C002A/C.

NOTE: Only one JPM Steps 8 or 9 is a critical step.

• • 8. Ensure CLOSED Shutdown Cooling At panel 2H11-P601, SDC Suction Valve, 2E11-F008, SUCTION VLV, 2E11-F008, is CLOSED, green light ONLY 34SO-E11-010-2, (Step 4.4.9.4.b). illuminated.

• • 9. Ensure CLOSED Shutdown Cooling At panel 2H11-P602, SDC Suction Valve, 2E11-F009, SUCTION VLV, 2E11-F009, is CLOSED, green light ONLY 34SO-E11-010-2, (Step 4.4.9.4.c). illuminated.

• • 10. Ensure CLOSED Shutdown Cooling At panel 2H11-P601, the Suction Valve, 2E11-F006A, following valve is CLOSED, green light ONLY illuminated:

SHUTDOWN COOLING VLV, 34SO-E11-010-2, (Step 4.4.9.4.d). 2E11-F006A

• • 11. Ensure CLOSED Shutdown Cooling At panel 2H11-P601, the Suction Valve, 2E11-F006C, following valve is CLOSED, green light ONLY illuminated:

SHUTDOWN COOLING VLV, 34SO-E11-010-2, (Step 4.4.9.4.d). 2E11-F006C

(** Indicates critical step)

2021-301 CR-SIM 4 Page 8 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

12. Open Torus Suction Valve, 2E11- At panel 2H11-P601, TORUS F065A, SUCTION VLV, 2E11-F065A, is 34SO-E11-010-2, (Step 4.4.9.4.e). OPEN, red light ONLY illuminated.

13. Open Torus Suction Valve, 2E11- At panel 2H11-P601, TORUS F065C, SUCTION VLV, 2E11-F065C, is 34SO-E11-010-2, (Step 4.4.9.4.e). OPEN, red light ONLY illuminated.

NOTE: Valve in Step 10 must be closed, green light ONLY, before valve in Step 14 will open.

Valve in Step 11 must be closed, green light ONLY, before valve in Step 15 will open.

• • 14. Open Torus Suction Valve, At panel 2H11-P601, the 2E11-F004A, following valve is OPEN, red light ONLY illuminated:

TORUS SUCTION VLV, 34SO-E11-010-2, (Step 4.4.9.4.f). 2E11-F004A

• • 15. Open Torus Suction Valve, At panel 2H11-P601, the 2E11-F004C, following valve is OPEN, red light ONLY illuminated:

TORUS SUCTION VLV, 34SO-E11-010-2, (Step 4.4.9.4.f). 2E11-F004C NOTE: The control switch for each pump must be taken to STOP before the RHR pump will start on the loop that was in Shutdown Cooling.

• • 16. Start RHR Pump 2A by placing the At panel 2H11-P601, control control switch to STOP, switch for the following pump has been taken to STOP and then

• • • • • • • • • • • • . to STOP, green light illuminated:

RHR PUMP, 2E11-C002A 34SO-E11-010-2, (Step 4.4.9.4.g).

(** Indicates critical step)

2021-301 CR-SIM 4 Page 9 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 17. ************ At panel 2H11-P601, control switch for the following pump then to START, has been taken to START, red light illuminated:

34SO-E11-010-2, (Step 4.4.9.4.g). RHR PUMP, 2E11-C002A

• • 18. Start RHR Pump 2C by placing the At panel 2H11-P601, control control switch to STOP, switch for the following pump has been taken to STOP and then

• • • • • • • • • • • • . to STOP, green light illuminated:

RHR PUMP, 2E11-C002C.

34SO-E11-010-2, (Step 4.4.9.4.g).

• • 19. ************ At panel 2H11-P601, control switch for the following pump then to START, has been taken to START, red light illuminated:

34SO-E11-010-2, (Step 4.4.9.4.g). RHR PUMP, 2E11-C002C.

NOTE: At least one RHR pump must be started to satisfy the critical step in step 16 or step 17.

NOTE: 2E11-F015A has failed to AUTO open. The operator will be required to MANUALLY open 2E11-F015A

• • 20. Ensure Open 2E11-F015A At panel 2H11-P601, RHR INBD INJ VLV, 2E11-F015A, is OPEN, red light ONLY 34SO-E11-010-2, (Step 4.4.9.4.h). illuminated.

NOTE: 2E11-F015A will close on a Group II Signal level signal if 2E11-F008 and 2E11-F009 are open and RPV pressure is less than 138 psig.

NOTE: 2E11-F048A has failed to AUTO open. The operator will be required to MANUALLY open 2E11-F048A if previously throttled closed. If 2E11-F048A was not throttled then step 21 is not critical.

(** Indicates critical step)

2021-301 CR-SIM 4 Page 10 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 21. Ensure Open Heat Exchanger Bypass At panel 2H11-P601, HX Valve, 2E11-F048A BYPASS VLV, 2E11-F048A, is 34SO-E11-010-2, (Step 4.4.9.4.i). OPEN, red light illuminated.

22. Ensure Open and Throttle the RHR At panel 2H11-P601, the Outboard Injection Vlv, 2E11-F017A, following has been performed:

to obtain 17,000 gpm (7,700 gpm for RHR OUTBD INJ VLV, one RHR pump). 2E11-F017A, has been THROTTLED, red and green lights illuminated.

Operator has OBTAINED less than 17,000 gpm (7,700 gpm for one RHR pump) as indicated on RHR FLOW, 2E11-R603A (accept 2,000 gpm).

34SO-E11-010-2, (Step 4.4.9.4.j).

NOTE: After restoring RWL above TAF (-155 inches), the operator may throttle 2E11-F017A or secure one RHR Loop A pump to control RWL.

NOTE: Once the operator has a After restoring RWL above TAF (-155 inches),

the operator may throttle 2E11-F017A or secure one RHR Loop A pump to control RWL.

PROMPT: IF the operator addresses additional steps in the procedure, INFORM the operator that another operator will complete the remainder of the procedure.

PROMPT: IF the operator addresses shutting down LPCI, as the Shift Supervisor, INFORM the operator that shutdown of RHR is NOT required at this time.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when:

When the operator completes step 22.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

2021-301 CR-SIM 4 Page 11 of 12 Summary of JPM Attributes JPM 2021-301 CR-SIM 4:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 12 Step 1 Open 2E11-F003A Opening F003A is required to raise cooling rate.

Step 2 Open 2E11-F048A Closing F048A is required to raise cooling rate.

Step 3 Open 2E11-F068A Opening F068A is required to raise cooling rate.

Step 8/9 Close 2E11-F008/9 Required to open 2E11-F015A (Removes F015A as a Group 2.

Step 10 Close 2E11-F006A Required to open 2E11-F004A.

Step 11 Close 2E11-F006C Required to open 2E11-F004C.

Step 14 Open 2E11-F004A Required to establish suction path.

Step 15 Open 2E11-F004C Required to establish suction path.

Step 16 Start RHR Pump 2A Required to provide motive force for injection.

Step 17 Start RHR Pump 2C Required to provide motive force for injection.

Step 18 Open 2E11-F015A Required to establish injection flowpath.

Step 19 Open 2E11-F048A Required to establish full LPCI injection flowpath.

Number of JPM Steps <30 20 Time to Perform JPM <45 min 20 min Normal / Faulted /

Alternate Path Alternate Path Manual start of LPCI from SDC and inject into the RPV. LPCI will NOT auto start on low RWL or high DW pressure.

Setting (administered)

Simulator Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is shutdown.

2. RPV pressure is 100 PSIG and slowly rising.

3. RHR loop 2A is in the Shutdown Cooling mode with RHR Pump 2A in service.

4. Both Core Spray System Pumps are inoperable.

5. HPCI and RCIC are isolated.

6. RHR Pumps 2B and 2D are inoperable.

INITIATING CUES:

IAW 34SO-E11-010-2, RHR System, Section 4.2.3, step 82, lower and maintain RPV pressure between 80 PSIG to 90 PSIG.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 5 (ALL)

Title Version LOWER TORUS WATER LEVEL 1.0 Author: Media Number Times Anthony Ball 2021-301 CR-SIM 5 10.0 Minutes Line Review By: Date N/A N/A Reviewed by Instructional Technologist or designee: Date N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 CR-SIM 5 Page 2 of 9 Course Number Program Name Media Number N/A OPERATIONS TRAINING 2021-301 CR-SIM 5 Author Print Peer Review Ver. No. Date Reason for Revision Initials/Name Print Initials/Name 00 10/11/09 Initial development FNF CME 1.0 2/9/2021 Updated for ILT-13 NRC Exam 2021-301. ARB JDW

2021-301 CR-SIM 5 Page 3 of 9 UNIT 1 () UNIT 2 (X)

TASK TITLE: Lower Torus Water Level JPM NUMBER: 2021-301 CR-SIM 5 TASK STANDARD: The task shall be complete when the operator has lowered Torus water level to 148 (+ 0.5).

TASK NUMBER:

OBJECTIVE NUMBER: E11-RHR-LP-00701, 013.004.A PLANT HATCH JTA IMPORTANCE RATING:

RO SRO K/A CATALOG NUMBER: 223001A2.11 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.6 SRO 3.8 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 & 2 34SO-E11-010-2 REQUIRED MATERIALS: Unit 1 & 2 34SO-E11-010-2, Section 7.4.5 APPROXIMATE COMPLETION TIME: 10.0 Minutes SIMULATOR SETUP: See next page.

2021-301 CR-SIM 5 Page 4 of 9 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to an IC 113 or Snap 615 and leave in FREEZE.

2. INSERT the following REMOTE FUNCTIONS:

RF # TITLE FINAL RAMP Key VALUE RATE rfE21_214 E21-F002A Suction From CST to CS Pump A OPEN rfE21_215 E21-F002B Suction From CST to CS Pump B OPEN

3. INSERT the following OVERRIDES:

KEY# OR # TITLE FINAL RAMP VALUE RATE RB-1 loE11-F003BR2 RHR A HT EXCH OUTLET OFF RB-2 loE11-F047BR2 RHR A HT EXCH INLET OFF

4. Place the simulator in RUN.

5. Allow Torus Level to increase to 149.5, ensure annunciator Torus Water Level High/Low, 602-235, in alarm, THEN return rfE21_214 and rfE21_215 to NORM.

6. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS OR RUN SCENARIO FILE and EVENT TRIGGER (current rev) 2021-301 CR-SIM 5:

7. ESTIMATED Simulator SETUP TIME: 5 Minutes 4

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is at normal full power operations.

2. Annunciator 602-235, TORUS WATER LEVEL HIGH/LOW, is ALARMED.

3. Known and documented Torus in-leakage has caused Torus level to rise to 149.5 inches.

4. Both loops of RHR have been filled and vented IAW 34SV-SUV-017-2, Core Spray and RHR Keepfill and RHR Cross Header Valve Check.

INITIATING CUES:

IAW 34SO-E11-010-2, Residual Heat Removal System, Section 4.4.5 Step 4.4.5.2.g, lower Torus Water Level to 148 inches.

2021-301 CR-SIM 5 Page 6 of 9 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

NOTE: Unless otherwise indicated, all manipulations are on 2H11-P601.

START TIME:__________

1. Monitor Suppression Pool level. Monitor Suppression Pool level on 2T48-R607A at 2H11-P602 OR on 2T48-R607B at 2H11-Step 4.4.5.2.g P654.

• • 2. START an RHR Loop B Pump. Operator STARTS RHR Pump B OR D by placing its control switch to START, red light Step 4.4.5.2.h illuminated.

3. Acknowledge expected annunciators. Acknowledges the following annuciators:

602-312 Auto Blowdown CS or RHR Press Permissive 650-234 SEC System Auto Initiation Signal Present 601-222 RHR Flow Low

4. Dispatch an operator to locally check Operator dispatches an operator the RHR pump for seal leakage. to locally check the RHR pump Step 4.4.5.2.h(1) for seal leakage.

PROMPT: AFTER approximately 2 minutes, REPORT back to the operator that there is NO seal leakage.

(** Indicates critical step)

2021-301 CR-SIM 5 Page 7 of 9 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

5. CONFIRM RHR discharge water Operator CONFIRMS RHR temperature is < 200°F. discharge water temperature is <

200°F, as read on 2T47-R627, point 3 at panel 2H11-P650.

Step 4.4.5.2.i

• • 6. Slowly THROTTLE OPEN 2E11- Operator slowly THROTTLES F040, RHR To Radwaste Vlv. OPEN 2E11-F040, RHR To Radwaste Vlv by placing its control switch to OPEN, red light Step 4.4.5.2.j illuminated.

7. Acknowledge cleared annunciators Acknowledges the following cleared annunciators:

601-222 RHR Flow Low 602-235 Torus Water Level High/Low

8. Notify the Shift Supervisor to refer to Operator notifies the Shift SPECIAL REQUIREMENT Section Supervisor to refer to SPECIAL 3.2.3 Step 2 and the above NOTE for REQUIREMENT Section 3.2.3 the appropriate Tech Specs to enter, Step 2 and the above NOTE for for an INOP Loop of RHR. the appropriate Tech Specs to Step 4.4.5.2.k enter, for an INOP Loop of RHR.

• • 9. WHEN the Suppression Pool has WHEN the Suppression Pool been pumped down to the desired level is lowered to 148 level CLOSE 2E11-F040, RHR To (+ or - .5), Operator CLOSES Radwaste Vlv. 2E11-F040, RHR To Radwaste Vlv by placing its control switch Step 4.4.5.2.l to CLOSE, green light illuminated.

PROMPT: WHEN the Operator starts to secure 2E11-C002B, THEN inform the operator that another operator will continue from here.

END TIME:__________

NOTE: The terminating cue shall be given to the Operator when:

When the operator completes step 9.

With NO reasonable progress, the Operator exceeds double the allotted time.

Operator starts to secure 2E11-C002B.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

2021-301 CR-SIM 5 Page 8 of 9 Summary of JPM Attributes JPM 2021-301 CR-SIM 5:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 3 Step 2 Start an RHR Loop B Pump The RHR Pump is started to provide the motive force.

Step 6 Slowly open 2E11-F040 Aligns final valve in flowpath for lowering Torus level.

Step 9 Close 2E11-F040 Isolates the flowpath for lowering Torus level.

Number of JPM Steps <30 12 Time to Perform JPM <45 min 10 min Normal / Faulted /

Alternate Path Normal Path Setting (administered)

Simulator Is LOD 1 or 5 NO NO

UNIT 2 READ AND GIVE A COPY TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is at normal full power operations.

2. Annunciator 602-235, TORUS WATER LEVEL HIGH/LOW, is ALARMED.

3. Known and documented Torus in-leakage has caused Torus level to raise to 149.5.

4. Both loops of RHR have been filled and vented IAW 34SV-SUV-017-2, Core Spray and RHR Keepfill and RHR Cross Header Valve Check.

INITIATING CUES:

IAW 34SO-E11-010-2, Residual Heat Removal System, Section 4.4.5 Step 4.4.5.2.g, lower Torus Water Level to 148 inches.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 6 (ALL)

Title HOT TRANSFER 600VAC 2A TO ALTERNATE SUPPLY - ALTERNATE PATH Author: Media Number: Time:

Anthony Ball 2021-301 CR-SIM 6 10 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee (N/A for minor revisions) Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 CR-SIM 6 Page 1 of 9 Course Number Program Name Media Number N/A OPERATIONS TRAINING 2021-301 CR-SIM 6 Author Print Peer Review Ver. No. Date Reason for Revision Initials/Name Print Initials/Name 0.0 2/9/2021 Updated for ILT-13 NRC Exam 2021-301. ARB JDW

2021-301 CR-SIM 6 Page 3 of 9 UNIT 1 ( ) UNIT 2 (X)

TASK TITLE: Hot Transfer 600VAC 2A to Alternate Supply JPM NUMBER: 2021-301 CR-SIM 6 TASK STANDARD: This task shall be successfully completed when the applicant performs the following actions:

o Close the alternate supply breaker ACB 135466 to Station Service Transformer 2AB o Closes alternte supply breaker ACB 135632 to 600V 2A Bus o Lowers generator load below 14,000 amps TASK NUMBER: 027.049 OBJECTIVE NUMBER: 027.049.A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.07 SRO 2.83 K/A CATALOG NUMBER: 262001A4.01 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.4 SRO 3.7 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 2 34SO-R23-004-2, Ver. 4.3 REQUIRED MATERIALS: Unit 2 34SO-R23-004-2, Ver. 4.3 APPROXIMATE COMPLETION TIME: 10 Minutes SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

2021-301 CR-SIM 6 Page 4 of 9 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to IC 111 or Snap 616 and leave in FREEZE.

2. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS OR RUN SCENARIO FILE and EVENT TRIGGER (current rev) 2021-301 CR-SIM 6:

ET # Description EGR23-4 Inserts malfunction (mfR23_174) to de-energize 600VAC 2A

3. INSERT the following REMOTE FUNCTIONS:

REM # ACTIVATOR DESCRIPTION STATUS ST-0 rfR25_142 2AB XFORMER SUPPLY 2C

4. PLACE the Simulator in FREEZE until the INITIATING CUE is given.

5. PLACE DANGER TAGS on the following equipment:

MPL # COMPONENT TAGGED POSITION NONE

6. ESTIMATED Simulator SETUP TIME: 10 Minutes

2021-301 CR-SIM 6 Page 5 of 9 EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Maintenance is required for 600VAC 2A Normal Supply breaker.

2. 600 VAC Buses 2A, 2B, 2AA, 2BB are on their Normal power supply.

3. NO maintenance has been performed on 2S11-S006, 600V SST 2AB, that has the potential to cause a change in the phase angle readings.

INITIATING CUES:

Transfer 600VAC Bus 2A to its Alternate power supply IAW 34SO-R23-004-2, Hot Transfer 600V AC System, starting at step 1.8 of Attachment 1.

2021-301 CR-SIM 6 Page 6 of 9 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

START TIME:__________

• • 1. On panel 2H11-P651, ensure closed On panel 2H11-P651, the ALT FDR TO SST 2AB, ACB operator closes ACB 135466.

135466 - 2C Bus. Check the breaker is CLOSED, RED indicating light is RED indicating light is ON AND ON AND the GREEN light is OFF. the GREEN light is OFF.

(34SO-R23-004-2 Att. 1 step 1.8)

PROMPT: IF the operator addresses exercising breaker 135632, INFORM the operator that electricians have exercised the breaker and is now confirmed open and racked in. (Step 1.9 & 1.11)

PROMPT: IF the operator addresses jumper installation at Att. 1 step 1.12 & 1.13, INFORM the operator that the jumper has been installed at step 1.13 of Att. 1.

NOTE: When 2R23-S001 ACB 135632 control switch is placed to CLOSE, Event Trigger EGR23-4 will de-energize 600V Bus 2A.

(** Indicates critical step)

2021-301 CR-SIM 6 Page 7 of 9 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 2. Place ALT SPLY to 2R23-S001, ACB On panel 2H11-P651, the 135632 control switch to CLOSE. operator closes ACB 135632.

Both ACB 135632 and ACB 135634 trip.

(34SO-R23-004-2 Att. 1 step 1.14.1) Red lights & Green lights OFF and Amber lights ON.

ALTERNATE PATH STARTS HERE PROMPT: IF the operator reports the de-energization of 600V Bus 2A, INFORM the operator that you will get Maintenance to investigate and you respond to the plant.

• • 3. Enter 34AB-R23-002-2, Loss of 600V On panel 2H11-P603, operator 2A, 2AA, 2BB, or 2B. lowers Recirc pump speed using Reduce generator stator amps the Master Recirc Flow Contoller to < 14,000 amps. Lower Fast IAW 34GO-OPS-005-2 and 34SO-B31-001-2 until (34AB-R23-002-2 step 4.1) generator amps are < 14,000.

NOTE: AFTER the operator has lowered generator amps to < 14,000 amps, INFORM the operator that another operator will continue responding to the loss of 600V 2A.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when:

When the operator completes step 3.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

2021-301 CR-SIM 6 Page 8 of 9 Summary of JPM Attributes JPM 2021-301 CR-SIM 6:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 3 Step 1 Close ACB 135466 Energizes High side of Station Service Transformer 2AB.

Step 2 Close ACB 135632 Energizes 600VAC Bus 2A from Alternate Supply.

Step 3 Lowers Generator Amps Reduces Generator Amps to procedure limits.

Number of JPM Steps

<30 3 Time to Perform JPM

<10 min 10 min Normal / Faulted /

Alternate Path Alternate Path When Alternate Supply breaker is closed both Normal and Alternate breakers will trip resulting in loss of bus duct cooling requiring Generator load to be reduced below 14,000 amps.

Setting (administered)

Control Room/Simulator Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR

1. Maintenance is required for 600VAC 2A NORMAL SUPPLY breaker

2. 600 VAC Buses 2A, 2B, 2AA, 2BB are on their normal power supply.

3. No maintenance has been performed on 2S11-S006, 600V SST 2AB.

INITIATING CUES:

Transfer 600VAC Bus 2A to its Alternate power supply IAW 34SO-R23-004-2, Hot Transfer 600V AC System, starting at step 1.8 of Attachment 1.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 7 (ALL)

Title Version LOSS OF AIR ACTIONS FOR RX BLDG VENTILATION

0.2 Author

Media Number Times Anthony Ball 2021-301 CR-SIM 7 10.0 Minutes Line Review By: Date N/A N/A Reviewed by Instructional Technologist or designee: Date N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 CR-SIM 7 Page 2 of 13 Course Number Program Name Media Number N/A OPERATIONS TRAINING 2021-301 CR-SIM 7 Author Print Peer Review Ver. No. Date Reason for Revision Initials/Name Print Initials/Name 00 05/18/09 Initial development FNF CME 0.1 03/10/2015 Reviewed JPM against current procedure to be used ARB ELJ on ILT-9 NRC Exam. Changed Media Number to Sim 7 and deleted Fundamental Review Question.

Both will be added back to become new LR-JP-13.53-14.3 after NRC Exam.

Updated for ILT-13 NRC Exam 2021-301 & removed 0.2 2/9/2021 ARB JDW Alternate Path.

2021-301 CR-SIM 7 Page 3 of 13 UNIT 1 () UNIT 2 (X)

TASK TITLE: LOSS OF AIR ACTIONS FOR RX BLDG VENTILATION JPM NUMBER: 2021-301 CR-SIM 7 TASK STANDARD: This task shall be successfully completed when all of the JPM Critical Steps corresponding to 34AB-P51-001-2, Section 4.14-4.14.3, have been correctly performed to align ventilation in the Secondary Containment for a loss of air.

TASK NUMBER: H-OPR0200.025 OBJECTIVE NUMBER: 200.025.C from SG50273 PLANT HATCH JTA IMPORTANCE RATING:

RO 3.93 SRO 3.61 K/A CATALOG NUMBER: 295019AK2.08 K/A CATALOG JTA IMPORTANCE RATING:

RO 2.8 SRO 2.9 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 & 2 34AB-P51-001-2 Ver. 7.1 REQUIRED MATERIALS: Unit 1 & 2 34AB-P51-001-2 Ver. 7.1, completed through step 4.13.

APPROXIMATE COMPLETION TIME: 10.0 Minutes SIMULATOR SETUP: See the next sheet.

2021-301 CR-SIM 7 Page 4 of 13 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to IC 113 or Snap 617 and leave in FREEZE.

2. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS OR RUN SCENARIO FILE and EVENT TRIGGER (current rev) 2021-301 CR-SIM 7:

3. INSERT the following MALFUNCTIONS:

MALF # TITLE FINAL RAMP ACT.

VALUE RATE TIME mfP51_222A Service Air Compressor 2A Trip 1 mfP51_222B Service Air Compressor 2B Trip 1 mfP51_222C Service Air Compressor 2C Trip 1 mfP52_191 Instrument Air Leakage 1 mfC71_59 Spurious Reactor Scram 1

4. INSERT the following OVERRIDES:

OVERIDE # TITLE FINAL VALUE diP52-F565 Rx Bldg Inst. N2 to Noninter. Ser. Vlv. CLOSED (2)

5. Create the following EVENT TRIGGERS:

SCN/ET ET INFORMATION SCN INFORMATION NAME NONE

6. ACTIVATE event triggers EGT46-11 and EGT46-12.

7. Place Rx Mode Switch to Shutdown.

8. Place RCIC in service, injecting into the vessel, with level slowly rising (this is to prevent the auto start of SBGT).

9. Allow the simulator to run until the SBGT air operated valves (F001/3) fail open (~4 minutes)

10. Mark up 34AB-P51-001-2 up to, but NOT including, step 4.14.

11. PLACE the Simulator in FREEZE until the INITIATING CUE is given.

12. ESTIMATED Simulator SETUP TIME: 10 Minutes

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 has lost all Service Air Compressors and they can not be restarted.

2. Electrical Maintenance and I&C are checking all air system electrical circuits.

3. The reactor has been scrammed and 34AB-C71-001-2, Scram Procedure, is being carried out.

4. 34AB-P51-001-2, Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System, has been partially completed.

INITIATING CUES:

Complete procedure 34AB-P51-001-2 starting at step 4.14.

2021-301 CR-SIM 7 Page 6 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

START TIME:__________

NOTE: Provide the operator with 34AB-P51-001-2 completed up to step 4.13.

1. The operator starts at the correct step. Operator refers to 34AB-P51-001-2 and starts at step 4.14.

2. Determine if Control Air header On panel 2H11-P650, Control Air Pressure is below 45 PSIG AND NOT Pressure, 2P52-R600, the increasing. operator observes pressure is less (step 4.14) then 45 psig and NOT increasing.

NOTES:

If the operator attempts to first start the A SBGT, complete steps 3-7 and skip steps 8-12.

If the operator attempts to first start the B SBGT, complete steps 8-12 and skip steps 3-7.

All A controls are located on 2H11-P657.

All B controls are located on 2H11-P654.

SBGT air operated valves F001/2/3 fail in the OPEN position.

(** Indicates critical step)

2021-301 CR-SIM 7 Page 7 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

NOTE: JPM steps 3 - 7 BELOW are for starting SBGT A first.

NOTE: The operator may use 34SO-T46-001-2, SBGT System, Att. 6, (Placard) to start SBGT A or the system operating procedure, either is acceptable.

3. OPEN 2T46-F003A, Fltr Inlet from The operator places the keylock Refuel Flr. switch for 2T46-F003A, Fltr Inlet (Placard step 1.1) from Refuel Flr, to OPEN.

AND/OR Open 2T46-F001A, Fltr Inlet from Rx The operator places the keylock Bldg. switch for 2T46-F001A, Fltr Inlet (Placard step 1.1) from Rx Bldg, to OPEN.

• • 4. PLACE SBGT A in RUN position. The operator places the control switch for SBGT A to RUN.

(Placard step 1.2)

5. CONFIRM 2T46-F002A OPENS. The operator observes 2T46-F002A red light LLUMINATED.

(Placard step 1.3)

6. CONFIRM SBGT A HTR Red Light The operator observes SBGT A ILLUMINATES. HTR Red Light ILLUMINATED.

(Placard step 1.4)

7. CONFIRM SBGT Flow increases to The operator observes SBGT 1500-4000 SCFM. flow between 1500-4000 scfm on (Placard step 1.5) 2T41-R618.

NOTES:

If the operator attempts to first start the A SBGT, complete steps 3-7 and skip steps 8-12.

If the operator attempts to first start the B SBGT, complete steps 8-12 and skip steps 3-7.

All A controls are located on 2H11-P657.

All B controls are located on 2H11-P654.

SBGT air operated valves F001/2/3 fail in the OPEN position.

(** Indicates critical step)

2021-301 CR-SIM 7 Page 8 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

NOTE: JPM steps 8 - 12 BELOW are for starting SBGT B first.

NOTE: The operator may use 34SO-T46-001-2, SBGT System, Att. 6, (Placard) to start SBGT B.

8. OPEN 2T46-F003B, Fltr Inlet from The operator places the keylock Refuel Flr. switch for 2T46-F003B, Fltr Inlet (Placard step 1.1) from Refuel Flr, to OPEN.

AND/OR Open 2T46-F001B, Fltr Inlet from Rx The operator places the keylock Bldg. switch for 2T46-F001B, Fltr Inlet (Placard step 1.1) from Rx Bldg, to OPEN.

• • 9. PLACE SBGT B in RUN position. The operator places the control switch for SBGT B in RUN.

(Placard step 1.2)

10. CONFIRM 2T46-F002B OPENS. The operator observes 2T46-F002B red light ILLUMINATED.

(Placard step 1.3)

11. CONFIRM SBGT B HTR Red Light The operator observes SBGT B ILLUMINATES. HTR Red Light ILLUMINATED.

(Placard step 1.4)

12. CONFIRM SBGT Flow increases to The operator observes SBGT 1500-4000 SCFM. flow between 1500-4000 scfm on (Placard step 1.5) 2U41-R600.

NOTE: The operator may NOT check the next step until after all are other steps of this JPM are complete.

13. Checks the Rx Bldg. and RF Floor On panel 2H11-P700 the operator Diff pressures are negative. checks the RF Floor to Outside Air dp and the Rx Bldg to Outside Air dp on recorders 2T46-R604A and 2T46-R604B.

The dp will be approximately (Placard step 1.6) (negative) -0.25 inches.

(** Indicates critical step)

2021-301 CR-SIM 7 Page 9 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

NOTE: The following steps may be performed non-sequential. The step is to be marked SAT if, after the operator is done, the fan is NOT running (green light illuminated). May take the Standby fan to OFF first.

• • 14. TRIP 2U41-C001A, Turb Bldg Vent On panel 2H11-P654 the operator Supply Fan. places control switch for 2U41-C001A, Turb Bldg Vent Supply Fan, to the OFF position, green (step 4.14.2) light illuminated.

• • 15. TRIP 2U41-C001B, Turb Bldg Vent On panel 2H11-P654 the operator Supply Fan. places control switch for 2U41-C001B, Turb Bldg Vent Supply Fan, to the OFF position, green (step 4.14.2) light illuminated.

• • 16. TRIP 2U41-C002A, Turb Bldg Vent On panel 2H11-P654 the operator Exhaust Fan. places control switch for 2U41-C002A, Turb Bldg Vent Exhaust Fan, to the OFF position, green (step 4.14.2) light illuminated.

• • 17. TRIP 2U41-C002B, Turb Bldg Vent On panel 2H11-P654 the operator Exhaust Fan. places control switch for 2U41-C002B, Turb Bldg Vent Exhaust Fan, to the OFF position, green (step 4.14.2) light illuminated.

• • 18. TRIP 2T41-C001A, Rx Bldg Vent On panel 2H11-P657 the operator Supply Fan. places control switch for 2T41-C001A, Rx Bldg Vent Supply Fan, to the OFF position, green (step 4.14.2) light illuminated.

(** Indicates critical step)

2021-301 CR-SIM 7 Page 10 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 19. TRIP 2T41-C001B, Rx Bldg Vent On panel 2H11-P657 the operator Supply Fan. places control switch for to the OFF position, green light (step 4.14.2) illuminated.

• • 20. TRIP 2T41-C007A, Rx Bldg Vent On panel 2H11-P657 the operator Exhaust Fan. places control switch for 2T41-C001B, Rx Bldg Vent Supply Fan, to the OFF position, green (step 4.14.2) light illuminated.

• • 21. TRIP 2T41-C007B, Rx Bldg Vent On panel 2H11-P657 the operator Exhaust Fan. places control switch for 2T41-C007B, Rx Bldg Vent Exhaust Fan, to the OFF position, green (step 4.14.2) light illuminated.

• • 22. TRIP 2T41-B017 Fan 1, Rx Bldg On panel 2H11-P657 the operator Recirc Fan. places control switch for 2T41-B017 Fan 1, Rx Bldg Recirc Fan, to the OFF position, green light (step 4.14.2) illuminated.

• • 23. TRIP 2T41-B017 Fan 2, Rx Bldg On panel 2H11-P657 the operator Recirc Fan. places control switch for 2T41-B017 Fan 2, Rx Bldg Recirc Fan, to the OFF position, green light (step 4.14.2) illuminated.

• • 24. TRIP 2T41-C002A, Refuel Flr Vent On panel 2H11-P657 the operator Supply Fan. places control switch for 2T41-C002A, Refuel Flr Vent Supply Fan, to the OFF position, green (step 4.14.2) light illuminated.

• • 25. TRIP 2T41-C002B, Refuel Flr Vent On panel 2H11-P657 the operator Supply Fan. places control switch for 2T41-C002B, Refuel Flr Vent Supply Fan, to the OFF position, green (step 4.14.2) light illuminated.

(** Indicates critical step)

2021-301 CR-SIM 7 Page 11 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 26. TRIP 2T41-C005A, Refuel Flr Vent On panel 2H11-P657 the operator Exh Fan. places control switch for 2T41-C005A, Refuel Flr Vent Exh Fan, to the OFF position, green light (step 4.14.2) illuminated.

• • 27. TRIP 2T41-C005B, Refuel Flr Vent On panel 2H11-P657 the operator Exh Fan. places control switch for 2T41-C005B, Refuel Flr Vent Exh Fan, to the OFF position, green light (step 4.14.2) illuminated.

28. Ensure OPEN/OPEN 2N21-F014, The operator sends a SO to ensure Condensate Demineralizer Bypass OPEN/OPEN 2N21-F014, Valve. Condensate Demineralizer Bypass Valve, at panel 2N21-(step 4.14.3) P001.

PROMPT: WHEN the operator sends a SO to confirm the valve is open, INFORM the operator that another operator will complete the remainder of 34AB-P51-001-2.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when:

Operator completes step 28 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator is prompted that another operator will complete 34AB-P51-001-2.

Operator states the task is complete.

(** Indicates critical step)

2021-301 CR-SIM 7 Page 12 of 13 Summary of JPM Attributes JPM 2021-301 CR-SIM 7:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 15 Step 4 (9) Place SBGT A(B) in run Starts SBGT Train Step 14 TRIP 2U41-C001A Secures Turb Vent Supply Fan Step 15 TRIP 2U41-C001B Secures Turb Vent Supply Fan Step 16 TRIP 2U41-C002A Secures Turb Vent Exhaust Fan Step 17 TRIP 2U41-C002B Secures Turb Vent Exhaust Fan Step 18 TRIP 2T41-C001A Secures Rx Bldg Vent Supply Fan Step 19 TRIP 2T41-C001B Secures Rx Bldg Vent Supply Fan Step 20 TRIP 2T41-C007A Secures Rx Bldg Vent Exhaust Fan Step 21 TRIP 2T41-C007B Secures Rx Bldg Vent Exhaust Fan Step 22 TRIP 2T41-B017 Fan 1 Secures Rx Bldg Recirc Fan Step 23 TRIP 2T41-B017 Fan 2 Secures Rx Bldg Recirc Fan Step 24 TRIP 2T41-C002A Secures Refuel Flr Vent Supply Fan Step 25 TRIP 2T41-C002B Secures Refuel Flr Vent Supply Fan Step 26 TRIP 2T41-C005A Secures Refuel Flr Vent Exhaust Fan Step 27 TRIP 2T41-C005B Secures Refuel Flr Vent Exhaust Fan Number of JPM Steps <30 28 Time to Perform JPM <10 min 10 min Normal / Faulted /

Alternate Path Normal Path Setting (administered)

Simulator Is LOD 1 or 5 NO NO

(** Indicates critical step)

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 has lost all Service Air Compressors and they can not be restarted.

2. Electrical Maintenance and I&C are checking all air system electrical circuits.

3. The reactor has been scrammed and 34AB-C71-001-2, Scram Procedure, is being carried out.

4. 34AB-P51-001-2, Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System, has been partially completed.

INITIATING CUES:

Complete procedure 34AB-P51-001-2 starting at step 4.14.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 8 (RO ONLY)

Title Version PLACE THE CONTROL ROOM HVAC SYSTEM IN THE 7.3 PURGE MODE Author: Media Number Times 2021-301 CR-SIM 8 15 Minutes Anthony Ball Line Review By: Date N/A N/A Reviewed by Instructional Technologist or designee: Date N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 CR-SIM 8 Page 2 of 11 Course Number Program Name Media Number N/A OPERATIONS TRAINING 2021-301 CR-SIM 8 Author Print Peer Review Ver. No. Date Reason for Revision Initials/Name Print Initials/Name Reviewed JPM against current procedure to be used on ILT-9 NRC 7.2 03/10/2015 Exam. Updated General References. Changed Media Number to CR-Sim 8 and deleted Fundamental Review Question. Both will ARB ELJ be added back to become new LR-JP-25026-7.3 after NRC Exam.

7.3 02/09/2021 Updated for ILT-13 NRC Exam 2019-301. ARB JDW 2

2021-301 CR-SIM 8 Page 4 of 11 UNIT 1 (X) UNIT 2 ( )

TASK TITLE: PLACE THE CONTROL ROOM HVAC SYSTEM IN THE PURGE MODE JPM NUMBER: 2021-301 CR-SIM 8 TASK STANDARD: This task shall be successfully completed when all of the JPM Critical Steps corresponding to 34SO-Z41-001-1, Section 7.1.4, have been correctly performed to place the Control Room Ventilation System in the Purge Mode.

TASK NUMBER: 037.010 OBJECTIVE NUMBER: 037.010.O PLANT HATCH JTA IMPORTANCE RATING:

RO 3.00 SRO 2.63 K/A CATALOG NUMBER: 290003G2.1.30 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.90 SRO 3.40 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 34SO-Z41-001-1 (current version) 34AB-T41-001-1 (current version)

REQUIRED MATERIALS: Unit 1 34SO-Z41-001-1 (Ver. 24.0)

APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: N/A

EVALUATOR COPY UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Purging of Unit 1 Control Room is desired.

2. The Main Control Room Ventilation System has been operating in a Normal Ventilation configuration for several days with the following alignment:

1Z41-B003A, HVAC Unit, RUN 1Z41-B003B, HVAC Unit, STBY 1Z41-B003C, HVAC Unit RUN INITIATING CUES:

Purge the Unit 1 Main Control Room with the Main Control Room Ventilation System per 34SO-Z41-001-1, Step 7.1.4.

2021-301 CR-SIM 8 Page 6 of 11 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

START TIME:_________

1. Operator identifies the procedure Operator has obtained the correct needed to perform the task. procedure, 34SO-Z41-001-1, Section 7.1.4.

2. Operator reviews the procedures Operator has REVIEWED the precautions and limitations. precautions and limitations.

3. Operator notifies SS to declare one Operator has notified the SS to MCREC system INOPERABLE and declare one MCREC system enter into the associated RAS. INOPERABLE and enter into the (NOTE before step 7.1.4.1) associated RAS.

(** Indicates critical step)

2021-301 CR-SIM 8 Page 7 of 11 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

NOTE: Operating the fan AND opening 1Z41-F018A, Suction Damper, presents a single failure concern regarding isolation of the exhaust duct in the event a pressurization mode actuation occurs.

• • 4. Start Exhaust Fan, 1Z41-C011A. At panel 1H11-P657, PLACES the control switch for 1Z41-(step 7.1.4.1.1) C011A in START, RED light illuminated.

As found should be OFF

5. Confirms suction damper 1Z41- At panel 1H11-P657, F018A opens. CONFIRMS 1Z41-F018A (step 7.1.4.1.1.1) OPENS, RED light illuminated.

As found should be CLOSED NOTE: 1Z41-F018A automatically opens when the 1Z41-C011A fan is started.

• • 6. Open Inlet Control vane, 1Z41-F017A. Have SSS send a SO to the 180 elevation of the Control Building to OPEN inlet control damper (step 7.1.4.1.1.2) 1Z41-F017A.

SEE PROMPT BELOW PROMPT: WHEN asked to send someone to open 1Z41-F017A, INFORM the Operator that 1Z41-F017A is open.

PROMPT: IF the Operator asks the status of Main Control Room Ventilation, per the initial conditions, INFORM the Operator that it is operating in the normal configuration.

7. Ensure OPERATING or START At panel 1H11-P657, ENSURES 1Z41-B003A HVAC unit. 1Z41-B003A control switch in (step 7.1.4.1.2) RUN, RED light illuminated.

As found should be ON

8. Ensure STOPPED or STOPS At panel 1H11-P654, PLACES 1Z41-B003C HVAC unit. 1Z41-B003C control switch in STOP (OFF), GREEN light (step 7.1.4.1.3) illuminated.

As found should be ON

(** Indicates critical step)

2021-301 CR-SIM 8 Page 8 of 11 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

PROMPT: IF the Operator asks if 1Z41-B003B is required for additional temperature control, INFORM the Operator that it is NOT needed for additional temperature control.

9. Ensure STOPPED or STOP At panel 1H11-P654, ENSURES 1Z41-B003B HVAC unit. 1Z41-B003B control switch in STOP (OFF), GREEN light (step 7.1.4.1.4) illuminated.

As found should be OFF

10. Ensure OPEN the following dampers: At panel 1H11-P657, 1Z41-F009A CONFIRMS 1Z41-F009A &

1Z41-F030A 1Z41-F030A, OPENS, RED light (step 7.1.4.1.5) illuminated.

As found should be OPEN NOTE: 1Z41-F009A & 1Z41-F030A will open when AHU 1Z41-B003A is started.

11. Confirm CLOSE the following At panel 1H11-P654, dampers: CONFIRMS 1Z41-F009C &

1Z41-F009C 1Z41-F030C, CLOSES, GREEN 1Z41-F030C light illuminated.

(step 7.1.4.1.6)

As found should be CLOSED NOTE: 1Z41-F009C & 1Z41-F030C will close when AHU 1Z41-B003C is stopped.

12. CLOSE the following dampers: At panel 1H11-P654, PLACES 1Z41-F028A control switch for 1Z41-F028A &

1Z41-F028B 1Z41-F028B in CLOSE, GREEN (step 7.1.4.1.6) light illuminated.

As found should be CLOSED

(** Indicates critical step)

2021-301 CR-SIM 8 Page 9 of 11 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

13. CLOSE the following dampers: At panel 1H11-P654, PLACES 1Z41-F010A control switch for 1Z41-F010A &

1Z41-F010B 1Z41-F010B in CLOSE, GREEN (step 7.1.4.1.6) light illuminated.

As found should be CLOSED

14. Ensure CLOSE 1Z41-F009B, Recirc At panel 1H11-P654, ENSURES Line Isol Damper. 1Z41-F009B closes, GREEN (step 7.1.4.1.6) light illuminated.

As found should be CLOSED

15. Ensure CLOSE the following At panel 1H11-P654, PLACES dampers: control switch for 1Z41-F014A &

1Z41-F014A, Recirc Inlet 1Z41-F014B in CLOSE, GREEN 1Z41-F014B, Recirc Inlet light illuminated.

(step 7.1.4.1.6)

As found should be CLOSED

• • 16. OPEN Roll Filter Bypass, 1Z41-F015. At MCR Door C70, ROLL FILTER BYPASS, 1Z41-F015 (step 7.1.4.1.7) control switch is in OPEN, RED light illuminated.

As found should be CLOSED

17. Ensure OPEN Outside Air Intake At panel 1H11-P657, ENSURES Damper, 1Z41-F016. FILTER INLET control switch, (step 7.1.4.1.8) 1Z41-F016, is in OPEN position, RED light illuminated.

As found should be OPEN

18. Ensure OPEN or OPENS 1Z41-F011, At panel 1H11-P657, FILTER Filter Bypass. BYPASS control switch, 1Z41-F011, is in OPEN position, (step 7.1.4.1.9) RED light illuminated.

As found should be OPEN

(** Indicates critical step)

2021-301 CR-SIM 8 Page 10 of 11 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

19. Confirm OPEN or OPENS 1Z41- At panel 1H11-P654, FILTER F012, Filter Bypass. BYPASS control switch, (step 7.1.4.1.10) 1Z41-F012, is in OPEN position, RED light illuminated.

As found should be OPEN PROMPT: IF the Operator asks if additional smoke removal is required, INFORM the Operator that additional smoke removal is NOT required at this time.

END TIME:__________

NOTE: The terminating cue shall be given to the Operator when:

Operator completes step 19 of this JPM.

With NO reasonable progress, the Operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

2021-301 CR-SIM 8 Page 11 of 11 Summary of JPM Attributes JPM 2021-301 CR-SIM 8:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC Attributes JPM CONTENT Total Critical Steps At least 2 3 Step 4 Start Exhaust Fan, 1Z41-C011A Starts motive force needed to purge Step 6 Open Inlet Control vane, 1Z41-F017A Establishes flow Step 16 Open Roll Filter bypass (F015) Allows maximum intake air flowrate Number of JPM Steps <30 19

<45 min 15 min Time to Perform JPM Normal / Faulted / Alternate Path Normal Path Setting (administered)

Control Room NO NO Is LOD 1 or 5

2021-301 CR-SIM 8 Page 12 of 11 UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Purging of Unit 1 Control Room is desired.

2. The Main Control Room Ventilation System has been operating in a Normal Ventilation configuration for several days with the following alignment:

1Z41-B003A, HVAC Unit, RUN 1Z41-B003B, HVAC Unit, STBY 1Z41-B003C, HVAC Unit RUN INITIATING CUES:

Purge the Unit 1 Main Control Room with the Main Control Room Ventilation System per 34SO-Z41-001-1, Step 7.1.4.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL PLANT 1 (ALL)

Title FROM OUTSIDE THE MCR, INSERT A MANUAL REACTOR SCRAM (ALTERNATE PATH)

Author: Media Number Times Anthony Ball 2021-301 PLANT 1 14 Minutes Line Review By: Date N/A N/A Reviewed by Instructional Technologist or designee: Date N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 PLANT 1 Page 2 of 22 Course Number Program Name Media Number N/A OPERATIONS TRAINING 2021-301 PLANT 1 Ver. No. Date Reason for Revision Author Print Peer Review Initials/Name Print Initials/Name Reviewed JPM against current procedure for use on 2016-301 NRC Exam. Changed Media number to PLANT 1 2016-0.1 05/30/16 ARB ELJ 301 and will be returned to LR-JP-01018A after 2016-301 NRC Exam.

0.2 02/09/21 Updated for ILT-13 NRC Exam 2021-301. ARB JDW

2021-301 PLANT 1 Page 3 of 22 UNIT 1 (X) UNIT 2 (X)

TASK TITLE: FROM OUTSIDE THE MCR, INSERT A MANUAL REACTOR SCRAM (ALTERNATE PATH)

JPM NUMBER: 2021-301 PLANT 1 TASK STANDARD: The task shall be completed when the operator has successfully inserted a reactor scram using the SDV Level Switches per 31RS-OPS-001 by tripping magnetrol switches 1C11-N013A & B OR 1C11-N013C & D.

TASK NUMBER: 010.018 OBJECTIVE NUMBER: 010.018.A PLANT HATCH JTA IMPORTANCE RATING:

RO 4.20 SRO 4.67 K/A CATALOG NUMBER: 295006AA1.05 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.6 SRO 4.2 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 Unit 2 31RS-OPS-001-1, Ver 6.2 31RS-OPS-001-2, Ver 7.2 REQUIRED MATERIALS: Unit 1 Unit 2 31RS-OPS-001-1, Ver 6.2 31RS-OPS-001-2, Ver 7.2 APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: N/A

2021-301 PLANT 1 Page 4 of 22 EVALUATOR COPY UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. A condition has occurred which required the Control Room to be evacuated.

2. The Reactor is NOT shutdown.

3. 31RS-OPS-001-1, Shutdown From Outside the Control Room, is in progress.

4. Pre-Job Brief is NOT required.

INITIATING CUES:

Insert a Manual Scram by de-energizing RPS per 31RS-OPS-001-1.

2021-301 PLANT 1 Page 5 of 22 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

START TIME:__________

1. Operator identifies the procedure The Operator has IDENTIFIED needed to perform the task. the correct procedure as 31RS-OPS-001-1, step 4.4.

2. De-energize RPS. At panel 1C71-P001, the Operator OPENS breaker OPEN the following breakers at RPS distribution panel 1C71-P001: 1C71-CB3A.

1C71-CB3A Drawing Page 14 (Step 4.4.a.1)

(** Indicates critical step)

2021-301 PLANT 1 Page 6 of 22 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

3. De-energize RPS. At panel 1C71-P001, the OPEN the following breakers at RPS Operator ATTEMPTS to open breaker 1C71-CB3B. The distribution panel 1C71-P001:

Operator RECOGNIZES that the

• • • • • • • • • • breaker will NOT reposition.

1C71-CB3B (Step 4.4.a.1) Drawing Page 15 PROMPT: WHEN the Operator attempts to open breaker 1C71-CB3B, INFORM the Operator that the breaker did NOT reposition and can NOT be moved.

PROMPT: IF the Operator requests direction from the Shift Supervisor, INFORM the Operator to Insert a Manual Scram per 31RS-OPS-001-1.

NOTE: The Operator may elect to reclose breaker 1C71-CB3A prior to addressing the SDV Level Switches.

ALTERNATE PATH STARTS HERE (Step 4)

NOTE: The critical steps will be either steps 4, 5, 8, and 9 OR steps 6, 7, 10, and 11.

Both switches on one side of the Reactor Building will insert a Full Reactor Scram.

To receive credit, the Operator ONLY has to trip both magnetrol switches on one side of the Reactor Building.

• • 4. Scram Discharge Volume Level At location 139RER11, the Switches. Operator REMOVES the cover At the Scram Discharge Volume, from magnetrol switch 1C11-N013A using a flat head remove the covers to one of the following sets of level switches: screwdriver obtained from either the EOP Gang box on the 130 ft 1C11-N013A and ********* NE elevation, Maintenance Tool OR room or any OPS tool gangbox.

(Step 4.4.b.1) Drawing Page 16

(** Indicates critical step)

2021-301 PLANT 1 Page 7 of 22 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 5. Scram Discharge Volume Level At location 139RER11, the Switches. Operator REMOVES the cover At the Scram Discharge Volume, from magnetrol switch 1C11-N013B using a flat head remove the covers to one of the following sets of level switches: screwdriver obtained from either the EOP Gang box on the 130 ft

• • • • • • • • • • and 1C11-N013B, NE elevation, Maintenance Tool OR room or any OPS tool gangbox.

(Step 4.4.b.1) Drawing Page 16 NOTE: The Operator may remove the covers for 1C11-N013A and B, then trip their magnetrol switches and replace their covers. The Operator may stop there or proceed to performing the same actions for 1C11-N013C and D.

• • 6. Scram Discharge Volume Level At location 139RER03, the Switches. Operator REMOVES the cover from magnetrol switch At the Scram Discharge Volume, remove the covers to one of the 1C11-N013C using a flat head screwdriver obtained from either following sets of level switches:

the EOP Gang box on the 130 ft

• • • • • • • • • • • • • • • • • • • • • • • • • • • NE elevation, Maintenance Tool OR room or any OPS tool gangbox.

1C11-N013C and ************

(Step 4.4.b.1) Drawing Page 16

• • 7. Scram Discharge Volume Level At location 139RER03, the Switches. Operator REMOVES the cover from magnetrol switch At the Scram Discharge Volume, 1C11-N013D using a flat head remove the covers to one of the screwdriver obtained from either following sets of level switches:

the EOP Gang box on the 130 ft

• • • • • • • • • • • • • • • • • • • • • • • • • • • NE elevation, Maintenance Tool OR room or any OPS tool gangbox.

• • • • • • • • • • and 1C11-N013D (Step 4.4.b.1) Drawing Page 16

• • 8. Trip magnetrol switches for the At location 139RER11, the switches with removed covers: Operator TRIPS magnetrol switch 1C11-N013A and ***********, 1C11-N013A using a non-OR conductive object on switch

• • • • • • • • • • • • • • • • • • • • • • • • • • swing arm to the left.

(Step 4.4.b.2)

Drawing Page 17

(** Indicates critical step)

2021-301 PLANT 1 Page 8 of 22 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 9. Trip magnetrol switches for the At location 139RER11, the switches with removed covers: Operator TRIPS magnetrol

• • • • • • • • • • and 1C11-N013B, switche 1C11-N013B using a OR non-conductive object on switch

• • • • • • • • • • • • • • • • • • • • • • • • • • swing arm to the left.

(Step 4.4.b.2)

Drawing Page 17 PROMPT: IF the Operator trips 1C11-N013A & N013B FIRST, INFORM the Operator that a large amount of noise from the HCU & SDV area is occuring.

• • 10. Trip magnetrol switches for the At location 139RER03, the switches with removed covers: Operator TRIPS magnetrol

• • • • • • • • • • • • • • • • • • • • • • • • • , switche 1C11-N013C using a OR non-conductive object on switch 1C11-N013C and ********** swing arm to the left.

(Step 4.4.b.2)

Drawing Page 17.

• • 11. Trip magnetrol switches for the At location 139RER03, the switches with removed covers: Operator TRIPS magnetrol

• • • • • • • • • • • • • • • • • • • • • • • • • , switche 1C11-N013D using a OR non-conductive object on switch

• • • • • • • • • • AND 1C11-N013D swing arm to the left.

(Step 4.4.b.2)

Drawing Page 17 PROMPT: IF the Operator trips 1C11-N013C & N013D FIRST, INFORM the Operator that a large amount of noise from the HCU & SDV area is occuring.

(** Indicates critical step)

2021-301 PLANT 1 Page 9 of 22 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

12. Replace the covers to the magnetrol Operator REPLACES all switches. removed magnetrol switch (Step 4.4.b.3) covers.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when any of the following conditions are met:

Operator completes step 12 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: Another operator will continue from here.

(** Indicates critical step)

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. A condition has occurred which required the Control Room to be evacuated.

2. The Reactor is NOT shutdown.

3. 31RS-OPS-001-2, Shutdown From Outside the Control Room, is in progress.

4. Pre-Job Brief is NOT required.

INITIATING CUES:

Insert a Manual Scram by de-energizing RPS per 31RS-OPS-001-2.

2021-301 PLANT 1 Page 11 of 22 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

START TIME:__________

1. Operator identifies the procedure Operator has IDENTIFIED the needed to perform the task. correct procedure as 31RS-OPS-001-2 step 4.4

2. De-energize RPS. At panel 2C71-P001, the Operator OPENS breaker OPEN the following breakers at RPS 2C71-CB3A.

distribution panel 2C71-P001, at 130TGT12.

2C71-CB3A Drawing Page 14 (Step 4.4.1.1)

(** Indicates critical step)

2021-301 PLANT 1 Page 12 of 22 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

3. De-energize RPS. At panel 2C71-P001, the Operator ATTEMPTS to open OPEN the following breakers at RPS breaker 2C71-CB3B. The distribution panel 2C71-P001, Operator RECOGNIZES that the at 130TGT12.

breaker will NOT reposition.

2C71-CB3B (Step 4.4.1.1) Drawing Page 15 PROMPT: WHEN the Operator attempts to open breaker 2C71-CB3B, INFORM the Operator that the breaker did NOT reposition and can NOT be moved.

PROMPT: IF the Operator requests direction from the Shift Supervisor, INFORM the Operator to Insert a Manual Scram per 31RS-OPS-001-2.

NOTE: The Operator may elect to reclose breaker 2C71-CB3A prior to addressing the SDV Level Switches.

ALTERNATE PATH STARTS HERE (Step 4)

NOTE: The critical steps will be either steps 4, 5, 8, and 9 OR steps 6, 7, 10, and 11.

Both switches on one side of the Reactor Building will insert a Full Reactor Scram.

To receive credit, the Operator ONLY has to trip both magnetrol switches on one side of the Reactor Building.

• • 4. Scram Discharge Volume Level At location 130RBR15, the Switches. Operator REMOVES the cover Remove the covers to 2C11-N013A & from magnetrol switch 2C11-N013A using a flat head

• • • • • • • • • • • , Magnetrol Switches, at 130RBR15 ******************* screwdriver obtained from either

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • the EOP Gang box on the 130 ft NW elevation, Maintenance Tool (Step 4.4.2.1) room or any OPS tool gangbox.

Drawing Page 16

(** Indicates critical step)

2021-301 PLANT 1 Page 13 of 22 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 5. Scram Discharge Volume Level At location 130RBR15, the Switches. Operator REMOVES the cover from magnetrol switch Remove the covers to ********* &

2C11-N013B using a flat head 2C11-N013B, Magnetrol Switches, at 130RBR15 ******************* screwdriver obtained from either

• • • • • • • • • • • • • • • • • • • • • • • • • • • • • • • the EOP Gang box on the 130 ft NW elevation, Maintenance Tool (Step 4.4.2.1) room or any OPS tool gangbox.

Drawing Page 16 NOTE: The Operator may remove the covers for 2C11-N013A and B, then trip their magnetrol switches and replace their covers. The Operator may stop there or proceed to performing the same actions for 2C11-N013C and D.

• • 6. Scram Discharge Volume Level At location 130RBR23, the Switches. Operator REMOVES the cover from magnetrol switch Remove the covers *************

2C11-N013C using a flat head

• • • • • • • • • • • • • • OR 2C11-N013C &

screwdriver obtained from either

• • • • • • • • • • • , Magnetrol Switches, at the EOP Gang box on the 130 ft 130RBR23. (Step 4.4.2.1)

NW elevation, Maintenance Tool room or any OPS tool gangbox.

Drawing Page 16

• • 7. Scram Discharge Volume Level At location 130RBR23, the Switches. Operator REMOVES the cover from magnetrol switch Remove the covers ***************

2C11-N013D using a flat head

• • • • • • • • • • • • OR ************ &

screwdriver obtained from either 2C11-N013D, Magnetrol Switches, the EOP Gang box on the 130 ft at 130RBR23. (Step 4.4.2.1)

NW elevation, Maintenance Tool room or any OPS tool gangbox.

Drawing Page 16

(** Indicates critical step)

2021-301 PLANT 1 Page 14 of 22 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 8. Trip the magnetrol switches. At location 130RBR15, the (Step 4.4.2.2) Operator TRIPS magnetrol switche 2C11-N013A using a non-conductive object on switch swing arm to the left.

Drawing Page 17

• • 9. Trip the magnetrol switches. At location 130RBR15, the (Step 4.4.2.2) Operator TRIPS magnetrol switche 2C11-N013B using a non-conductive object on switch swing arm to the left.

Drawing Page 17 PROMPT: IF the Operator trips 2C11-N013A & N013B FIRST, INFORM the Operator that a large amount of noise from the HCU & SDV area is occuring.

• • 10. Trip the magnetrol switches. At location 130RBR23, the (Step 4.4.2.2) Operator TRIPS magnetrol switche 2C11-N013C using a non-conductive on switch swing arm to the left.

Drawing Page 17

• • 11. Trip the magnetrol switches. At location 130RBR23, the (Step 4.4.2.2) Operator TRIPS magnetrol switche 2C11-N013D using a non-conductive on switch swing arm to the left.

Drawing Page 17 PROMPT: IF the Operator trips 2C11-N013C & N013D FIRST, INFORM the Operator that a large amount of noise from the HCU & SDV area is occuring.

(** Indicates critical step)

2021-301 PLANT 1 Page 15 of 22 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

12. Replace the covers to the magnetrol Operator REPLACES all switches. removed magnetrol switch (Step 4.4.2.3) covers.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when any of the following conditions are met:

Operator completes step 12 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: Another operator will continue from here.

(** Indicates critical step)

Page 16 of 22 Page 17 of 22 Page 18 of 22 Page 19 of 22 2021-301 PLANT 1 Page 20 of 22 Summary of JPM Attributes JPM 2021-301 PLANT 1:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 4 Step 4/6 Remove SDV Level Switch Cover Operator removes 1/2C11-N013A(C) magnetrol switch cover to gain access to switch.

Step 5/7 Remove SDV Level Switch Cover Operator removes 1/2C11-N013B(D) magnetrol switch cover to gain access to switch.

Step 8/10 Trip SDV Level Switch Operator Trips 1/2C11-N013A(C) magnetrol switch to de-energize RPS A.

Step 9/11 Trip SDV Level Switch Operator Trips 1/2C11-N013B(D) magnetrol switch to de-energize RPS B.

Number of JPM Steps <30 12 Time to Perform JPM <45 min 14 min Normal / Faulted /

Alternate Path Alternate Path When the Operator attempts to insert a Reactor Scram by de-energizing RPS, one of the breakers will NOT open. The Operator must decide to continue with the procedure and insert a Reactor Scram with the SDV Level Switches in the Reactor Building.

Setting (administered)

Plant Is LOD 1 or 5 NO NO

Page 21 of 22 UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. A condition has occurred which required the Control Room to be evacuated.

2. The Reactor is NOT shutdown.

3. 31RS-OPS-001-1, Shutdown From Outside the Control Room, is in progress.

4. Pre-Job Brief is NOT required.

INITIATING CUES:

Insert a Manual Scram by de-energizing RPS per 31RS-OPS-001-1.

Page 22 of 22 UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. A condition has occurred which required the Control Room to be evacuated.

2. The Reactor is NOT shutdown.

3. 31RS-OPS-001-2, Shutdown From Outside the Control Room, is in progress.

4. Pre-Job Brief is NOT required.

INITIATING CUES:

Insert a Manual Scram by de-energizing RPS per 31RS-OPS-001-2.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL PLANT 2 (ALL)

Title FROM THE REMOTE SHUTDOWN PANEL, START RCIC FOR INJECTION INTO THE REACTOR Author: Media Number Times Anthony Ball 2021-301 PLANT 2 24 Minutes Line Technical Review By (N/A for minor revisions) Date:

Reviewed by Instructional Technologist or designee Date Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 PLANT 2 Page 2 of 17 Course Number Program Name Media Number OPERATIONS TRAINING 2021-301 PLANT 2 Ver. No. Date Reason for Revision Author Print Peer Review Initials/Name Print Initials/Name 15.1 02/09/21 Updated for ILT-13 NRC Exam 2021-301. ARB JDW

2021-301 PLANT 2 Page 3 of 17 UNIT 1 (X) UNIT 2 (X)

TASK TITLE: FROM THE REMOTE SHUTDOWN PANEL, START RCIC FOR INJECTION INTO THE REACTOR JPM NUMBER: 2021-301 PLANT 2 TASK STANDARD: The task shall be completed when the RCIC System is started and injecting to the Reactor per 31RS-OPS-001.

TASK NUMBER: 039.016 OBJECTIVE NUMBER: 039.016.O PLANT HATCH JTA IMPORTANCE RATING:

RO 3.86 SRO 3.80 K/A CATALOG NUMBER: 2950162130 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.90 SRO 3.40 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 Unit 2 31RS-OPS-001-1 Ver 6.2 31RS-OPS-001-2 Ver 7.2 REQUIRED MATERIALS: Unit 1 Unit 2 31RS-OPS-001-1 Ver 6.2 31RS-OPS-001-2 Ver 7.2 Key for Remote Shutdown (current version)

Panel (if performed in Plant) Key for Remote Shutdown Panel (if performed in Plant)

APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to a 100% power IC and leave in FREEZE.

2. INSERT the following MALFUNCTIONS:

MALF # TITLE FINAL RAMP ACT.

VALUE RATE TIME mf60233253 RCIC Turbine Trip (Annunciator OFF) N/A N/A 0000 mf60313337 Remote Shutdown Transfer Switch In Emerg N/A N/A 0000 Pos (Annunciator OFF) mf65013401 Turbine Trouble (Annunciator OFF) N/A N/A 0000 mf65023496 SEC System Auto Initiation Signal Present N/A N/A 0000 (Annunciator OFF)

3. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A. Allow the simulator to run for two minutes.

4. PLACE the Simulator in FREEZE until the INITIATING CUE is given.

5. ESTIMATED Simulator SETUP TIME: 15 Minutes

EVALUATOR COPY UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. An event has occurred which required the Control Room to be evacuated.

2. The Unit 1 Reactor was scrammed prior to the evacuation.

3. RCIC is in standby.

4. 31RS-OPS-001-1 is in progress.

INITIATING CUES:

Start the RCIC System from the Remote Shutdown Panel and inject water into the Reactor per 31RS-OPS-001-1, Attachment 3.

2021-301 PLANT 2 Page 6 of 17 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

START TIME:__________

NOTE: NRC EXAMINER MAINTAINS U1 RSDP KEY, RB-18, (CAT-60) BETWEEN DIFFERENT STUDENT EVALUATIONS.

1. Operator identifies the materials that Operator identifies required the are required. materials and where to obtain them.

PROMPT: IF the operator addresses posting of RCIC Diagonal, as the Shift Supervisor, INFORM the operator that Health Physics is posting the area.

(** Indicates critical step)

2021-301 PLANT 2 Page 7 of 17 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

2. Place the following Transfer Switches At panel 1C82-P001, the in EMERGENCY: following Transfer Switches are in EMER:

1C82-S23G (Att. 3 Step 1.a) XFER SW 1C82-S23G 1C82-S23B (Att. 3 Step 1.b) XFER SW 1C82-S23B 1C82-S23C (Att. 3 Step 1.c) XFER SW 1C82-S23C 1C82-S23D (Att. 3 Step 1.c) XFER SW 1C82-S23D 1C82-S23E (Att. 3 Step 1.e) XFER SW 1C82-S23E 1C82-S23F (Att. 3 Step 1.f) XFER SW 1C82-S23F

3. Locally ensure the position of the The operator has addressed following valves: contacting a SO to VERIFY the 1E51-F010 (Att. 3 Step 2.a) following valves are in the correct position:

1E51-F012 (Att. 3 Step 2.b)

CONDENSATE STORAGE 1E51-F029 (Att. 3 Step 2.c)

SUCTION VLV, 1E51-F010, is 1E51-F031 (Att. 3 Step 2.d) OPEN.

PUMP DISCHARGE VLV, 1E51-F012, is OPEN.

SUPPRESSION POOL SUCTION VLV, 1E51-F029, is CLOSED.

SUPPRESSION POOL SUCTION VLV, 1E51-F031, is CLOSED.

PROMPT: WHEN the operator addresses locally confirming positions of valves, as the SO, INFORM the operator that:

1E51-F010 and 1E51-F012 are open.

1E51-F029 and 1E51-F031 are closed.

4. Ensure 1E51-F045 is closed. At panel 1C82-P001, STM TO (Att. 3 Step 3.a) TURB VLV, 1E51-F045, is in CLOSE, green light illuminated.

• • 5. Open 1E51-F046. At panel 1C82-P001, TURB CLG (Att. 3 Step 3.b) WTR VLV, 1E51-F046, is in OPEN, red light illuminated.

6. Ensure 1E51-F013 is closed. At panel 1C82-P001, RCIC (Att. 3 Step 3.c) PUMP DISCH VLV, 1E51-F013, is in CLOSE, green light illuminated.

(** Indicates critical step)

2021-301 PLANT 2 Page 8 of 17 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

7. Ensure 1E51-F007 is open. At panel 1C82-P001, INBD ISOL (Att. 3 Step 3.d) VLV, 1E51-F007, is in OPEN, red light illuminated.

8. Ensure 1E51-F524 is open. At panel 1C82-P001, RCIC TRIP (Att. 3 Step 3.e) & THRT VLV, 1E51-F524, is OPEN, red light illuminated.

9. Confirm 1E51-F008 is open. At panel 1C82-P001, OUTBD (Att. 3 Step 3.f) ISOL VLV, 1E51-F008, is in OPEN, red light illuminated.

10. Start the Barometric Condenser At panel 1C82-P001, Vacuum Pump. BAROMETRIC CNDSR VAC (Att. 3 Step 3.g) PUMP Switch is in START, red light illuminated.

11. Start the Barometric Condenser At panel 1C82-P001, Condensate Pump. BAROMETRIC CNDSR COND (Att. 3 Step 3.h) PUMP Switch is in RUN, red light illuminated.

NOTE: The operator should not address opening 1E41-F011 and 1E51-F022 since RCIC operation will NOT be for Reactor pressure control.

PROMPT: IF the operator addresses purpose for RCIC operation, as the Shift Supervisor, INFORM the operator that RCIC operation is for RWL control.

• • 12. Open valve 1E51-F045. At panel 1C82-P001, STM TO (Att. 3 Step 5) TURB VLV, 1E51-F045, is OPEN, red light illuminated.

PROMPT: WHEN the operator opens 1E51-F045, INFORM the operator that turbine speed is rising.

• • 13. Open valve 1E51-F013. At panel 1C82-P001, RCIC (Att. 3 Step 6) PUMP DISCH VLV, 1E51-F013, is OPEN, red light illuminated.

PROMPT: WHEN the operator opens 1E51-F013, as the 1H21-P173 Panel operator, INFORM the operator that flow is rising.

(** Indicates critical step)

2021-301 PLANT 2 Page 9 of 17 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

14. Locally confirm valve 1E51-F019 The operator has addressed closes when RCIC flow exceeds 122.5 contacting a SO to confirm MIN gpm. FLOW VLV, 1E51-F019, is (Att. 3 Step 7) CLOSED.

PROMPT: WHEN the operator addresses 1E51-F019, as the SO, INFORM the operator that 1E51-F019 is closed.

PROMPT: IF the operator addresses RWL band, as the Shift Supervisor, INFORM the operator that another operator will maintain RWL.

PROMPT: WHEN the operator addresses monitoring parameters at 1H21-P173, as the Shift Supervisor, INFORM the operator that they are being monitored by an operator at 1H21-P173.

PROMPT: IF the operator addresses securing RCIC or system restoration, as the Shift Supervisor, INFORM the operator that it is NOT desired at this time.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when:

Operator completes step 14 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

2021-301 PLANT 2 Page 10 of 17 EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. An event has occurred which required the Control Room to be evacuated.

2. The Unit 2 Reactor was scrammed prior to the evacuation.

3. RCIC is in standby.

4. 31RS-OPS-001-2 is in progress.

INITIATING CUES:

Start the RCIC System from the Remote Shutdown Panel and inject water into the Reactor per 31RS-OPS-001-2, Attachment 3.

2021-301 PLANT 2 Page 11 of 17 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-111, On-The-Job Training and Task Performance Evaluation START TIME:__________

NOTE: NRC EXAMINER MAINTAINS RSDP KEY (2RB-22) BETWEEN DIFFERENT STUDENT EVALUATIONS.

1. Operator identifies the materials that Operator identifies the required are required. materials and where to obtain them.

PROMPT: IF the operator addresses posting of RCIC Diagonal, as the Shift Supervisor, INFORM the operator that Health Physics is posting the area.

(** Indicates critical step)

2021-301 PLANT 2 Page 12 of 17 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 2. Place the following Transfer Switches At panel 2C82-P001, the in EMERGENCY: following Transfer Switches are 2C82-S7 (Att. 3 Step 1.1) in EMERGENCY:

2C82-S53 (Att. 3 Step 1.2) XFER SW 2C82-S7 2C82-S52 (Att. 3 Step 1.3) XFER SW 2C82-S53 2C82-S6 (Att. 3 Step 1.4) XFER SW 2C82-S52 2C82-S4 (Att. 3 Step 1.4) XFER SW 2C82-S6 2C82-S5 (Att. 3 Step 1.5) XFER SW 2C82-S4 2C82-S3 (Att. 3 Step 1.6) XFER SW 2C82-S5 2C82-S2 (Att. 3 Step 1.7) XFER SW 2C82-S3 2C82-S8 (Att. 3 Step 1.8) XFER SW 2C82-S2 2C82-S18 (Att. 3 Step 1.9) XFER SW 2C82-S8 XFER SW 2C82-S18

3. Ensure the following valves are open: At panel 2C82-P001, the operator 2E51-F010 (Att. 3 Step 2.1) VERIFIES the following valves are OPEN, red light illuminated:

2E51-F012 (Att. 3 Step 2.2)

CST SUCTION VLV, 2E51-F010 2E51-F007 (Att. 3 Step 2.3)

DISCH VLV, 2E51-F012 2E51-F008 (Att. 3 Step 2.4)

STEAM SUPPLY INBD ISOL VLV, 2E51-F007 STEAM SUPPLY OUTBD ISOL VLV, 2E51-F008.

NOTE: The operator should not perform Section 3.0 of Attachment 3 since RCIC operation will NOT be for Reactor pressure control.

4. Confirm the RCIC Flow Controller is At panel 2C82-P001, the operator in AUTO and set for 400 gpm. VERIFIES RCIC FLOW CONTROL, 2C82-R001:

Is in AUTO.

Is set for 400 gpm (accept 350 to (Att. 3 Step 2.d) 450 gpm).

(** Indicates critical step)

2021-301 PLANT 2 Page 13 of 17 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

5. Ensure the following valves are At panel 2C82-P001, the operator closed: VERIFIES the following valves 2E51-F029 (Att. 3 Step 6.1) are CLOSED, green light illuminated:

2E51-F031 (Att. 3 Step 6.2)

TORUS OUTBD SUCTION 2E51-F022 (Att. 3 Step 6.3)

VLV, 2E51-F029 TORUS INBD SUCTION VLV, 2E51-F031 TEST LINE TO CST, 2E51-F022 NOTE: The operator should not address opening 2E51-F029 and 2E51-F031 since 2E51-F010 is open.

6. Start the Barometric Condenser At panel 2C82-P001, the Vacuum Pump. BAROMETRIC CNDSR VAC (Att. 3 Step 7.0) PUMP, 2E51-C002-2, is in START, red light illuminated.

7. Start the Barometric Condenser At panel 2C82-P001, the Condensate Pump. BAROMETRIC CNDSR COND (Att. 3 Step 8.0) PUMP, 2E51-C002-1, is in START, red light illuminated.

8. Ensure the Trip and Throttle Vlv is At panel 2C82-P001, the operator open. has verified TRIP & THROTTLE (Att. 3 Step 9.0) VLV, 2E51-F524, is OPEN, red light illuminated.

• • 9. Open valve 2E51-F046. At panel 2C82-P001, TURB CLG (Att. 3 Step 10.0) WTR VLV, 2E51-F046, is OPEN, red light illuminated.

10. Open valve 2E51-F019. At panel 2C82-P001, MIN (Att. 3 Step 11.0) FLOW VLV, 2E51-F019, is OPEN, red light illuminated.

• • 11. Open valve 2E51-F045. At panel 2C82-P001, STM TO (Att. 3 Step 12.0) TURB VLV, 2E51-F045 is OPEN, red light illuminated.

PROMPT: WHEN the operator opens 2E51-F045, INFORM the operator that speed is rising.

PROMPT: IF the operator addresses purpose for RCIC operation, as the Shift Supervisor, INFORM the operator that RCIC operation is for RWL control.

(** Indicates critical step)

2021-301 PLANT 2 Page 14 of 17 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 12. Open valve 2E51-F013. At panel 2C82-P001, DISCH (Att. 3 Step 13.0) VLV, 2E51-F013, is OPEN, red light illuminated.

PROMPT: WHEN the operator opens 2E51-F013, INFORM the operator that flow is rising on RCIC PUMP FLOW 2C82-R001 indicator at panel 2C82-P001.

• • 13. Close the Minimum Flow Valve, At panel 2C82-P001, when flow 2E51-F019 when flow exceeds 122.5 is greater than 122.5 gpm on gpm. RCIC FLOW, 2C82-R002, MIN FLOW VLV, 2E51-F019, is (Att. 3 Step 16.0) CLOSED, green light illuminated.

PROMPT: WHEN the operator requests RCIC flow, INFORM the operator that flow is greater than 122.5 gpm on RCIC PUMP FLOW 2C82-R001 indicator at panel 2C82-P001.

PROMPT: IF the operator addresses RWL band, as the Shift Supervisor, INFORM the operator that another operator will maintain RWL.

PROMPT: IF the operator addresses securing RCIC or system restoration, as the Shift Supervisor, INFORM the operator that it is not desired at this time.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when:

Operator completes step 13 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

2021-301 PLANT 2 Page 15 of 17 Summary of JPM Attributes JPM 2021-301 Plant 2:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC Attributes JPM CONTENT Total Critical Steps At least 2 4/5 Step 2 Place Unit 2 transfer switches in emergency Transfer control 2C82-P001 Step 5/9 Open 1/2E51-F046 Supply RCIC Lube oil cooler Step 12/11 Open valve 1/2E51-F045 Steam to RCIC turbine Step 13/12 Open valve 1/2E51-F013 RCIC pump discharge Step 13 Close 2E51-F019 Prevents flow from CST to Torus Number of JPM Steps <30 13

<45 min 24 min Time to Perform JPM Normal / Faulted / Alternate Path Normal Path Setting (administered)

Plant NO NO Is LOD 1 or 5

UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. An event has occurred which required the Control Room to be evacuated.

2. The Unit 1 Reactor was scrammed prior to the evacuation.

3. RCIC is in standby.

4. 31RS-OPS-001-1 is in progress.

INITIATING CUES:

Start the RCIC System from the Remote Shutdown Panel and inject water into the Reactor per 31RS-OPS-001-1, Attachment 3.

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. An event has occurred which required the Control Room to be evacuated.

2. The Unit 2 Reactor was scrammed prior to the evacuation.

3. RCIC is in standby.

4. 31RS-OPS-001-2 is in progress.

INITIATING CUES:

Start the RCIC System from the Remote Shutdown Panel and inject water into the Reactor per 31RS-OPS-001-2, Attachment 3.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL PLANT 3 (ALL)

Title CROSSTIE INSTRUMENT BUS "B" TO INSTRUMENT BUS "A" Author: Media Number Times Anthony Ball 2021-301 PLANT 3 15.0 Minutes Line Review By: Date N/A N/A Reviewed by Instructional Technologist or designee: Date N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 PLANT 3 Page 2 of 8 Course Number Program Name Media Number N/A OPERATIONS TRAINING 2021-301 PLANT 3 Ver. No. Date Reason for Revision Author Print Peer Review Initials/Name Print Initials/Name This JPM was modified to match procedure and renumbered 7.2 08/16/13 from LR-JP-20019 for ILT-8 NRC Exam. After this exam it ARB CME will be re-titled back to original LR JPM number.

7.3 02/09/21 Updated for ILT-13 NRC Exam 2021-301. ARB JDW

2021-301 PLANT 3 Page 3 of 8 UNIT 1 ( ) UNIT 2 (X)

TASK TITLE: CROSSTIE INSTRUMENT BUS "B" TO INSTRUMENT BUS "A" JPM NUMBER: 2021-301 PLANT 3 TASK STANDARD: The task shall be completed when Instrument Bus B is crosstied to Instrument Bus A per 34AB-R25-002.

TASK NUMBER: 200.019 OBJECTIVE NUMBER: 200.019.A PLANT HATCH JTA IMPORTANCE RATING:

RO 4.00 SRO 3.64 K/A CATALOG NUMBER: 262001A207 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.00 SRO 3.20 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 Unit 2 34AB-R25-002-2, Ver 11.1 REQUIRED MATERIALS: Unit 1 Unit 2 34AB-R25-002-2 Ver 11.1 Unit 2 RPS MG Set Room CAT 60 key APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: N/A

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is operating at 60% power.

2. Essential Cabinet 2B, 2R25-S037, is de-energized.

3. Instrument Bus 2B, 2R25-S065, is de-energized due to the loss of Essential Cabinet 2B, 2R25-S037.

4. 34AB-R24-001-2, Loss of Essential AC Distribution Buses, is in progress.

5. Essential Cabinet 2B, 2R25-S037, cannot be energized due to a faulted Feeder Breaker from 600 VAC Bus 2D, 2R23-S004.

6. 34AB-R25-002-2, Loss of Instrument Buses, is in progress.

INITIATING CUES:

Energize Instrument Bus 2B, 2R25-S065, from Instrument Bus 2A, 2R25-S064, per 34AB-R25-002-2.

2021-301 PLANT 3 Page 5 of 8 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

START TIME:_________

• • 1. At Essential Cabinet 2B, At Essential Cabinet 2B, 2R25-S037, OPEN Breaker 28. 2R25-S037, Breaker 28, 120/208V CAB 2C INSTR BUS (step 4.2.4.4.b.1) 2B, is OPEN. Breaker switch is in the OFF position.

• • 2. In the Unit 2 RPS M/G Set Room, at At Instrument Bus 2B, Instrument Bus 2B, 2R25-S065, 2R25-S065, Breaker 40, CLOSE Breaker 40. CROSSTIE TO INSTR BUS 2A, is CLOSED. Breaker switch is in (step 4.2.4.4.b.2) the ON position.

• • 3. At Instrument Bus 2A, 2R25-S064, At Instrument Bus 2A, CLOSE Breaker 39. 2R25-S064, Breaker 39, CROSSTIE TO INSTR BUS 2B, (step 4.2.4.4.b.3) is CLOSED. Breaker is in the ON position.

(** Indicates critical step)

2021-301 PLANT 3 Page 6 of 8 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 4. At Essential Cabinet 2B, OPEN At Essential Cabinet 2B, switch switch 2R26-M004 and REMOVE 2R26-M004 is OPEN and both both keys. keys are removed.

(step 4.2.4.4.b.4)

• • 5. In the Unit 2 RPS MG Set Room, In the Unit 2 RPS MG Set Room, INSERT one key in 2R26-M003 and 2R26-M003 is CLOSED.

CLOSE the switch.

(step 4.2.4.4.b.5)

• • 6. In the Unit 2 RPS MG Set Room, In the Unit 2 RPS MG Set Room, INSERT one key in 2R26-M005 and 2R26-M005 is CLOSED.

CLOSE the switch.

(step 4.2.4.4.b.6)

PROMPT: IF the operator addresses restoring any of the loads of the Instrument Bus, as the Shift Supervisor, INFORM the operator that another operator will perform the load restoration.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when:

When the operator completes step 6.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

2021-301 PLANT 3 Page 7 of 8 Summary of JPM Attributes JPM 2021-301-PLANT 3:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC Attributes JPM CONTENT Total Critical Steps At least 2 6 Step 1 Open Breaker 28 Opens normal supply breaker to instrument bus.

Step 2 Close Breaker 40 Aligns for crosstieing.

Step 3 Close Breaker 39 Aligns for crosstieing.

Step 4 OPEN switch 2R26-M004 At Essential Cabinet 2B, switch 2R26-M004 is OPEN and both and REMOVE both keys keys are removed.

Step 5 Close 2R26-M003 Closes first disconnect to crosstie.

Step 6 Close 2R26-M005 Closes second disconnect completes crosstie steps.

Number of JPM Steps <30 6 Time to Perform JPM <45 min 15 min Normal / Faulted / Alternate Path Normal Operator told to energize Instrument Bus 2B.

Setting (administered)

Plant Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is operating at 60% power.

2. Essential Cabinet 2B, 2R25-S037, is de-energized.

3. Instrument Bus 2B, 2R25-S065, is de-energized due to the loss of Essential Cabinet 2B, 2R25-S037.

4. 34AB-R24-001-2, Loss of Essential AC Distribution Buses, is in progress.

5. Essential Cabinet 2B, 2R25-S037, cannot be energized due to a faulted Feeder Breaker from 600 VAC Bus 2D, 2R23-S004.

6. 34AB-R25-002-2, Loss of Instrument Buses, is in progress.

INITIATING CUES:

Energize Instrument Bus 2B, 2R25-S065, from Instrument Bus 2A, 2R25-S064, per 34AB-R25-002-2.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL RO ADMIN 1 Title DIESEL GENERATOR FUEL OIL TANK Author: Media Number: Time Anthony Ball 2021-301 RO ADMIN 1 20.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

Reviewed by Instructional Technologist or designee Date Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 RO ADMIN 1 Page 2 of 13 Course Number Program Name Media Number OPERATIONS TRAINING 2021-301 RO ADMIN 1 Ver. No. Date Reason for Revision Author Print Peer Review Initials/Name Print Initials/Name 00 10/16/09 Initial development ARB CME 0.1 02/09/21 Updated for ILT-13 NRC Exam 2021-301. ARB JDW

2021-301 RO ADMIN 1 Page 1 of 13 UNIT 1 (X) UNIT 2 (X)

TASK TITLE: DIESEL GENERATOR FUEL OIL TANK JPM NUMBER: 2021-301 RO ADMIN 1 TASK STANDARD: The task shall be complete when the operator has determined the Total quantity of fuel.

TASK NUMBER:

OBJECTIVE NUMBER: R43-EDG-LP-02801, 028.011A PLANT HATCH JTA IMPORTANCE RATING:

RO SRO K/A CATALOG NUMBER: 2.1.26 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.4 SRO 3.6 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 & 2 34SO-R43-001-1, Diesel Generator Standby AC System, Ver. 29.3 REQUIRED MATERIALS: Unit 1 & 2 34SO-R43-001-1, Diesel Generator Standby AC System, Ver. 29.3, and Attachment 8.

APPROXIMATE COMPLETION TIME: 20 Minutes SIMULATOR SETUP: N/A

1 EVALUATOR COPY UNIT 1 & 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Fuel Oil was transferred from the 1A Main Storage Tank to the 2A and 2C Main Storage Tanks IAW Section 4.5.1 of 34SO-R43-001-1, Diesel Generator Standby AC System, and is complete up to and including step 4.5.1.11.

2. Final Control Room indications & Dipstick values (AFTER THE TRANSFER) for all Main Storage Tank quantities are listed below:

1A Main Storage Tank 35,000 gallons Dipstick value - 115 inches 1B Main Storage Tank 37,700 gallons Dipstick value - 125 inches 1C Main Storage Tank 38,120 gallons Dipstick value - 126.5 inches 2A Main Storage Tank 38,180 gallons Dipstick value - 127 inches 2C Main Storage Tank 37,950 gallons Dipstick value - 126 inches

3. You are a licensed operator performing this activity.

INITIATING CUES:

IAW 34SO-R43-001-1, Determine that the Main Fuel Oil Tank Inventories are correct by performing the appropriate subsection of Attachment 8.

2021-301 RO ADMIN 1 Page 3 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

START TIME:__________

1. Obtains the procedures. Operator has obtained the procedure 34SO-R43-001-1.

2. Review the procedures precautions Operator reviews precautions and and limitations. limitations.

3. Identifies the correct section. Operator identifies Attachment 8 as the correct section to reference.

NOTE: Precaution 2.1.8 allows Control Room indication for 2A to be used for level determination since it is NOT sensitive to the variations in specific gravity of the received fuel oil.

• • 4. If 2R43-R608A Control Room Main Operator enters 2A storage tank Tk Indication is operable level 38,180 gallons.

Record reading.

Diesel Gen 2A Storage Tank Level (Att. 8 Step 1.1)

2021-301 RO ADMIN 1 Page 4 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

NOTE: Precaution 2.1.8 allows Control Room indication for 2C to be used for level determination since it is NOT sensitive to the variations in specific gravity of the received fuel oil.

• • 5. If 2R43-R608C Control Room Main Operator enters 2C storage tank Tk Indication is operable level 37,950 gallons.

Record reading Diesel Gen 2C Storage Tank Level (Att. 8 Step 1.1)

6. If 2R43-R608A Control Room Main Operator enters N/A for Diesel Tk Indication is INOP with a Gen 2A Storage Tank Level dipstick, measure the level of the tank inches.

then record the level.

Diesel Gen 2A Storage Tank Level (Att. 8 Step 1.2)

7. If 2R43-R608C Control Room Main Operator enters N/A for Diesel Tk Indication is INOP with a Gen 2C Storage Tank Level dipstick, measure the level of the tank inches.

then record the level.

Diesel Gen 2C Storage Tank Level (Att. 8 Step 1.2)

8. IF Attachment 8 Section 1.0 Step 2 Operator enters N/A for Diesel was performed convert the storage Gen 2A Storage Tank Level tank level from inches to gallons gallons.

utilizing Table 1, Diesel Gen Main Fuel Oil Storage Tank; AND record the quantities:

(Att. 8 Step 1.3)

2021-301 RO ADMIN 1 Page 5 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

9. IF Attachment 8 Section 1.0 Step 2 Operator enters N/A for Diesel was performed convert the storage Gen 2C Storage Tank Level tank level from inches to gallons gallons.

utilizing Table 1, Diesel Gen Main Fuel Oil Storage Tank; AND record the quantities:

(Att. 8 Step 1.3)

NOTE: A Note on page 2 of Att. 8 states that Control Room indication can NOT be used for 1A since the level is approaching the administrative limit of 35,000 gallons.

• • 10. IF 1R43-R901A Control Room Main Operator enters N/A for Diesel Tk Indicator is operable AND tank Gen 1A Storage Tank Level level is NOT approaching the lower gallons due to approaching Administrative limit of 35,000 35,000 gallons.

gallons OR raised due to fuel oil Indicated level is 35,000 gallons.

addition, record reading.

(Att. 8 Step 1.4)

NOTE: A Note on page 2 of Att. 8 states that Control Room indication can be used for 1B and 1C since no addition of fuel oil has occurred to this tank.

• • 11. IF 1R43-R901B Control Room Main Operator enters 37,700 for Diesel Tk Indicator is operable AND tank Gen 1B Storage Tank Level level is NOT approaching the lower gallons.

Administrative limit of 35,000 gallons OR raised due to fuel oil addition, record reading.

(Att. 8 Step 1.4)

• • 12. IF 1R43-R901C Control Room Main Operator enters 38,120 for Diesel Tk Indicator is operable AND tank Gen 1C Storage Tank Level level is NOT approaching the lower gallons.

Administrative limit of 35,000 gallons OR raised due to fuel oil addition, record reading.

(Att. 8 Step 1.4)

2021-301 RO ADMIN 1 Page 6 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 13. IF Control Room Indicators are Operator enters 115.0 inches for inoperable OR otherwise required, Diesel Gen 1A Storage Tank.

THEN at Diesel Gen 1A Storage Tank, with a dipstick, measure the level of the tank AND record reading.

(Att. 8 Step 1.5)

14. IF Control Room Indicators are Operator enters N/A for Diesel inoperable OR otherwise required, Gen 1B Storage Tank Level THEN at Diesel Gen 1B Storage inches.

Tank, with a dipstick, measure the level of the tank AND record reading.

(Att. 8 Step 1.5)

15. IF Control Room Indicators are Operator enters N/A for Diesel inoperable OR otherwise required, Gen 1C Storage Tank Level THEN at Diesel Gen 1C Storage inches.

Tank, with a dipstick, measure the level of the tank AND record reading.

(Att. 8 Step 1.5)

• • 16. IF Attachment 8 Section 1.0 Step 5 Operator enters 34,993.36 for was performed, convert the storage Diesel Gen 1A Storage Tank tank level from inches to gallons Level gallons.

utilizing Table 1, Diesel Gen Main Fuel Oil Storage Tank; AND record the quantities:

(Att. 8 Step 1.6)

17. IF Attachment 8 Section 1.0 Step 5 Operator enters N/A for Diesel was performed, convert the storage Gen 1B Storage Tank Level tank level from inches to gallons gallons.

utilizing Table 1, Diesel Gen Main Fuel Oil Storage Tank; AND record the quantities:

(Att. 8 Step 1.6)

2021-301 RO ADMIN 1 Page 7 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

18. IF Attachment 8 Section 1.0 Step 5 Operator enters N/A for Diesel was performed, convert the storage Gen 1C Storage Tank Level tank level from inches to gallons gallons.

utilizing Table 1, Diesel Gen Main Fuel Oil Storage Tank; AND record the quantities:

(Att. 8 Step 1.6)

• • 19. Add Diesel Gen Storage Tanks 1A, Operator enters 186,943.36 for 1B, 1C, 2A AND 2C quantities AND total inventory gallons when record the total inventory. using 1A Dipstick & four (Att. 8 Step 1.7) remaining CR indicators OR enters 186,955 for total inventory gallons when using All Dipstick values.

Acceptable range is between 186,700 to 187,200 gallons

(+ 100 gallons per tank avg.).

20. Check the total inventory of Fuel Oil Operator initials for inventory Storage Tanks 1A, 1B, 1C, 2A, AND being greater than 175,000 2C is greater than 175,000 gallons. gallons.

(Att. 8 Step 1.9)

21. Check the level in each of the Operator initials for tanks following Fuel Oil Storage Tanks is 2Y52-A001A, 2Y52-A001C, greater than 35,000 gallons (Tech. 1R43-A002B, 1R43-A002C Spec. greater than/equal to 33,320 gallons).

(Att. 8 Step 1.10) But not for 1R43-A002A

• • 22. IF any Main Fuel Oil Storage Tank Operator notifies the SS that tank level is less than 35,000 gallons 1R43-A002A is 34,993.36 (Tech. Spec. greater than/equal to gallons which less than 35,000 33,320 gallons), AND/OR the total gallons but greater than 33,320 inventory of fuel oil is less than gallons and total inventory is 175,000 gallons, THEN notify the 186,943.36 gallons greater than Unit 1 Shift Supervisor. 175,000 gallons.

(Att. 8 Step 1.11)

2021-301 RO ADMIN 1 Page 8 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

PROMPT: IF the student asks about performing Day Tank quantities, INFORM the operator that another operator will perform these items.

END TIME:__________

NOTE: The terminating cue shall be given to the Operator when:

Operator completes step 22 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

2021-301 RO ADMIN 1 Page 9 of 13 Summary of JPM Attributes JPM: 2021-301 RO ADMIN 1:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 8 Step 4 Determines 2A Tk indication valid Records 2A tank volume for TS purpose.

Step 5 Determines 2C Tk indication valid Records 2C tank volume for TS purpose.

Step 10 Determine 1A Tk indication invalid N/A step due to tank level approaching limit.

Step 11 Determines 1B Tk indication valid Records 1B tank volume for TS purpose.

Step 12 Determines 1C Tk indication valid Records 1C tank volume for TS purpose.

Step 13 Record 1A Storage Tank dipped level Records 1A Tk level inches for TS purpose.

Step 16 Convert 1A TK level to gallons Records 1A tank volume for TS purpose.

Step 19 Add all tanks Record total inventory for TS purpose.

Step 22 Notify SS Reports 1A Tk not meeting admin limit.

Number of JPM Steps <30 22 Time to Perform JPM

<45 min 20 min Normal / Faulted /

Alternate Path Normal Setting (administered)

Classroom Is LOD 1 or 5 NO NO

2021-301 RO ADMIN 1 Page 10 of 13 ANSWER KEY DO NOT GIVE TO OPERATORS JPM Step **4. (Att. 8 Step 1.1) Records 38,180 gallons for 2A Storage Tank JPM Step **5. (Att. 8 Step 1.1) Records 37,950 gallons for 2C Storage Tank JPM Step **10. (Att. 8 Step 1.4) Records N/A (Diesel Gen 1A Storage Tank Level cannot be used)

JPM Step **11. (Att. 8 Step 1.4) Records 37,700 gallons for 1B Storage Tank JPM Step **12. (Att. 8 Step 1.4) Records 38,120 gallons for 1C Storage Tank JPM Step **13. (Att. 8 Step 1.5) Records 115 inches for 1A Storage Tank JPM Step **16. (Att. 8 Step 1.6) Converts inches to gallons & Records 34,993.36 gallons for 1A Storage Tank JPM Step **19. (Att. 8 Step 1.7) Records Total of 186,943.36 gallons

UNIT 1 & 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Fuel Oil was transferred from the 1A Main Storage Tank to the 2A and 2C Main Storage Tanks IAW Section 4.5.1 of 34SO-R43-001-1, Diesel Generator Standby AC System, and is complete up to and including step 4.5.1.11.

2. Final Control Room indications & Dipstick values (AFTER THE TRANSFER) for all Main Storage Tank quantities are listed below:

1A Main Storage Tank 35,000 gallons Dipstick value - 115 inches 1B Main Storage Tank 37,700 gallons Dipstick value - 125 inches 1C Main Storage Tank 38,120 gallons Dipstick value - 126.5 inches 2A Main Storage Tank 38,180 gallons Dipstick value - 127 inches 2C Main Storage Tank 37,950 gallons Dipstick value - 126 inches

3. You are a licensed operator performing this activity.

INITIATING CUES:

IAW 34SO-R43-001-1, Determine that the Main Fuel Oil Tank Inventories are correct by performing the appropriate subsection of Attachment 8.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL RO ADMIN 2 Title DETERMINE IF PLANT CONDITIONS ALLOW A "QUICK RESTART" OF A RECIRC PUMP Author: Media Number: Time Anthony Ball 2021-301 RO ADMIN 2 15.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

Reviewed by Instructional Technologist or designee Date Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 RO ADMIN 2 Page 2 of 14 Course Number Program Name Media Number OPERATIONS TRAINING 2021-301 RO ADMIN 2 Ver. No. Date Reason for Revision Author Print Peer Review Initials/Name Print Initials/Name Modified from LR-JP-25050 & will become new 0.0 06/07/12 ARB CME LR-JP-25053 after NRC Exam.

Minor revision to match procedure and use on ILT-10 NRC Exam. Reviewed JPM against current procedure. Changed 1.0 05/30/16 Media Number to 2016-301 ADMIN 6. This JPM will RAG ELJ become LR-JP-25061 after NRC Exam.

1.1 02/09/21 Updated for ILT-13 NRC Exam 2021-301. ARB JDW

2021-301 RO ADMIN 2 Page 3 of 14 UNIT 1 (X) UNIT 2 (X)

TASK TITLE: DETERMINE IF PLANT CONDITIONS ALLOW A "QUICK RESTART" OF A RECIRC PUMP JPM NUMBER: 2021-301 RO ADMIN 2 TASK STANDARD: The task shall be complete when Attachment 6 of 34SO-B31-001-1, Reactor Recirculation System, has been performed through Step 5.2, and it has been determined that the requirements have NOT been met to start Recirc pump 1B.

TASK NUMBER: 004.002 OBJECTIVE NUMBER: 004.002.C K/A CATALOG NUMBER: Generic 2.1.20 K/A CATALOG JTA IMPORTANCE RATING:

RO 4.6 SRO 4.6 OPERATOR APPLICABILITY: NPO and SRO GENERAL

REFERENCES:

Unit 1 34SO-B31-001-1, Ver 48.2 REQUIRED MATERIALS: Unit 1 34SO-B31-001-1, Ver 48.2 APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: N/A

2 EVALUATOR COPY UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. 10 minutes ago, the Unit 1 reactor scrammed from 100% power.

2. Both Recirc Pumps tripped during the scram transient.

3. RWL went as low as -10 inches and has been restored to +37 inches using Reactor Feedwater Pumps.

4. Data has been collected for use in Attachment 6 of 34SO-B31-001-1.

5. Per the STA, the Power/flow condition is acceptable for restart of Recirc Pump 1B.

INITIATING CUES:

Perform Attachment 6 of 34SO-B31-001-1, Reactor Recirculation System, AND, Determine if plant conditions meet the procedural requirements for the Quick Re-Start of Recirc Pump 1B.

Indicate below your determination:

Plant conditions DO / DO NOT allow for Recirc Pump 1B to be restarted.

2021-301 RO ADMIN 2 Page 5 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

START TIME:__________

NOTE: 34SO-B31-001-1, Attachment 6 serves as an answer key for this JPM. It is NOT to be provided to the student.

NOTE: At this time, PROVIDE the operator with Attachment 1 (Plant Data page) and a copy of 34SO-B31-001-1.

1. Operator refers to step 7.1.4.2.6 and is The operator enters Att. 6 of directed to Att. 6 of 34SO-B31-001-1. 34SO-B31-001-1.

2. Recirc Loop and RPV Limit Checks: The operator places a check mark (Att. 6 Step 1.0) next to B Recirc.

2021-301 RO ADMIN 2 Page 6 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

3. Confirm the reactor is at least 13% The operator determines the below the 78% load line of Att. 1 of reactor is SHUTDOWN and 34GO-OPS-005-1, Initials Step 2.0 (1) and marks AND Step 2.0 (2) as N/A.

The Power/flow condition is acceptable for restart per the STA/Rx Engineering OR If the OPRM System is inoperable, the reactor is at least 10% below the 61%

load line of Att. 1 of 34AB-C51-001-1.

(Att. 6 Step 2.0)

4. Record the following data: Time The operator records the CURRENT TIME.

(Att. 6 Step 3.0) The operator initials the step.

NOTE: Data is NOT required to be entered for Recirc Pump 1A in the following step.

• • 5. Record the following data: RPV The operator determines the RPV Saturation Temp. Saturation Temp for 820 psia (805 psig + 15 psi) is 521F, by (Att. 6 Step 3.0.A) using Att. 1 of 34SO-B31-001-1

6. Record the following data: The operator records A Recirc A Recirc Suction Temp Suction Temp as 470F (Plant (Att. 6 Step 3.0.B) Data Sheet)

7. Record the following data: The operator records B Recirc B Recirc Suction Temp Suction Temp as 475F (Plant (Att. 6 Step 3.0.C) Data Sheet)

8. Record the following data: The operator records Vessel Vessel Bottom Head Drain. Bottom Head Drain temperature (Att. 6 Step 3.0.D) as N/A or Not Available.

2021-301 RO ADMIN 2 Page 7 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 9. Confirm the T between reactor The operator records Loop B coolant temp in the loop AND the T as 46F (+ 2F)

RPV coolant temp is < 50 F:

Loop B T = l(A)-(C)l The operator initials the step.

(Att. 6 Step 4.1)

• • 10. Confirm the T between the bottom The operator determines the step head coolant temp AND the RPV 5.2 must be used because Vessel coolant temp by performing step 5.1 Bottom Head Drain temp is NOT OR 5.2. available.

(Att. 6 Step 5.0) The operator records Step 5.1 as N/A

• • 11. Confirm ALL of the following: The operator determines loop One OR more loop drive flows were drive flows were > 40% prior to

>40% of rated flow prior to the RPT. the RPT (Unit 1 was at 100%

RTP prior to the scram and RPT).

(Att. 6 Step 5.2.a)

The operator initials the step.

• • 12. Confirm ALL of the following: The operator determines HPCI HPCI and RCIC have not injected and RCIC have not injected since since the RPT. the RPT (RWL decreased to -10 and was restored using RFPTs).

(Att. 6 Step 5.2.b)

The operator initials the step.

• • 13. Confirm ALL of the following: The operator determines Feedwater temp has remained > 300F Feedwater temp has NOT since the RPT. remained > 300F since the RPT (Plant Data sheet lists current (Att. 6 Step 5.2.c)

Feedwater temp as 295F).

14. Confirm ALL of the following: The operator records the RPT Time between the RPT and restart is time (T1) and time Recirc start is

< 30 minutes. required.

(Att. 6 Step 5.2.d)

15. IF only ONE Recirc pump is idle, The operator determines BOTH THEN confirm the operating pump Recirc pumps are tripped and loop flow is < 22,500 gpm. marks Step 6.0 as N/A.

(Att. 6 Step 6.0)

16. Verify the operating pump loop flow The operator determines BOTH is < 22,500 gpm. Recirc pumps are tripped and (Att. 6 Step 6.3) marks Step 6.3 as N/A.

2021-301 RO ADMIN 2 Page 8 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

17. Independently verify the data recorded above is ACCEPTABLE prior to proceeding with the recirc pump start.

(Att. 6 Step 7.0)

• • 18. The operator reports to the Shift The operator reports that plant Supervisor. conditions do NOT meet the procedural requirements for the Quick Re-Start of Recirc Pump 1B. Based on Feedwater temperature not remaining

>300°F since the Recirc Pump trip.

PROMPT: IF addressed by the operator, as the Shift Supervisor, INFORM the operator that another operator will perform Att. 6. Step 7.0.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when:

After JPM step #18 is complete.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR - PICK UP the Initiating Cue sheet.

2021-301 RO ADMIN 2 Page 9 of 14 Summary of JPM Attributes JPM: 2021-301 RO ADMIN 2:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 7 Step 5 Record Saturation Temperature Recorded for verifying compliance.

Step 9 Confirm delta T between coolant & loop Recorded for verifying compliance.

Step 10 Confirms Bottom Head Drain Temp Recorded for verifying correct step.

Step 11 Confirms drive flows were >40% Recorded for verifying compliance.

Step 12 Confirms HPCI & RCIC not injected Recorded for verifying compliance.

Step 13 Confirms FW temperature not met Recorded for verifying compliance.

Step 18 Notifies SS requirements not met Recorded for TS purpose.

Number of JPM Steps <30 18 Time to Perform JPM

<45 min 15 Min Normal / Faulted /

Alternate Path Normal Setting (administered)

Classroom Is LOD 1 or 5 NO NO

(** Indicates critical step)

ANSWER KEY SNC PLANT E. I. HATCH Pg 182 of 205 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION No:

REACTOR RECIRCULATION SYSTEM 34SO-B31-001-1 48.2 ATTACHMENT 6 Attachment Page TITLE: RECIRC PUMP QUICK RE-START LIMIT CHECKS 2 of 4 CONTINUOUS NOTE: This attachment may be performed in Modes 1, 2, AND 3.

1.0 Recirc Loop and RPV Limit Checks:

Pre-startup checks for (): __________ A recirc

_________ B recirc LOAD LINE INCREASES OF UP TO 10% HAVE BEEN OBSERVED WHEN A CAUTION:

RECIRC PUMP IS STARTED.

Critical 2.0 Confirm the:

(1) The reactor is at least 13% below the 78% load line of Attachment 1, Power vs. flow map in 34GO-OPS-005-1, INITIALS AND The Power/flow condition is acceptable for restart per the STA/Rx Engineering. INITIALS OR (2) IF the OPRM System is inoperable, the reactor is at least 10% below the 61% Load Line of Attachment 1, OPRM System INOP Power vs. Flow map in 34AB-C51-001-1, in order to avoid inadvertent entry into the RPI. N/A 3.0 Record the following data: Time CURRENT TIME INITIALS Parameter Location Value SPDS MISC RPV Heatup/

(A) RPV Saturation Temp. (A)

Cooldown OR Steam Tables 521F (2F) 1B31-R650 OR Equivalent, average (B) A Recirc Suction Temp of process computer (B) 470F points B034, B035 1B31-R650 OR Equivalent, average (C) B Recirc Suction Temp of process computer (C) 475F points B036, B037

• 1B21-R606 Pt 3 OR 1G31-N601 Pt 5 OR (D) *Vessel Bottom Head Drain point AVSLBHDT, Vessel Not Available (D)

Bottom Drain Temp on SPDS OPS-1321 Ver. N/A G16.030

ANSWER KEY SNC PLANT E. I. HATCH Pg 183 of 203 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION No:

REACTOR RECIRCULATION SYSTEM 34SO-B31-001-1 46.2 ATTACHMENT 6 Attachment Page TITLE: RECIRC PUMP QUICK RE-START LIMIT CHECKS 3 of 4

• The Bottom Head Drain temperature (D) may still be used even IF RWCU is NOT in service.

(See Limitation 5.2.14). IF Bottom Head Drain temperature is NOT available, (i.e., inoperable),

THEN use the alternate method of confirming the Bottom Head to Coolant T in step 5.0.

Critical 4.0 FOR the Recirc loop to be started, confirm the T between the reactor coolant temperature in the loop AND the RPV coolant temperature is 50F by performing step 4.1 OR 4.2 below:

4.1 IF both recirc loops are idle; Loop A T = (A) - (B) = ____________ (acceptable 50F) N/A OR Loop B T = (A) - (C) = 46F (2F) (acceptable 50F) INITIALS OR 4.2 IF only one recirc loop is idle, THEN loop T = (B) - (C) = ________________ (acceptable 50F) N/A IF a direct indication is NOT available for Vessel Bottom Head Drain temp (D),

NOTE: THEN within 30 minutes of an RPT, the bottom head to coolant T ( 145F) may be confirmed per the alternate method in step 5.2.

Critical 5.0 Confirm the T between the bottom head coolant temperature AND the reactor pressure vessel (RPV) coolant temperature is 145F by performing step 5.1 OR 5.2 below:

5.1 T = (A) - (D) = __________ (acceptable 145F) N/A OR 5.2 Per Tech Spec BASES B.3.4.9 (Bases SR 3.4.9.3 and SR 3.4.9.4),

confirm ALL of the following:

(a) One OR more loop drive flows were > 40% (18,000 gpm) of rated flow prior to the RPT, AND INITIALS (b) HPCI and RCIC Systems have NOT injected since the RPT, AND INITIALS (c) Feedwater temperature has remained > 300F since the RPT, AND NOT MET (d) Time between the RPT AND restart is < 30 minutes.

Record Recirc RPT trip time: RPT time (T1)

Recirc start is required prior to:

(T1) + 30 minutes = RPT time + 30 min INITIALS OPS-1321 Ver. N/A G16.030

ANSWER KEY SNC PLANT E. I. HATCH Pg 184 of 205 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION No:

REACTOR RECIRCULATION SYSTEM 34SO-B31-001-1 48.2 ATTACHMENT 6 Attachment Page TITLE: RECIRC PUMP QUICK RE-START LIMIT CHECKS 4 of 4 Critical 6.0 IF only ONE Recirc pump is idle, THEN confirm the operating pump loop flow is < 22,500 gpm. N/A 6.3 Verify the operating pump loop flow is < 22,500 gpm. ________ N/A 7.0 Independently verify the data recorded above is ACCEPTABLE prior to proceeding with the recirc pump start. (VERIFIED) _____

Critical 8.0 Confirm the steps 1.0 thru 7.0 above, was performed within the last 15 minutes. _____

9.0 Record Recirc pump start time: _______________ _____

OPS-1321 Ver. N/A G16.030

2 UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. 10 minutes ago, the Unit 1 reactor scrammed from 100% power.

2. Both Recirc Pumps tripped during the scram transient.

3. RWL went as low as -10 inches and has been restored to +37 inches using Reactor Feedwater Pumps.

4. Data has been collected for use in Attachment 6 of 34SO-B31-001-1.

5. Per the STA, the Power/flow condition is acceptable for restart of Recirc Pump 1B.

INITIATING CUES:

Perform Attachment 6 of 34SO-B31-001-1, Reactor Recirculation System, AND, Determine if plant conditions meet the procedural requirements for the Quick Re-Start of Recirc Pump 1B.

Indicate below your determination:

Plant conditions DO / DO NOT allow for Recirc Pump 1B to be restarted.

PROVIDE TO APPLICANT Plant Data Reactor pressure: 805 psig A Recirc Suction Temp (1B31-R650): 470 F B Recirc Suction Temp (1B31-R650): 475 F Vessel Bottom Head Drain: NOT AVAILABLE Reactor Feedwater temperature: 295 F

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL RO ADMIN 3

Title:

EQUIPMENT CONTROL, 34SV-SUV-019-1 SURVEILLANCE Author: Media Number: Time:

Anthony Ball 2021-301 RO ADMIN 3 15.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee: Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021 ADMINISTER ON THE SAME DAY WITH SRO ADMIN #3

2021-301 RO ADMIN 3 Page 2 of 12 Course Number Program Name Media Number OPERATIONS TRAINING 2021-301 RO ADMIN 3 Ver. No. Date Reason for Revision Author Print Peer Review Initials/Name Print Initials/Name Made editorial changes from LR-JP-10022 to use on 2011-301 1 5/26/11 ELJ CME NRC Exam. Changed K/A to G2.1.7.

Minor revision to match procedure and use on ILT-10 NRC Exam. Reviewed JPM against current procedure. Changed 1.1 05/30/16 Media Number to 2016-301 ADMIN 4. This JPM will become ARB ELJ LR-JP-10022 after NRC Exam.

1.2 2/09/2021 Updated for ILT-13 NRC Exam 2021-301. Modified temperatures to Tech Spec Limit. Changed K/A to ARB JDW G2.2.12.

2021-301 RO ADMIN 3 Page 3 of 12 UNIT 1 (X) UNIT 2 ()

TASK TITLE: EQUIPMENT CONTROL, 34SV-SUV-019-1 SURVEILLANCE JPM NUMBER: 2021-301 RO ADMIN 3 TASK STANDARD: This task will be satisfactorily met when the operator has:

Completeted section 7.5 of 34SV-SUV-019-1, SURVEILLANCE CHECKS, and calculated that Drywell Average Temperature is 151.1°F Informed the evaluator that Unit 1 Drywell Cooling System should be placed in Additional Cooling Operating Mode Informed evaluator the LCO 3.6.1.5, Drywell Air Temperature, is not met TASK NUMBER:

OBJECTIVE NUMBER:

JTA IMPORTANCE RATING:

K/A CATALOG NUMBER: G2.2.12 RO 3.70 SRO 4.10 OPERATOR APPLICABILITY: Reactor Operator (RO)

GENERAL

REFERENCES:

Unit 1 34SV-SUV-019-1, Ver 37.35 REQUIRED MATERIALS: Unit 1 34SV-SUV-019-1, Ver 37.35 Complete previous shift data in step 7.5.4 (154 and 153)

Calculators APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: NOT applicable

3 EVALUATOR COPY UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 1 is operating at 100 % power.

2. 1T47-R611 is out of service.

3. 1T47-R612 is out of service.

4. The SS has directed this surveillance be completed as a paper version.

5. 1T47-R611 PT 14 and 1T47-R612 PT 10 Previous readings:

1T47-R611 PT 14 (1T47-N009) was 154ºF 1T47-R612 PT 10 (1T47-N003) was 153ºF INITIATING CUES:

Complete section 7.5 of 34SV-SUV-019-1, SURVEILLANCE CHECKS, which evaluates Drywell Temperatures, AND Inform the evaluator of any actions (if any) that need to be taken as a result of the readings or results obtained from this surveillance.

AND Determine and inform the evaluator whether the Drywell Average Temperature LCO is / is not met.

2021-301 RO ADMIN 3 Page 5 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

START TIME:__________

PROMPT: GIVE the operator the copy of 34SV-SUV-019-1 and SPDS readings from Attachment 1 of JPM.

1. Determine method for obtaining Per NOTE S of 34SV-SUV-temperature readings. 019-1, the operator determines temperature readings can be obtained from SPDS.

• • 2. Performs step 7.5.1 of From the SPDS screen shot, the 34SV-SUV-019-1. operator has listed the following temperature readings on the surveillance sheet for; 1T47-N001L 140 N004 129 N008, 134 N001M, 134 N005 134

(** Indicates critical step)

2021-301 RO ADMIN 3 Page 6 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

3. Performs step 7.5.2 of The operator evaluates the 34SV-SUV-019-1. temperatures from step 7.5.1 and determines the maximum temperatute minus the minimum temperature is less than 40ºF.

4. Performs step 7.5.3 of The operator evaluates the 34SV-SUV-019-1. readings in step 7.5.1. and concludes the highest is less than 275ºF and the lowest temperature is greater than 50ºF.

• • 5. Performs step 7.5.4 of From the SPDS screen shot, the 34SV-SUV-019-1. operator has listed the following temperature readings on the surveillance sheet for; 1T47-N009 181 1T47-N003 180 AND Has listed the temperatures from the previous readings provided in the Initial Conditions.

• • 6. Performs step 7.5.5 of The operator compares the 34SV-SUV-019-1. current temperature readings in step 7.5.4 to those from the previous reading and concludes the temperatures DO differ by more than 10ºF AND that a CR must be written.

(** Indicates critical step)

2021-301 RO ADMIN 3 Page 7 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

7. Performs step 7.5.6 of The operator confirms the 34SV-SUV-019-1. maximum reading in step 7.5.4 is less than 275ºF and the minimum is greater than 50ºF AND the maximum temperature minus the minimum temperature of step 7.5.4 is less than 50ºF.

• • 8. Performs step 7.5.7 of From the SPDS screen shot, the 34SV-SUV-019-1. operator has listed the following temperature readings on the surveillance sheet for; 1T47-N001J, 204 N001K, 169 N002, 162 N001A, 187 N001B, 192 N010. 159

9. Performs step 7.5.8 of The operator determines the 34SV-SUV-019-1. maximum temperature from step 7.5.7 minus the lowest temperature from step 7.5.7 is less than 100ºF.

10. Performs step 7.5.9 of The operator confirms the 34SV-SUV-019-1. maximum reading in step 7.5.7 is less than 275ºF and the minimum is greater than 50ºF.

• • 11. Performs step 7.5.10 of Using the formula at the bottom 34SV-SUV-019-1. of the surveillance page, the operator calculates the average drywell temperature to be 151.1ºF. (Accept +/-1°F due to rounding errors)

(** Indicates critical step)

2021-301 RO ADMIN 3 Page 8 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 12. Addresses any additional actions that The operator informs the are required as a result of the average evaluator that since average drywell temperature reading. drywell temperature exceeds 135ºF, per note L of the surveillance the shift is to place the Drywell Cooling System in Additional Cooling Operating mode per 34SO-T47-001-1.

• • 13. Addresses Technical Specification The operator informs the LCO 3.6.1.5, Drywell Air evaluator that since average Temperature. Drywell Temperature exceeds 150ºF, LCO 3.6.1.5, Drywell Air Temperature is NOT met.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when:

Operator completes step 13 of this JPM With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: That completes this JPM.

(** Indicates critical step)

2021-301 RO ADMIN 3 Page 9 of 12 Summary of JPM Attributes JPM 2021-301 RO ADMIN 3:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 7 Step 2 Performs 7.5.1 Calculation required for TS DW Temperature determination.

Step 5 Performs 7.5.4 Calculation required for TS DW Temperature determination.

Step 6 Performs 7.5.5 Calculation required for TS DW Temperature determination.

Step 8 Performs 7.5.7 Temperatures required for TS DW Temperature determination.

Step 11 Performs 7.5.10 Calculation required for TS DW Temperature determination.

Step 12 Addresses additional actions Additional DW Cooling is required.

Step 13 Addresses TS met/not met TS DW Temperature LCO not met.

Number of JPM Steps <30 13 Time to Perform JPM <45 min 15 min Normal / Faulted /

Alternate Path Admin (Normal) Determine Exit Point, Site Exit Route and Evacuation Route during an Emergency with a Release.

Setting (administered)

Anywhere reference material is available Is LOD 1 or 5 NO NO

Answer Key 2021-301 RO ADMIN 3 Page 10 of 12 REAC T/S OR OPER 7.5 PANEL - INSTRUMENT / TECH SPEC. NOTE FREQ N D MODE LIM 1H11-P657: - 1T47-R611, Pt 9 (1T47-N001L) 140 Pt 11 (1T47-N004) R,S,C 129 7.5.1 Pt 13 (1T47-N008) (spec 1,2,3 c NA 134 1H11-P654: - 1T47-R612, Pt 9 (1T47-N001M) only) 134 Pt 11 (1T47-N005) 134 7.5.2 Check max minus min in 7.5.1 < 40°F B 1,2,3 c SAT 7.5.3 Check max < 275°F and min > 50°F in 7.5.1 B,C 1,2,3 c NA SAT 1H11-P657: - 1T47-R611, PT 14 (1T47-N009)

Previous shift reading 154 Present reading 181 7.5.4 R,S 1,2,3 c NA 1H11-P654: - 1T47-R612, PT 10 (1T47-N003)

Previous shift reading 153 Present reading 180 IF the previous reading differs from the present reading YES IF CR by greater than 10°F OR submitted.

IF erratic instrument behavior is observed YES 7.5.5 N/A 1,2,3 c THEN submit a CR to evaluate the Operability of the NR IF NOT instruments in step 7.5.4.

required (SR 3.3.3.1.1 for 3.3.3.1-1(10))

Check max < 275°F and min > 50°F AND 7.5.6 max minus min < 50F in 7.5.4 B 1,2,3 c NA (SR 3.3.3.1.1 for 3.3.3.1-1(10)) SAT 1H11-P657: - 1T47-R611, Pt 7, (1T47-N001J) 204 Pt 8, (1T47-N001K) 169 Pt 10, (1T47-N002) 162 7.5.7 R,S 1,2,3 c NA 1H11-P654: - 1T47-R612, Pt 7, (1T47-N001A) 187 Pt 8, (1T47-N001B) 192 Pt 13, (1T47-N010) 159 Check max minus min in 7.5.7 < 100°F 7.5.8 B 1,2,3 c (SR 3.3.3.1.1 for 3.3.3.1.1(10)) SAT 7.5.9 Check max < 275°F and min > 50°F in 7.5.7 B,C 1,2,3 c NA SAT Average Drywell Temperature 7.5.10 (SR 3.6.1.5.1) 1 L 1,2,3 c < 150°F 151.1 INITIALS Calculations verified DATE TIME DW Temp = (7.5.1 TE's ) (0.63) + (7.5.4 TEs) (0.22) + (7.5.7 TE's ) (0.15) 1 5 2 6

UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 1 is operating at 100 % power.

2. 1T47-R611 is out of service.

3. 1T47-R612 is out of service.

4. The SS has directed this surveillance be completed as a paper version.

5. 1T47-R611 PT 14 and 1T47-R612 PT 10 Previous readings:

1T47-R611 PT 14 (1T47-N009) was 154ºF 1T47-R612 PT 10 (1T47-N003) was 153ºF INITIATING CUES:

Complete section 7.5 of 34SV-SUV-019-1, SURVEILLANCE CHECKS, which evaluates Drywell Temperatures, AND Inform the evaluator of any actions (if any) that need to be taken as a result of the readings or results obtained from this surveillance.

AND Determine and inform the evaluator whether the Drywell Average Temperature LCO is / is not met.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL RO ADMIN 4

Title:

DETERMINE THE EVACUATION ROUTE DURING AN EMERGENCY Author: Media Number: Time:

Anthony Ball 2021-301 RO ADMIN 4 10 Minutes Line Technical Review By (N/A for minor revisions Date:

N/A N/A Reviewed by Instructional Technologist or designee: Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 RO ADMIN 4 Page 2 of 13 Course Number Program Name Media Number N/A OPERATIONS TRAINING 2021-301 RO ADMIN 4 Author Print Peer Review Ver. Date Reason for Revision Initials/Name Print No. Initials/Name 1.0 5/16/2019 Developed for ILT-12 NRC Exam 2019-301 ARB ABG 1.1 2/09/2021 Modified for ILT-13 NRC Exam 2021-301. ARB JDW

2021-301 RO ADMIN 4 Page 3 of 13 UNIT 1 (X) UNIT 2 (X)

TASK TITLE: DETERMINE THE EVACUATION ROUTE DURING AN EMERGENCY JPM NUMBER: 2021-301 RO ADMIN 4 TASK STANDARD: The task shall be satisfactorily completed when the wind direction has been checked and the operator has determined the correct exit point, site exit route and evacuation route IAW NMP-EP-144 to evacuate via Gate 17, then using the Main Access Road and then NORTH on US Highway 1.

TASK NUMBER: 200.059 OBJECTIVE NUMBER: 200.059.A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.86 SRO 3.96 K/A CATALOG NUMBER: G2.4.39 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.9 SRO 3.8 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 & 2 NMP-EP-144,Ver. 6.0 NMP-EP-142-F10, Ver. 2.0 REQUIRED MATERIALS: Unit 1 & 2 NMP-EP-144, Ver. 6.0 NMP-EP-142-F10, Ver. 2.0 APPROXIMATE COMPLETION TIME: 10 Minutes SIMULATOR SETUP: N/A

2021-301 RO ADMIN 4 Page 4 of 13 EVALUATOR COPY UNIT 1 & 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. The Emergency Director (ED) has declared a Site Area Emergency.

2. The Emergency Director (ED) has ordered evacuation with radiation monitoring.

3. The Prompt Off-Site Dose Assessment indicated an offsite release is in progress.

4. The release is from the Unit 2 Reactor Building.

5. The ED has directed YOU to prepare for the PA announcement using NMP-EP-142- F10, SAE Public Announcement Script.

6. SPDS MIDAS & Meteorological Data is provided as an Attachment.

INITIATING CUES:

In preparation of making a page announcement for the above emergency condition, DETERMINE the applicable:

Exit point Exit route Evacuation route INFORM the ED of the results NOTE: Another Operator will make the actual page announcement.

2021-301 RO ADMIN 4 Page 5 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

START TIME:__________

NOTE: The Operator may review NMP-EP-142-F10, Site Area Emergency Public Address Announcement Script.

1. Select correct section of The Operator uses NMP-EP-144 NMP-EP-144. Table of Contents and determines that Instruction 4.1.6 - Site Evacuation With Radiological Monitoring, is the required section.

2. Operator must determine which Operator determines that NMP-attachment is required to be performed EP-144 Attachment 11, Hatch to correctly identify the evacuation Site Evacuation Routes, is routes. required to be performed.

(Step 4.1.6.1.a)

• • 3. Is a radiological release in progress? Operator reviews Initial Conditions and determines (Att. 11, step 1) YES and goes to Att. 11 step 1. B.

NOTE: If the operator marks NO, the wrong Evacuation Route and State Reception Center (s) will be determined.

(** Indicates critical step)

2021-301 RO ADMIN 4 Page 6 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

NOTE: Att. 11 NOTE after Step 1.b informs the operator to use the 15-minute average wind direction information using the meteorological instrumentation that corresponds to the primary release point:

The 100M instrument must be used for Main Stack (elevated) release.

The 10M instrument must be used for RB Vent (ground) release.

NOTE: The Operator will determine the 10M wind direction is required to be used (Reactor Building) due to the MIDAS handout indicating the Main Stack and Unit 1 Reactor Building stacks Normal range rad monitors being in service and the Unit 2 Reactor Building Accident Range Monitor (KAMAN system 2D11-R631) being in service with the Normal Range out of service. This indicates a release out of the Unit 2 Reactor Building Stack which is considered a Ground release.

• • 4. The operator must determine if the From the SPDS MIDAS screen, 10M or 100M meteorological the Operator determines that the instruments will be used to determine 10M instruments will be used.

meteorological conditions.

(Att. 11. step 1.b)

• • 5. IF a radiological release is in progress, At a SPDS terminal, determines THEN, based on wind direction, 10M wind direction is 55 degrees determine using either:

• • • • • • • • • • • • • • • SPDS MIDAS screen OR (Att. 11 step 1.b Table) SPDS MET Data screen

• • 6. *************** Determines the Exit Point is the Gate 17 the Exit point, (Att. 11 step 1.b Table)

(** Indicates critical step)

2021-301 RO ADMIN 4 Page 7 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

NOTE: If the operator uses the 100 Meter wind direction, the Exit Point will (INCORRECTLY) be Plant Entry Security Building.

• • 7. *************** Determines the Site Exit Route is the Main Access Road.

site exit route, (Att. 11 step 1.b Table)

NOTE: If the operator uses the 100 Meter wind direction, the Site Exit Route will (INCORRECTLY) be the Road behind Low Level Radwaste Building.

• • 8. *************** Determines the Evacuation Route is U.S. Hwy 1 - North to Toombs Evacuation route/State Reception Co. Middle School/ Lyons.

Center (Att. 11 step 1.b Table)

NOTE: If the operator uses the 100 Meter wind direction, the evacuation route will (INCORRECTLY) state U.S. Hwy. 1 - South to Appling Co. High School/Baxley.

(** Indicates critical step)

2021-301 RO ADMIN 4 Page 8 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

9. The Operator informs the ED of the The Operator informs the ED of applicable Exit point, exit route, and the following:

evacuation route Exit Point:

Gate 17 Exit Route:

Main Access Road Evacuation Route/Reception Center:

U.S. Hwy 1 - North to Toombs Co. Middle School/ Lyons NOTE: If the operator uses the 100 Meter wind direction, the Site Exit Route will (INCORRECTLY) state Road behind Low Level Radwaste Building.

PROMPT: IF the operator addresses Page Announcements, as the Shift Supervisor, INFORM the operator that will performed by another Operator.

END TIME:__________

NOTE: The terminating cue shall be given to the Operator when:

After JPM step #9 is complete.

With NO reasonable progress, the Operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

2021-301 RO ADMIN 4 Page 9 of 13 Summary of JPM Attributes JPM 2021-301 RO ADMIN 4:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 6 Step 3 Determine Release Y/N Operator determines YES for a release is in progress Step 4 Determines Release Level Determines a ground release and that the 10M instruments will be used or the wrong Evacuation Route and State Reception Centers will be determined causing undue exposure to evacuees.

Step 5 Wind Direction Improper wind direction of 65 degrees using the 100 Meter vice the 10 Meter reading of 55 degrees (correct wind direction) will cause the wrong Evacuation Route and State Reception Centers to be determined causing undue exposure to evacuees.

Step 6 Exit Point Using the Table and selecting the correct Exit Point will prevent undue exposure to evacuees.

Step 7 Site Exit Route Using the Table and selecting the correct Site Exit Route will prevent undue exposure to evacuees.

Step 8 Evacuation Route Using the Table and selecting the correct Evacuation Route will prevent undue exposure to evacuees.

Number of JPM Steps <30 9 Time to Perform JPM <45 min 10 min Normal / Faulted /

Alternate Path Admin (Normal) Determine Exit Point, Site Exit Route and Evacuation Route during an Emergency with a Release.

Setting (administered)

Classroom Is LOD 1 or 5 NO NO

MIDAS INFORMATION METEOROLOGICAL 10M WIND SPD 100M WIND SPD 10M WIND DIR 100M WIND DIR 133-R601 1Y33-R603 1Y33-R601 1Y33-R603 5.0 4.0 55 65 AMBIENT TMP DELTA T DELTA T RAINFALL (F) 10M 60-10 100-10 15 MIN AVG 55 -0.5 -1.0 .000 RADIOLOGICAL U1 RX BLDG U2 RX BLDG MAIN STACK VENT VENT NORMAL RANGE KAMAN NORMAL RANGE KAMAN NORMAL RANGE KAMAN 1D11-K600A 1D11-R631 1D11-K619A 1D11-R631 2D11-K636A 2D11-R631 4.65E+00 6.70E+01 8.00E+02 1D11-K600B 1D11-K19B 2D11-K636B 5.00E+00 6.67E+01 7.56E+02 STABILITY CLASS D

METEOROLOGICAL DATA (DIRECTION 15 MIN 15 MIN Wind FROM) AVERAGE STD-DEV SPEED AVERAGE 10M ELEVATION 57 DEG 55 DEG 12 1 MPH 5 MPH 60M ELEVATION 53 DEG 65 DEG 6 2 MPH 2 MPH 100M ELEVATION 52 DEG 65 DEG 4 4 MPH 4 MPH 45M ELEVATION-BACKUP 53 DEG 50 DEG 4 2 MPH 2 MPH 15 MIN TEMPERATURE AVERAGE 10M ELEVATION AMBIENT 55 DEG F FLOW*

10M ELEVATION AMBIENT-BACKUP 55 DEG F FLOW 10M DEWPOINT 73 DEG F 60M - 10M DELTA TEMP. -0.5 DEG F FLOW -4.1 DEG F 100M - 10M DELTA TEMP. -1.0 DEG F FLOW -2.4 DEG F 45M - 10M DELTA TEMP.-Backup -1.0 DEG F FLOW -2.4 DEG F Precipitation .00 INCHES SINCE MIDNIGHT

EVALUATOR ANSWER KEY ATTACHMENT 11 Page 1 of 3 HATCH SITE EVACUATION ROUTES

1. Is a radiological release in progress? Yes No

a. IF a radiological release is NOT in progress, use the following exit point, site exit route, and evacuation route.

Exit Point - Plant Entry & Security Building (PESB)

Site Exit Route - Main Access Road Evacuation Route - Either direction on U.S. Hwy. 1

b. IF a radiological release is in progress, THEN, based on wind direction, determine the rally point, site exit route, evacuation route, and State Reception Center with the chart below.

NOTE Security should be consulted to determine alternative(s) IF designated exit point and/or site exit route cannot be used. Using an alternate exit point requires discussion with Security and RP.

The 15 minute average wind direction information must be read using the meteorological instrumentation that corresponds to the primary release point:

The 100M instrument must be used for Main Stack (elevated) release.

The 10M instrument must be used for RB Vent (ground) release.

Consult the On-Shift Dose Analyst or the EOF Dose Assessment Staff for alternate locations IF either of these instruments are INOPERABLE.

Wind Direction Exit Evacuation Route/

Site Exit Route From Point State Reception Center 340º - 60º Main Access U.S. Hwy. 1 - North to Toombs Co. Middle School/

Gate 17 (55°) Road Lyons Road behind 61º - 110º PESB U.S. Hwy. 1 - South to Appling Co. High School/ Baxley LLRWB Main Access 111º - 225º PESB U.S. Hwy. 1 - South to Appling Co. High School/ Baxley Road EITHER direction on U.S. Hwy. 1 Main Access 226º - 339º PESB to Toombs Co. Middle School/ Lyons Road OR Appling Co. High School/ Baxley

UNIT 1 & 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. The Emergency Director (ED) has declared a Site Area Emergency.

2. The Emergency Director (ED) has ordered evacuation with radiation monitoring.

3. The Prompt Off-Site Dose Assessment indicated an offsite release is in progress.

4. The release is from the Unit 2 Reactor Building.

5. The ED has directed YOU to prepare for the PA announcement using NMP-EP-142- F10, SAE Public Announcement Script.

6. SPDS MIDAS & Meteorological Data is provided as an Attachment.

INITIATING CUES:

In preparation of making a page announcement for the above emergency condition, DETERMINE the applicable:

Exit point Exit route Evacuation route INFORM the ED of the results NOTE: Another Operator will make the actual page announcement.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL SRO ADMIN 1

Title:

FAILED RWL INSTRUMENTS - SRO DETERMINE REQUIRED ACTIONS Author: Media Number: Time:

Anthony Ball 2021-301 SRO ADMIN 1 20.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee: Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 SRO ADMIN 1 Page 2 of 9 Course Number Program Name Media Number OPERATIONS TRAINING 2021-301 SRO ADMIN 1 Ver. No. Date Reason for Revision Author Print Peer Review Initials/Name Print Initials/Name 00 03/10/2015 Modified from LR-JP-25101 for use on 2015-301 ARB ELJ NRC Exam. Incorporated SRO TS determination for RWL instruments. After exam will be incorporated into JPM database and renumbered.

1.0 02/09/21 Updated JPM for ILT-13 NRC Exam 2021-301. ARB JDW

2021-301 SRO ADMIN 1 Page 3 of 9 UNIT 1 (X) UNIT 2 ( )

TASK TITLE: FAILED RWL INSTRUMENTS - SRO DETERMINE REQUIRED ACTIONS JPM NUMBER: 2021-301 SRO ADMIN 1 TASK STANDARD: For an SRO to successfully complete the SRO must evaluate the tables & reference LFDs in the TRM and then determine that TS Required Action 3.3.5.3.B.2 is required to be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by placing a channel in trip and that TS Required Action 3.3.5.3.B.1 is required to be performed.

TASK NUMBER: 201.099 OBJECTIVE NUMBER: 201.099.B PLANT HATCH JTA IMPORTANCE RATING:

RO 4.57 SRO 3.83 STA 4.00 K/A CATALOG NUMBER: G2.1.25 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.9 SRO 4.2 OPERATOR APPLICABILITY: Senior Reactor Operator (SRO)

GENERAL

REFERENCES:

Unit 1 Unit 2 Unit 1 TS 3.3.5.3 N/A Unit 1 TRM REQUIRED MATERIALS: Unit 1 Unit 2 Unit 1 TS 3.3.5.3 N/A Unit 1 TRM APPROXIMATE COMPLETION TIME: 20.0 Minutes SIMULATOR SETUP: N/A

(** Indicates critical step)

EVALUATOR COPY UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. 1B21-N091A instrument detector has failed causing 1B21-R604A, Wide Range Instrument, to indicate High Upscale.

2. 1B21-N691B, Master Trip Unit (MTU), has failed and will NOT provide a trip signal.

INITIATING CUES:

Determine Technical Specification required actions with regards to RCIC ONLY.

(** Indicates critical step)

2021-301 SRO ADMIN 1 Page 5 of 9 SAT/UNSAT STEP# PERFORMANCE STEP STANDARD (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-111, On-The-Job Training and Task Performance Evaluation.

START TIME:__________

1. Operator identifies the procedure Operator has identified the correct needed to perform the task. procedure as Unit 1 TRM/TS.

2. Determines the correct LFD by using Determines the correct LFD to be section Table T10.1-1 Master LFD-1-RCIC-01 by referencing Equipment Cross Reference-Sorted by 1B21-N691 A, B, C, D.

MPL of the TRM. (1B21-N091A and 1B21-N691B both reference LFD-1-RCIC-01)

3. Determines correct Technical Determines Technical Specifications section to be entered by Specification section to be using section Table T10.1-1 Master referenced by TRM section Table Equipment Cross Reference-Sorted by T10.1-1 Master Equipment Cross MPL of the TRM. Reference is TS 3.3.5.3-1(1.)

• • 4. Determines if RCIC Initiation is being Determines that 1E11-K79A maintained by using Loss of Function (RWL level 2 -35 inches) contact Diagram (LFD). (Channel A1) will NOT close since the instrument has failed high as given in the Initiating Cue.

(** Indicates critical step)

2021-301 SRO ADMIN 1 Page 6 of 9 SAT/UNSAT STEP# PERFORMANCE STEP STANDARD (COMMENTS)

• • 5. Determines if RCIC Initiation is being Determines that 1E11-K79B maintained by using LFD. (Channel B1) contact will NOT close since the MTU will NOT trip as given in the Initiating Cue.

• • 6. Determines if RCIC Initiation is being Determines that RCIC Initiation maintained by using LFD. is NOT being maintained since relay E51-K2, K3, K81, K85 can NOT be energized by using drawing for the TRIP Logic or by using the Minimum Channel Requirements for System Initiation Capability at bottom of LFD.

NOTE: Minimum Channel Requirements for System Initiation Capability:

A1 & A2 A1 & B2 B1 & A2 B1 & B2

7. Determines Technical Specification SRO determines that TS Table Required Actions 3.3.5.2-1(1.) requires 4 channels to be operable AND SRO determines 2 of the 4 required Channels (A1 and B1) are INOP.

• • 8. Determines Technical Specification SRO enters TS 3.3.5.2.A and Required Actions performs Required Action A.1 Immediately by Entering Condition referenced in Table 3.3.5.2-1 for the channel.

• • 9. Determines Technical Specification SRO determines Required Action Required Actions B.1 is required to be performed for each channel since RCIC Initiation Capability is NOT maintained and will declare RCIC inoperable within one hour.

NOTE: TS for RCIC inoperability is TS LCO 3.5.3 Condition A.

(** Indicates critical step)

2021-301 SRO ADMIN 1 Page 7 of 9 SAT/UNSAT STEP# PERFORMANCE STEP STANDARD (COMMENTS)

• • 10. Determines Technical Specification SRO performs Required Action Required Actions B.2 for each channel by directing Channel placed in trip within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

END TIME:__________

NOTE: The terminating cue shall be given to the Operator when:

After JPM step #10 is complete.

With NO reasonable progress, the Operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR - PICK UP the Initiating Cue sheet.

(** Indicates critical step)

2021-301 SRO ADMIN 1 Page 8 of 9 Summary of JPM Attributes JPM 2021-301 SRO ADMIN 1

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 6 Step 4 Determines K79A will not close Instrument failed high & will not initiate Step 5 Determines K79B will not close Instrument failed & will not initiate Step 6 RCIC initiation not maintained RCIC will not initiate Step 8 Determines 3.3.5.3.A Action A.1 Required Action IAW TS Step 9 Determines Action B.1 required Loss of initiation capability Step 10 Determines Action B.2 required Channel placed in trip within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Number of JPM Steps <30 10 Time to Perform JPM

<45 Min 20.0 Min Normal / Faulted /

Alternate Path Admin (Normal) Determine that RCIC has lost initiation capability and the required TS Actions.

Setting (administered)

Classroom Is LOD 1 or 5 NO NO

UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. 1B21-N091A instrument detector has failed causing 1B21-R604A, Wide Range Instrument, to indicate High Upscale.

2. 1B21-N691B, Master Trip Unit (MTU), has failed and will NOT provide a trip signal.

INITIATING CUES:

Determine Technical Specification required actions with regards to RCIC ONLY.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL SRO ADMIN 2

Title:

VERIFY FUEL MOVEMENT SHEET Author: Media Number: Time:

Anthony Ball 2021-301 SRO ADMIN 2 20.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee: Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 SRO ADMIN 3 Page 2 of 10 Course Number Program Name Media Number N/A OPERATIONS TRAINING 2021-301 SRO ADMIN 2 Ver. No. Date Reason for Revision Author Print Peer Review Initials/Name Print Initials/Name Minor revision for use on 2016-301 NRC Exam. Reviewed JPM against current procedure. Changed Media Number to 2016-1.1 05/30/16 301 ADMIN 3. Incorporated JPM into a Fuel Movement Sheet ARB ELJ Verification. After NRC Exam, Media Number will be changed to LR-JP-45.33B.

Modified JPM for use on 2021-301 NRC Exam.

Reviewed JPM against current procedure. Changed 2.0 02/09/21 Media Number to 2021-301 SRO ADMIN 2. After ARB JDW NRC Exam, Media Number will be changed to LR-JP-45.33C.

2021-301 SRO ADMIN 2 Page 3 of 10 UNIT 1 (X) UNIT 2 (X)

TASK TITLE: VERIFY FUEL MOVEMENT SHEET JPM NUMBER: 2021-301 SRO ADMIN 2 TASK STANDARD: The task will be complete when the operator has identified all in-core placement errors of all components listed on Page 1 of the attached Fuel Movement Sheet.

TASK NUMBER: 045.033 OBJECTIVE NUMBER: 045.033.O PLANT HATCH JTA IMPORTANCE RATING:

RO Not Available SRO Not Available K/A CATALOG NUMBER: G2.1.35 K/A CATALOG JTA IMPORTANCE RATING:

RO 2.2 SRO 3.9 OPERATOR APPLICABILITY: Senior Reactor Operator GENERAL

REFERENCES:

Refuel Floor 34FH-OPS-001-0 Ver 27.3 NMP-RE-011-001 Ver 2.6 REQUIRED MATERIALS: Refuel Floor Fuel Movement Sheets 34FH-OPS-001-0 Ver 27.3 NMP-RE-011-001 Ver 2.6 APPROXIMATE COMPLETION TIME: 20.0 Minutes SIMULATOR SETUP: N/A

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is in a refueling outage.

2. You are the oncoming Refuel Floor SRO.

3. You are performing a turnover with the off-going Refuel Floor SRO.

4. You are asked to verify the attached Fuel Movement Sheet which was completed last shift.

5. The fuel movement sheet and pictures of the associated core cells are available.

INITIATING CUES:

IAW 34FH-OPS-001-0, Fuel Movement Operation,

1. VERIFY fuel movement on the attached Fuel Movement Sheet.

2. If verification results in any discovered errors, identify the error(s) and corrective action(s) required.

2021-301 SRO ADMIN 2 Page 5 of 10 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

START TIME: __________

PROMPT: Hand the operator the fuel movement sheets, pictures of the core cells and 34FH-OPS-001-2 & NMP-RE-011-001.

PROMPT: IF the operator has problems reading the bundle serial numbers, THEN provide the serial numbers to the operator.

PROMPT: IF the operator asks about Spent Fuel Pool verification, THEN tell the operator they are only responsible for in-core verifications.

1. Obtains the correct procedures. Obtains and reviews NMP-RE-011-001, SPECIAL NUCLEAR MATERIAL Movement -

HATCH SPECIFIC and 34FH-OPS-001-0, Fuel Movement Operation.

2. Verify Step #1 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLV675) has been loaded in its proper location and Step #1 of Fuel Movement Sheet is correct.

(** Indicates critical step)

2021-301 SRO ADMIN 2 Page 6 of 10 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

3. Verify Step #2 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLV682) has been loaded in its proper location and Step #2 of Fuel Movement Sheet is correct.

NOTE: Step #3 of Fuel Movement Sheet is a Double Blade Guide and is in the Fuel Pool.

• • 4. Verify Step #4 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLK805) has NOT been loaded in its proper location and Step #4 of Fuel Movement Sheet is INCORRECT. (JLK804 should be loaded in this location)

5. Verify Step #5 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLK817) has been loaded in its proper location and Step #5 of Fuel Movement Sheet is correct.

NOTE: Control Cell 38-37 is NOT correct.

NOTE: The applicant may report the findings to the Shift Supervisor at this time or wait until all of the Fuel Movement Sheet has been verified, either is acceptable.

6. Verify Step #6 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLV678) has been loaded in its proper location and Step #6 of Fuel Movement Sheet is correct.

7. Verify Step #7 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLV670) has been loaded in its proper location and Step #7 of Fuel Movement Sheet is correct.

NOTE: Step #8 of Fuel Movement Sheet is a Double Blade Guide and is in the Fuel Pool.

(** Indicates critical step)

2021-301 SRO ADMIN 2 Page 7 of 10 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 8. Verify Step #9 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLK804) has NOT been loaded in its proper location and Step #9 of Fuel Movement Sheet is INCORRECT. (JLK805 should be loaded in this location)

NOTE: The applicant may report the findings to the Shift Supervisor at this time or wait until all of the Fuel Movement Sheet has been verified, either is acceptable.

• • 9. Verify Step #10 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLK821) has NOT been loaded in its proper location and Step

1. 10 of Fuel Movement Sheet is INCORRECT. (JLK812 should be loaded in this location)

NOTE: Control Cell 14-37 is NOT correct.

10. Verify Step #11 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLV698) has been loaded in its proper location and Step #11 of Fuel Movement Sheet is correct.

11. Verify Step #12 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLV708) has been loaded in its proper location and Step #12 of Fuel Movement Sheet is correct.

NOTE: Step #13 of Fuel Movement Sheet is a Double Blade Guide and is in the Fuel Pool.

12. Verify Step #14 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLK807) has been loaded in its proper location and Step #14 of Fuel Movement Sheet is correct.

13. Verify Step #15 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLK820) has been loaded in its proper location and Step #15 of Fuel Movement Sheet is correct.

NOTE: Control Cell 38-17 is correct.

(** Indicates critical step)

2021-301 SRO ADMIN 2 Page 8 of 10 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 14. Perform 34FH-OPS-001-0 Step 4.1.c. Operator reports to Shift Supervisor the following Steps are INCORRECT:

Step#4 Step#9 Step#10

• • 15. Perform 34FH-OPS-001-0, Step 4.1.d. Operator reports to Shift Supervisor to NOTIFY Reactor Engineering of the fuel movement errors.

• • 16. Perform 34FH-OPS-001-0, Step 4.1.e. Operator reports to Shift Supervisor to INITIATE a CR documenting the fuel movement error

• • 17. Perform 34FH-OPS-001-0, Step 4.1.f. Operator reports to Shift Supervisor to NOT make any further fuel movements, until directed by Plant Management AND Reactor Engineering has provided a Reactivity Plan for recovery from the fuel movement error.

END TIME: __________

NOTE: The terminating cue shall be given to the Operator when:

After JPM step #17 is complete.

With NO reasonable progress, the Operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR - PICK UP the Initiating Cue sheet.

(** Indicates critical step)

2021-301 SRO ADMIN 2 Page 9 of 10 Summary of JPM Attributes JPM 2021-301 SRO Admin 2:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 7 Step 4 Verify Step#4 of Fuel Movement Sheet is correct Operator determines Fuel Bundle (JLK805) is not loaded in proper location.

Step 8 Verify Step#9 of Fuel Movement Sheet is correct Operator determines Fuel Bundle (JLK804) is not loaded in proper location.

Step 9 Verify Step#10 of Fuel Movement Sheet is correct Operator determines Fuel Bundle (JLK821) is not loaded in proper location.

Step 14 Notify Shift Supervisor Reports the fuel movement error.

Step 15 Notify Reactor Engineering Reports the fuel movement error.

Step 16 Initiate CR Documents the fuel movement error.

Step 17 Do not make any further fuel movements Stops fuel movement until reactivity plan provided from Reactor Engineering.

Number of JPM Steps <30 17 Time to Perform JPM <45 min 20 min Normal / Faulted /

Alternate Path Normal Setting (administered)

Classroom Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is in a refueling outage.

2. You are the oncoming Refuel Floor SRO.

3. You are performing a turnover with the off-going Refuel Floor SRO.

4. You are asked to verify the attached Fuel Movement Sheet which was completed last shift.

5. The fuel movement sheet and pictures of the associated core cells are available INITIATING CUES:

IAW 34FH-OPS-001-0, Fuel Movement Operation,

1. VERIFY fuel movement on the attached Fuel Movement Sheet.

2. If verification results in any discovered errors, identify the error(s) and corrective action(s) required.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL SRO ADMIN 3

Title:

EQUIPMENT CONTROL, 34SV-SUV-019-1 SURVEILLANCE WITH TECH SPECS Author: Media Number: Time:

Anthony Ball 2021-301 SRO ADMIN 3 15.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee: Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021 ADMINISTER ON THE SAME DAY WITH RO ADMIN #3

2021-301 SRO ADMIN 3 Page 2 of 12 Course Number Program Name Media Number OPERATIONS TRAINING 2021-301 SRO ADMIN 3 Ver. No. Date Reason for Revision Author Print Peer Review Initials/Name Print Initials/Name 1.0 02/09/21 New JPM for ILT-13 NRC Exam 2021-301. ARB JDW

2021-301 SRO ADMIN 3 Page 3 of 12 UNIT 1 (X) UNIT 2 ()

TASK TITLE: EQUIPMENT CONTROL, 34SV-SUV-019-1 SURVEILLANCE WITH TECH SPECS JPM NUMBER: 2021-301 SRO ADMIN 3 TASK STANDARD: This task will be satisfactorily met when the student has:

Completeted section 7.5 of 34SV-SUV-019-1, SURVEILLANCE CHECKS, and calculated that Drywell Average Temperature is 151.1°F Informed the evaluator that Unit 1 Drywell Cooling System should be placed in Additional Cooling Operating Mode Informed evaluator the LCO 3.6.1.5, Drywell Air Temperature, is not met requiring Require Action A.1 to be performed.

TASK NUMBER:

OBJECTIVE NUMBER:

JTA IMPORTANCE RATING:

K/A CATALOG NUMBER: G2.2.12 RO 3.70 SRO 4.10 OPERATOR APPLICABILITY: Senior Reactor Operator (SRO)

GENERAL

REFERENCES:

Unit 1 34SV-SUV-019-1, Ver 37.35 REQUIRED MATERIALS: Unit 1 34SV-SUV-019-1, Ver 37.35 Complete previous shift data in step 7.5.4 (154 and 153)

Calculators APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: NOT applicable

3 EVALUATOR COPY UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 1 is operating at 100 % power.

2. 1T47-R611 is out of service.

3. 1T47-R612 is out of service.

4. The SS has directed this surveillance be completed as a paper version.

5. 1T47-R611 PT 14 and 1T47-R612 PT 10 Previous readings:

1T47-R611 PT 14 (1T47-N009) was 154ºF 1T47-R612 PT 10 (1T47-N003) was 153ºF INITIATING CUES:

Complete section 7.5 of 34SV-SUV-019-1, SURVEILLANCE CHECKS, which evaluates Drywell Temperatures, AND Inform the evaluator of any actions (if any) that need to be taken as a result of the readings or results obtained from this surveillance.

AND Determine and inform the evaluator whether the Drywell Average Temperature LCO is / is not met. If LCO is not met determine any Technical Specification required actions with regards to Drywell Temperature.

2021-301 SRO ADMIN 3 Page 5 of 12 STEP# PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

START TIME:__________

PROMPT: GIVE the operator the copy of 34SV-SUV-019-1 and SPDS readings from Attachment 1 of JPM.

1. Determine method for obtaining Per NOTE S of 34SV-SUV-Temperature readings. 019-1, the operator determines temperature readings can be obtained from SPDS.

(** Indicates critical step)

2021-301 SRO ADMIN 3 Page 6 of 12 STEP# PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS)

• • 2. Performs step 7.5.1 of From the SPDS screen shot, the 34SV-SUV-019-1. operator has listed the following temperature readings on the surveillance sheet for; 1T47-N001L 140 N004 129 N008, 134 N001M, 134 N005 134

3. Performs step 7.5.2 of The operator evaluates the 34SV-SUV-019-1. temperatures from step 7.5.1 and determines the maximum temperatute minus the minimum temperature is less than 40ºF.

4. Performs step 7.5.3 of The operator evaluates the 34SV-SUV-019-1. readings in step 7.5.1. and concludes the highest is less than 275ºF and the lowest temperature is greater than 50ºF.

• • 5. Performs step 7.5.4 of From the SPDS screen shot, the 34SV-SUV-019-1. operator has listed the following temperature readings on the surveillance sheet for; 1T47-N009 181 1T47-N003 180 AND Has listed the temperatures from the previous readings provided in the Initial Conditions.

(** Indicates critical step)

2021-301 SRO ADMIN 3 Page 7 of 12 STEP# PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS)

• • 6. Performs step 7.5.5 of The operator compares the 34SV-SUV-019-1. current temperature readings in step 7.5.4 to those from the previous reading and concludes the temperatures DO differ by more than 10ºF AND that a CR must be written.

7. Performs step 7.5.6 of The operator confirms the 34SV-SUV-019-1. maximum reading in step 7.5.4 is less than 275ºF and the minimum is greater than 50ºF AND the maximum temperature minus the minimum temperature of step 7.5.4 is less than 50ºF.

• • 8. Performs step 7.5.7 of From the SPDS screen shot, the 34SV-SUV-019-1. operator has listed the following temperature readings on the surveillance sheet for; 1T47-N001J, 204 N001K, 169 N002, 162 N001A, 187 N001B, 192 N010. 159

9. Performs step 7.5.8 of The operator determines the 34SV-SUV-019-1. maximum temperature from step 7.5.7 minus the lowest temperature from step 7.5.7 is less than 100ºF.

10. Performs step 7.5.9 of The operator confirms the 34SV-SUV-019-1. maximum reading in step 7.5.7 is less than 275ºF and the minimum is greater than 50ºF.

(** Indicates critical step)

2021-301 SRO ADMIN 3 Page 8 of 12 STEP# PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS)

• • 11. Performs step 7.5.10 of Using the formula at the bottom 34SV-SUV-019-1. of the surveillance page, the operator calculates the average Drywell Temperature to be 151.1ºF. (Accept +/-1°F due to rounding errors)

• • 12. Addresses any additional actions that The operator informs the are required as a result of the average evaluator that since average Drywell Temperature reading. Drywell Temperature exceeds 135ºF, per note L of the surveillance the shift is to place the Drywell Cooling System in Additional Cooling Operating mode per 34SO-T47-001-1.

• • 13. Addresses Technical Specification The operator informs the LCO 3.6.1.5, Drywell Air evaluator that since average Temperature. Drywell Temperature exceeds 150ºF, LCO 3.6.1.5, Drywell Air Temperature is NOT met.

• • 14. Determines Technical Specification SRO enters TS 3.6.1.5.A and LCO 3.6.1.5, Drywell Air performs Required Action A.1 by Temperature, Required Actions. Restoring Drywell Average Air Temperature within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when:

Operator completes step 14 of this JPM With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: That completes this JPM.

(** Indicates critical step)

2021-301 SRO ADMIN 3 Page 9 of 12 Summary of JPM Attributes JPM 2021-301 SRO ADMIN 3:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 8 Step 2 Performs 7.5.1 Calculation required for TS DW Temperature determination.

Step 5 Performs 7.5.4 Calculation required for TS DW Temperature determination.

Step 6 Performs step 7.5.5 Concludes the temperatures DO differ by more than 10ºF AND that a CR must be written.

Step 8 Performs 7.5.7 Temperatures required for TS DW Temperature determination.

Step 11 Performs step 7.5.10 Calculation required for TS DW Temperature and results in 151.1ºF.

Step 12 Addresses Note L Reports Additional Cooling Operating mode per 34SO-T47-001-1 is required.

Step 13 Addresses LCO 3.6.1.5 Reports drywell temperature exceeds 150ºF, LCO 3.6.1.5, Drywell Air Temperature, is NOT met.

Step 14 TS Required Actions TS DW Temperature Required Action A.1 must be restored within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Number of JPM Steps <30 14 Time to Perform JPM

<45 Min 15.0 Min Normal / Faulted /

Alternate Path Admin (Normal) Determine the correct DW temperature and the associated procedure and TS Required Actions.

Setting (administered)

Anywhere reference material is available Is LOD 1 or 5 NO NO

Answer Key 2021-301 SRO ADMIN 3 Page 10 of 12 REAC T/S OR OPER 7.5 PANEL - INSTRUMENT / TECH SPEC. NOTE FREQ N D MODE LIM 1H11-P657: - 1T47-R611, Pt 9 (1T47-N001L) 140 Pt 11 (1T47-N004) R,S,C 129 7.5.1 Pt 13 (1T47-N008) (spec 1,2,3 c NA 134 1H11-P654: - 1T47-R612, Pt 9 (1T47-N001M) only) 134 Pt 11 (1T47-N005) 134 7.5.2 Check max minus min in 7.5.1 < 40°F B 1,2,3 c SAT 7.5.3 Check max < 275°F and min > 50°F in 7.5.1 B,C 1,2,3 c NA SAT 1H11-P657: - 1T47-R611, PT 14 (1T47-N009)

Previous shift reading 154 Present reading 181 7.5.4 R,S 1,2,3 c NA 1H11-P654: - 1T47-R612, PT 10 (1T47-N003)

Previous shift reading 153 Present reading 180 IF the previous reading differs from the present reading YES IF CR by greater than 10°F OR submitted.

IF erratic instrument behavior is observed YES 7.5.5 N/A 1,2,3 c THEN submit a CR to evaluate the Operability of the NR IF NOT instruments in step 7.5.4.

required (SR 3.3.3.1.1 for 3.3.3.1-1(10))

Check max < 275°F and min > 50°F AND 7.5.6 max minus min < 50F in 7.5.4 B 1,2,3 c NA (SR 3.3.3.1.1 for 3.3.3.1-1(10)) SAT 1H11-P657: - 1T47-R611, Pt 7, (1T47-N001J) 204 Pt 8, (1T47-N001K) 169 Pt 10, (1T47-N002) 162 7.5.7 R,S 1,2,3 c NA 1H11-P654: - 1T47-R612, Pt 7, (1T47-N001A) 187 Pt 8, (1T47-N001B) 192 Pt 13, (1T47-N010) 159 Check max minus min in 7.5.7 < 100°F 7.5.8 B 1,2,3 c (SR 3.3.3.1.1 for 3.3.3.1.1(10)) SAT 7.5.9 Check max < 275°F and min > 50°F in 7.5.7 B,C 1,2,3 c NA SAT Average Drywell Temperature 7.5.10 (SR 3.6.1.5.1) 1 L 1,2,3 c < 150°F 151.1 INITIALS Calculations verified DATE TIME DW Temp = (7.5.1 TE's ) (0.63) + (7.5.4 TEs) (0.22) + (7.5.7 TE's ) (0.15) 1 5 2 6

UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 1 is operating at 100 % power.

2. 1T47-R611 is out of service.

3. 1T47-R612 is out of service.

4. The SS has directed this surveillance be completed as a paper version.

5. 1T47-R611 PT 14 and 1T47-R612 PT 10 Previous readings:

1T47-R611 PT 14 (1T47-N009) was 154ºF 1T47-R612 PT 10 (1T47-N003) was 153ºF INITIATING CUES:

Complete section 7.5 of 34SV-SUV-019-1, SURVEILLANCE CHECKS, which evaluates Drywell Temperatures, AND Inform the evaluator of any actions (if any) that need to be taken as a result of the readings or results obtained from this surveillance.

AND Determine and inform the evaluator whether the Drywell Average Temperature LCO is / is not met. If LCO not met determine any Technical Specification required actions with regards to Drywell Temperature.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL SRO ADMIN 4

Title:

ASSESS RADIOLOGICAL CONDITIONS IN AN EMERGENCY AND APPROVE EMERGENCY EXPOSURE PERMITS Author: Media Number Time Anthony Ball 2021-301 SRO ADMIN 4 15.0 Minutes Line Review By: Date N/A N/A Reviewed by Instructional Technologist or designee: Date N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 SRO ADMIN 4 Page 2 of 18 Course Number Program Name Media Number N/A OPERATIONS TRAINING 2021-301 SRO ADMIN 4 Ver. No. Date Reason for Revision Author Print Peer Review Initials/Name Print Initials/Name 1.0 02/09/21 Developed for ILT-13 NRC Exam 2021-301 ARB JDW

2021-301 SRO ADMIN 4 Page 3 of 18 UNIT 1 (X) UNIT 2 (X)

TASK TITLE: ASSESS RADIOLOGICAL CONDITIONS IN AN EMERGENCY AND APPROVE EMERGENCY EXPOSURE PERMITS JPM NUMBER: 2021-301 SRO ADMIN 4 TASK STANDARD: This task shall be satisfactorily completed when the applicant has correctly:

1. Calculated the projected total dose to each Operator.

2. Reviewed and approved the Emergency Exposure Permits.

One Permit will be completed incorrectly and will not be approved.

TASK NUMBER: 200.052 OBJECTIVE NUMBER: 200.052.A PLANT HATCH JTA IMPORTANCE RATING:

RO N/A SRO 4.4 K/A CATALOG NUMBER: G2.3.4 K/A CATALOG JTA IMPORTANCE RATING:

RO N/A SRO 3.7 OPERATOR APPLICABILITY: Senior Reactor Operator (SRO)

GENERAL Unit 1 & 2

REFERENCES:

NMP-EP-144, Protective Actions, Ver. 5.0 NMP-EP-144-F02, Emergency Exposure Authorization, Ver. 3.0 REQUIRED Unit 1 & 2 MATERIALS:

NMP-EP-144, Protective Actions, Ver. 5.0 NMP-EP-144-F02, Emergency Exposure Authorization, Ver. 3.0 Calculator Unit 1 RWCU HX Room survey map Three completed Emergency Exposure Permits for approval APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: NA

2021-301 SRO ADMIN 4 Page 4 of 18 EVALUATOR COPY UNIT 1 & 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. You are the On Shift Shift Manager.

2. Unit 2 is in a General Emergency.

3. Three Systems Operators are being dispatched to protect valuable equipment by isolating 2G31-F004, RWCU Outboard Valve in the RWCU HX Room.

4. An Emergency Exposure Permit has been generated for each Operator.

5. The TOTAL round-trip TRANSIT dose will be 120 mrem to each Operator.

6. The TOTAL time at the job site will be 5 minutes for each Operator.

INITIATING CUES:

You are the Emergency Director.

Based on the given conditions and using the survey map provided, perform the following:

a. Calculate the projected dose to each Operator.

b. Review and approve or disapprove, as appropriate, the three Emergency Exposure Permits provided per NMP-EP-144-F02, Emergency Exposure Authorization.

2021-301 SRO ADMIN 4 Page 5 of 18 STEP# PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

START TIME:__________

PROMPT: GIVE the operator Radiological Survey Map and the three (3) NMP-EP-144-F02 forms.

1. Operator identifies the procedure(s) The operator has OBTAINED needed to perform the task which NMP-EP-144-F02.

includes NMP-EP-144-F02.

(** Indicates critical step)

2021-301 SRO ADMIN 4 Page 6 of 18 STEP# PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS)

• • 2. Calculate projected total dose to Using survey map, a dose rate of each Operator. 108 Rem/hour at the valve is determined.

The task will take 5 minutes.

108 Rem/hour (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> / 60 minutes) (5 minutes) = 9 Rem

[no range on calculated value]

Transit dose of 120 mrem is added to calculated dose for each Operator.

9 Rem + 120 mrem = 9.12 Rem

[no range on calculated value]

• • 3. Review and approve Emergency NMP-EP-144-F02, Exposure Permit #1. Applicant reviews all entries on Emergency Exposure Permit #1 and approves the Permit since the dose limit is correct.

• • 4. Review and Emergency Exposure NMP-EP-144-F02, Permit #2. Applicant reviews all entries on Emergency Exposure Permit #2 and determines that the dose limit is NOT correct and does NOT approve the Permit.

(** Indicates critical step)

2021-301 SRO ADMIN 4 Page 7 of 18 STEP# PERFORMANCE STEP STANDARD SAT/UNSAT (COMMENTS)

• • 5. Review and Emergency Exposure NMP-EP-144-F02, Permit #3. Applicant reviews all entries on Emergency Exposure Permit #3 and approves the Permit since the dose limit is correct.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when any of the following conditions are met:

Operator completes step 5 of this JPM.

The operator exceeds the allotted time of 30 minutes.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

2021-301 SRO ADMIN 4 Page 8 of 18 Summary of JPM Attributes JPM 2021-301 SRO ADMIN 4:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 4 Step 2 Calculate projected total dose SRO performs calculation.

Step 3 Reviews Emergency Exposure Permit #1 SRO approves Exposure Permit #1.

Step 4 Reviews Emergency Exposure Permit #2 SRO DOES NOT approve Exposure Permit #2.

(WRONG DOSE LIMIT)

Step 5 Reviews Emergency Exposure Permit #3 SRO approves Exposure Permit #3.

Number of JPM Steps <30 5 Time to Perform JPM <30 min 15 min Normal / Faulted /

Alternate Path Admin (Normal) Review and approve Emergency Exposure Permits.

Setting (administered)

Classroom Is LOD 1 or 5 NO NO

KEY 2021-301 SRO ADMIN 4 Page 9 of 18

KEY 2021-301 SRO ADMIN 4 Page 10 of 18 OPERATOR #2

KEY 2021-301 SRO ADMIN 4 Page 11 of 18 OPERATOR #3

UNIT 1 & 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. You are the On Shift Shift Manager.

2. Unit 2 is in a General Emergency.

3. Three Systems Operators are being dispatched to protect valuable equipment by isolating 2G31-F004, RWCU Outboard Valve in the RWCU HX Room.

4. An Emergency Exposure Permit has been generated for each Operator.

5. The TOTAL round-trip TRANSIT dose will be 120 mrem to each Operator.

6. The TOTAL time at the job site will be 5 minutes for each Operator.

INITIATING CUES:

You are the Emergency Director.

Based on the given conditions and using the survey map provided, perform the following:

a. Calculate the projected dose to each Operator.

b. Review and approve or disapprove, as appropriate, the three Emergency Exposure Permits provided per NMP-EP-144-F02, Emergency Exposure Authorization.

WORKER #1 Emergency Exposure Authorization NMP-EP-144-F02 SNC Version 3.0 Unit S Page 1 of 2 IF an internal hazard is present, dose limits SHALL be reduced by a factor of two, unless a compensatory measure has been used to eliminate the internal hazard.

OSLDs of personnel who receive an emergency exposure in excess of the 10 CFR 20 limits will be pulled and read PRIOR TO receiving further nonemergency exposure.

Approval to exceed 10 CFR 20 radiation exposure limits MUST be approved by the onsite ED in accordance with EPA 400R92001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents.

Emergency situations may transcend the normal requirement of maintaining personnel exposures below 10 CFR 20 limits. Emergency exposures SHALL be minimized to every degree practicable.

SNC personnel MUST voluntarily agree to receive an emergency dose in excess of 25 Rem but less than 100 Rem.

Emergency dose limits DO NOT have to take into account the annual dose to date.

Persons volunteering to receive in excess of 25 Rem MUST be made fully aware of the risks involved.

Dose Limits 10CFR20 Limit Plant Administrative Limit Whole body (TEDE) 5 Rem 2 Rem Lens of the eyes 15 Rem 6 Rem Skin of the whole body 50 Rem 20 Rem Extremities 50 Rem 20 Rem Internal organs 50 Rem 20 Rem EMERGENCY RESPONSE PERSONNEL EXPOSURE GUIDES Dose Limit* Activity Condition (REM) 5 all n/a 10 protecting valuable property lower dose not practicable 25 lifesaving or protection of large lower dose not practicable populations

>25 up to 100 lifesaving or protection of large only on a voluntary basis to populations persons fully aware of the risks involved

• This limit is expressed as the sum of the effective dose equivalent (EDE) and the committed effective dose equivalent (CEDE). The lens of the eye will normally be limited to three (3) times the values AND doses to other organs (including skin and extremities) will normally be limited to ten (10) times the listed value.

WORKER #1 Emergency Exposure Authorization NMP-EP-144-F02 SNC Version 3.0 Unit S Page 2 of 2 Mike R. Jones 21133 (FIRST) (M.I.) (LAST) OSLD NUMBER is authorized to receive an exposure of 10 REM and a thyroid exposure of 10 REM for the period of Today to Tomorrow .

Reason for requesting exposure in excess of 10 CFR 20 limits:

Close 2G31F004, RWCU HX ROOM 158 Reactor Building Current year exposure: 1.2 Rem Exposure determined by: Current RP Records RP Representative: Thomas Smith / Thomas Smith Date: Today Print / Sign EXPOSURE ABOVE 25 REM I have been made aware of the risks involved with the exposures listed above and I accept that risk.

/ /

Print Sign Date EMERGENCY DIRECTOR APPROVAL

/ /

Print Sign Date Verbal approval may be obtained from Site Emergency Director to expedite activities.

WORKER #2 Emergency Exposure Authorization NMP-EP-144-F02 SNC Version 3.0 Unit S Page 1 of 2 IF an internal hazard is present, dose limits SHALL be reduced by a factor of two, unless a compensatory measure has been used to eliminate the internal hazard.

OSLDs of personnel who receive an emergency exposure in excess of the 10 CFR 20 limits will be pulled and read PRIOR TO receiving further nonemergency exposure.

Approval to exceed 10 CFR 20 radiation exposure limits MUST be approved by the onsite ED in accordance with EPA 400R92001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents.

Emergency situations may transcend the normal requirement of maintaining personnel exposures below 10 CFR 20 limits. Emergency exposures SHALL be minimized to every degree practicable.

SNC personnel MUST voluntarily agree to receive an emergency dose in excess of 25 Rem but less than 100 Rem.

Emergency dose limits DO NOT have to take into account the annual dose to date.

Persons volunteering to receive in excess of 25 Rem MUST be made fully aware of the risks involved.

Dose Limits 10CFR20 Limit Plant Administrative Limit Whole body (TEDE) 5 Rem 2 Rem Lens of the eyes 15 Rem 6 Rem Skin of the whole body 50 Rem 20 Rem Extremities 50 Rem 20 Rem Internal organs 50 Rem 20 Rem EMERGENCY RESPONSE PERSONNEL EXPOSURE GUIDES Dose Limit* Activity Condition (REM) 5 all n/a 10 protecting valuable property lower dose not practicable 25 lifesaving or protection of large lower dose not practicable populations

>25 up to 100 lifesaving or protection of large only on a voluntary basis to populations persons fully aware of the risks involved

• This limit is expressed as the sum of the effective dose equivalent (EDE) and the committed effective dose equivalent (CEDE). The lens of the eye will normally be limited to three (3) times the values AND doses to other organs (including skin and extremities) will normally be limited to ten (10) times the listed value.

WORKER #2 Emergency Exposure Authorization NMP-EP-144-F02 SNC Version 3.0 Unit S Page 2 of 2 Ed R. Brown 22111 (FIRST) (M.I.) (LAST) OSLD NUMBER is authorized to receive an exposure of 25 REM and a thyroid exposure of 25 REM for the period of Today to Tomorrow .

Reason for requesting exposure in excess of 10 CFR 20 limits:

Close 2G31F004, RWCU HX ROOM 158 Reactor Building Current year exposure: 1.8 Rem Exposure determined by: Current RP Records RP Representative: Thomas Smith / Thomas Smith Date: Today Print / Sign EXPOSURE ABOVE 25 REM I have been made aware of the risks involved with the exposures listed above and I accept that risk.

/ /

Print Sign Date EMERGENCY DIRECTOR APPROVAL

/ /

Print Sign Date Verbal approval may be obtained from Site Emergency Director to expedite activities.

WORKER #3 Emergency Exposure Authorization NMP-EP-144-F02 SNC Version 3.0 Unit S Page 1 of 2 IF an internal hazard is present, dose limits SHALL be reduced by a factor of two, unless a compensatory measure has been used to eliminate the internal hazard.

OSLDs of personnel who receive an emergency exposure in excess of the 10 CFR 20 limits will be pulled and read PRIOR TO receiving further nonemergency exposure.

Approval to exceed 10 CFR 20 radiation exposure limits MUST be approved by the onsite ED in accordance with EPA 400R92001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents.

Emergency situations may transcend the normal requirement of maintaining personnel exposures below 10 CFR 20 limits. Emergency exposures SHALL be minimized to every degree practicable.

SNC personnel MUST voluntarily agree to receive an emergency dose in excess of 25 Rem but less than 100 Rem.

Emergency dose limits DO NOT have to take into account the annual dose to date.

Persons volunteering to receive in excess of 25 Rem MUST be made fully aware of the risks involved.

Dose Limits 10CFR20 Limit Plant Administrative Limit Whole body (TEDE) 5 Rem 2 Rem Lens of the eyes 15 Rem 6 Rem Skin of the whole body 50 Rem 20 Rem Extremities 50 Rem 20 Rem Internal organs 50 Rem 20 Rem EMERGENCY RESPONSE PERSONNEL EXPOSURE GUIDES Dose Limit* Activity Condition (REM) 5 all n/a 10 protecting valuable property lower dose not practicable 25 lifesaving or protection of large lower dose not practicable populations

>25 up to 100 lifesaving or protection of large only on a voluntary basis to populations persons fully aware of the risks involved

• This limit is expressed as the sum of the effective dose equivalent (EDE) and the committed effective dose equivalent (CEDE). The lens of the eye will normally be limited to three (3) times the values AND doses to other organs (including skin and extremities) will normally be limited to ten (10) times the listed value.

WORKER #3 Emergency Exposure Authorization NMP-EP-144-F02 SNC Version 3.0 Unit S Page 2 of 2 Judy R. Grant 78251 (FIRST) (M.I.) (LAST) OSLD NUMBER is authorized to receive an exposure of 10 REM and a thyroid exposure of 10 REM for the period of Today to Tomorrow .

Reason for requesting exposure in excess of 10 CFR 20 limits:

Close 2G31F004, RWCU HX ROOM 158 Reactor Building Current year exposure: 1.5 Rem Exposure determined by: Current RP Records RP Representative: Thomas Smith / Thomas Smith Date: Today Print / Sign EXPOSURE ABOVE 25 REM I have been made aware of the risks involved with the exposures listed above and I accept that risk.

/ /

Print Sign Date EMERGENCY DIRECTOR APPROVAL

/ /

Print Sign Date Verbal approval may be obtained from Site Emergency Director to expedite activities.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL SRO ADMIN 5

Title:

EMERGENCY CLASSIFICATION - COMPLETE NMP-EP-142-F01 Author: Media Number Time Critical Anthony Ball 2021-301 SRO ADMIN 5 15.0 Minutes Line Review By: Date N/A N/A Reviewed by Instructional Technologist or designee: Date N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Charlie Edmund 2/9/2021

2021-301 SRO ADMIN 5 Page 2 of 12 Course Number Program Name Media Number N/A OPERATIONS TRAINING 2021-301 SRO ADMIN 5 Ver. No. Date Reason for Revision Author Print Peer Review Initials/Name Print Initials/Name 1.0 5/15/2019 Developed for ILT-12 NRC Exam 2019-301 ABG ARB 2.0 02/09/21 Modified for ILT-13 NRC Exam 2021-301 ARB JDW

2021-301 SRO ADMIN 5 Page 3 of 12 UNIT 1 (X) UNIT 2 (X)

TASK TITLE: EMERGENCY CLASSIFICATION - COMPLETE NMP-EP-142-F01 JPM NUMBER: 2021-301 SRO ADMIN 5 TASK STANDARD: This task shall be satisfactorily completed when the student has correctly completed NMP-EP-142-F01 lines 2 through 6 within 15 minutes.

TASK NUMBER: 200.052 OBJECTIVE NUMBER: 200.052.A PLANT HATCH JTA IMPORTANCE RATING:

RO N/A SRO 4.4 K/A CATALOG NUMBER: G2.4.41 K/A CATALOG JTA IMPORTANCE RATING:

RO N/A SRO 4.6 OPERATOR APPLICABILITY: Senior Reactor Operator (SRO)

GENERAL Unit 1 & 2

REFERENCES:

NMP-EP-141-002, Hatch Emergency Action Levels and Bases, (Ver 3.0,)

NMP-EP-141-002-F01, EAL Classifcation Matrix, (Ver 2.0)

NMP-EP-141-F01, Emergency Classification Determination, (Ver. 2.0,)

REQUIRED Unit 1 & 2 MATERIALS:

NMP-EP-141-002, Hatch Emergency Action Levels and Bases, (Ver 3.0,)

NMP-EP-141-002-F01, EAL Classifcation Matrix, (Ver 2.0)

NMP-EP-141-F01, Emergency Classification Determination, (Ver. 2.0,)

APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: NA

EVALUATOR COPY UNIT 1 & 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. You are the On Shift Shift Manager.

2. Unit 2 is in a LOSP due to a failure of the 2C, 2D and 2E SUTs and a Loss of all onsite Emergency AC power due to a failure of all three Emergency Diesel Generators to start.

3. The Reactor scrammed and All rods fully inserted on the scram signal.

4. For the last 16 minutes, Emergency Diesel Generator start attempts have not been successful on any Emergency Diesel.

5. Maintenance estimates that the 2A Emergency Diesel can be returned to service in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

6. RWL is at -30 inches and being restored to the normal band using HPCI and RCIC.

7. All other Unit 2 parameters are in the desired bands.

8. Current meteorological conditions are available on SPDS MIDAS Information provided

9. The following Unit 1 conditions exists:

100% power All parameters normal

10. NO Peer Check is available.

INITIATING CUES:

EXAM SECURITY CAUTION:

Do Not Make Any Verbal Crew Announcements During This JPM

1. Evaluate the current conditions and complete NMP-EP-141-F01, Emergency Classification.

THIS IS A TIME CRITICAL JPM Current time is: ___________________

2019-301 SRO ADMIN 5 Page 5 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly FAIL Above standards not met Mark the JPM as a FAIL (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

NOTE: The CLASSIFICATION must be made within 15 minutes of the initial prompt and the Student states they understand the initial conditions.

NOTE: The Student may obtain a copy of NMP-EP-141-F01 (Form 1) if the Initiating Cue is given in the Simulator or Control Room. This form is required to be filled out for this examination, with the Emergency declaration identifier in step 6 and its description in step 7 (Form 1 line 5) are the critical items to be met within the critical time.

START TIME:__________

1. Operator identifies the procedure(s) The operator has OBTAINED needed to perform the task which NMP-EP-141-F01 and IC/EAL includes NMP-EP-141-F01, Step 1. Matrix Evaluation Charts.

Refer to the site specific IC/EAL Matrix Evaluation Charts

2. NMP-EP-141-F01, Step 2. NMP-EP-141-F01, Step 2.

Determine the appropriate IC/EAL The operator has selected HOT Matrix Evaluation Chart for IC/EAL Matrix Evaluation Chart.

classification of the event based on the current operating mode:

HOT IC/EAL Matrix Eval Chart COLD IC/EAL Matrix Eval Chart

(** Indicates critical step)

2019-301 SRO ADMIN 5 Page 6 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

3. NMP-EP-141-F01, Step 3. NMP-EP-141-F01, Step 3, Evaluate the status of the fission The operator has selected product barriers. INTACT for Fuel Cladding Fuel Cladding Integrity Integrity, INTACT for Reactor Reactor Coolant System Cooling System, INTACT for Containment Integrity Containment Integrity.

4. NMP-EP-141-F01, Step 3.a. NMP-EP-141-F01, Step 3.a, Determine the highest applicable The operator has selected NONE Fission Product Barrier Initiating Condition (IC).

5. NMP-EP-141-F01, Step 4. NMP-EP-141-F01, Step 4.

Record the highest applicable The operator has identified SS1 IC/EAL. for Unit 2.

• • 6. NMP-EP-141-F01, Step 5. NMP-EP-141-F01, Step 5.

Check the highest emergency The operator has selected Site classification level identified from Area Emergency as the either step 3.a OR 4: Classification. The operator has Classification entered SS1, for the based on IC#.

Based on IC #

• • 7. NMP-EP-141-F01, Step 5. NMP-EP-141-F01, Step 5.

Remarks (Identify the specific The operator has written Loss of EAL, as needed). all offsite and all AC power to emergency buses for 15 min or longer. (or similar wording)

(** Indicates critical step)

2019-301 SRO ADMIN 5 Page 7 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

• • 8. NMP-EP-141-F01, Step 6. NMP-EP-141-F01, Step 6.

Approve the emergency The operator has signed their classification and declare the event. name as the Emergency Director, entered the current Date, and entered the current Time in the spaces provided.

Time Critical Stop Time: .

NOTE: For this step to be considered SAT, the time entered must be within 15 minutes of the time recorded on the Initial Conditions sheet provided to the operator.

NOTE: If follow-up questioning reveals that a classification was declared and based on another IC #, the classification should be evaluated for validity.

9. NMP-EP-141-F01, Step 7. The operator has obtained Obtain Meteorological Data (not Meteorological Data (i.e. MIDAS required prior to event declaration). Information Sheet).

10. NMP-EP-141-F01, Step 7. NMP-EP-141-F01, Step 7.

Record the following: The operator has entered: 130 in Wind Direction (from) the space provided for Wind Wind Speed Direction (from), 5 in the space provided for Wind Speed, 0 in Precipitation the space provided for Stability Class Precipitation, entered D in the space provided for Stability Class.

11. NMP-EP-141-F01, Step 8. NMP-EP-141-F01, Step 8.

HAS a radiological release occurred? The operator has selected NO

12. NMP-EP-141-F01, Step 9. NMP-EP-141-F01, Step 9.

IS a radiological release occurring? The operator has selected NO

(** Indicates critical step)

2019-301 SRO ADMIN 5 Page 8 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

1. (COMMENTS)

13. NMP-EP-141-F01, Step 10. NMP-EP-141-F01, Step 10.

IS/WAS the release above normal The operator has selected NO operating limits?

PROMPT: Operator raises hand to stop Time Critical Clock.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when any of the following conditions are met:

Operator completes step 13 of this JPM.

The operator exceeds the allotted time of 15 minutes.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

2021-301 SRO ADMIN 5 Page 9 of 12 Summary of JPM Attributes JPM 2021-301 SRO ADMIN 5

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 3 Step 6 Annotate Emerg Classification SRO identifies the highest Emergency Classification identifier.

Step 7 Highest Emerg Classification SRO identifies the basis for the classification.

Step 8 Approves Emerg Classification SRO approves emergency classification.

Number of JPM Steps <30 13 Time to Perform JPM <30 min 15 min (Time Critical)

Normal / Faulted /

Alternate Path Admin (Normal) Normal Emergency Classification of an event.

Setting (administered)

Classroom Is LOD 1 or 5 NO NO

2021-301 SRO ADMIN 5 KEY Page 10 of 12 Emergency Classification Determination NMP-EP-141-F01 SNC Version 2.0 Unit S Page 1 of 12 NOTE The site specific emergency classification document is the controlling procedure for classification. The Initiating Condition (IC)/Emergency Action Level (EAL) Matrix Evaluation Charts are to be used as tools to assist the Emergency Director (ED) in determining emergency classification.

1. Refer to the site specific IC/EAL Matrix Evaluation Charts.

2. Determine the appropriate IC/EAL Matrix Evaluation Chart for classification based on the current operating mode.

HOT IC/EAL Matrix Evaluation Chart (FNP/VEGP: Modes 1-4; HNP: Modes 1-3)

COLD IC/EAL Matrix Evaluation Chart (FNP/VEGP: Modes 5-6 & None; HNP: Modes 4-5 & None)

3. IF the HOT IC/EAL Matrix Evaluation Chart is applicable, evaluate the status of the Fission Product Barriers.

POTENTIAL Fission Product Barrier LOSS INTACT LOSS Fuel Clad Integrity Reactor Coolant System Containment Integrity

a. Determine the highest applicable Fission Product Barrier IC (select one).

FG1 FS1 FA1 None

4. Record the highest applicable IC/EAL.

Hot IC/EAL # SS1 Unit 2 None Cold IC/EAL # Unit None

5. Document the highest emergency classification level determined from either Step 3.a OR 4.

Classification Based on IC # Classification Based on IC #

General Emergency Alert None Site Area Emergency SS1 Unusual Event Remarks (Identify the specific EAL threshold, as needed): Loss of all offsite and all AC power to emergency buses for 15 min or longer.

NOTE Completion of Line 6 constitutes the official emergency declaration time.

Lines 7 - 10 not required prior to event declaration.

6. Approve the emergency classification AND declare the event.

Student Date: ***** / ***** / ***** Time: ******

Emergency Director

7. Obtain Meteorological Data.

Wind Direction (from) 130 Wind Speed 5 Precipitation 0 Stability Class D

8. HAS a radiological release occurred? YES NO

9. IS a radiological release occurring? YES NO

10. IS/WAS the release above normal operating limits YES NO

2021-301 SRO ADMIN 5 Page 11 of 12

UNIT 1 & 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. You are the On Shift Shift Manager.

2. Unit 2 is in a LOSP due to a failure of the 2C, 2D and 2E SUTs and a Loss of all onsite Emergency AC power due to a failure of all three Emergency Diesel Generators to start.

3. The Reactor scrammed and All rods fully inserted on the scram signal.

4. For the last 16 minutes, Emergency Diesel Generator start attempts have not been successful on any Emergency Diesel.

5. Maintenance estimates that the 2A Emergency Diesel can be returned to service in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

6. RWL is at -30 inches and being restored to the normal band using HPCI and RCIC.

7. All other Unit 2 parameters are in the desired bands.

8. Current meteorological conditions are available on SPDS MIDAS Information provided

9. The following Unit 1 conditions exists:

100% power All parameters normal

10. NO Peer Check is available.

INITIATING CUES:

EXAM SECURITY CAUTION:

Do Not Make Any Verbal Crew Announcements During This JPM

1. Evaluate the current conditions and complete NMP-EP-141-F01, Emergency Classification.

THIS IS A TIME CRITICAL JPM Current time is: ___________________