Text

ADAMS 2B
	ML20140A065
Person / Time
Site:	McGuire, Mcguire
Issue date:	05/19/2020
From:	; NRC/RGN-II
To:	; Duke Energy Carolinas
References
	50-369/20-301, 50-370/20-301 50-369/OL-20, 50-370/OL-20
	Download: ML20140A065 (445)
	v • d • e

Appendix D Scenario Outline Form ES-D-1 (Rev_011320)

Facility: McGuire Scenario No.: 1 Op Test No.: N20-1 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: The plant is at 100% power (EOL). The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Turnover: The following equipment is Out-Of-Service: The 1A NS Pump is OOS for preventative maintenance. ACTION has been taken in accordance with Technical Specification LCO 3.6.6 ACTION A. 1NCPT-5150, Pzr Pressure Channel 2, has failed and has been removed from service in accordance with plant procedures. ACTION has been taken in accordance with Technical Specification LCO 3.3.1 and 3.3.2. MCB Annunciator 1AD-12, F-5, FWST EMERGENCY LO TEMP, has alarmed spuriously several times over the last hour and has currently failed ON (IAE has verified that the issue is limited to an annunciator card issue).

Critical Tasks: See Below Event Malf. Event Type* Event No. No. Description 1 REM C-RO High Pressure Heaters Bypass/Overpower CF0075 C-SRO 2 MAL C-BOP Power Range Failure ENB013D C(TS)-SRO 3 REM R-RO MSR Relief Valve fails OPEN/Downpower HS0179 N-BOP N-SRO 4 MAL C-RO Dropped Rod/Downpower IRE006K2 C(TS)-SRO 5 MAL C-RO 1B NCP Pump Bearing Oil Cooler Leak NCP007BU C-BOP C-SRO 6 MAL M-RO Loss of VIAC 1EKVC/Inadvertent SI Actuation EPL003C M-BOP M-SRO 7 MAL C-RO Failure of the Turbine to Trip in AUTO DEH003A C-SRO

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 (Rev_011320)

McGuire 2020 NRC Scenario #1 The plant is at 100% power (EOL). The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The following equipment is Out-Of-Service: The 1A NS Pump is OOS for preventative maintenance.

ACTION has been taken in accordance with Technical Specification LCO 3.6.6 ACTION A. 1NCPT-5150, Pzr Pressure Channel 2, has failed and has been removed from service in accordance with plant procedures. ACTION has been taken in accordance with Technical Specification LCO 3.3.1 and 3.3.2. MCB Annunciator 1AD-12, F-5, FWST EMERGENCY LO TEMP, has alarmed spuriously several times over the last hour and has currently failed ON (IAE has verified that the issue is limited to an annunciator card issue).

Shortly after taking the watch, the High-Pressure Heater Bypass Valve (1CF-75) will inadvertently open. The operator will respond in accordance with OAC Alarm Response Procedure M1L2917, U1 WATER BYPASSING A&B HEATERS, and OMP 4-3, Use of Emergency and Abnormal Procedures and FLEX Support Guidelines, and immediately reduce Turbine load as needed to maintain Rx power less than pre-transient condition.

After this, Power Range Instrument N42 will drift high. The operator will enter AP/1/A/5500/16, Malfunction of Nuclear Instrumentation. The operator will address Technical Specification LCO 3.3.1, Reactor Trip System (RTS) Instrumentation.

When the power range channel is removed from service, MSR Relief Valve 1HS179 will fail open causing a loss of turbine efficiency and an increase in reactor power. The operator will implement AP/1/A/5500/01, Steam Leak. The operator will recognize the failure and perform a rapid downpower in accordance with AP/1/A/5500/04, Rapid Downpower, in an attempt to shut the valve.

Eventually the valve will re-close and the downpower will be stabilized.

Subsequently, one Control Bank B Control Rod will drop into the core. The operator will respond in accordance with ARP 1AD-2/D-9, RPI at Bottom Rod Drop and will implement AP/1/A/5500/14, Rod Control Malfunction, and ultimately reduce power to less than 50% using AP/1/A/5500/04, Rapid Downpower. The operator will address Technical Specification LCO 3.1.4, Rod Group Alignment Limits and LCO 3.2.4 Quadrant Power Tilt Ratio (QPTR).

During the downpower, a leak will develop on the 1B NCP Upper Bearing Oil Reservoir. The operator will respond in accordance with AP/1/A/5500/08, Malfunction of NC Pump, and the operator will be required to trip the reactor, stop the 1B NCP, and go to EP/1/A/5000/E-0, Reactor Trip and/or Safety Injection.

Upon the reactor trip, a loss of Vital AC Panel 1EKVC will occur resulting in an inadvertent Safety Injection. Also, on the reactor trip, the Turbine will fail to trip automatically, and must be tripped manually. The operator will enter EP/1/A/5000/E-0, Reactor Trip or Safety Injection, reset SI and stop all ECCS Pumps except for one NV Pump.

Ultimately, the crew will transition to step 9 of EP/1/A/5000/ES-1.1, Safety Injection Termination.

Once SI is terminated, the operator may address AP/1/A/5500/15, Loss of Vital or Aux Control Power.

The scenario will terminate in EP/1/A/5000/ES-1.1 at Step 14.l prior to the operator re-establishing Letdown.

Appendix D Scenario Outline Form ES-D-1 (Rev_011320)

Critical Tasks:

Trip the Reactor prior to stopping the 1B NCP during a low oil level condition and trip the NCP only after Reactor power level has dropped to less than 5%; before the CRS starts to read the Immediate Actions of EP/1/A/5000/E-0, Reactor Trip or Safety Injection to the Control Board Operators to verify that a Reactor Trip has occurred.

Safety Significance: The transient placed on the unit when an NCP is secured at power can challenge both reactor protection and control systems. Station management has decided that the conservative approach to dealing with this transient is to trip the reactor anytime a NCP malfunction warrants stopping a pump in Mode 1. Guidance is given to wait until reactor power is less than 5%

before stopping the NC pump to ensure that the NC pump will provide adequate flow/core cooling until reactor power is sufficiently low enough to preclude a challenge to fuel integrity. If the action can be taken, and is not taken, this demonstrates mis-operation or incorrect operation that could unnecessarily challenge a fission product barrier (NCS).

Manually trip the Turbine before a valid Orange Path develops on the Integrity Critical Safety Function.

Safety Significance: Failure to trip the Main Turbine when conditions exist that allow the operator to do so, constitutes mis-operation or incorrect operator performance that unnecessarily challenges the Integrity Critical Safety Function. An overcooling event, such as a failure of the Turbine to trip on a reactor trip, in the presence of an inadvertent actuation of Safety Injection creates the potentiality of creating a Pressurized Thermal Shock conditions that otherwise would not exist.

PROGRAM: McGuire Operations Training MODULE: Initial License Operator Training Class ILT 20-1 TOPIC: NRC Simulator Exam Scenario N20-1-1

REFERENCES:

1. Technical Specification LCO 3.3.1, Reactor Trip System (RTS) Instrumentation (184/166)

2. Technical Specification LCO 3.3.2, Engineered Safety Feature Actuation System (ESFAS)

Instrumentation (Amendment 184/166)

3. Technical Specification LCO 3.6.6, Containment Spray System (Amendment 308/287)

4. PT/0/A/4600/113, McGuire Time Critical Action/Time Sensitive Actions (Rev 28)

5. OMP 4-3, Use of Emergency and Abnormal Procedures and FLEX Support Guidelines (Rev 48)

6. AP/1/A/5500/16, Malfunction of Nuclear Instrumentation (Rev 15)

7. AP/1/A/5500/01, Steam Leak (Rev 19)

8. AP/1/A/5500/04, Rapid Downpower (Rev 31)

9. AP/1/A/5500/14, Rod Control Malfunction (Rev 16)

10. Technical Specification LCO 3.1.4, Rod Group Alignment Limits (Amendment 184/166)

11. Technical Specification LCO 3.2.4, Quadrant Power Tilt Ratio (QPTR) (Amendment 184/166)

12. OP/1/A/6100/010 C, Annunciator Response for Panel 1AD-12 (Rev 71)

13. AP/1/A/5500/08, Malfunction of NC Pump (Rev 17)

14. EP/1/A/5000/E-0, Reactor Trip or Safety Injection (Rev 36)

15. EP/1/A/5000/ES-1.1, Safety Injection Termination (Rev 30)

Validation Time: 120 minutes Author: David Lazarony, Essential Training & Consulting, LLC Facility Review: ________________________

Rev. 011320 McGuire 2020 NRC Scenario #1 Objectives:

Given the simulator at an initial condition of 100% power evaluate:

1. the SROs ability to supervise the control room team during the normal, abnormal, and emergency situations that arise, including compliance with all facility procedures, Technical Specifications, and other commitments.

2. each crew members ability to effectively communicate as part of a control room team during the normal, abnormal, and emergency situations that arise.

3. the ROs ability to effectively diagnose and mitigate the consequences an overpower event in accordance with OMP 4-3, Use of Emergency and Abnormal Procedures and FLEX Support Guidelines.

4. each crew members ability to effectively diagnose an Excore Power Range Instrument failure and the BOPs ability to mitigate the consequences in accordance with AP/1/A/5500/16, Malfunction of Nuclear Instrumentation.

5. each crew members ability to effectively diagnose a failed open MSR Relief Valve and the RO and BOPs ability to respond to such an event in accordance with AP/1/A/5500/01, Steam Leak.

6. each crew members ability to conduct a rapid downpower in accordance with AP/1/A/5500/04, Rapid Downpower, whenever plant conditions dictate the need to do so.

7. each crew members ability to effectively diagnose a dropped control rod at power, and the ROs ability to respond to such an event in accordance with AP/1/A/5500/14, Rod Control Malfunction.

8. each crew members ability to effectively diagnose an NCP Pump Bearing Oil Cooler leak, and their ability to respond to such an event in accordance with AP/1/A/5500/08, Malfunction of NC Pump.

9. each crew members ability to effectively diagnose an inadvertent actuation of Safety Injection and the RO and BOPs ability to respond to such an event in accordance with EP/1/A/5000/E-0, Reactor Trip or Safety Injection, and EP/1/A/5000/ES-1.1, Safety Injection Termination.

10. the ROs ability to determine that the Main Turbine has failed to automatically trip during a reactor trip from power and take action to manually trip the Main Turbine.

Scenario Event Description NRC Scenario 1 Facility: McGuire Scenario No.: 1 Op Test No.: N20-1 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: The plant is at 100% power (EOL). The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Turnover: The following equipment is Out-Of-Service: The 1A NS Pump is OOS for preventative maintenance. ACTION has been taken in accordance with Technical Specification LCO 3.6.6 ACTION A. 1NCPT-5150, Pzr Pressure Channel 2, has failed and has been removed from service in accordance with plant procedures. ACTION has been taken in accordance with Technical Specification LCO 3.3.1 and 3.3.2. MCB Annunciator 1AD-12, F-5, FWST EMERGENCY LO TEMP, has alarmed spuriously several times over the last hour and has currently failed ON (IAE has verified that the issue is limited to an annunciator card issue).

Critical Tasks: See Below Event Malf. Event Type* Event No. No. Description 1 REM C-RO High Pressure Heaters Bypass/Overpower CF0075 C-SRO 2 MAL C-BOP Power Range Failure ENB013D C(TS)-SRO 3 REM R-RO MSR Relief Valve fails OPEN/Downpower HS0179 N-BOP N-SRO 4 MAL C-RO Dropped Rod/Downpower IRE006K2 C(TS)-SRO 5 MAL C-RO 1B NCP Pump Bearing Oil Cooler Leak NCP007BU C-BOP C-SRO 6 MAL M-RO Loss of VIAC 1EKVC/Inadvertent SI Actuation EPL003C M-BOP M-SRO 7 MAL C-RO Failure of the Turbine to Trip in AUTO DEH003A C-SRO

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 1 McGuire 2020 NRC Scenario #1 The plant is at 100% power (EOL). The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The following equipment is Out-Of-Service: The 1A NS Pump is OOS for preventative maintenance. ACTION has been taken in accordance with Technical Specification LCO 3.6.6 ACTION A. 1NCPT-5150, Pzr Pressure Channel 2, has failed and has been removed from service in accordance with plant procedures. ACTION has been taken in accordance with Technical Specification LCO 3.3.1 and 3.3.2. MCB Annunciator 1AD-12, F-5, FWST EMERGENCY LO TEMP, has alarmed spuriously several times over the last hour and has currently failed ON (IAE has verified that the issue is limited to an annunciator card issue).

Shortly after taking the watch, the High-Pressure Heater Bypass Valve (1CF-75) will inadvertently open. The operator will respond in accordance with OAC Alarm Response Procedure M1L2917, U1 WATER BYPASSING A&B HEATERS, and OMP 4-3, Use of Emergency and Abnormal Procedures and FLEX Support Guidelines, and immediately reduce Turbine load as needed to maintain Rx power less than pre-transient condition.

After this, Power Range Instrument N42 will drift high. The operator will enter AP/1/A/5500/16, Malfunction of Nuclear Instrumentation. The operator will address Technical Specification LCO 3.3.1, Reactor Trip System (RTS) Instrumentation.

When the power range channel is removed from service, MSR Relief Valve 1HS179 will fail open causing a loss of turbine efficiency and an increase in reactor power. The operator will implement AP/1/A/5500/01, Steam Leak. The operator will recognize the failure and perform a rapid downpower in accordance with AP/1/A/5500/04, Rapid Downpower, in an attempt to shut the valve. Eventually the valve will re-close and the downpower will be stabilized.

Subsequently, one Control Bank B Control Rod will drop into the core. The operator will respond in accordance with ARP 1AD-2/D-9, RPI at Bottom Rod Drop and will implement AP/1/A/5500/14, Rod Control Malfunction, and ultimately reduce power to less than 50% using AP/1/A/5500/04, Rapid Downpower. The operator will address Technical Specification LCO 3.1.4, Rod Group Alignment Limits and LCO 3.2.4 Quadrant Power Tilt Ratio (QPTR).

During the downpower, a leak will develop on the 1B NCP Upper Bearing Oil Reservoir. The operator will respond in accordance with AP/1/A/5500/08, Malfunction of NC Pump, and the operator will be required to trip the reactor, stop the 1B NCP, and go to EP/1/A/5000/E-0, Reactor Trip and/or Safety Injection.

Upon the reactor trip, a loss of Vital AC Panel 1EKVC will occur resulting in an inadvertent Safety Injection. Also, on the reactor trip, the Turbine will fail to trip automatically, and must be tripped manually. The operator will enter EP/1/A/5000/E-0, Reactor Trip or Safety Injection, reset SI and stop all ECCS Pumps except for one NV Pump.

Ultimately, the crew will transition to step 9 of EP/1/A/5000/ES-1.1, Safety Injection Termination.

Once SI is terminated, the operator may address AP/1/A/5500/15, Loss of Vital or Aux Control Power.

The scenario will terminate in EP/1/A/5000/ES-1.1 at Step 14.l prior to the operator re-establishing Letdown.

Scenario Event Description NRC Scenario 1 Critical Tasks:

Trip the Reactor prior to stopping the 1B NCP during a low oil level condition and trip the NCP only after Reactor power level has dropped to less than 5% but before the CRS starts to read the Immediate Actions of EP/1/A/5000/E-0, Reactor Trip or Safety Injection, to the Control Board Operators to verify that a Reactor Trip has occurred.

Safety Significance: The transient placed on the unit when an NCP is secured at power can challenge both reactor protection and control systems. Station management has decided that the conservative approach to dealing with this transient is to trip the reactor anytime a NCP malfunction warrants stopping a pump in Mode 1. Guidance is given to wait until reactor power is less than 5% before stopping the NC pump to ensure that the NC pump will provide adequate flow/core cooling until reactor power is sufficiently low enough to preclude a challenge to fuel integrity. If the action can be taken, and is not taken, this demonstrates mis-operation or incorrect operation that could unnecessarily challenge a fission product barrier (NCS).

Manually trip the Turbine before a valid Orange Path develops on the Integrity Critical Safety Function.

Safety Significance: Failure to trip the Main Turbine when conditions exist that allow the operator to do so, constitutes mis-operation or incorrect operator performance that unnecessarily challenges the Integrity Critical Safety Function. An overcooling event, such as a failure of the Turbine to trip on a reactor trip, in the presence of an inadvertent actuation of Safety Injection creates the potentiality of creating a Pressurized Thermal Shock conditions that otherwise would not exist.

Scenario Event Description NRC Scenario 1 SIMULATOR OPERATOR INSTRUCTIONS Bench Mark ACTIVITY DESCRIPTION Reset to Temp IC 230 T = 0 Malfunctions (From IC-53):

(Base IC-53, [100% insert LOA_NS005 eq RACKED_OUT, insert EOL]) LOA_NS005A eq RACKED_OUT (1A NS Pump is OOS) insert XMT_NC_1NCPT5150 eq 1700 (1NCPT-5150 is OOS) insertBST_NC_PB_456A SET insertBST_NC_PB_456C SET insertBST_NC_PB_456D SET insertBST_NC_TB_421C SET insert OVR_1AD12_F05 eq ON (MCB Annunciator 1AD12/F5) insert MAL_EPL003C eq ACTIVE (Loss of EKVC); cd = H_X01_094_2 = 1 (RTB Open Light) insert MAL_DEH003A (Failure of the Turbine to Trip in AUTO)

RUN Place Tagout/O-Stick on:

1A NS Pump (Tagout)

Reset all SLIMs

1NCPT-5150 (O-stick)

MCB Annunciator 1AD12/F5 (O-stick)

Update Status Board, NOTE: RMWST DO = >1000 ppb.

Setup OAC Freeze.

Update Fresh Tech.

Spec. Log.

Fill out the AO's Available section of Shift Turnover Info.

Prior to Crew RUN Briefing Scenario Event Description NRC Scenario 1 Bench Mark ACTIVITY DESCRIPTION Crew Briefing

1. Assign Crew Positions based on evaluation requirements

2. Review the Shift Turnover Information with the crew.

3. Direct the crew to Review the Control Boards taking note of present conditions, alarms.

T-0 Begin Familiarization Period At direction of Execute Simulator examiner Scenario N20-1-1.

At direction of Event 1 High Pressure Heaters Bypass/Overpower examiner Insert REM_CF0075=0.5, Ramp = 30 At direction of Event 2 Power Range Failure examiner Insert MAL_ENB013D =

100 (High)

Ramp = 20 Seconds At direction of Event 3 MSR Relief Valve fails OPEN/Downpower examiner insert REM_HS0179 =

1.0 At direction of Event 4 Dropped Rod/Downpower examiner insert MAL_IRE006K2 STATIONARY_GRPPR (Control Rod K2 drops)

At direction of Event 5 1B NCP Pump Bearing Oil Cooler Leak examiner insertMAL_NCP007BU

= TRUE Scenario Event Description NRC Scenario 1 Bench Mark ACTIVITY DESCRIPTION Post-Rx Trip Event 6 Loss of VIAC 1EKVC/Inadvertent SI Actuation Insert MAL_EPL003C= NOTE: The Loss of VIAC 1EKVC will occur on ACTIVE Rx Trip.

(cd = H_X01_094_2 = 1)

Post-Rx Trip Event 7 Failure of the Turbine to Trip in AUTO Insert: NOTE: The Malfunction is inserted at T=0.

MAL_DEH003A = 2 Terminate the scenario upon direction of Lead Examiner Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 1 Page 9 of 61 Event

Description:

High Pressure Heaters Bypass/Overpower Shortly after taking the watch, the High-Pressure Heater Bypass Valve (1CF-75) will inadvertently open. The operator will respond in accordance with OAC Alarm Response Procedure M1L2917, U1 WATER BYPASSING A&B HEATERS, and OMP 4-3, Use of Emergency and Abnormal Procedures and FLEX Support Guidelines, and immediately reduce Turbine load as needed to maintain Rx power less than pre-transient condition.

Booth Operator Instructions: Insert REM_CF0075=0.5, Ramp = 30 Indications Available:

OAC Alarm M1L2917 (U1 Water Bypassing A&B Heaters).

TPBE will update over 100%.

Excore NIs will read in excess of 100%.

Main Generator MW output rises.

Time Pos. Expected Actions/Behavior Comments M1L2917, U1 WATER BYPASSING A&B HEATERS CRS (Step 1) Dispatch operator to check position of 1CF-75 (HP HTRS Bypass Vlv).

CRS (Step 2) Investigate for leakage through 1CF-75 (HP HTRS Bypass Vlv).

CRS (Step 3) Notify System Engineering.

NOTE: The crew may diagnose an overpower condition and adjust turbine load per OMP 4-3.

OMP 4-3, USE OF EMERGENCY AND ABNORMAL PROCEDURES AND FLEX SUPPORT GUIDELINES ATTACHMENT 10.1, PRUDENT OPERATOR ACTIONS RO Transient Load Changes

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 1 Page 10 of 61 Event

Description:

High Pressure Heaters Bypass/Overpower Time Pos. Expected Actions/Behavior Comments

Manual is preferred - Immediately reduce Examiner Note: There is a up to 20 MWe and then reduce as possibility that the Technical needed to maintain reactor power less Specification LCO 3.4.1 (DNB) than pre-transient condition. After the will be entered and exited initial load reduction, the operators during this transient.

should use multiple and diverse indications to determine any additional load reduction.

TPBE on the OAC updates once per NOTE: After the plant is minute. Other indications (PR meters and stabilized the RO will place the Delta T meters) will indicate reactor Turbine back in AUTO.

response more quickly and will enable the operators to control the plant more precisely. (This combines the Operator Fundamentals of Conservatism and Controlling Plant Evolutions Precisely.)

NOTE: The CRS will dispatch an AO.

If so, Floor/Booth Instructor acknowledge as AO.

Wait 3 minutes of time, and report that 1CF-75 is OPEN.

NOTE: The CRS may call WCC/IAE to address the valve position.

If so, Booth Instructor acknowledge as WCC.

If the CRS directs that the valve be closed, Booth Instructor, as the WCC Supervisor, inform CRS that IAE will investigate prior to operating valve.

NOTE: The CRS will likely conduct a Focus Brief.

At the discretion of the Lead Examiner move to Event #2.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 2 Page 11 of 61 Event

Description:

Power Range Failure After this, Power Range Instrument N42 will drift high. The operator will enter AP/1/A/5500/16, Malfunction of Nuclear Instrumentation. The operator will address Technical Specification LCO 3.3.1, Reactor Trip System (RTS) Instrumentation.

Booth Operator Instructions: Insert MAL_ENB013D = 100 (High) Ramp

= 20 Seconds Indications Available:

MCB Annunciator 1AD-2 B3, P/R CHANNEL DEVIATION

MCB Annunciator 1AD-2 C8, P/R OVERPOWER ROD STOP

MCB Annunciator 1AD-2 A8, OTDT RUNBACK/ROD STOP ALERT

MCB Annunciator 1AD-2 E8, DCS TROUBLE

MCB Annunciator 1AD-6, F8, OPDT PROTECTION ALERT

MCB PR N42 indicates HIGHER than other Power Range channels

PR N42 Drawer indicates HIGHER than other Power Range drawers

PR N42 Drawer Upper Detector indicates HIGH.

Time Pos. Expected Actions/Behavior Comments AP/1/A/5500/16, MALFUNCTION OF NUCLEAR INSTRUMENTATION CASE III, POWER RANGE MALFUNCTION RO (Step 1) Place control rods in manual.

RO (Step 2) Check S/G levels - AT PROGRAMMED LEVEL.

CRS (Step 3) Announce occurrence on paging NOTE: The CRS may ask U2 system. RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 4) Check P/R channels - ONLY ONE NOTE: A Channel Check will CHANNEL FAILED. reveal that only N42 has failed.

CRS (Step 5) Secure any power increase in progress.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 2 Page 12 of 61 Event

Description:

Power Range Failure Time Pos. Expected Actions/Behavior Comments RO (Step 6) Check the following interlocks - IN REQUIRED STATE FOR EXISTING PLANT CONDITONS:

P-7 Lo Power Rx Trips Blocked NOTE: The status light is DARK as expected.

P-8 Hi Pwr Lo Flo Rx Trip Blocked NOTE: The status light is DARK as expected.

P-10 Nuclear at Power. NOTE: The status light is LIT as expected.

BOP (Step 7) Perform the following actions at the MISCELLANIOUS CONTROL AND INDICATION PANEL drawer:

Place the appropriate ROD STOP NOTE: The BOP will operate BYPASS switch to the failed channel the switch for N42.

position.

Place the POWER MISMATCH NOTE: The BOP will place BYPASS switch to the failed channel the switch in the N42 position.

position.

BOP (Step 8) Perform the following actions at the DETECTOR CURRENT COMPARATOR drawer:

Place the UPPER SECTION switch to NOTE: The BOP will place the failed channel position. the switch in the N42 position.

Check the CHANNEL DEFEAT light for the upper section - LIT.

Place the LOWER SECTION switch to NOTE: The BOP will place the failed channel position. the switch in the N42 position.

Check the CHANNEL DEFEAT light for the lower section - LIT.

BOP (Step 9) Perform the following action at the COMPARATOR AND RATE drawer:

Place the COMPARATOR CHANNEL NOTE: The BOP will place DEFEAT switch to the failed channel the switch in the N42 position.

position.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 2 Page 13 of 61 Event

Description:

Power Range Failure Time Pos. Expected Actions/Behavior Comments

Check the COMPARATOR DEFEAT light - LIT.

NOTE Removing fuses from power range drawers may cause associated NIS annunciators to alarm.

BOP (Step 10) Trip bistables of failed channel as follows:

Remove Control Power fuses from NOTE: This action will cause POWER RANGE A drawer for failed Annunciators to alarm on MCB channel. Panel 1AD-2.

BOP

IF Power Range Cabinet shows evidence NOTE: There is no such of damage evidence displayed.

BOP/ (Step 11) Check the following status lights for RO the failed channel - LIT:

NUC OVERPOWER ROD STOP CH I(II, III, IV) BYP (1SI-19)

P/R HI FLUX LO STPT (1SI-2)

P/R HI FLUX HI STPT (1SI-2)

P/R HI FLUX RATE (1SI-3)

BOP/ (Step 12) Check the following annunciator RO lights - LIT:

P/R HI VOLTAGE FAILURE (1AD-2, F-3)

P/R HI FLUX HI STPT ALERT (1AD-2.

A-3)

P/R HI FLUX RATE ALERT (1AD-2, A-1)

BOP/ (Step 13) Check the following status lights on RO 1SI LIT:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 2 Page 14 of 61 Event

Description:

Power Range Failure Time Pos. Expected Actions/Behavior Comments

P/R LO SETPOINT TRAIN A TRIP BLOCKED

P/R LO SETPOINT TRAIN B TRIP BLOCKED RO (Step 14) Check all CF control valves - IN AUTO.

RO (Step 15) Adjust control rods to maintain T-Avg at T-Ref.

RO (Step 16) WHEN T-Avg within 1°F of T-Ref NOTE: The RO may place the AND auto rod control desired, THEN return Control Rods back in AUTO.

control rods to auto.

CRS (Step 17) Instruct IAE to trip the following NOTE: The CRS may call bistables associated with failed P/R channel WCC/IAE to address the failed within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of failure PER channel and insert bistables.

IP/1/A/3090/014 (Tripping Inoperable If so, Booth Instructor Protection Channels): acknowledge as WCC (Note that there are already four Channel II Bistables tripped already due to the failed Pzr Pressure Channel).

OPDT

OTDT CRS (Step 18) IF AT ANY TIME failed P/R NOTE: The Power Range channel is repaired prior to IAE tripping Channel will NOT be repaired.

bistables,.

CRS (Step 20) IF AT ANY TIME IAE completes NOTE: IAE will not complete Step 17. Step 17.

CRS (Step 20) WHEN malfunctioning P/R channel repaired, ..

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 2 Page 15 of 61 Event

Description:

Power Range Failure Time Pos. Expected Actions/Behavior Comments NOTE: The CRS will likely conduct a Focus Brief.

TECHNICAL SPECIFICATION 3.3.1, REACTOR TRIP SYSTEM (RTS)

INSTRUMENTATION CRS LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE CRS APPLICABILITY: According to Table 3.3.1-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with A.1 Enter the Condition Immediately one or more required referenced in Table 3.3.1-1 for channels inoperable. the channel(s).

NOTE: The CRS will determine that Functions 2a, 2b, 3, 6, 7, 16b, 16c, and 16d are affected by this failure and that Condition A is required and that ACTION A.1 must be taken.

D. One channel inoperable D.1.1 Perform SR 3.2.4.2 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND D.1.2 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR D.2 Be in MODE 3 78 Hours NOTE: This Action is associated with Functions 2.a and 3 (Hi Flux Hi setpoint and hi positive rate trips).

E. One channel inoperable. E.1 Place channel in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR E.2 Be in MODE 3 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months NOTE: This Action is associated with Functions 2.b,

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 2 Page 16 of 61 Event

Description:

Power Range Failure Time Pos. Expected Actions/Behavior Comments 6 and 7 (Hi Flux Lo setpoint, OPDT and OTDT trips).

T. One or more channel(s) T.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. required state for existing unit conditions.

OR 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months T.2 Be in MODE 2 NOTE: This Action is associated with Functions 16.b and 16.c (P-7 and P-8)

S. One or more channel(s) S.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. required state for existing unit conditions.

OR 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months S.2 Be in MODE 3 NOTE: This Action is associated with Function 16.c (P-10).

NOTE: The CRS will likely conduct a Focus Brief.

At the discretion of the Lead Examiner move to Event #3.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 3 Page 17 of 61 Event

Description:

MSR Relief Valve fails OPEN/Downpower When the power range channel is removed from service, MSR Relief Valve 1HS179 will fail open causing a loss of turbine efficiency and an increase in reactor power. The operator will implement AP/1/A/5500/01, Steam Leak. The operator will recognize the failure and perform a rapid downpower in accordance with AP/1/A/5500/04, Rapid Downpower, in an attempt to shut the valve. Eventually the valve will re-close and the downpower will be stabilized.

Booth Operator Instructions: insert REM_HS0179 = 1.0 (Once inserted reduce size to ensure that leak stays within allowable makeup limit).

Indications Available:

Turbine MWe lowers rapidly

Core Ts initially lowers and then starts to rise

Reactor power rises

Steam pressure initially lowers and then starts to rise

OAC Alarm: 1C1 L/P TURBINE CROSSOVER STEAM TEMP RATE

OAC Alarm: 1C2 L/P TURBINE CROSSOVER STEAM TEMP RATE Time Pos. Expected Actions/Behavior Comments NOTE: The crew may diagnose an overpower condition and adjust turbine load per OMP 4-3.

OMP 4-3, USE OF EMERGENCY AND ABNORMAL PROCEDURES AND FLEX SUPPORT GUIDELINES ATTACHMENT 10.1, PRUDENT OPERATOR ACTIONS RO Transient Load Changes

Manual is preferred - Immediately reduce up to 20 MWe and then reduce as needed to maintain reactor power less than pre-transient condition. After the initial load reduction, the operators should use multiple and diverse indications to determine any additional load reduction.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 3 Page 18 of 61 Event

Description:

MSR Relief Valve fails OPEN/Downpower Time Pos. Expected Actions/Behavior Comments

TPBE on the OAC updates once per minute. Other indications (PR meters and Delta T meters) will indicate reactor response more quickly and will enable the operators to control the plant more precisely. (This combines the Operator Fundamentals of Conservatism and Controlling Plant Evolutions Precisely.)

AP/1/A/5500/01, STEAM LEAK NOTE: The CRS may dispatch AOs to look for steam leaks.

If so, Booth Instructor as AO, respond back in 3-5 minutes per script (See Page 20).

After 3-5 minutes of Non-investigatory Action, Call as Security and report Steam Release to atmosphere on U1 TB Roof.

RO/ (Step 1) Monitor Foldout page.

BOP Manual Reactor Trip Criteria: (IF any of the following occur: (1) Steam leak is jeopardizing personnel safety or plant equipment, (2) T-Avg is less than 551°F AND going down, or (3) UST level is less than 1 ft

- NOT Expected).

RO (Step 2) Reduce turbine load to maintain the NOTE: The RO may take the following: Turbine Control to MANUAL.

Excore NIs - LESS THAN OR EQUAL NOTE: Per OMP 4-3, the RO TO 100% has the authority to remove 20 Mwe initially, and then additional load as needed to stabilize temperature.

NC Loop D/Ts - LESS THAN 60ºF D/T

T-Avg - AT T-REF.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 3 Page 19 of 61 Event

Description:

MSR Relief Valve fails OPEN/Downpower Time Pos. Expected Actions/Behavior Comments CRS/ (Step 3) Check containment entry - IN NOTE: There is no BOP PROGRESS. Containment Entry in progress.

CRS (Step 3 RNO) GO TO Step 5.

BOP (Step 5) Check Pzr pressure prior to event -

GREATER THAN P-11 (1955 PSIG)

BOP (Step 6) Check Pzr level - STABLE OR NOTE: If Pzr level is lowering GOING UP the crew will perform the RNO prior to performing Step 7.

CRS (Step 7) IF AT ANY TIME while in this NOTE: This is a Continuous procedure Pzr level cannot be maintained Action. The CRS will make stable, THEN RETURN TO Step 6. one or more board operators aware.

CRS (Step 8) GO TO Step 12.

CRS (Step 12) Announce occurrence on paging NOTE: The CRS may ask U2 system. RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 13) Identify and isolate leak on Unit 1 as follows:

Check SM PORVs - CLOSED.

Check condenser dump valves -

CLOSED.

BOP

Check containment conditions -

NORMAL:

Containment temperature

Containment pressure

Containment humidity

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 3 Page 20 of 61 Event

Description:

MSR Relief Valve fails OPEN/Downpower Time Pos. Expected Actions/Behavior Comments

Containment floor and equipment sump level.

Check TD CA pump - OFF.

Check valves on "STEAM LINE DRAIN NOTE: The BOP may need to VALVES" board (1MC-9) - CLOSED. perform the RNO and close valves.

RO/

Check opposite Unit (Unit 2) STEAM NOTE: The CRS will ask U2 BOP HEADER PRESSURE - GREATER RO.

THAN 200 PSIG. If so, Floor Instructor acknowledge as U2 RO, and report U2 Steam Header Pressure is 1000 psig.

CRS

Dispatch operator to check for leaks. NOTE: If not already done, the CRS will dispatch AOs to look for steam leaks.

After 2-3 minutes, Booth Instructor, as AO, report that MSR 1C1 Shell Side Relief Valve (1HS179) is lifting.

BOP (Step 14) Check UST level - STABLE OR NOTE: The UST level may be GOING UP. rising or lowering. If rising go to Step 15.

BOP (Step 14 RNO) Makeup to UST as required to maintain level.

CRS (Step 15) Evaluate unit shutdown as follows:

Check unit status - IN MODE 1 OR 2.

Determine if unit shutdown or load reduction is warranted based on the following criteria:

Size of leak

Location of leak

Rate of depletion of secondary inventory

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 3 Page 21 of 61 Event

Description:

MSR Relief Valve fails OPEN/Downpower Time Pos. Expected Actions/Behavior Comments

IF steam is leaking from a secondary NOTE: Steam is leaking from heater relief OR MSR relief valve, an MSR relief valve.

THEN reducing turbine load may reduce pressure enough to close relief valve.

IF turbine trip will isolate steam leak NOTE: It is NOT necessary to (such as feedwater heater leak or trip the Turbine.

MSR leak), THEN it may be desirable to perform an orderly shutdown of the turbine and maintain reactor power in Mode 1.

CRS

Check unit shutdown or load reduction - NOTE: It is necessary to REQUIRED. reduce load in an attempt to close the lifting relief valve.

CRS

Check reactor trip - REQUIRED. NOTE: A reactor trip is NOT required.

CRS (Step 15.D RNO) GO TO Step 15.H.

CRS * (Step 15.H) Determine if turbine trip is desired to isolate steam leak:

Check steam leak location -

KNOWN TO BE ISOLABLE BY TURBINE TRIP

Turbine trip - DESIRED. NOTE: A turbine trip is NOT desired.

CRS (Step 15.H RNO) Perform the following:

Reduce load as necessary PER one of the following:

OP/1/A/6100/003 OR

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 3 Page 22 of 61 Event

Description:

MSR Relief Valve fails OPEN/Downpower Time Pos. Expected Actions/Behavior Comments

AP/1/A/5500/04 (Rapid Downpower). NOTE: The CRS will transition to AP-4.

Floor/Booth Instructor: If it appears likely that the crew will use the OP rather than the AP, state as the Operations Manager that it is desired to use AP-4.

AP/1/A/5500/04, RAPID DOWNPOWER RO/ (Step 1) Monitor Foldout page.

BOP Uncontrolled Cooldown (If Tavg < 551°F and lowering..Not Expected)

Power Factor (Adjust power factor during NOTE: The RO will adjust load reduction to maintain power factor MVARS as needed.

between 0.9 to 1.0 lagging, using "VOLTAGE ADJUST" pushbutton)

Manual Rx Power Control (< C-5, Not Expected)

Turbine Shutdown (Turbine Load < 15 MWe Not Expected)

CRS (Step 2) Announce occurrence on page. NOTE: The CRS may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 3) Check turbine control - IN AUTO.

RO (Step 4) Check MW LOOP - IN SERVICE. NOTE: If MW LOOP is NOT in service, the RO will place MW LOOP in service per RNO.

RO (Step 4 RNO) Depress "MW IN/MW OUT" pushbutton.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 3 Page 23 of 61 Event

Description:

MSR Relief Valve fails OPEN/Downpower Time Pos. Expected Actions/Behavior Comments CRS (Step 5) Check shutdown to Mode 3 -

DESIRED.

CRS (Step 5 RNO) IF turbine will be shutdown during downpower, THEN enter target load of 15 MWE in turbine control panel

Observe Note prior to Step 8 and GO TO Step 8.

NOTE The following table can be used to determine unloading rates. Rates other than specified are acceptable.

CRS (Step 8) Determine the required power NOTE: The CRS will reduce reduction rate (MW/min). load at 10-20 MWe/minute.

BOP (Step 9) Notify DEC BA (Balancing Authority) Booth Instructor: as DEC of load reduction. BA, acknowledge.

RO (Step 10) Check control rods - IN AUTO.

BOP (Step 11) Borate NC System as follows:

Energize all backup Pzr heaters.

Check unit to be shutdown - VIA REACTOR TRIP FROM 15% POWER.

CRS (Step 11.B RNO) GO TO Step 11.D.

BOP (Step 11.D) Determine boration amount based on the following:

Power Reduction Rate (MW/min)

Present NC System Boron Concentration (ppm)

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 3 Page 24 of 61 Event

Description:

MSR Relief Valve fails OPEN/Downpower Time Pos. Expected Actions/Behavior Comments

Total Power change (%). NOTE: The total power change will be determined by the CRS and will affect the amount of boron inserted by the BOP.

(Expected 300-500 gallons)

Record calculated boration amount:

RO

Check auto or manual rod control -

AVAILABLE.

NOTE If load reduction of greater than 60% is planned and Unit 1 is to remain in Mode 1, the final (1/4) addition of boron may not be required based on rate of Xenon production and control rod response.

BOP

Perform boration in four equal additions during load reduction PER Enclosure 2 (Emergency Boration).

NOTE: The CRS may assign the BOP to perform this action.

If so, BOP Examiner follow actions of Enclosure 2.

Other Examiners follow AP-4 Actions, Step 12, on Page 25.

AP/1/A/5500/04, RAPID DOWNPOWER ENCLOSURE 2, EMERGENCY BORATION BOP (Step 1) Check OAC AVAILABLE.

BOP (Step 2) Use OAC point M1P0785 (U1 Gallons Boric Acid Added Via 1NV-265B) to monitor boric acid gallons added while 1NV 265B (U1 NV Pump Boric Acid Sup Isol) is open.

BOP (Step 3) GO TO Step 5.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 3 Page 25 of 61 Event

Description:

MSR Relief Valve fails OPEN/Downpower Time Pos. Expected Actions/Behavior Comments BOP (Step 5) Check boric acid transfer pump NOTE: The 1B Boric Acid RUNNING. Transfer Pump is running.

BOP (Step 6) OPEN 1NV265B (U1 NV Pump Boric Acid Sup Isol).

BOP (Step 7) Do not continue until desired amount of boric acid has been added.

BOP (Step 8) CLOSE 1NV265B (U1 NV Pump Boric Acid Sup Isol).

BOP (Step 9) IF boric acid transfer pump was NOTE: The 1B Boric Acid started in Step 5 RNO, THEN . Transfer Pump was running initially.

BOP (Step 10) Repeat enclosure as required.

AP/1/A/5500/04, RAPID DOWNPOWER Examiner NOTE: Examiners following the CRS/RO continue HERE.

RO (Step 12) WHEN boration commenced, THEN initiate turbine load reduction to desired load at desired rate.

BOP (Step 13) Display Rod Insertion Limits on OAC by entering turn on code RIL.

NOTE Control Rods may approach rod insertion limits during load reduction.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 3 Page 26 of 61 Event

Description:

MSR Relief Valve fails OPEN/Downpower Time Pos. Expected Actions/Behavior Comments CRS (Step 14) IF AT ANY TIME "CONTROL ROD NOTE: This is a Continuous BANK LO LO LIMIT" alarm (1AD-2, B-9) is Action. The CRS will make lit, THEN perform one of the following to one or more board operators comply with Tech Spec 3.1.6 (Control Bank aware.

Insertion Limits):

Ensure alarm clears within one hour as Xenon builds in.

OR

Initiate boration as necessary within one hour to restore control rods above insertion limits.

NOTE Unloading rates greater than 55 MW/min will meet C-7A interlock.

CRS (Step 15) IF AT ANY TIME during this NOTE: This is a Continuous procedure C-7A is received, THEN ensure Action. The CRS will make Transient Monitor freeze is triggered. one or more board operators aware.

CRS (Step 16) REFER TO the following: NOTE: The CRS may ask SM to address.

If so, Floor Instructor acknowledge as SM.

RP/0/A/5700/000 (Classification of Emergency)

RP/0/A/5700/010 (NRC Immediate Notification Requirements).

CRS (Step 17) Notify Reactor Engineer on duty of NOTE: The CRS may call load reduction. WCC/RE.

If so, Booth Instructor acknowledge.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 3 Page 27 of 61 Event

Description:

MSR Relief Valve fails OPEN/Downpower Time Pos. Expected Actions/Behavior Comments RO (Step 18) Check target load - LESS THAN NOTE: The CRS may have 1000 MW. selected a target load greater than 1000 MWe. If so, the crew will perform the RNO and wait until target load is reached. If not, continue to Step 19 Booth Operator Instructions: Insert REM_HS0179 = 0 (Remove 1HS179 Relief Valve Failure - At direction of Lead Examiner and after the 1st boration is complete.)

Booth Instructor: as AO, report that 1HS179 Relief Valve has reseated.

NOTE: The CRS will direct the RO to go to HOLD on the Turbine. The BOP may adjust boron concentration as needed to stabilize the plant.

CRS (Step 19) Check Unit 2 available to supply NOTE: The CRS will ask U2 aux steam as follows: RO.

Floor Instructor: As U2 RO report All these conditions are met.

Unit 2 Reactor power - GREATER THAN 15%

Unit 2 2AS-12 (U2 SM to AS Hdr Control Inlet Isol) - OPEN

Unit 2 - AVAILABLE TO SUPPLY AS HEADER.

RO (Step 20) Check SM flow on all S/Gs -

GREATER THAN 25%.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 3 Page 28 of 61 Event

Description:

MSR Relief Valve fails OPEN/Downpower Time Pos. Expected Actions/Behavior Comments RO (Step 21) WHEN all SM flows are less than NOTE: This is a conditional 75%, THEN ensure the following valves step. The CRS will make the ramp CLOSED: RO aware of this action, if NOT already done.

1CF-104AB (1A S/G CF Control Bypass)

1CF-105AB (1B S/G CF Control Bypass)

1CF-106AB (1C S/G CF Control Bypass)

1CF-107AB (1D S/G CF Control Bypass) Examiner NOTE: It may be necessary to allow the crew to stabilize the plant prior to moving to Event 4.

NOTE: The CRS may continue beyond this step in AP-4, however, it is expected that the plant will be stabilizing, and Event 4 is imminent.

After the RO has lowered Turbine Load by 10MWe, AND an AUTO Rod motion signal exists with Tavg > Tref by 1.5°F and Lead Examiner concurrence, move to Event #4.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 4 Page 29 of 61 Event

Description:

Dropped Rod/Downpower Subsequently, one Control Bank B Control Rod will drop into the core. The operator will respond in accordance with ARP 1AD-2/D-9, RPI at Bottom Rod Drop and will implement AP/1/A/5500/14, Rod Control Malfunction, and ultimately reduce power to less than 50%

using AP/1/A/5500/04, Rapid Downpower. The operator will address Technical Specification LCO 3.1.4, Rod Group Alignment Limits and LCO 3.2.4 Quadrant Power Tilt Ratio (QPTR).

Booth Operator Instructions: insert MAL_IRE006K2 STATIONARY_GRPPR (Control Rod K2 drops)

Indications Available:

DRPI for Control Rod K-2 indicates Rod on Bottom

MCB Annunciator 1AD-2/B-3, P/R CHANNEL DEVIATION

MCB Annunciator 1AD-2/B-10, ROD CONTROL NON URGENT FAILURE

MCB Annunciator 1AD-2/D-9, RPI AT BOTTOM ROD DROP

Tref > Tavg Time Pos. Expected Actions/Behavior Comments AP/1/A/5500/14, ROD CONTROL MALFUNCTION RO (Step 1) IF two or more rods are either Immediate Action dropped OR misaligned by greater than 24 NOTE: Only one Rod Dropped steps, during this event.

RO (Step 2) Place control rods in manual. Immediate Action NOTE: The RO will place the rods in Manual.

RO (Step 3) Check rod movement - STOPPED. Immediate Action RO (Step 4) Check all rods - ALIGNED WITH ASSOCIATED BANK.

RO (Step 4 RNO) Perform the following.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 4 Page 30 of 61 Event

Description:

Dropped Rod/Downpower Time Pos. Expected Actions/Behavior Comments NOTE DRPI problems are not addressed by this AP.

IF misaligned rod(s) due to DRPI NOTE: The misaligned rod is indication failure only, NOT a DRPI indication failure.

IF T-Avg has gone down, THEN lower NOTE: The RO may adjust Turbine load as necessary to restore T- load on the Turbine to Avg to T-Ref. maintain Tavg-Tref = 1oF.

GO TO Enclosure 1 (Response To Dropped or Misaligned Rod)

NOTE: The CRS will transition to Enclosure 1.

AP/1/A/5500/14, ROD CONTROL MALFUNCTION ENCLOSURE 1, RESPONSE TO DROPPED OR MISALIGNED ROD CRS (Step 1) Announce occurrence on paging NOTE: The CRS may ask U2 system. RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

CRS (Step 2) Dispatch rod control system NOTE: The CRS may call qualified IAE to perform the following: WCC/IAE to address.

If so, Booth Instructor acknowledge as WCC/IAE as appropriate.

Correct cause of misaligned rod.

Notify Control Room operators when auto or manual rod motion is available for reactivity control.

RO (Step 3) Do not move rods until IAE determines rod movement is available.

RO (Step 4) IF AT ANY TIME a runback occurs NOTE: This is a Continuous while in this procedure, THEN observe the Action. The CRS will make following guidance: one or more board operators aware.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 4 Page 31 of 61 Event

Description:

Dropped Rod/Downpower Time Pos. Expected Actions/Behavior Comments

IF IAE has determined that it is permissible to move rods, THEN respond to the runback PER AP/1/A/5500/03 (Load Rejection).

For all other circumstances, assume rod control is not available and respond to the runback as follows:

Trip Reactor.

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

RO (Step 5) Check ROD CONTROL URGENT FAILURE alarm (1AD-2, A-10) - DARK.

RO (Step 6) Use OAC point M1P1385 (Reactor Thermal Power, Best Estimate) to determine reactor power in subsequent steps.

RO (Step 7) Check AFD (Tech Spec 3.2.3) -

WITHIN TECH SPEC LIMITS.

NOTE If any control rod is misaligned more than 12 steps, Step 15 will provide guidance for performing any Tech Spec required power reduction.

CRS (Step 8) REFER TO the following Tech Specs while continuing in the enclosure:

Tech Spec 3.1.4 (Rod Group Alignment NOTE: The CRS may check Limits). the TS now and conclude that LCO 3.1.4 must be entered.

Tech Spec 3.1.5 (Shutdown Bank Insertion Limits).

Tech Spec 3.1.6 (Control Bank Insertion NOTE: The CRS may check Limits). the TS now and conclude that LCO 3.1.6 is NOT required to be entered.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 4 Page 32 of 61 Event

Description:

Dropped Rod/Downpower Time Pos. Expected Actions/Behavior Comments

Tech Spec 3.2.4 (QPTR) NOTE: The CRS may check the TS now and conclude that LCO 3.2.4 must be entered.

Ensure shutdown margin calculation is NOTE: The CRS may ask the performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . U2 BOP or call WCC to perform SDM calculation.

If so, Floor/Booth Instructor acknowledge as WCC as appropriate.

CRS (Step 9) Contact Reactor Engineer for NOTE: The CRS may call instructions. WCC/RE to address.

If so, Booth Instructor acknowledge as WCC/RE as indicate that a dropped Rod recovery plan will be developed.

CRS (Step 10) If Tech Specs permit continued NOTE: The CRS may direct operation in the current mode for an the SM to evaluate.

unlimited period of time with control rods If so, Floor Instructor, misaligned.. acknowledge as SM.

CRS (Step 11) IF AT ANY TIME IAE desires to NOTE: This is a Continuous operate the lift coil disconnect switches as Action. The CRS will make part of troubleshooting activities, THEN one or more board operators REFER TO OP/1/A/6150/008 (Rod Control), aware.

Enclosure 4.9 (Operating Lift Coil Disconnect Switches for Maintenance Troubleshooting).

RO (Step 12) Check reactor power - GREATER THAN OR EQUAL TO 5%

RO/ (Step 13) Maintain T-Avg within 1°F of T-Ref BOP as follows:

Adjust Turbine load. NOTE: The RO may adjust load on the Turbine as needed.

OR

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 4 Page 33 of 61 Event

Description:

Dropped Rod/Downpower Time Pos. Expected Actions/Behavior Comments

Borate/Dilute NC System. NOTE: The BOP may adjust NCS Boron Concentration as needed.

CRS (Step 14) Determine if power reduction is required as follows:

Check any misaligned rod - GREATER THAN 12 STEPS MISALIGNED.

RO

Check only one rod - MISALIGNED. NOTE: Control Rod K-2 is dropped.

Check reactor power - GREATER than NOTE: Power is > 50%.

50%

CRS (Step 15) Reduce reactor power below 50% Booth Instructor: If the CRS prior to rod realignment as follows: contacts the WCC, as the Operations Manager direct that AP-4 be used; and lower power to 40% at 10MWe/min within 30 minutes.

Ensure reactor power is less than 75% NOTE: The CRS may check within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of rod misalignment to the TS now and conclude that comply with Tech Spec 3.1.4. LCO 3.1.4 must be entered.

Check QPTR (Tech Spec 3.2.4) - NOTE: The CRS may check WITHIN TECH SPEC LIMITS. the TS now and conclude that LCO 3.2.4 must be entered.

(Step 15.b RNO) Ensure reactor power is also reduced in subsequent steps as required PER Tech Spec 3.2.4 (QPTR).

Continue reducing load as directed in subsequent steps until reactor power is less than 50% to comply with Reactor Engineering requirements.

RO/

Observe the following limitations during BOP power reduction:

Do not move rods until IAE determines rod movement is available.

Borate as required during power reduction to maintain T-Avg at T-Ref.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 4 Page 34 of 61 Event

Description:

Dropped Rod/Downpower Time Pos. Expected Actions/Behavior Comments

Monitor AFD during load reduction.

IF AT ANY TIME AFD reaches Tech NOTE: This is a Continuous Spec limit AND reactor power is Action. The CRS will make greater than 50%, THEN perform the one or more board operators following: aware.

Trip Reactor

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

Reduce reactor power to less than 50% PER one of the following procedures:

OP/1/A/6100/003 (Controlling Procedure For Unit Operation).

Enclosure 4.2 (Power Reduction)

OR

AP/1/A/5500/04 (Rapid Booth Instructor: If the CRS Downpower). contacts the WCC, as the Operations Superintendent direct that AP-4 be used; and lower power to 40% at 10MWe/min within 30 minutes.

NOTE: The CRS will likely conduct a Focus Brief.

AP/1/A/5500/04, RAPID DOWNPOWER RO/ (Step 1) Monitor Foldout page.

BOP Uncontrolled Cooldown (If Tavg < 551°F and lowering..Not Expected)

Power Factor (Adjust power factor during NOTE: The RO will adjust load reduction to maintain power factor MVARS as needed.

between 0.9 to 1.0 lagging, using "VOLTAGE ADJUST" pushbutton)

Manual Rx Power Control (< C-5, Not Expected)

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 4 Page 35 of 61 Event

Description:

Dropped Rod/Downpower Time Pos. Expected Actions/Behavior Comments Turbine Shutdown (Turbine Load < 15 MWe Not Expected)

CRS (Step 2) Announce occurrence on page.

RO (Step 3) Check turbine control - IN AUTO.

RO (Step 4) Check MW LOOP - IN SERVICE. NOTE: MW Loop may be in service RO (Step 4 RNO) Depress MW IN/MW OUT pushbutton.

CRS (Step 5) Check shutdown to Mode 3 -

DESIRED.

CRS (Step 5 RNO) IF turbine will be shutdown during downpower, THEN enter target load of 15 MWE in turbine control panel

Observe Note prior to Step 8 and GO TO Step 8.

NOTE The following table can be used to determine unloading rates. Rates other than specified are acceptable.

CRS (Step 8) Determine the required power NOTE: The CRS will reduce reduction rate (MW/min). load at 10-12 MWe/minute.

BOP (Step 9) Notify DEC BA (Balancing Authority) Booth Instructor: as DEC of load reduction. BA, acknowledge.

RO (Step 10) Check control rods - IN AUTO. NOTE: The control rods are in MANUAL for the dropped Rod event.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 4 Page 36 of 61 Event

Description:

Dropped Rod/Downpower Time Pos. Expected Actions/Behavior Comments RO (Step 10 RNO) Perform the following:

IF auto control available, NOTE: AUTO rod control is NOT available.

IF manual control available, THEN NOTE: MANUAL rod control is NOT available.

BOP

IF rods cannot be moved in auto or manual, THEN perform the following:

Borate as required to maintain T-Avg at T-Ref.

Monitor AFD during load reduction.

RO/

IF AT ANY TIME AFD reaches Tech NOTE: This is a Continuous BOP Spec limit AND reactor power is Action. The CRS will make greater than 50%, THEN perform the one or more board operators following: aware.

Trip Reactor.

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

CAUTION Power reduction without rod control may require periodically halting or varying the load reduction rate to allow boration time to take effect. Focused coordination of load reduction rate and boration will be required to maintain T-Avg at T-Ref.

Maintain T-Avg at T-Ref BOP (Step 11) Borate NC System as follows:

Energize all backup Pzr heaters. NOTE: All Pzr Heaters are expected to be energized.

Check unit to be shutdown - VIA REACTOR TRIP FROM 15% POWER.

CRS (Step 11.B RNO) GO TO Step 11.D.

BOP (Step 11.D) Determine boration amount based on the following:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 4 Page 37 of 61 Event

Description:

Dropped Rod/Downpower Time Pos. Expected Actions/Behavior Comments

Power Reduction Rate (MW/min)

Present NC System Boron Concentration (ppm)

Total Power change (%). NOTE: The total power change will be determined by the CRS and will affect the amount of boron inserted by the BOP.

Record calculated boration amount:

RO

Check auto or manual rod control -

AVAILABLE.

NOTE If load reduction of greater than 60% is planned and Unit 1 is to remain in Mode 1, the final (1/4) addition of boron may not be required based on rate of Xenon production and control rod response.

BOP

Perform boration in four equal additions during load reduction PER Enclosure 2 (Emergency Boration).

NOTE: The CRS may assign the BOP to perform this action.

If so, BOP Examiner follow actions of Enclosure 2.

Other Examiners follow AP-4 Actions, Step 12, on Page 38.

AP/1/A/5500/04, RAPID DOWNPOWER ENCLOSURE 2, EMERGENCY BORATION BOP (Step 1) Check OAC AVAILABLE.

BOP (Step 2) Use OAC point M1P0785 (U1 Gallons Boric Acid Added Via 1NV-265B) to monitor boric acid gallons added while 1NV 265B (U1 NV Pump Boric Acid Sup Isol) is open.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 4 Page 38 of 61 Event

Description:

Dropped Rod/Downpower Time Pos. Expected Actions/Behavior Comments BOP (Step 3) GO TO Step 5.

BOP (Step 5) Check boric acid transfer pump NOTE: The 1B Boric Acid RUNNING. Transfer Pump is running.

BOP (Step 6) OPEN 1NV265B (U1 NV Pump Boric Acid Sup Isol).

BOP (Step 7) Do not continue until desired amount of boric acid has been added.

BOP (Step 8) CLOSE 1NV265B (U1 NV Pump Boric Acid Sup Isol).

BOP (Step 9) IF boric acid transfer pump was NOTE: The 1B Boric Acid started in Step 5 RNO, THEN . Transfer Pump was running initially.

BOP (Step 10) Repeat enclosure as required.

AP/1/A/5500/04, RAPID DOWNPOWER Examiner NOTE: Examiners following the CRS/RO continue HERE.

RO (Step 12) WHEN boration commenced, THEN initiate turbine load reduction to desired load at desired rate.

Examiner NOTE: Once the 1st boration is initiated MOVE to Event #5.

TECHNICAL SPECIFICATION 3.1.4, ROD GROUP ALIGNMENT LIMITS

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 4 Page 39 of 61 Event

Description:

Dropped Rod/Downpower Time Pos. Expected Actions/Behavior Comments CRS LCO 3.1.4 All shutdown and control rods shall be OPERABLE, with all individual indicated rod positions within 12 steps of their group step counter demand position.

CRS APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. One rod not within B.1Restore rod to within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months alignment limits. alignment limits.

OR B.2.1.1 Verify SDM is within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the limit specified in the COLR.

OR 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B.2.1.2 Initiate boration to restore SDM to within limit.

AND 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B.2.2 Reduce THERMAL POWER to < 75% RTP.

AND Once per B.2.3 Verify SDM is within the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months limit specified in the COLR.

AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B.2.4 Perform SR 3.2.1.1.

AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B.2.5 Perform SR 3.2.2.1.

AND B.2.6 Re-evaluate safety 5 days analyses and confirm results remain valid for duration of operation under these conditions.

NOTE: The CRS will determine that Condition B is required and that ACTION B.1 or B.2.1.1 and B.2.1.2 and B.2.2, B.2.3, B.2.4, B.2.5 and B.2.6 must be taken.

TECHNICAL SPECIFICATION 3.2.4, QPTR CRS LCO 3.2.4 The QPTR shall be 1.02.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 4 Page 40 of 61 Event

Description:

Dropped Rod/Downpower Time Pos. Expected Actions/Behavior Comments CRS APPLICABILITY: MODE 1 with THERMAL IF power > 75% RTP the crew POWER > 50% RTP. should NOT enter 3.2.4 until either an incore flux map is completed or power is , 75%

and QPTR>1.02 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. QPTR not within limit A.1.1Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER 3% from RTP for each 1% of QPTR >

1.02.

AND A.2.2 Perform SR 3.2.4.1 and Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months reduce THERMAL POWER 3% from RTP for each 1% of QPTR > 1.02.

AND A.3 Perform SR 3.2.2.1 and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.2.2.1. AND AND Once per 7 days thereafter A.4 Reduce Power Range Neutron Flux - High Trip 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Setpoint 3% for each 1%

of QPTR > 1.02.

AND A.5 Reevaluate safety analyses and confirm Prior to increasing THERMAL results remain valid for POWER above the more duration of operation under restrictive limit of Required this condition. Action A.1 or A.2.

AND A.6 Calibrate excore detectors Prior to increasing THERMAL to show zero QPT. POWER above the more restrictive limit of Required AND Action A.1 or A.2.

A.7 Perform SR 3.2.1.1 and Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after reaching SR 3.2.21 RTP.

OR Within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after increasing THERMAL

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 4 Page 41 of 61 Event

Description:

Dropped Rod/Downpower Time Pos. Expected Actions/Behavior Comments POWER above the more restrictive limit of Required Action A1 or A.2.

NOTE: The CRS will determine that Condition A is required and that ACTION A.1, A.2, A.3, A.4, A.5, A.6, and A.7 must be taken.

Examiner Note: The CRS may request Chemistry to sample for Dose Equivalent Iodine per Technical Specification LCO 3.4.16.

Move to Event #5 after the crew has lowered power to 75% and concurrence of the Lead Examiner.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 5 Page 42 of 61 Event

Description:

1B NCP Pump Bearing Oil Cooler Leak During the downpower, a leak will develop on the 1B NCP Upper Bearing Oil Reservoir.

The operator will respond in accordance with AP/1/A/5500/08, Malfunction of NC Pump, and the operator will be required to trip the reactor, stop the 1B NCP, and go to EP/1/A/5000/E-0, Reactor Trip and/or Safety Injection.

Booth Operator Instructions: insertMAL_NCP007BU = TRUE Indications Available:

OAC Alarm M1P2764 1B NCP UPPER OIL RESERVOIR LVL 1 MIN AVG

OAC Alarm M1A0732 1B NCP MTR UPPER BRG TEMP (will alarm 8-9 minutes after the first OAC alarm)

Time Pos. Expected Actions/Behavior Comments OAC ALARM M1P2764 1B NCP UPPER OIL RESERVOIR LVL 1 MIN AVG CRS (LO-LO Step 1) Go To AP/1/A/5500/08, Malfunction of NC Pump.

NOTE: The CRS will enter AP-08.

AP/1/A/5500/08, MALFUNCTION OF NC PUMP CASE II, NC PUMP MOTOR BEARING MALFUNCTION NOTE Step 1 RNO should be used to validate the abnormal parameter unless it has been previously validated or is clearly known to be valid.

BOP (Step 1) Check abnormal NC pump NOTE: The BOP will use the parameter - KNOWN TO BE VALID. Step 1 RNO and Enclosure 1 to determine that the parameter is known to be valid. (NOT scripted)

BOP (Step 2) Check NC pump parameters within operating limits:

All NC pump stator winding temperatures

- LESS THAN 311°F.

All NC pump motor bearing temperatures

- LESS THAN 195°F.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 5 Page 43 of 61 Event

Description:

1B NCP Pump Bearing Oil Cooler Leak Time Pos. Expected Actions/Behavior Comments CRS (Step 3) IF AT ANY TIME any operating limit NOTE: This is a Continuous in Step 2 exceeded, THEN GO TO Step 5. Action. The CRS will make one or more board operators aware.

CRS (Step 4) GO TO Step 6.

CRS (Step 6) Announce occurrence on paging NOTE: CRS may ask U2 system. RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

RO/ (Step 7) Correct any of the following which BOP may affect NC Pump stator or motor bearing cooling:

High ambient temperature

Abnormal NC Pump bus voltage

Interference with ventilation

Abnormal RN alignment and flow

Abnormal KC alignment and flow

High KC temperature.

RO/ (Step 8) Check all NC Pump oil reservoir NOTE: The 1B NC Pump BOP level computer alarms - CLEAR. oil reservoir level computer alarm is NOT clear.

RO/ (Step 8 RNO) Perform the following:

BOP

Evaluate clearing level alarm by adjusting KC temperature to NC Pump oil cooler.

IF upper oil reservoir in alarm, THEN trend the following indications on affected NC pump:

Motor upper bearing temperature

Motor upper thrust bearing temperature

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 5 Page 44 of 61 Event

Description:

1B NCP Pump Bearing Oil Cooler Leak Time Pos. Expected Actions/Behavior Comments

Motor lower thrust bearing temperature.

IF lower oil reservoir in alarm, THEN trend motor lower bearing temperature on affected NC pump.

IF AT ANY TIME oil level is in alarm AND NOTE: The CRS will return associated bearing temperature is to Step 5 and stop the 1B greater than 160°F, THEN RETURN TO NC Pump.

Step 5 to trip affected NC pump.

BOP (Step 5) Stop affected NC pump as follows:

BOP

IF A or B NC pump is the affected pump, NOTE: The 1B NC Pump is THEN CLOSE associated spray valve: the affected NC Pump.

1NC-29C (B NC Loop PZR Spray Control).

Check unit status - IN MODE 1 OR 2.

RO

Trip reactor.

BOP

WHEN reactor power less than 5%, NOTE: The plant power is THEN stop affected NC pump. currently < 5%.

CRS

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

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 5 Page 45 of 61 Event

Description:

1B NCP Pump Bearing Oil Cooler Leak Time Pos. Expected Actions/Behavior Comments Critical Task:

Trip the Reactor prior to stopping the 1B NCP during a low oil level condition and trip the NCP only after Reactor power level has dropped to less than 5% but before the CRS starts to read the Immediate Actions of EP/1/A/5000/E-0, Reactor Trip or Safety Injection, to the Control Board Operators to verify that a Reactor Trip has occurred.

Safety Significance: The transient placed on the unit when an NCP is secured at power can challenge both reactor protection and control systems. Station management has decided that the conservative approach to dealing with this transient is to trip the reactor anytime a NCP malfunction warrants stopping a pump in Mode 1. Guidance is given to wait until reactor power is less than 5% before stopping the NC pump to ensure that the NC pump will provide adequate flow/core cooling until reactor power is sufficiently low enough to preclude a challenge to fuel integrity. If the action can be taken, and is not taken, this demonstrates mis-operation or incorrect operation that could unnecessarily challenge a fission product barrier (NCS).

At the discretion of the Lead Examiner, move to Events #6-7.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 46 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Upon the reactor trip, a loss of Vital AC Panel 1EKVC will occur resulting in an inadvertent Safety Injection. Also, on the reactor trip, the Turbine will fail to trip automatically, and must be tripped manually. The operator will enter EP/1/A/5000/E-0, Reactor Trip or Safety Injection, reset SI and stop all ECCS Pumps except for one NV Pump. Ultimately, the crew will transition to step 9 of EP/1/A/5000/ES-1.1, Safety Injection Termination. Once SI is terminated, the operator may address AP/1/A/5500/15, Loss of Vital or Aux Control Power. The scenario will terminate in EP/1/A/5000/ES-1.1 at Step 14.l prior to the operator re-establishing Letdown.

h Booth Operator Instructions: MAL_DEH003A (Failure of the Turbine to Trip in AUTO)

MAL_EPL003C = ACTIVE (Loss of EKVC); cd = H_X01_094_2 =

1(RTB Open Light)

(Both malfunctions occur on Rx Trip - No Action Needed)

Indications Available:

All Control Rods Fully Inserted

3rd Row of Status Lights are all LIT

Safety Injection actuation has occurred (1SI-18 is LIT)

Main Turbine Governor Valves are OPEN Time Pos. Expected Actions/Behavior Comments Examiner Note: It is a management expectation that an inadvertent SI will be mitigated by closing NI-9 and 10 within 15 minutes.

NOTE: Crew will carry out Immediate Actions of E-0, prior to the CRS addressing the EP.

E-0, REACTOR TRIP OR SAFETY INJECTION RO/ (Step 1) Monitor Foldout page.

BOP NC Pump Trip Criteria (Not Expected)

CA Suction Sources (CA storage tank (water tower) goes below 1.5 ft - Not expected)

Position Criteria for 1NV-150B and 1NV-151A (U1 NV Pump Recirc Isol)

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 47 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Time Pos. Expected Actions/Behavior Comments

IF NV S/I flowpath aligned AND NC NOTE: The BOP will pressure is less than 1500 PSIG, THEN monitor these conditions.

CLOSE 1NV-150B and 1NV-151A.

IF NC pressure is greater than 2000 PSIG, THEN OPEN 1NV-150B and 1NV-151A.

Ruptured S/G Aux Feedwater Isolation Criteria (Not expected)

Faulted S/G Aux Feedwater Isolation Criteria (Not expected)

RO (Step 2) Check Reactor Trip: Immediate Action

All rod bottom lights - LIT

Reactor trip and bypass breakers -

OPEN

I/R power - GOING DOWN.

RO (Step 3) Check Turbine Trip: Immediate Action

All throttle valves - CLOSED. NOTE: The Turbine will fail to Auto Trip.

RO (Step 3 RNO) Perform the following: Immediate Action

Trip turbine.

IF turbine will not trip.

Critical Task:

Manually trip the Turbine before a valid Orange Path develops on the Integrity Critical Safety Function.

Safety Significance: Failure to trip the Main Turbine when conditions exist that allow the operator to do so, constitutes mis-operation or incorrect operator performance that unnecessarily challenges the Integrity Critical Safety Function. An overcooling event, such as a failure of the Turbine to trip on a reactor trip, in the presence of an inadvertent actuation of Safety Injection creates the potentiality of creating a Pressurized Thermal Shock conditions that otherwise would not exist.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 48 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Time Pos. Expected Actions/Behavior Comments BOP (Step 4) Check 1ETA and 1ETB - Immediate Action ENERGIZED.

RO / (Step 5) Check if S/I is actuated: Immediate Action BOP

SAFETY INJECTION ACTUATED status light (1SI-18) - LIT.

Both LOCA Sequencer Actuated status lights (1SI-14) - LIT.

CRS (Step 6) Announce Unit 1 Safety Injection. NOTE: CRS may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 7) Check all Feedwater Isolation status lights (1SI-4) - LIT BOP (Step 8) Check Phase A RESET lights -

DARK.

BOP (Step 9) Check ESF Monitor Light Panel on energized train(s):

Groups 1,2,5 - DARK.

Group 3 - LIT.

Group 4 - LIT AS REQUIRED.

Group 6 - LIT.

CRS

GO TO Step 10.

RO / (Step 10) Check proper CA pump status:

BOP

MD CA pumps - ON.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 49 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Time Pos. Expected Actions/Behavior Comments

N/R level in at least 3 S/Gs - GREATER THAN 17%.

BOP (Step 11) Check all KC pumps - ON BOP (Step 12) Check both RN pumps - ON.

CRS (Step 13) Notify Unit 2 to perform the Floor Instructor: As U2 following: RO report 2A RN Pump is running.

Start 2A RN pump.

THROTTLE Unit 2 RN flow to minimum Booth Instructor:

for existing plant conditions. insert LOA_RN087 (Start 2A RN Pump) insert LOA_RN083 8050.000000 delay=0 ramp=10 (Unit 2 Train A Demand Flow)

RO (Step 14) Check all S/G pressures -

GREATER THAN 775 psig.

BOP (Step 15) Check Containment Pressure - NOTE: Containment HAS REMAINED LESS THAN 3 PSIG. Pressure is 0.15 psig.

BOP (Step 16) Check S/I flow:

Check NV PMPS TO COLD LEG NOTE: NV Flow is 320 FLOW gauge - INDICATING FLOW. gpm.

Check NC pressures - LESS THAN NOTE: NC System 1600 PSIG. pressure is 2250-2300 psig.

BOP (Step 16b RNO) Perform the following:

Ensure ND pump miniflow valve on running pump(s) open:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 50 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Time Pos. Expected Actions/Behavior Comments

1ND-68A (1A ND Pump & Hx Mini Flow Isol)

1ND-67B (1B ND Pump & Hx Mini Flow Isol).

CRS

IF valve(s) open on all running ND pumps, THEN GO TO Step 17.

CRS (Step 17) Notify Shift Manager or other SRO NOTE: CRS may ask SM to to perform EP/1/A/5000/G-1 (Generic address.

Enclosures), Enclosure 22 (Shift Manager If so, Floor Instructor Actions Following an S/I) within 10 minutes.

acknowledge as SM.

RO / (Step 18) Check CA flow:

BOP

Total CA flow - GREATER THAN 450 GPM.

Check VI header pressure - GREATER THAN 60 PSIG.

WHEN each S/G N/R level is greater than 11% (32% ACC), THEN control CA flow to maintain that S/G N/R level between 11% (32% ACC) and 50%.

RO (Step 19) Check NC temperatures:

IF any NC pump on, THEN check NC NOTE: All NC Pumps will T-Avg - STABLE OR TRENDING TO be ON, except the 1B NCP.

557°F RO (Step 19 RNO) Perform the following based Examiner NOTE: If Tavg is on plant conditions: stable or trending to 557F, Enclosure 3 of E-0 will NOT be performed. Proceed to Step 20 of E-0 on Page 52.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 51 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Time Pos. Expected Actions/Behavior Comments

IF temperature less than 557°F AND NOTE: The CRS may going down, THEN attempt to stop assign the RO (BOP) to Cooldown PER Enclosure 3 perform this action.

(Uncontrolled NC System Cooldown). If so, RO (BOP) Examiner follow actions of Enclosure 3.

Other Examiners follow E-0 Actions, Step 20, on Page 52.

EP/1/A/5000/E-0, REACTOR TRIP OR SAFETY INJECTION ENCLOSURE 3, UNCONTROLLED NC SYSTEM COOLDOWN RO/ (Step 1) Check steam dump valves -

(BOP) CLOSED.

RO/ (Step 2) Check all SM PORVs - CLOSED.

(BOP)

RO/ (Step 3) Check MSR RESET light - LIT (BOP)

RO/ (Step 4) Check any NC pump - ON. NOTE: All NC Pumps are (BOP) ON except the 1B NCP.

RO/ (Step 5) Check NC TAvg GOING DOWN.

(BOP)

RO/ (Step 6) Control feed flow as follows:

(BOP)

IF S/G N/R level is less than 11% (32%

ACC) in all S/Gs, THEN

WHEN N/R level is greater than 11%

(32% ACC) in at least one S/G, THEN THROTTLE feed flow further to:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 52 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Time Pos. Expected Actions/Behavior Comments

Minimize cooldown

Maintain at least one S/G N/R level greater than 11% (32%ACC).

RO/ (Step 7) Check MSIVs - ANY OPEN. NOTE: All MSIVs are (BOP) OPEN.

RO/ (Step 8) CLOSE 1SM-15 (U1 SM To MSR (BOP) 2nd Stg Tube Bundles Isol).

RO/ (Step 9) Check any NC pump - ON. NOTE: All NC Pumps are (BOP) ON except the 1B NCP.

RO/ (Step 10) Check NC T-Avg - STABLE.

(BOP)

RO/ (Step 11) Notify Control Room Supervisor (BOP) of the following:

NC temperature trend

Status of MSIV and Bypass Valves EP/1/A/5000/E-0, REACTOR TRIP OR SAFETY INJECTION BOP (Step 20) Check Pzr PORV and spray Examiner NOTE:

valves: Examiners following the CRS/BOP(RO) continue HERE.

All Pzr PORVs - CLOSED.

Normal Pzr spray valves - CLOSED. NOTE: depending on NC System pressure the Spray Valve may be OPEN requiring performance of the Step 20.b RNO (Close Spray valves).

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 53 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Time Pos. Expected Actions/Behavior Comments BOP

At least one Pzr PORV isolation valve -

OPEN.

BOP (Step 21) Check NC subcooling based on NOTE: NC System core exit T/Cs - GREATER THAN 0°F. Subcooling will be 80-90oF.

RO (Step 22) Check if main steamlines intact:

All S/G pressure - STABLE OR GOING NOTE: All SG Pressures are UP 1100psig.

All S/Gs - PRESSURIZED.

BOP (Step 23) Check if S/G tubes intact: NOTE: All EMF instrumentation reads normal.

The following secondary EMFs -

NORMAL:

1EMF-33 (Condenser Air Ejector Exhaust)

1EMF-34(L) (S/G Sample (Lo Range))

1EMF-24 (S/G A)

1EMF-25 (S/G B)

1EMF-26 (S/G C)

1EMF-27 (S/G D)

S/G levels - STABLE OR GOING UP IN A CONTROLLED MANNER.

BOP (Step 24) Check if NC System intact: NOTE: All EMF instrumentation reads normal.

1EMF-38(L) (Containment Particulate (LR)) - NORMAL

1EMF-39(L) (Containment Gas (Lo Range)) - NORMAL

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 54 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Time Pos. Expected Actions/Behavior Comments

1EMF-40 (Containment Iodine) -

NORMAL

Check containment pressure - LESS NOTE: Containment THAN 1 PSIG Pressure is 0.20 psig.

Check containment sump level -

NORMAL.

RO / (Step 25) Check S/I termination criteria:

BOP

NC subcooling based on core exit T/Cs -

GREATER THAN 0°F.

Secondary heat sink:

N/R level in at least one S/G -

GREATER THAN 11%

OR

Total feed flow to S/Gs - GREATER THAN 450 gpm.

NC Pressure - STABLE OR GOING UP.

Pzr level - GREATER THAN 11%.

BOP (Step 26) Reset the following:

S/I

Sequencers.

BOP (Step 27) Stop all but one NV pump. NOTE: The BOP will stop one of the two NV Pumps.

BOP (Step 28) Check NC pressure - STABLE OR GOING UP.

BOP (Step 29) Isolate NV S/I flowpath as follows:

Check NV pumps miniflow valves -

OPEN:

1NV-150B (U1 NV Pump Recirc Isol)

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 55 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Time Pos. Expected Actions/Behavior Comments

1NV-151A (U1 NV Pump Recirc Isol).

CLOSE the following valves:

1NI-9A (NC Cold Leg Inj From NV)

1NI-10B (NC Cold Leg Inj From NV).

Examiner Note: It is a management expectation that an inadvertent SI will be mitigated by closing NI-9 and 10 within 15 minutes.

BOP (Step 30) Establish charging as follows:

BOP

Check VI header pressure - GREATER THAN 60 PSIG.

BOP

THROTTLE 1NV-238 (U1 Charging Hdr Control) to maintain 6-10 GPM seal injection flow to each NC pump.

BOP

Close 1NV-241 (U1 Seal Water Inj Flow Control).

BOP

Check one of the following valves -

OPEN:

1NV-13B (U1 NV Supply to 1A NC NOTE: 1NV-13B is OPEN.

Loop Isol).

OR

1NV-16A (U1 NV Supply to 1D NC Loop Isol).

BOP

Check 1NV-21A (U1 NV Spray to U1 Aux PZR Spray Isol) - CLOSED.

BOP

Open the following valves:

1NV-244A (Charging Hdr Cont Outside Isol)

1NV-245B (Charging Hdr Cont Outside Isol).

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 56 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Time Pos. Expected Actions/Behavior Comments

WHEN controlling NV flow in subsequent NOTE: This is a Continuous steps, THEN maintain flow within the Action. The CRS will make following limits while THROTTLING one or more board operators charging and seal injection control aware.

valves:

Charging flow - LESS THAN 200 GPM.

Seal injection flow to each NC pump 10 GPM.

BOP (Step 31) Control charging flow as follows:

Control charging flow as required to maintain Pzr level stable.

Check Pzr level - STABLE OR GOING UP.

BOP (Step 32) Reset the following:

Phase A Isolation

Phase B Isolation.

BOP (Step 33) Establish VI to containment as follows:

OPEN the following valves:

1VI-129B (VI Supply to A Cont Ess VI Hdr Outside Isol).

1VI-160B (VI Supply to B Cont Ess VI Hdr Outside Isol).

1VI-150B (Lwr Cont Non-Ess Cont Outside Isol).

Check VI header pressure - GREATER THAN 85 PSIG.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 57 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Time Pos. Expected Actions/Behavior Comments CRS (Step 34) Implement EP/1/A/5000/F-0 NOTE: The CRS will direct (Critical Safety Function Status Trees). the STA to implement this action.

Floor Instructor: As STA, acknowledge.

Examiner NOTE: A Red path will exist on the Subcriticality Critical Safety Function Status Tree because of the previously failed N42.

CRS (Step 35) WHEN EP/1/A/5000/ES-1.1 (Safety Injection Termination) is implemented in next step, THEN monitor its Foldout page.

CRS (Step 35) GO TO Step 9 of EP/1/A/5000/ES- NOTE: The CRS will 1.1 (Safety Injection Termination). transition to ES-1.1 Step 9.

ES-1.1, SAFETY INJECTION TERMINATION RO/ Foldout Page NOTE: None of the Foldout BOP Page Criteria are expected to apply.

S/I Reinitiation Criteria (applies after Step 10 in body of this procedure)

Secondary Integrity Criteria:

Cold Leg Recirc Switchover Criteria:

CA Suction Sources:

BOP (Step 9) Check if NI pumps should be Examiner NOTE: After stopped: transition to ES-1.1, terminate Exam at Lead Examiner discretion.

Check NC pressure -

STABLE OR GOING UP.

GREATER THAN 1600 PSIG.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 58 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Time Pos. Expected Actions/Behavior Comments BOP

Stop NI pumps. NOTE: The BOP will stop both NI Pumps.

CRS

GO TO Step 10.

BOP (Step 10) Check if ND pumps should be stopped:

Check any ND pump - ON.

Check running ND pumps suction -

ALIGNED TO FWST.

Stop ND pumps. NOTE: The BOP will stop both ND Pumps.

RO (Step 11) Check S/I flow not required:

NC subcooling based on core exit T/Cs - NOTE: NC System GREATER THAN 0°F. Subcooling will be 65-85oF.

BOP

Pzr level - GREATER THAN 11% (29% NOTE: Pzr Level will be 60-ACC). 90%.

RO (Step 12) Check steam dumps:

Check condenser available as follows:

C-9 COND AVAILABLE FOR STEAM DUMP status light (1SI-18)

- LIT.

MSIVs on intact S/Gs - OPEN.

RO

Using STEAM DUMP SELECT switch, place steam dumps in steam pressure mode.

Check P-12 LO-LO TAVG status light (1SI-18) - DARK.

Ensure steam dumps maintain NC T-Hots stable using auto or manual control.

CRS

GO TO Step 13.

RO (Step 13) Check NC T-Hots - STABLE.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 59 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Time Pos. Expected Actions/Behavior Comments RO/ (Step 14) Check if letdown can be BOP established:

Pzr level - GREATER THAN 25%

Check ND pumps - OFF.

BOP

OPEN the following valves:

1KC-1A (Trn A Aux Bldg Non Ess Ret Isol).

1KC-2B (Trn B Aux Bldg Non Ess Ret Isol).

Monitor the following while aligning KC to aux bldg non essential header:

KC surge tank levels

KC System flow.

BOP

Place the following in AUTO for the operating KC train(s):

1KC-54B (Train B Recirc Isol).

Check 1KC-1A - OPEN.

BOP

Perform the following concurrently:

CLOSE 1KC-56A (1A ND Hx KC Inlet Isol)

As flow goes down, OPEN 1KC-50A (Trn A Aux Bldg Non Ess Sup Isol).

Check 1KC-2B - OPEN.

BOP

Perform the following concurrently:

CLOSE 1KC-81B (1B ND Hx KC Inlet Isol)

As flow goes down, OPEN 1KC-53B (Trn B Aux Bldg Non Ess Sup Isol).

NOTE Resetting modulating valves establishes control of RN to KC Hx control.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 1 Event # 6-7 Page 60 of 61 Event

Description:

Loss of VIAC 1EKVC/Inadvertent SI Actuation/ Failure of the Turbine to Trip in AUTO Time Pos. Expected Actions/Behavior Comments

Reset modulating valves using reset buttons on RN control board.

Check the following:

1EMF-51A (Containment Train A (Hi Range)) - LESS THAN 25 R/HR

1EMF-51B (Containment Train B (Hi Range)) - LESS THAN 25 R/HR.

Establish letdown PER EP/1/A/5000/G-1 (Generic Enclosures), Enclosure 1 (Establishing Normal Letdown) while continuing in procedure.

At the discretion of the Lead Examiner terminate the exam.

UNIT 1 STATUS:

Power Level: 100% NCS [B] 85 ppm Pzr [B]: 85 ppm Xe: Per OAC Power History: At this power level for 357 days Core Burnup: 471.1 EFPDs UNIT 2 STATUS:

Power Level: 100%

CONTROLLING PROCEDURE:

OP/1/A/6100/003 (Controlling Procedure for Unit Operation)

OTHER INFORMATION NEEDED TO ASSUME THE SHIFT:

The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The following equipment is Out-Of-Service:

The 1A NS Pump is OOS for preventive maintenance. ACTION has been taken in accordance with Technical Specification LCO 3.6.6 ACTION A.

1NCPT-5150, Pzr Pressure Channel 2, has failed and has been removed from service in accordance with plant procedures. ACTION has been taken in accordance with Technical Specification LCO 3.3.1 and 3.3.2.

MCB Annunciator 1AD-12, F-5, FWST EMERGENCY LO TEMP, has alarmed spuriously several times over the last hour and has currently failed ON (IAE has verified that the issue is limited to an annunciator card issue).

Crew Directions:

Maintain Steady-State operations.

Work Control SRO Jim Field SRO Joe (FB)

AO's AVAILABLE Unit 1 Unit 2 Aux Bldg. John Aux Bldg. Chris Turb Bldg. Bob (FB) Turb Bldg. Mike (FB)

Extra(s) Bill (FB) Ed (FB) Gus (RW) Carol

Appendix D Scenario Outline Form ES-D-1 (Rev_011420)

Facility: McGuire Scenario No.: 2 Op Test No.: N20-1 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: The plant is at 75% power (MOL). The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Turnover: The following equipment is Out-Of-Service: The 1D S/G PORV is isolated and its actuator is currently removed for maintenance. 1KFP-5130, Spent Fuel Pool Temperature, failed last shift (IAE is investigating) and MCB Annunciator 1AD-11, L-1, ETA DEGRADED VOLTAGE, has alarmed spuriously several times over the last hour, and has currently failed ON (IAE has verified that the issue is limited to an annunciator card issue). The crew will raise power to 100% after taking the shift.

Critical Tasks: See Below Event Malf. Event Type* Event No. No. Description 1 NA R-RO Power Increase w/Simple Dilute N-BOP N-SRO 2 MAL C-RO Uncontrolled outward Rod Motion in AUTO DCS1288 C-SRO 3 MAL C-BOP Pzr Spray Valve (1NC-27) Controller fails OPEN DCS1762 DCS1763 C(TS)-SRO 4 REM C-BOP 1B RN Pump Suction Valve inadvertently CLOSES RN0018B C(TS)-SRO 5 MAL C-RO 1B CF Pump Trip/SGTL/Turbine Runback w/rods in Manual LF003B IRE009 C-BOP SG001C C-SRO 6 REM M-RO 1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR SM003AB MAL M-BOP IPE001A/B M-SRO IPE002A/B SG001C SM004C1 7 MAL C-BOP TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in CA004A C-SRO AUTO CA004B CA005

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 (Rev_011420)

McGuire 2020 NRC Scenario #2 The plant is at 75% power (MOL). The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The 1D S/G PORV is isolated and its actuator is currently removed for maintenance. 1KFP-5130, Spent Fuel Pool Temperature, failed last shift (IAE is investigating) and MCB Annunciator 1AD-11, L-1, ETA DEGRADED VOLTAGE, has alarmed spuriously several times over the last hour, and has currently failed ON (IAE has verified that the issue is limited to an annunciator card issue). The crew will raise power to 100% after taking the shift.

Shortly after taking the watch, the operator will commence a load increase to 100% starting with Step 3.37.11 of Enclosure 4.1, Power Increase, of OP/1/A/6100/003, Controlling Procedure for Unit Operation. The operator will dilute the NC System Boron concentration in accordance with .19, Simple Dilution, of OP/1/A/6150/009, Boron Concentration Control, and raise Turbine load in accordance with OP/1/A/6300/001 A, Turbine-Generator Load Change.

After the load increase is started, the Control Rods will fail such that rods are moving outward in AUTO. The operator will enter AP/1/A/5500/14, Rod Control Malfunction. The control rods will subsequently remain in MANUAL.

After this, the Pzr Spray Valve Controller, 1NC-27C A Spray, demand will fail to full output. The operator will enter AP/1/A/5500/11, Pressurizer Pressure Anomalies. The operator will address Technical Specification LCO 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits.

Next, the 1B RN Pump Suction Isolation valve will inadvertently CLOSE. The operator will respond using one or more Annunciator Response Procedures and ultimately enter AP/1/A/5500/20, Loss of RN, to place the standby train in service. The operator will address Technical Specification LCO 3.7.7, Nuclear Service Water System (NSWS), and Technical Specification LCO 3.8.1, AC Sources-Operating.

Subsequently, the 1B CF Pump will trip causing the turbine to automatically runback to 55%.

Simultaneously, a 40 gpm Steam Generator Tube Leak (SGTL) will occur in the 1C Steam Generator. The operator will implement AP/1/A/5500/03, Load Rejection. During the runback the operator will need to drive rods in manually.

When the plant is stabilized or AP/1/A/5500/10 is entered to mitigate the SGTL, the 1C MSIV will inadvertently CLOSE, and the Reactor will fail to trip automatically and manually. Additionally, the low set Safety Valve on the 1C Steam Generator will lift and stick fully OPEN. Additionally, the TD CA Pump will trip on overspeed on auto start, and both MDCA Pumps will fail to start automatically.

The operator will enter EP/1/A/5000/E-0, Reactor Trip or Safety Injection, and then transition to EP/1/A/5000/FR-S.1, Response to Nuclear Power Generation/ATWS. During the performance of FR-S.1, the operator will continuously drive rods in manually, successfully trip the Reactor locally, and manually start the MDCA Pumps and establish 450 gpm of flow the Steam Generators.

The SGTL will degrade to a tube rupture in the 1C Steam Generator when the reactor is locally tripped.

After completion of FR-S.1, the operator will transition back to E-0, and then to EP/1/A/5000/E-2, Faulted Steam Generator Isolation. After the 1C Steam Generator is isolated, the operator will transition to EP/1/A/5000/E-3, Steam Generator Tube Rupture.

Appendix D Scenario Outline Form ES-D-1 (Rev_011420)

The scenario will terminate at Step 6 of E-3 after the operator has transitioned to EP/1/A/5000/ECA-3.1, SGTR with Subcooled Recovery Desired, or at Step 9 of E-3 upon initiating an NCS cooldown.

Critical Tasks:

Manually close the Failed OPEN Pzr Spray Valve before the Pressurizer pressure drops to 1945 psig.

Safety Significance: failure to close the Spray Valve and stop the pressure transient, under the postulated plant conditions, results in an unnecessary transient to the plant and challenge to the Reactor Protection System. Performance of the critical task would stabilize the pressure transient.

A failure to stabilize the pressure transient, when able to do so, constitutes a mis-operation or incorrect crew performance which leads to incorrect NCS pressure control.

Start one or more MD CA Pumps before entry into FR-H.1 is required.

Safety Significance: Failure to establish a Secondary Heat Sink through the initiation of CA flow unnecessarily challenges both the HEAT SINK and the CORE COOLING Critical Safety Functions.

Additionally, the FSAR Safety Analysis results are predicated on the assumption that at least one train of safeguards actuates and delivers a minimum amount of AFW flow to the Steam Generators.

Failure to perform this task, when the ability to do so exists, results in a violation of the Facility License Condition and places the plant in an unanalyzed condition.

PROGRAM: McGuire Operations Training MODULE: Initial License Operator Training Class ILT 20-1 TOPIC: NRC Simulator Exam Scenario N20-1-2

REFERENCES:

1. OP/1/A/6100/003, Controlling Procedure for Unit Operation (Rev 212)

2. OP/1/A/6150/009, Boron Concentration Control (Rev 138)

3. OP/1/A/6300/001 A, Turbine-Generator Load Change (Rev 13)

4. AP/1/A/5500/14, Rod Control Malfunction (Rev 16)

5. AP/1/A/5500/11, Pressurizer Pressure Anomalies (Rev 12)

6. Technical Specification LCO 3.4.1, RCS Pressure, Temperature and Flow Departure From Nucleate Boiling (DNB) Limits (Amendment 219/201)

7. MCEI -0400-379, McGuire 1 Cycle 27 Core Operating Limits Report (Rev 1)

8. AP/1/A/5500/20, Loss of RN (Rev 38)

9. Technical Specification LCO 3.7.7, Nuclear Service Water System (NSWS) (Amendment 308/287)

10. Technical Specification LCO 3.8.1, AC Sources - Operating (Amendment 314/293)

11. AP/1/A/5500/03, Load Rejection (Rev 34)

12. EP/1/A/5000/E-0, Reactor Trip or Safety Injection (Rev 36)

13. EP/1/A/5000/E-2, Faulted Steam Generator Isolation (Rev 10)

14. EP/1/A/5000/E-3, Steam Generator Tube Rupture (Rev 27)

15. EP/1/A/5000/ECA-3.1, SGTR With Loss of Reactor Coolant- Subcooled Recovery Desired (Rev 20)

16. EP/1/A/5000/FR-S.1, Response To Nuclear Power Generation/ATWS (Rev 17)

Validation Time: 110 minutes Author: David Lazarony, Essential Training & Consulting, LLC Facility Review: ________________________

Rev. 011420 McGuire 2020 NRC Scenario #2 Objectives:

Given the simulator at an initial condition of 75% power with a normal power increase planned evaluate:

1. the SROs ability to supervise the control room team during the normal, abnormal, and emergency situations that arise, including compliance with all facility procedures, Technical Specifications, and other commitments.

2. each crew members ability to effectively communicate as part of a control room team during the normal, abnormal, and emergency situations that arise.

3. the RO and BOPs ability to effectively raise power in accordance with Enclosure 4.1, Power Increase, of OP/1/A/6100/003, Controlling Procedure for Unit Operation, and the Simple Dilution process.

4. each crew members ability to effectively diagnose an uncontrolled withdrawal of the Control Rods when operating in AUTO, and the ROs ability to respond to such an event in accordance with AP/1/A/5500/14, Rod Control Malfunction.

5. each crew members ability to effectively diagnose a failure of a Pressurizer Spray Valve controller when operating in AUTO, and the BOPs ability to respond to such an event in accordance with AP/1/A/5500/11, Pressurizer Pressure Anomalies.

6. each crew members ability to effectively diagnose an inadvertent closure of an RN Pump Suction Valve, and the BOPs ability to respond to such an event in accordance with AP/1/A/5500/20, Loss of RN.

7. each crew members ability to effectively diagnose a trip of a CF Pump, and their ability to respond to such an event in accordance with AP/1/A/5500/03, Load Rejection, including ROs ability to control rods in MANUAL during a downpower.

8. each crew members ability to effectively diagnose a Steam Generator Tube Leak in accordance with AP/1/A/5500/10, NC System Leakage within Capacity of Both NV Pumps.

9. each crew members ability to effectively diagnose an ATWS event and the RO and BOPs ability to respond to such an event in accordance with EP/1/A/5000/FR-S.1, Response to Nuclear Power Generation/ATWS.

10. each crew members ability to effectively diagnose a ruptured-faulted Steam Generator and the RO and BOPs ability to respond to such an event in accordance with EP/1/A/5000/E-0, Reactor Trip or Safety Injection, EP/1/A/5000/E-2, Faulted Steam Generator Isolation, EP/1/A/5000/E-3, Steam Generator Tube Rupture, and EP/1/A/5000/ECA-3.1, SGTR with Subcooled Recovery Desired.

Scenario Event Description NRC Scenario 2 Facility: McGuire Scenario No.: 2 Op Test No.: N20-1 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: The plant is at 75% power (MOL). The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Turnover: The following equipment is Out-Of-Service: The 1D S/G PORV is isolated and its actuator is currently removed for maintenance. 1KFP-5130, Spent Fuel Pool Temperature, failed last shift (IAE is investigating) and MCB Annunciator 1AD-11, L-1, ETA DEGRADED VOLTAGE, has alarmed spuriously several times over the last hour, and has currently failed ON (IAE has verified that the issue is limited to an annunciator card issue). The crew will raise power to 100% after taking the shift.

Critical Tasks: See Below Event Malf. Event Type* Event No. No. Description 1 NA R-RO Power Increase w/Simple Dilute N-BOP N-SRO 2 MAL C-RO Uncontrolled outward Rod Motion in AUTO DCS1288 C-SRO 3 MAL C-BOP Pzr Spray Valve (1NC-27) Controller fails OPEN DCS1762 DCS1763 C(TS)-SRO 4 REM C-BOP 1B RN Pump Suction Valve inadvertently CLOSES RN0018B C(TS)-SRO 5 MAL C-RO 1B CF Pump Trip/SGTL/Turbine Runback w/rods in Manual LF003B IRE009 C-BOP SG001C C-SRO 6 REM M-RO 1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR SM003AB MAL M-BOP IPE001A/B M-SRO IPE002A/B SG001C SM004C1 7 MAL C-BOP TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in CA004A C-SRO AUTO CA004B CA005

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 2 McGuire 2020 NRC Scenario #2 The plant is at 75% power (MOL). The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The 1D S/G PORV is isolated and its actuator is currently removed for maintenance. 1KFP-5130, Spent Fuel Pool Temperature, failed last shift (IAE is investigating) and MCB Annunciator 1AD-11, L-1, ETA DEGRADED VOLTAGE, has alarmed spuriously several times over the last hour, and has currently failed ON (IAE has verified that the issue is limited to an annunciator card issue).

The crew will raise power to 100% after taking the shift.

Shortly after taking the watch, the operator will commence a load increase to 100% starting with Step 3.37.11 of Enclosure 4.1, Power Increase, of OP/1/A/6100/003, Controlling Procedure for Unit Operation. The operator will dilute the NC System Boron concentration in accordance with .19, Simple Dilution, of OP/1/A/6150/009, Boron Concentration Control, and raise Turbine load in accordance with OP/1/A/6300/001 A, Turbine-Generator Load Change.

After the load increase is started, the Control Rods will fail such that rods are moving outward in AUTO. The operator will enter AP/1/A/5500/14, Rod Control Malfunction. The control rods will subsequently remain in MANUAL.

After this, the Pzr Spray Valve Controller, 1NC-27C A Spray, demand will fail to full output. The operator will enter AP/1/A/5500/11, Pressurizer Pressure Anomalies. The operator will address Technical Specification LCO 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits.

Next, the 1B RN Pump Suction Isolation valve will inadvertently CLOSE. The operator will respond using one or more Annunciator Response Procedures and ultimately enter AP/1/A/5500/20, Loss of RN, to place the standby train in service. The operator will address Technical Specification LCO 3.7.7, Nuclear Service Water System (NSWS), and Technical Specification LCO 3.8.1, AC Sources-Operating.

Subsequently, the 1B CF Pump will trip causing the turbine to automatically runback to 55%.

Simultaneously, a 40 gpm Steam Generator Tube Leak (SGTL) will occur in the 1C Steam Generator. The operator will implement AP/1/A/5500/03, Load Rejection. During the runback the operator will need to drive rods in manually.

When the plant is stabilized or AP/1/A/5500/10 is entered to mitigate the SGTL, the 1C MSIV will inadvertently CLOSE, and the Reactor will fail to trip automatically and manually. Additionally, the low set Safety Valve on the 1C Steam Generator will lift and stick fully OPEN. Additionally, the TD CA Pump will trip on overspeed on auto start, and both MDCA Pumps will fail to start automatically. The operator will enter EP/1/A/5000/E-0, Reactor Trip or Safety Injection, and then transition to EP/1/A/5000/FR-S.1, Response to Nuclear Power Generation/ATWS. During the performance of FR-S.1, the operator will continuously drive rods in manually, successfully trip the Reactor locally, and manually start the MDCA Pumps and establish 450 gpm of flow the Steam Generators.

The SGTL will degrade to a tube rupture in the 1C Steam Generator when the reactor is locally tripped.

Scenario Event Description NRC Scenario 2 After completion of FR-S.1, the operator will transition back to E-0, and then to EP/1/A/5000/E-2, Faulted Steam Generator Isolation. After the 1C Steam Generator is isolated, the operator will transition to EP/1/A/5000/E-3, Steam Generator Tube Rupture.

The scenario will terminate at Step 6 of E-3 after the operator has transitioned to EP/1/A/5000/ECA-3.1, SGTR with Subcooled Recovery Desired, or at Step 9 of E-3 upon initiating an NCS cooldown.

Critical Tasks:

Manually close the Failed OPEN Pzr Spray Valve before the Pressurizer pressure drops to 1945 psig.

Safety Significance: failure to close the Spray Valve and stop the pressure transient, under the postulated plant conditions, results in an unnecessary transient to the plant and challenge to the Reactor Protection System. Performance of the critical task would stabilize the pressure transient. A failure to stabilize the pressure transient, when able to do so, constitutes a mis-operation or incorrect crew performance which leads to incorrect NCS pressure control.

Start one or more MD CA Pumps before entry into FR-H.1 is required.

Safety Significance: Failure to establish a Secondary Heat Sink through the initiation of CA flow unnecessarily challenges both the HEAT SINK and the CORE COOLING Critical Safety Functions. Additionally, the FSAR Safety Analysis results are predicated on the assumption that at least one train of safeguards actuates and delivers a minimum amount of AFW flow to the Steam Generators. Failure to perform this task, when the ability to do so exists, results in a violation of the Facility License Condition and places the plant in an unanalyzed condition.

Scenario Event Description NRC Scenario 2 SIMULATOR OPERATOR INSTRUCTIONS Bench Mark ACTIVITY DESCRIPTION Reset to Temp IC 231 T = 0 Malfunctions:

(Base IC-37 [75% Insert REM_SV0025 = 0 (Close 1SV-25 [1D S/G MOL]) PORV Isolation])

Insert LOA_SV004= Racked_Out (SG PORV Breaker Racked Out)

H_X02_098_3 = 0 (1D PORV Controller LEFT lamp)

H_X02_098_4 = 0 (1D PORV Controller RIGHT lamp)

Insert LOA_SV020=0 (SM PORV D LOCAL OPERATION) insert XMT_KFTT5130 = 0 (Spent Fuel Pool Temperature Failure) insert OVR_1AD11_L01 = ON (MCB Annunciator 1AD11/L1)

Insert MAL_IPE001A = TRUE (ATWS)

Insert MAL_IPE001B = TRUE (ATWS)

Insert MAL_IPE002A = TRUE (ATWS)

Insert MAL_IPE002B = TRUE (ATWS) insert MAL_CA004A = AUTO (1BA MDCA Pump Start Failure [auto])

insert MAL_CA004B = AUTO (1B MDCA Pump Start Failure [auto])

insert MAL_CA005 TRIP insert MAL_SM004C1 = 100 cd='H_X02_078_3 EQ 1' delay=0 (Safety Valve on 1C SG sticks OPEN on C MSIV CLOSE Indicating Light) insert MAL_SG001C = 300 cd='H_X01_094_2 EQ 1' delay=0 (300 gpm SGTR occurs on 1C SG on Reactor Trip Breaker Open Indicating Light)

RUN Place Tagout/O-Stick on:

1SV-25 (Tagout)

Reset all SLIMs

1KFP-5130 (O-Stick)

MCB Annunciator 1AD-11, L-1 (O-stick)

Update Status Board, NOTE: RMWST DO = >1000 ppb.

Setup OAC Scenario Event Description NRC Scenario 2 Bench Mark ACTIVITY DESCRIPTION Freeze.

Update Fresh Tech.

Spec. Log.

Fill out the AO's Available section of Shift Turnover Info.

Prior to Crew RUN Briefing Crew Briefing

1. Assign Crew Positions based on evaluation requirements

2. Review the Shift Turnover Information with the crew.

3. Provide Enclosure 4.1 of OP/1/A/6100/003 marked up as required.

4. Provide the crew with OP/1/A/6150/009 (Boron Concentration Control) and OP/1/A/6300/1 A (Turbine-Generator Load Change).

5. Direct the crew to Review the Control Boards taking note of present conditions, alarms.

T-0 Begin Familiarization Period At direction of Execute Simulator examiner Scenario N20-1-2.

At direction of Event 1 Power Increase w/Simple Dilute examiner NA After adequate Event 2 Uncontrolled outward Rod Motion in AUTO power insert MAL_DCS1288 =

ascension/

TRUE direction of examiner Scenario Event Description NRC Scenario 2 Bench Mark ACTIVITY DESCRIPTION At direction of Event 3 Pzr Spray Valve (1NC-27) Controller fails OPEN examiner Insert MAL_DCS1762 =

PRESSED Insert MAL_DCS1763 =

PRESSED 10 Second Delay =

MAL_DCS1763 =

NORMAL At direction of Event 4 1B RN Pump Suction Valve inadvertently examiner CLOSES insert REM_RN0018B_1=0, Ramp = 30 seconds Upon entry Event 5 1B CF Pump Trip/SGTL/Turbine Runback w/rods into AP-10 or in Manual Insert:

at direction of examiner insert MAL_LF003B =

TRUE insert MAL_IRE009 =

FAIL_OF_AUTO insert MAL_SG001C =

40, Ramp = 600 seconds At direction of Event 6 1C MSIV fails CLOSED/ 1C SG SV fails examiner OPEN/ATWS/SGTR insert REM_SM003AB

=0.0 Ramp = 10 seconds Note: Malfunctions inserted at T = 0.

insert:

MAL_IPE001A MAL_IPE001B MAL_IPE002A MAL_IPE002B insert MAL_SM004C1 =

100 Insert MAL_SG001C =

300 Scenario Event Description NRC Scenario 2 Bench Mark ACTIVITY DESCRIPTION Post-Rx Trip Event 7 TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Insert:

Note: Malfunctions inserted at T = 0.

MAL_CA004A = Auto MAL_CA004B = Auto MAL_CA005 Terminate the scenario upon direction of Lead Examiner Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 1 Page 10 of 72 Event

Description:

Power Increase w/Simple Dilute Shortly after taking the watch, the operator will commence a load increase to 100% starting with Step 3.37.11 of Enclosure 4.1, Power Increase, of OP/1/A/6100/003, Controlling Procedure for Unit Operation. The operator will dilute the NC System Boron concentration in accordance with Enclosure 4.19, Simple Dilution, of OP/1/A/6150/009, Boron Concentration Control, and raise Turbine load in accordance with OP/1/A/6300/001 A, Turbine-Generator Load Change.

Booth Operator Instructions: NA Indications Available: NA Time Pos. Expected Actions/Behavior Comments OP/1/A/6100/003, CONTROLLING PROCEDURE FOR UNIT OPERATIONS ENCLOSURE 4.1, POWER INCREASE CRS (Step 3.37.11) Prior to increasing to greater NOTE: The power increase than 75% RTP, check all Main Turbine will be at 3 MWe/minute.

governor valves open.

RO/ (Step 3.37.12) WHEN 77-80% RTP, enable, NOTE: Based on the extent of BOP OTDT DCS alarming as follows: the power increase, this action may or may not be taken.

On DCS graphics, select MAINTENANCE MENU.

Select TAVG, DELTA T INPUTS &

ALARM CHECKING graphic.

Select ON for the following:

NCAA 5422

NCAA 5462

NCAA 5502

NCAA 5542

OTDELTAT-FAIL CRS (Step 3.37.13) IF startup from refueling outage..

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 1 Page 11 of 72 Event

Description:

Power Increase w/Simple Dilute Time Pos. Expected Actions/Behavior Comments (Step 3.37.14) IF performing Generator/Automatic Voltage Regulator (AVR) testing at 78% RTP OP/1/A/6150/009, BORON CONCENTRATION CONTROL ENCLOSURE 4.19, SIMPLE DILUTION BOP (Step 3.1) Evaluate all outstanding NOTE: The BOP may repeat Clearances that may impact performance of this task as needed during the this procedure. power increase.

BOP (Step 3.2) Determine current blender NOTE: The BOP will contents AND evaluate any potential recognize from the Turnover Reactivity effects prior to performing this that the Blender is filled with enclosure: Rx Makeup Water.

Rx Makeup Water

Blend

Boron BOP (Step 3.3) Evaluate energizing additional pressurizer heaters per OP/1/A/6100/003 (Controlling Procedure For Unit Operation) to enhance system mixing when changing NC System boron concentration. (R.M.)

BOP (Step 3.4) Determine amount of reactor NOTE: The BOP will add 400 makeup water needed to obtain desired gallons of Rx Makeup Water boron concentration using McGuire Data as recommended by RE.

Book, OAC, Reactor Group Guidance, or plant parameters (T-Ave, Steam Pressure, Xenon worth, etc.). (R.M.)

Total Reactor Makeup Water:

BOP (Step 3.5) Ensure the following reset to zero:

(R.M.)

Total Make Up Flow Counter

Boric Acid Flow Counter

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 1 Page 12 of 72 Event

Description:

Power Increase w/Simple Dilute Time Pos. Expected Actions/Behavior Comments BOP (Step 3.6) Set Total Make Up Flow Counter to value determined in Step 3.4. (R.M.)

BOP (Step 3.7) Select DILUTE on NC Sys M/U Controller.

BOP (Step 3.8) IF AT ANY TIME it is desired to lower VCT level, perform the following:

(Step 3.8.1) Monitor Letdown Pressure.

NOTE An increase in Letdown Pressure greater than 20 psig during diverts may be indicative of excessive NB Feed Filter DP. {NCR 01597088}

(Step 3.8.2) Select HUT on 1NV-137A (U1 NOTE: The BOP may do this NC Filters Otlt to VCT 3-Way Diversion at any time to lower VCT level.

Contrl).

(Step 3.8.3) IF Letdown Pressure increases greater than 20 psig, notify CRS.

(Step 3.8.4) WHEN desired level achieved, THEN select AUTO on 1NV-137A (U1 NC Filters Otlt to VCT 3-Way Diversion Cntrl).

NOTE Steps 3.9 - 3.17 may be completed and then checked off as time allows.

BOP (Step 3.9) IF AT ANY TIME plant parameters require termination of dilution, perform the following:

(Step 3.9.1) Place NC System Make Up to STOP. (R.M.)

(Step 3.9.2) IF 1NV-137A (U1 NC Filters Otlt to VCT 3-Way Diversion Cntrl) was placed to HUT, place to AUTO.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 1 Page 13 of 72 Event

Description:

Power Increase w/Simple Dilute Time Pos. Expected Actions/Behavior Comments BOP (Step 3.10) Momentarily select START on NC System Make Up. (R.M.)

BOP (Step 3.11) Check NC System Make Up red light lit.

BOP (Step 3.12) Check 1NV-171A (U1 Boric Acid Blender To VCT Inlet Control) open.

BOP (Step 3.13) Check 1NV-252A (Rx M/U Water Supply To U1 BA Blender Cntrl) open or throttled as required.

BOP (Step 3.14) Check Rx M/U Water Pump starts.

BOP (Step 3.15) Monitor Total Make Up Flow Counter. (R.M.)

BOP (Step 3.16) HOLD until one of the following occurs:

Amount of reactor makeup water recorded per Step 3.4 added OR

Reactor makeup water addition manually terminated BOP (Step 3.17) Ensure dilution terminated as follows: (R.M.)

(Step 3.17.1) IF in AUTO, ensure the following off:

1A Rx M/U Water Pump

1B Rx M/U Water Pump BOP (Step 3.17.2) Ensure the following closed:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 1 Page 14 of 72 Event

Description:

Power Increase w/Simple Dilute Time Pos. Expected Actions/Behavior Comments

1NV-171A (U1 Boric Acid Blender To VCT Inlet Control)

1NV-252A (RX M/U Water Supply To U1 BA Blender Cntrl)

BOP (Step 3.18) Ensure 1NV-137A (U1 NC Filters Otlt to VCT 3-Way Diversion Cntrl) in AUTO.

NOTE CRS concurrence required if flush of blender not performed.

BOP (Step 3.19) IF desired to flush blender. NOTE: It is NOT desired to flush the blender.

BOP (Step 3.20) Select AUTO for NC Sys M/U Controller.

BOP (Step 3.21) Momentarily select START on NC System Make Up.

BOP (Step 3.22) Check NC System Make Up red light lit.

BOP (Step 3.23) Ensure the following reset to zero: (R.M.)

Total Make Up Flow Counter

Boric Acid Flow Counter BOP (Step 3.24) Record in Narrative Log that final blender content is Rx Makeup Water.

OP/1/A/6300/001A, TURBINE-GENERATOR STARTUP/SHUTDOWN ENCLOSURE 4.1, TURBINE-GENERATOR LOAD CHANGE

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 1 Page 15 of 72 Event

Description:

Power Increase w/Simple Dilute Time Pos. Expected Actions/Behavior Comments NOTE If reducing power to a level greater than 50%, it is preferable to reduce power at a rate less than 12% per hour in order to minimize sodium peaks. [NCR01574291]

RO (Step 3.4.1) IF Turbine in OPERATOR AUTO, perform the following:

(Step 3.4.1.1) Ensure desired change within Calculated Capability Curve.

(Step 3.4.1.2) IF turbine load will raise or lower more than 10 MWs, notify Dispatcher of expected load change.

(Step 3.4.1.3) IF desired to change load rate, THEN perform the following:

Depress LOAD RATE.

Enter desired load rate in VARIABLE NOTE: the RO will select 2 DISPLAY. MWe/Min loading rate.

Depress ENTER.

(Step 3.4.1.4) IF desired to change desired load, THEN perform the following:

Depress REFERENCE.

Enter desired load in VARIABLE DISPLAY.

Depress ENTER.

Depress GO

Check load changes at selected rate.

OP/1/A/6100/003, CONTROLLING PROCEDURE FOR UNIT OPERATIONS ENCLOSURE 4.1, POWER INCREASE CRS (Step 3.37.13) Continue power increase to NOTE: The power increase 95% RTP. will be at 3 MWe/minute.

After adequate power increase/discretion of the Lead Examiner move to Event #2.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 2 Page 16 of 72 Event

Description:

Uncontrolled outward Rod Motion in AUTO After the load increase is started, the Control Rods will fail such that rods are moving outward in AUTO. The operator will enter AP/1/A/5500/14, Rod Control Malfunction.

The control rods will subsequently remain in MANUAL.

Booth Operator Instructions: insert MAL_DCS1288 = TRUE (Rods Out Demand)

Indications Available:

Rods stepping out continuously with no demand.

WHITE Rods Out light is LIT Time Pos. Expected Actions/Behavior Comments NOTE: When the malfunction is diagnosed the CRS may go to HOLD on the Turbine.

AP/1/A/5500/14, ROD CONTROL MALFUNCTION RO (Step 1) IF two or more rods are either Immediate Action dropped or misaligned by greater than 24 NOTE: No control rods steps, THEN.. dropped during this event.

RO (Step 2) Place control rods in manual. Immediate Action RO (Step 3) Check rod movement - STOPPED. Immediate Action NOTE: There was no rod motion when the Rods were taken to Manual.

RO (Step 4) Check all rods - ALIGNED WITH ASSOCIATED BANK.

RO (Step 5) Check ROD CONTROL URGENT FAILURE alarm (1AD-2, A-10) - DARK.

RO (Step 6) Check T-AVG/T-REF FAILURE ROD STOP alarm (1AD-2, B-7) - DARK.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 2 Page 17 of 72 Event

Description:

Uncontrolled outward Rod Motion in AUTO Time Pos. Expected Actions/Behavior Comments RO (Step7) IF this AP entered due to NOTE: The SRO will transition unwarranted rod insertion or withdrawal, to AP-14, Enclosure 3.

THEN GO TO Enclosure 3 (Response to Continuous Rod Movement).

AP/1/A/5500/14, ROD CONTROL MALFUNCTION ENCLOSURE 3, RESPONSE TO CONTINUOUS ROD MOVEMENT CRS (Step 1) Announce occurrence on paging NOTE: The CRS may ask U2 system. RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

CRS (Step 2) Notify IAE to investigate problem. NOTE: The CRS may call WCC/IAE to address the Rod Control malfunction.

If so, Booth Instructor acknowledge as WCC.

RO (Step 3) Evaluate the following prior to any control rod withdrawal:

Ensure no inadvertent mode change will occur

Ensure control rods are withdrawn in a deliberate manner, while closely monitoring the reactors response.

RO (Step 4) Check T-Ref indication - NORMAL.

RO (Step 5) Do not move rods until IAE determines rod motion is permissible.

RO (Step 6) Maintain T-Avg within 1°F of programmed T-Ref as follows:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 2 Page 18 of 72 Event

Description:

Uncontrolled outward Rod Motion in AUTO Time Pos. Expected Actions/Behavior Comments

Adjust Turbine load NOTE: The RO will adjust Turbine Load as needed to maintain T-avg.

OR

Borate/dilute NC System.

RO (Step 7) IF AT ANY TIME a runback occurs NOTE: This is a Continuous while in this procedure, THEN observe the Action. The CRS will make following guidance: one or more board operators aware.

IF IAE has determined that it is NOTE: The CRS may call permissible to move rods, THEN WCC/IAE to address.

respond to the runback PER If so, Booth Instructor AP/1/A/5500/03 (Load Rejection). acknowledge as WCC. After 5 minutes, report that the Control Rods must be kept in MANUAL, and that they can move rods in MANUAL as needed.

For all other circumstances, assume rod control is not available and respond to the runback as follows:

Trip Reactor.

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

RO (Step 8) IF AT ANY TIME while in this NOTE: This is a Continuous procedure a unit shutdown is required AND Action. The CRS will make rods cannot be moved, THEN perform the one or more board operators following: aware.

Borate as required during shutdown to maintain T-Avg at T-Ref.

Monitor AFD during load reduction.

IF AT ANY TIME AFD reaches Tech Spec limit AND reactor power is greater than 50%, THEN perform the following:

Trip Reactor.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 2 Page 19 of 72 Event

Description:

Uncontrolled outward Rod Motion in AUTO Time Pos. Expected Actions/Behavior Comments

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

NOTE: The CRS may call WCC/IAE to address.

If so, Booth Instructor acknowledge as WCC. After 5 minutes, report that the Control Rods must be kept in MANUAL, and that they can move rods in MANUAL as needed.

RO (Step 9) WHEN problem is repaired, THEN NOTE: The CRS will likely perform the following: conduct a Focus Brief.

At the discretion of the Lead Examiner move to Event #3.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 3 Page 20 of 72 Event

Description:

Pzr Spray Valve (1NC-27) Controller fails OPEN After this, the Pzr Spray Valve Controller, 1NC-27C A Spray, demand will fail to full output.

The operator will enter AP/1/A/5500/11, Pressurizer Pressure Anomalies. The operator will address Technical Specification LCO 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits.

Booth Operator Instructions: Insert MAL_DCS1762 = PRESSED Insert MAL_DCS1763 = PRESSED 10 Second Delay = MAL_DCS1763 =

NORMAL Indications Available:

NCS/Pzr pressure lowers

OAC Alarm: U1 PZR PRESS I through IV

1NC-27C SLIMs LS indication 50 or 100%

MCB Annunciator 1AD6/C-6 PZR LO PRESS CONTROL Time Pos. Expected Actions/Behavior Comments NOTE: The BOP may take all the necessary actions in the Immediate Actions, before CRS reads AOP.

AP/1/A/5500/11, PRESSURIZER PRESSURE ANOMALIES BOP (Step 1) Check Pzr pressure - HAS GONE Immediate Action DOWN.

BOP (Step 2) Check Pzr PORVs - CLOSED. Immediate Action BOP (Step 3) Check Pzr spray valves - CLOSED Immediate Action NOTE: 1NC-27C is OPEN.

BOP (Step 3 RNO) CLOSE Pzr spray valve(s). NOTE: The BOP will close 1NC-27C using the SLIMS or the Emergency Close Switch.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 3 Page 21 of 72 Event

Description:

Pzr Spray Valve (1NC-27) Controller fails OPEN Time Pos. Expected Actions/Behavior Comments Critical Task:

Manually close the Failed OPEN Pzr Spray Valve before the Pressurizer pressure drops to 1945 psig.

Safety Significance: failure to close the Spray Valve and stop the pressure transient, under the postulated plant conditions, results in an unnecessary transient to the plant and challenge to the Reactor Protection System. Performance of the critical task would stabilize the pressure transient. A failure to stabilize the pressure transient, when able to do so, constitutes a mis-operation or incorrect crew performance which leads to incorrect NCS pressure control.

BOP (Step 4) Check Pzr PORVs - CLOSED.

BOP (Step 5) Check Pzr spray valves - CLOSED. NOTE: IF the BOP has already used the EMERG SWITCH, the CRS may answer YES, and continue to Step 6.

If NOT, the Step 5 RNO will be performed.

BOP (Step 5 RNO) IF NC pressure below desired pressure, THEN perform the following:

Ensure Pzr spray emergency close switch on 1MC-10 is in the "CLOSE" position for failed spray valve.

IF Pzr spray valve closed, THEN GO TO Step 6.

CRS (Step 6) Announce occurrence on page. NOTE: CRS may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

BOP (Step 7) Check 1NV-21A (NV Spray to PZR Isol) - CLOSED.

BOP (Step 8) Check the following Pzr heaters -

ON:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 3 Page 22 of 72 Event

Description:

Pzr Spray Valve (1NC-27) Controller fails OPEN Time Pos. Expected Actions/Behavior Comments

1A

1B

1D BOP (Step 9) Check 1C Pzr heaters - ON.

BOP (Step 10) Check PZR PRESS MASTER -

IN AUTO.

BOP (Step 11) Check 1NC-27 PRESSURIZER NOTE: In order to close the SPRAY EMERGENCY CLOSE switch - malfunctioning Spray Valve, SELECTED TO NORMAL. the BOP likely had to take the EMERG SWITCH to CLOSE.

CRS (Step 11 RNO) Notify station management to NOTE: The CRS may call ensure switch restored to NORMAL once WCC/Station Management to spray valve is repaired. address the switch position.

If so, Booth Instructor acknowledge as WCC.

BOP (Step 12) Check 1NC-29 PRESSURIZER SPRAY EMERGENCY CLOSE switch -

SELECTED TO NORMAL.

BOP (Step 13) Check Pzr pressure - GOING UP TO DESIRED PRESSURE.

CRS (Step 14) Exit this procedure. NOTE: The CRS may call WCC/IAE to address the valve failure.

If so, Booth Instructor acknowledge as WCC.

NOTE: The CRS will likely conduct a Focus Brief.

TECHNICAL SPECIFICATION 3.4.1, RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 3 Page 23 of 72 Event

Description:

Pzr Spray Valve (1NC-27) Controller fails OPEN Time Pos. Expected Actions/Behavior Comments CRS LCO 3.4.1 RCS DNB parameters for NOTE: According to Table pressurizer pressure, RCS average 3.4.1-1, Parameter 2, indicated temperature, and RCS total flow rate shall be Pressurizer Pressure will be within the limits specified in Table 3.4.1-1. The limit specified in the COLR.

CRS APPLICABILITY: MODE 1. NOTE: According to Table 4 of the COLR, indicated Pressurizer Pressure (with four channels available) must be 2212.3 psig via the meter indication and 2209.1 psig via the OAC.

During this failure Pressurizer Pressure will lower below these values.

CRS ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer pressure or A.1 Restore DNB parameter(s) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months RCS average temperature to within limit.

DNB parameters not within limits.

NOTE: When Pressurizer Pressure drops to < 2209.1 psig (OAC) on the failure, the CRS will determine that Condition A is required and that ACTION A.1 must be taken.

At the discretion of the Lead Examiner, move to Event #4.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 4 Page 24 of 72 Event

Description:

1B RN Pump Suction Valve inadvertently CLOSES Next, the 1B RN Pump Suction Isolation valve will inadvertently CLOSE. The operator will respond using one or more Annunciator Response Procedures and ultimately enter AP/1/A/5500/20, Loss of RN, to place the standby train in service. The operator will address Technical Specification LCO 3.7.7, Nuclear Service Water System (NSWS), and Technical Specification LCO 3.8.1, AC Sources-Operating.

Booth Operator Instructions: insert REM_RN0018B_1 = 0, Ramped =

30 seconds Indications Available:

OAC Alarm M1Q0180, 1RN18B RN PUMP SUCTION ISOL, alarms.

Numerous MCB Annunciator 1AD12 alarms associated with RN.

1RN-18B Green status light is LIT.

Low flow in RN header.

Time Pos. Expected Actions/Behavior Comments NOTE: If the load increase has been restarted, the RO will likely stop the load increase.

Examiner NOTE: The BOP may attempt to manually open the suction valve and if unsuccessful, stop the 1B RN Pump.

AP/1/A/5500/20, LOSS OF RN CASE I, LOSS OF OPERATING RN TRAIN BOP (Step 1) Check both D/Gs - OFF.

BOP (Step 2) Check for potential loss of LLI as follows:

Check Unit 2 RN pump(s) that are Floor Instructor: If asked, As aligned to LLI - OPERATING U2 RO report 2A RN Pump is PROPERLY. running properly.

Check suction flowpath - NOTE: The crew should AVAILABLE. recognize that the LLI flowpath is available, but that the Suction Valve to the 1B RN Pump has closed and continue to Step 3.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 4 Page 25 of 72 Event

Description:

1B RN Pump Suction Valve inadvertently CLOSES Time Pos. Expected Actions/Behavior Comments CRS (Step 3) Announce occurrence on page. NOTE: CRS may ask U2 RO to make Plant Announcement that AP-20 has been entered.

If so, Floor Instructor acknowledge as U2 RO.

BOP (Step 4) Check Any RN pump - ON. NOTE: The crew should recognize that the 1B RN Pump is operating with its suction valve closed and stop the pump. This will result in both RN pumps being OFF.

CRS (Step 4 RNO) Perform the following: Examiner NOTE: If the 1B RN Pump has been stopped the RNO will be performed (Go to Step 7).

If the 1B RN Pump is still running, Steps 5 and 6 will be performed.

IF strainer fouling has not occurred, THEN GO TO Step 7.

BOP (Step 5) Check VI header pressure -

GREATER THAN 60 PSIG.

BOP (Step 6) Check the following annunciators -

DARK:

"RN STRNR A HI D/P" (1AD-12, D-2)

"RN STRNR B HI D/P" (1AD-12, D-3).

BOP (Step 6 RNO) Perform the following:

IF discharge pressure on running RN pump(s) is less than 50 PSIG, THEN reduce RN flow to raise discharge pressure.

REFER TO appropriate annunciator response.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 4 Page 26 of 72 Event

Description:

1B RN Pump Suction Valve inadvertently CLOSES Time Pos. Expected Actions/Behavior Comments CRS

IF adequate RN flow cannot be maintained to RN cooled components OR it is desired to place idle RN train in service, THEN GO TO Step 7.

BOP (Step 7) Place RN train in service as follows: Examiner NOTE: Since the 1B RN Pump is running with its suction valve closed, the CRS should direct the BOP to stop the 1B RN Pump by now.

Check both RN pumps OFF.

BOP (Step 7.A RNO) IF one train of RN is NOTE: There is no Train of operating properly, THEN. RN that is operating properly.

(Step 7.B) Check RN train - AVAILABLE NOTE: The CRS may dispatch TO START. an AO.

If so, Booth Instructor acknowledge as the AO.

BOP

Start one train of RN as follows:

To start 1A RN pump perform the following:

Ensure flowpath available.

BOP

Place manual loader for 1RN-89A (RN to A KC Hx Control) to 10% OPEN.

BOP

Start 1A RN pump. NOTE: The BOP will start the 1A RN Pump.

Ensure the following valve for train being started - OPEN.

1RN-86A (A KC Hx Inlet Isol).

Check the following cross-tie valves

- OPEN:

1RN-40A (Train A To Non Ess Hdr Isol)

1RN-41B (Train B TO Non Ess Hdr Isol)

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 4 Page 27 of 72 Event

Description:

1B RN Pump Suction Valve inadvertently CLOSES Time Pos. Expected Actions/Behavior Comments

1RN-43A (Train B To Non Ess Hdr Isol).

BOP

Ensure malfunctioning RN pump is NOTE: The BOP will stop the off. 1B RN if not done already.

BOP

Check if local venting of RN pump NOTE: Local venting of RN has been performed PER one of the pump has NOT been following: performed.

Enclosure 5 (1A RN Pump Venting)

OR

Enclosure 6 (1B RN Pump Venting).

CRS (Step 7.G RNO) GO TO Step 7.I.

BOP * (Step 7.I) Check Enclosure 7 (NV NOTE: Enclosure 7 has NOT Pump Cooling Via Gravity Drain To been performed.

Sump) - HAS BEEN PERFORMED.

CRS (Step 7.I RNO) GO TO Sep 7.K BOP

Check Case II (Loss of Low Level or NOTE: Case II has NOT been RC Supply Crossover) - HAS BEEN performed.

IMPLEMENTED.

CRS (Step 7.K RNO) GO TO Step 8.

BOP (Step 8) Ensure cooling to KC as follows:

BOP

Check 1A KC pump(s) - RUNNING. NOTE: The B Train of KC is operating.

CRS (Step 8.A RNO) GO TO Step 8.H.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 4 Page 28 of 72 Event

Description:

1B RN Pump Suction Valve inadvertently CLOSES Time Pos. Expected Actions/Behavior Comments BOP

Check 1B KC pump(s) - RUNNING.

BOP

Ensure 1B KC pumps aligned to reactor bldg non essential header as follows:

OPEN the following valves:

1KC-18B (Trn B Rx Bldg Non Ess Ret Isol).

1KC-228B (Trn B Rx Bldg Non Ess Sup Isol).

CLOSE the following valves:

1KC-230A (Trn A Rx Bldg Non Ess Sup Isol).

1KC-3A (Trn A Rx bldg Non Ess Ret Isol).

BOP

Check 1B RN pump - OFF.

BOP

Check 1RN-187B (B KC Hx Inlet NOTE: 1RN-187B has NOT Isol) - LOCALLY THROTTLED been locally throttled.

DURING THIS PROCEDURE.

BOP (Step 8.K RNO) Perform the following:

IF VI header pressure is less than 60 PSIG, THEN.

BOP

Place 1RN-187B MODE SELECT switch to manual.

BOP

OPEN 1RN-187B (B KC Hx Inlet Isol).

BOP

THROTTLE 1RN89A (RN to A KC Hx Control) to maintain 1A RN pump discharge pressure greater than 50 PSIG.

IF 1A RN pump discharge pressure is greater than 50 PSIG, THEN GO TO Step 9.

BOP (Step 9) Maintain RN flow within operating limits as follows:

Check VI header pressure GREATER THAN 60 PSIG.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 4 Page 29 of 72 Event

Description:

1B RN Pump Suction Valve inadvertently CLOSES Time Pos. Expected Actions/Behavior Comments

Check 1A RN pump RUNNING

THROTTLE 1RN89A (RN to A KC Hx Control) to maintain 1A RN pump discharge pressure greater than 50 PSIG.

Check 1A RN pump flow LESS THAN 14,000 GPM.

Check 1B RN pump RUNNING. NOTE: 1B RN Pump is OFF.

BOP (Step 9.E RNO) GO TO Step 10.

BOP/ (Step 10) Investigate reason for loss of RN NOTE: The CRS may dispatch CRS train as follows: an AO.

If so, Floor/Booth Instructor acknowledge as the AO.

Dispatch operator to check RN pump.

Dispatch operator to check RN pump breaker.

Check suction flowpath alignment.

Check discharge flowpath alignment. NOTE: The CRS may call WCC/IAE to address the Pump malfunction, and request that the 1B RN Pump Breaker be racked out.

If so, Booth Instructor acknowledge as WCC, and indicate that the 1B RN Pump Breaker will be Racked Out.

Use:

LOA_RN006 = Racked_Out (1B RN Pump BKR)

LOA_RN006A = Racked_Out (1B RN Pump Cntrl Pwr)

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 4 Page 30 of 72 Event

Description:

1B RN Pump Suction Valve inadvertently CLOSES Time Pos. Expected Actions/Behavior Comments CRS (Step 11) Ensure Control Room Area Chiller NOTE: The CRS may assign in service PER Enclosure 2 (VC/YC the RO to perform this action, Operation). or have the BOP perform these actions prior to continuing with Step 12.

If actions are performed in parallel, Appropriate Examiner follow actions of Enclosure 2.

Other Examiners follow AP-20 Actions, Step 12, below.

AP/1/A/5500/20, LOSS OF RN ENCLOSURE 2, VC/YC OPERATION Examiner NOTE: Follow the actions associated with Enclosure 2 if RO is assigned by CRS to perform.

RO/ (Step 1) Check train selected Control Room NOTE: The Chiller is BOP Area Chiller - ON. expected to be ON. If not, the RO/BOP will take action per the RNO to restart the Chiller.

AP/1/A/5500/20, LOSS OF RN CASE I, LOSS OF OPERATING RN TRAIN Examiner NOTE: Examiners following the CRS/BOP continue HERE.

BOP (Step 12) Align operating train of equipment with running RN pump as follows:

Check 1A RN pump - ON.

Check the following equipment - ON:

1A1 and 1A2 KC pumps - ON CRS (Step 12.B RNO) GO TO Step 12.I.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 4 Page 31 of 72 Event

Description:

1B RN Pump Suction Valve inadvertently CLOSES Time Pos. Expected Actions/Behavior Comments BOP (Step 12.I) Perform one of the following as necessary to align operating RN train with train of equipment cooled by RN:

Swap operating equipment to opposite train as follows:

IF desired to swap KC trains, THEN perform Enclosure 1 (Shifting KC Trains).

NOTE: The CRS will transition to Enclosure 1.

AP/1/A/5500/20, LOSS OF RN ENCLOSURE 1, SHIFTING KC TRAINS BOP (Step 1) Limit KC flow to 4000 GPM per operating KC pump in subsequent steps.

BOP (Step 2) Check the following:

1RN-40A (Train A To Non Ess Hdr Isol) -

OPEN

1RN-41B (Train B To Non Ess Hdr Isol) -

OPEN

1RN-43A (Train B To Non Ess Hdr Isol) -

OPEN

Any KC pump - RUNNING. NOTE: The B Train KC Pumps are operating.

CRS (Step 3) GO TO Step 5.

BOP (Step 5) Check both ND pumps - OFF.

CRS (Step 6) Perform the following:

IF shifting from 1A KC Train to 1B KC NOTE: The crew will be Train, shifting from 1B KC Train to 1A KC Train.

OR

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 4 Page 32 of 72 Event

Description:

1B RN Pump Suction Valve inadvertently CLOSES Time Pos. Expected Actions/Behavior Comments

IF shifting from 1B KC Train to 1A KC Train, THEN GO TO Step 22.

BOP (Step 22) THROTTLE OPEN 1RN-89A (RN to A KC Hx Control) to establish desired flow to 1A KC Hx, while maintaining 1A RN pump discharge pressure greater than 50 psig.

BOP (Step 23) Place control switch for 1KC-51A (Train A Recirc Isol) in the AUTO position.

BOP (Step 24) Ensure 1KC-51A OPENS.

BOP (Step 25) Start 1A1 KC pump. NOTE: The CRS may contact the AO to start the pumps.

If so, Booth Instructor acknowledge as the AO.

BOP (Step 26) Start 1A2 KC pump.

BOP (Step 27) Align Reactor Bldg header to 1A Train as follows:

OPEN the following valves:

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

1KC-230A (Trn A Rx Bldg Non Ess Sup Isol).

CLOSE the following valves:

1KC-228B (Trn B Rx Bldg non Ess Sup Isol)

1KC-18B (Trn B Rx Bldg Non Ess Ret Isol).

BOP (Step 28) Check both ND pumps - OFF.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 4 Page 33 of 72 Event

Description:

1B RN Pump Suction Valve inadvertently CLOSES Time Pos. Expected Actions/Behavior Comments BOP (Step 29) Place 1RN-187B MODE SELECT switch to auto.

BOP (Step 30) Check 1RN-187B (B KC Hx Inlet Isol) - CLOSED.

BOP (Step 31) WHEN RN flow through the 1B KC Hx begins to go down, THEN THROTTLE OPEN 1RN-89A (RN to A KC Hx Control) to achieve desired flow rate while maintaining the following:

1A RN pump discharge pressure GREATER THAN 50 PSIG

1A RN pump flow LESS THAN 14,000 GPM.

BOP (Step 32) Place 1KC-54B (Train B Recirc Isol) in CLOSE.

BOP (Step 33) Ensure 1KC-54B is CLOSED.

BOP (Step 34) Stop the following pumps:

1B1 KC pump

1B2 KC pump.

BOP (Step 35) Ensure NC pump thermal barrier isolation valves are OPEN.

BOP (Step 36) RETURN TO step in effect in body of this procedure.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 4 Page 34 of 72 Event

Description:

1B RN Pump Suction Valve inadvertently CLOSES Time Pos. Expected Actions/Behavior Comments NOTE: The CRS will return to the main body of AP-20.

Examiner NOTE: Because there are still AP-related actions to take with this procedure, the CRS may NOT address the TS at the time.

Consequently, it may be necessary to move to next event, and address the TS after the scenario.

TECHNICAL SPECIFICATION 3.7.7, NUCLEAR SERVICE WATER SYSTEM CRS LCO 3.7.7 Two NSWS trains shall be OPERABLE.

CRS APPLICABILITY: MODES 1, 2, 3, and 4.

CRS ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.One NSWS train inoperable. A.1 Restore NSWS train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

NOTE: The CRS will determine that condition A is required and ACTION A.1 must be taken.

TECHNICAL SPECIFICATION 3.8.1, AC SOURCES - OPERATING CRS LCO 3.8.1 The following AC electrical sources shall be OPERABLE:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 4 Page 35 of 72 Event

Description:

1B RN Pump Suction Valve inadvertently CLOSES Time Pos. Expected Actions/Behavior Comments

Two qualified circuits between the offsite transmission network and the Onsite Essential Auxiliary Power System; and

Two diesel generators (DGs) capable of supplying the Onsite Essential Auxiliary Power Systems; and

The qualified circuit(s) between the offsite transmission network and the opposite units Onsite Essential Auxiliary Power System necessary to supply power to the Nuclear Service Water System (NSWS),

Control Room Area Ventilation System (CRAVS), Control Room Area Chilled Water System (CRACWS) and Auxiliary Building Filtered Ventilation Exhaust System (ABFVES); and

The DG(s) from the opposite unit necessary to supply power to the NSWS, CRAVS, CRACWS and ABFVES; AND The automatic load sequencers for Train A and Train B shall be OPERABLE.

CRS APPLICABILITY: MODES 1, 2, 3, and 4.

NOTE: The opposite unit electrical power sources in LCO 3.8.1.c and LCO 3.8.1.d are not required to be OPERABLE when the associated shared systems are inoperable.

CRS ACTIONS NOTE: LCO 3.0.4.b is not applicable to DGs.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 4 Page 36 of 72 Event

Description:

1B RN Pump Suction Valve inadvertently CLOSES Time Pos. Expected Actions/Behavior Comments CONDITION REQUIRED ACTION COMPLETION TIME B. One LCO 3.8.1.b DG B.1 Verify LCO 3.8.1.d DG(s) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE. AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.2 Perform SR 3.8.1.1 for the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months offsite circuit(s). AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND B.3Declare required feature(s) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of supported by the Condition B concurrent with inoperable DG inoperable inoperability of redundant when its required required feature(s) redundant feature(s) is inoperable.

AND B.4.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DG is not inoperable due to common cause failure.

OR B.4.2 Perform SR 3.8.1.2 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DG.

AND B.5 Evaluate availability of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Emergency Supplemental AND Power Source (ESPS) Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from discovery of unavailable ESPS **

B.6 Restore DG to AND OPERABLE status. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from discovery of Condition B entry 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months concurrent with unavailability of ESPS AND 14 days AND 17 days from discovery of failure to meet LCO 3.8.1.a or LCO 3.8.1.b

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 4 Page 37 of 72 Event

Description:

1B RN Pump Suction Valve inadvertently CLOSES Time Pos. Expected Actions/Behavior Comments NOTE: The CRS will determine that condition B is required and ACTION B.1, B.2, B3.1 or B.3.2, B.4, B.5 and B.6 must be taken.

At the discretion of the Lead Examiner, move to Event #5.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 5 Page 38 of 72 Event

Description:

1B CF Pump Trip/SGTL/Turbine Runback w/rods in Manual Subsequently, the 1B CF Pump will trip causing the turbine to automatically runback to 55%. Simultaneously, a 40 gpm Steam Generator Tube Leak (SGTL) will occur in the 1C Steam Generator. The operator will implement AP/1/A/5500/03, Load Rejection.

During the runback the operator will need to drive rods in manually.

Booth Operator Instructions: Insert MAL_LF003B = TRUE Insert MAL_IRE009 = FAIL_OF_AUTO Insert MAL_SG001C = 40 Indications Available:

1B CF Pump Trips.

MCB Annunciator 1AD-1, D6, DEH TURBINE RUNBACK, alarms.

Turbine Generator MWe lowering.

MCB Annunciator 1RAD-1, C-1, 1EMF 71 S/G A LEAKAGE HI RAD

MCB Annunciator 1RAD-1, D-1, 1EMF 72 S/G B LEAKAGE HI RAD

MCB Annunciator 1RAD-1, D-2, 1EMF 73 S/G C LEAKAGE HI RAD

MCB Annunciator 1RAD-1, D-3, 1EMF 74 S/G D LEAKAGE HI RAD Time Pos. Expected Actions/Behavior Comments AP/1/A/5500/03, LOAD REJECTION RO (Step 1) Ensure control rods in auto. Immediate Action NOTE: Rods are in MANUAL from a previous malfunction and will NOT work in AUTO.

RO (Step 2) Check Turbine Generator response as follows:

Check Generator - TIED TO GRID.

Check Generator output - GOING DOWN AS REQUIRED.

RO (Step 3) Check control rod response as follows:

Check control banks - MOVING IN AS NOTE: Rods are in REQUIRED. MANUAL from a previous malfunction and will NOT work in AUTO.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 5 Page 39 of 72 Event

Description:

1B CF Pump Trip/SGTL/Turbine Runback w/rods in Manual Time Pos. Expected Actions/Behavior Comments RO (Step 3a RNO) IF no rods will move in auto; THEN perform the following:

Place Control Rods in manual.

Insert rods to reduce T-avg equal to programmed T-Ref.

If no rods will move, THEN.. NOTE: The Control Rods will move in MANUAL.

RO

Check all rods - ALIGNED WITH ASSOCIATED BANK.

BOP (Step 4) Check CM system response as follows:

Standby Hotwell and Condensate Booster pumps - RUNNING.

1CM-420 (Unit 1 Generator Load Rejection Bypass control) - OPEN.

RO (Step 5) IF runback to 55% power in effect, THEN ensure turbine inlet pressure going down to less than or equal to 500 PSIG.

CRS (Step 6) Announce: UNIT 1 LOAD NOTE: CRS may ask U2 REJECTION, NON-ESSENTIAL RO to make Plant PERSONNEL STAY OUT OF UNIT 1 Announcement that AP-3 TURBINE BLDG. has been entered.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 7) Check P/R meters - LESS THAN 20%.

CRS / (Step 7 RNO) Perform the following:

RO

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 5 Page 40 of 72 Event

Description:

1B CF Pump Trip/SGTL/Turbine Runback w/rods in Manual Time Pos. Expected Actions/Behavior Comments

Designate an operator to continuously monitor reactor power.

IF AT ANY TIME reactor power is less NOTE: This is a Continuous than 20%, THEN perform Step 8 to Action. The CRS will stabilize reactor power. designate the RO to observe this action.

CRS

GO TO Step 9.

RO (Step 9) Check condenser dump valves -

MODULATING OPEN.

BOP (Step 10) Check IPB AIR FLOW TROUBLE alarm (1AD-11, J-5) - DARK.

BOP (Step 11) Check Pzr pressure control response as follows:

Ensure Pzr heaters are in auto.

Ensure Pzr spray control valves are in NOTE: 1NC-27C is NOT in auto. AUTO due to a previous malfunction.

Check Pzr PORVs - CLOSED.

Check Pzr spray control valves -

CLOSED Examiner NOTE: The CRS may enter AP10 to address the SGTL at any point once it is determined that the transient is over. If so, move to Events 6-7.

RO (Step 12) Check load rejection - DUE TO NOTE: The load rejection LOSS OF CF PUMP. was due to a Loss of CF Pump.

CRS (Step 13) Dispatch operator as necessary to NOTE: The CRS may determine cause of CF pump trip. dispatch an AO.

If so, Booth Instructor acknowledge as the AO.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 5 Page 41 of 72 Event

Description:

1B CF Pump Trip/SGTL/Turbine Runback w/rods in Manual Time Pos. Expected Actions/Behavior Comments CAUTION The CF pump high discharge pressure trip setpoint is 1435 PSIG.

BOP (Step 14) Ensure in service CF pump properly responds in auto as follows:

Monitor in service CF pump discharge pressure.

"1A CF PUMP DISCHARGE PRESS" (OAC point M1A1108).

OR

"1B CF PUMP DISCHARGE PRESS" (OAC point M1A1114).

Monitor S/G N/R Levels.

IF AT ANY TIME any of the following NOTE: This is a Continuous occurs: Action. The CRS will make one or more board operators aware.

"CF PUMP DISCHARGE HI PRESS" 1AD8, A4 alarms (Setpoint at 1335 PSIG),

OR

S/G N/R level approaches Hi Hi level (83%),

OR

S/G N/R level approaches Lo Lo level (17%).

THEN take manual control of in service CF pump as follows:

Place low pressure governor control in manual.

Place high pressure governor control in manual

Adjust CF pump speed to maintain CF header pressure 100120 PSIG above steam header pressure.

Do not continue until the following are satisfied:

In service CF pump discharge pressure is stable.

S/G levels are at setpoint.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 5 Page 42 of 72 Event

Description:

1B CF Pump Trip/SGTL/Turbine Runback w/rods in Manual Time Pos. Expected Actions/Behavior Comments Examiner NOTE: The CRS may enter AP10 to address the SGTL at any point once it is determined that the transient is over. If so, move to Events 6-7.

RO (Step 15) Check turbine inlet pressure -

LESS THAN 340 PSIG.

RO (Step 15 RNO) Perform the following:

IF AT ANY TIME turbine inlet pressure NOTE: This is a Continuous drops to less than 340 PSIG, THEN GO Action. The CRS will make TO Step 16. one or more board operators aware.

CRS

GO TO Step 19.

RO (Step 19) Check Main Generator as follows:

Check Generator Breakers - EITHER GENERATOR BREAKERS CLOSED.

Check Generator - TIED TO GRID.

Check generator power factor - 0.9 TO 1.0 LAGGING.

CRS

GO TO Step 20.

CRS (Step 20) Ensure the following have been NOTE: The CRS may ask implemented: SM to address.

If so, Floor Instructor acknowledge as SM.

RP/0/A/5700/000 (Classification of Emergency)

RP/0/A/5700/010 (NRC Immediate Notification Requirements).

RO/ (Step 21) WHEN transient is over, THEN BOP perform the following:

Determine if one CF pump should be shutdown as follows:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 5 Page 43 of 72 Event

Description:

1B CF Pump Trip/SGTL/Turbine Runback w/rods in Manual Time Pos. Expected Actions/Behavior Comments

Check two CF pumps - RUNNING. NOTE: the 1A CF is the only Main Feedwater Pump running.

(Step 21.A RNO) GO TO Step 21.B Examiner NOTE: The CRS may enter AP10 to address the SGTL at any point once it is determined that the transient is over. If so, move to Events 6-7.

(Step 21.B) Check the following on in service CF pump(s):

Low pressure governor control - IN AUTO

High pressure governor control - IN AUTO.

Check SM flow on all S/Gs - LESS NOTE: SM flow is 60%.

THAN 75%.

Check SM flow on all S/Gs - LESS NOTE: SM flow is 60%.

THAN 25%.

RO (Step 21.D RNO) Perform the following:

Check the following CF control bypass valves - CLOSED:

1CF-104AB (1A S/G CF Control Bypass) - CLOSED

1CF-105AB (1B S/G CF Control Bypass) - CLOSED

1CF-106AB (1C S/G CF Control Bypass) - CLOSED

1CF-107AB (1D S/G CF Control Bypass) - CLOSED

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 5 Page 44 of 72 Event

Description:

1B CF Pump Trip/SGTL/Turbine Runback w/rods in Manual Time Pos. Expected Actions/Behavior Comments RO

IF any CF control bypass valve is open ot NOTE: All CF control throttled bypass valves are closed.

CRS

GO TO Step 21.F.

BOP

Slowly CLOSE 1CM-420 (Unit 1 NOTE: The BOP will close Generator Load Rejection Bypass 1CM-420.

Control) while monitoring Condensate Booster pump suction pressure.

WHEN 1CM-420 is closed, THEN check load rejection signal reset (OAC turn on code CM).

BOP

Place 1CM-420 in auto.

IF thermal power is greater than 15%,

THEN within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of reaching stable conditions, ensure each power range channel is within 2% of heat balance.

Check T-Avg - GREATER THAN 561°F.

Check CONTROL ROD BANK LO LO LIMIT alarm (1AD-2, B-9) - DARK.

Check CONTROL ROD BANK LO NOTE: 1AD-2, A-9 may be LIMIT alarm (1AD-2, A-9) - DARK. LIT. If so, the operator will perform Step 21.I RNO.

RO (Step 21.l RNO) Ensure the CONTROL ROD BANK LO LIMIT alarm clears as Xenon builds in.

RO (Step 22) Check load rejection - DUE TO NOTE: The load rejection LOSS OF CF PUMP. was due to a Loss of CF Pump.

RO/ (Step 23) Reset CF pump recirc valves as BOP follows:

CLOSE recirc valve manual loader for CF pump that is tripped:

1CF-76 (1A CF Pump Recirc Control)

OR

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 5 Page 45 of 72 Event

Description:

1B CF Pump Trip/SGTL/Turbine Runback w/rods in Manual Time Pos. Expected Actions/Behavior Comments

1CF-81 (1B CF Pump Recirc Control).

Depress "1A OR 1B CF PUMP RECIRC VALVE CLOSURE CIRCUIT" "RESET" pushbutton and ensure red "ACTIVE" light goes out and yellow "RESET" light is lit.

Check the following valves - OPEN:

1CM-266 (1A CF Pump Suction Isol)

1CM-272 (1B CF Pump Suction Isol).

Check main oil pump on tripped CF pump

- RUNNING.

Check if CF pump - TRIPPED AUTOMATICALLY.

RO/

Slowly OPEN recirc valve on tripped CF BOP pump while monitoring suction pressure on in service CF pump.

Examiner NOTE: The CRS may enter AP10 to address the SGTL at any point once it is determined that the transient is over. If so, move to Events 6-7.

BOP (Step 24) Shutdown unnecessary running plant equipment as follows:

BOP

Excess Condensate Booster pumps and NOTE: The BOP may stop place in auto. one Condensate Booster Pump.

Excess Hotwell pumps and place in auto. NOTE: The BOP may stop one Hotwell Pump.

NOTE During normal load reductions, OP/1/A/6100/003 (Controlling Procedure For Unit Operation) secures G Heater Drain Tank pumps at 60% power and C Heater Drain Tank pumps at 50% power.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 5 Page 46 of 72 Event

Description:

1B CF Pump Trip/SGTL/Turbine Runback w/rods in Manual Time Pos. Expected Actions/Behavior Comments

IF desired to secure, THEN dispatch NOTE: The CRS may operator to shutdown PER dispatch an AO.

OP/1/B/6250/004 (Feedwater Heater If so, Booth Instructor Vents, Drains and Bleed System) acknowledge as the AO.

Enclosure 4.2 (System Shutdown) the following:

Unit 1 C Heater Drain Tank pumps

Unit 1 G Heater Drain Tank pumps.

CRS (Step 25) IF power change greater than 15% NOTE: The CRS may call in one hour, THEN notify Primary Chemistry Chemistry to address the to perform required Tech Spec sampling. power decrease.

If so, Booth Instructor acknowledge as Chemistry.

RO (Step 26) WHEN condenser dump valves closed AND no longer required for temperature control, THEN reset C-7A using STEAM DUMP SELECT switch.

Upon Entry into AP-10, or at the discretion of the Lead Examiner, move to Events #6-7.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 47 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO When the plant is stabilized or AP/1/A/5500/10 is entered to mitigate the SGTL, the 1C MSIV will inadvertently CLOSE, and the Reactor will fail to trip automatically and manually. Additionally, the low set Safety Valve on the 1C Steam Generator will lift and stick fully OPEN. Additionally, the TD CA Pump will trip on overspeed on auto start, and both MDCA Pumps will fail to start automatically. The operator will enter EP/1/A/5000/E-0, Reactor Trip or Safety Injection, and then transition to EP/1/A/5000/FR-S.1, Response to Nuclear Power Generation/ATWS. During the performance of FR-S.1, the operator will continuously drive rods in manually, successfully trip the Reactor locally, and manually start the MDCA Pumps and establish 450 gpm of flow the Steam Generators. The SGTL will degrade to a tube rupture in the 1C Steam Generator when the reactor is locally tripped. After completion of FR-S.1, the operator will transition back to E-0, and then to EP/1/A/5000/E-2, Faulted Steam Generator Isolation. After the 1C Steam Generator is isolated, the operator will transition to EP/1/A/5000/E-3, Steam Generator Tube Rupture. The scenario will terminate at Step 6 of E-3 after the operator has transitioned to EP/1/A/5000/ECA-3.1, SGTR with Subcooled Recovery Desired, or at Step 9 of E-3 upon initiating an NCS cooldown.

Booth Operator Instructions: Insert REM_SM003AB (1C MSIV Closure)

Insert MAL_SM004C1 = 100 cd='H_X02_078_3 EQ 1' delay=0 (Safety Valve on 1C SG sticks OPEN on C MSIV CLOSE Indicating Light)

Insert MAL_SG001C = 300 cd='H_X01_094_2 EQ 1' delay=0 (300 gpm SGTR occurs on 1C SG on Reactor Trip Breaker Open Indicating Light)

Indications Available:

1SM3AB Green status light is LIT (MSIV Closed).

1C SG Steam Flow lowering.

1C SG Feedflow lowering.

1C SG Narrow Range Level is lowering.

MCB Annunciator 1AD3, A-5, MAIN STEAM ISOLATION VLV CLOSED Time Pos. Expected Actions/Behavior Comments EP/1/A/5000/E-0, REACTOR TRIP OR SAFETY INJECTION

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 48 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments NOTE: At any time the CRS may dispatch an AO to close the steam supply valves to the TDCA Pump from the 1C S/G.

If so, Booth Instructor:

Insert REM_SA0001 = 0 Insert REM_SA0077 = 0 Within 3 minutes, as AO report that steam has been isolated to the TD CA Pump from the 1C SG.

NOTE: Crew will carry out Immediate Actions of E-0, prior to the CRS addressing the EP.

RO/ (Step 1) Monitor Foldout page.

BOP NC Pump Trip Criteria (Not Expected)

CA Suction Sources (CA storage tank (water tower) goes below 1.5 ft - Not expected)

Position Criteria for 1NV-150B and 1NV-151A (U1 NV Pump Recird Isol)

IF NV S/I flowpath aligned AND NC pressure is less than 1500 PSIG, THEN CLOSE 1NV-150B and 1NV-151A.

IF NC pressure is greater than 2000 PSIG, THEN OPEN 1NV-150B and 1NV-151A.

Ruptured S/G Aux Feedwater Isolation NOTE: The Crew may meet Criteria (IF both of the following conditions this criterion.

met, THEN stop CA flow to affected S/G(s):

(1) Level going up in an uncontrolled manner or radiation level in that S/G is abnormal and (2) N/R level - GREATER THAN 11% (32%

ACC).)

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 49 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments Faulted S/G Aux Feedwater Isolation Criteria NOTE: The Crew is (IF all of the following conditions met, THEN expected to meet this stop CA flow to affected S/G: (1) S/G criterion.

pressure going down in an uncontrolled manner or completely depressurized, (2)

Only one S/G is diagnosed as faulted, and (3) Secondary heat sink: is available [NR level in one SG > 11% or > 450 gpm CA flow].)

RO (Step 2) Check Reactor Trip: Immediate Action

All rod bottom lights - LIT

Reactor trip and bypass breakers -

OPEN

I/R power - GOING DOWN.

RO (Step 2 RNO) Perform the following: Immediate Action

Trip reactor.

RO

IF reactor will not trip, THEN perform the NOTE: The CRS may following: dispatch an AO to locally trip the reactor.

If so, Booth Instructor After 30 seconds insert:

LOA_IPE011=TRIP (Rx Trip Bkr 1A)

LOA_IPE012=TRIP (Rx Trip Bkr 1B)

As an Alternate Insert:

LOA_IRE001A = OPEN (MG Set 1A Gen Output Bkr)

LOA_IRE002A = OPEN (MG Set 1B Gen Output Bkr)

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

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 50 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments CRS

GO TO EP/1/A/5000/FR-S.1 NOTE: The CRS will (Response To Nuclear Power transition to FR-S.1.

Generation/ATWS).

EP/1/A/5000/FR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS CAUTION NC pumps should not be tripped with Reactor power greater than 5%.

RO (Step 1) Check Reactor Trip: Immediate Action

All rod bottom lights - LIT

Reactor trip and bypass breakers -

OPEN

I/R power - GOING DOWN.

RO (Step 1 RNO) Perform the following: Immediate Action

Trip the reactor.

IF reactor will not trip, THEN ensure rod NOTE: The RO will insertion in auto or manual. manually drive Rods inward.

BOP (Step 2) Check Turbine Trip:

All throttle valves - CLOSED.

RO/ (Step 3) Monitor Foldout page.

BOP Cold Leg Recirc Switchover Criteria CA Suction Sources Position Criteria for 1NV-150B and 1NV-151A (U1 NV Pump Recird Isol)

IF NV S/I flowpath aligned AND NC pressure is less than 1500 PSIG, THEN CLOSE 1NV-150B and 1NV-151A.

IF NC pressure is greater than 2000 PSIG, THEN OPEN 1NV-150B and 1NV-151A.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 51 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments BOP (Step 4) Check proper CA pump status:

MD CA pumps - ON. NOTE: Both MDCA Pumps have failed to AUTO start.

BOP (Step 4.A RNO) Start pumps. NOTE: The BOP will start one or both MDCA Pump.

BOP

Check N/R Level in at least 3 S/Gs -

GREATER THAN 17%.

Critical Task:

Start one or more MD CA Pumps before entry into FR-H.1 is required.

Safety Significance: Failure to establish a Secondary Heat Sink through the initiation of CA flow unnecessarily challenges both the HEAT SINK and the CORE COOLING Critical Safety Functions. Additionally, the FSAR Safety Analysis results are predicated on the assumption that at least one train of safeguards actuates and delivers a minimum amount of AFW flow to the Steam Generators. Failure to perform this task, when the ability to do so exists, results in a violation of the Facility License Condition and places the plant in an unanalyzed condition.

BOP (Step 5) Initiate emergency boration of NC System as follows:

Ensure one NV pump - ON

Align boration flowpath as follows:

Open 1NV-265B (Boric Acid To NV Pumps).

Start both boric acid transfer pumps.

Check emergency boration flow -

GREATER THAN 30 GPM.

Check if NV flowpath aligned to NC System:

1NV-244A (Charging Line Cont Outside Isol) - OPEN.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 52 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments

1NV-245B (Charging Line Cont Outside Isol) - OPEN.

Ensure charging flow is greater than emergency Boration flow.

Check Pzr pressure - LESS THAN 2335 PSIG.

BOP (Step 6) Close the following VQ valves:

CLOSE 1VQ-1A (U1 Cont Air Release Inside Isol)

CLOSE 1VQ-6A (U1 Cont Air Addition Inside Isol)

CLOSE 1VQ-2B (U1 Cont Air Release Outside Isol)

CLOSE 1VQ-5B (U1 Cont Air Addition Outside Isol)

BOP (Step 7) IF AT ANY TIME while in this NOTE: This is a Continuous procedure an S/I signal exists or occurs, Action. The CRS will make THEN perform the following: one or more board operators aware.

Have another Licensed Operator check S/I equipment PER Enclosure 3 (Subsequent S/I Actions).

CRS

Continue with this procedure.

RO (Step 8) Check if the following trips have occurred:

Reactor trip.

Turbine trip.

RO (Step 9) Check reactor subcritical:

P/R channels - LESS THAN 5%

I/R channels - LESS THAN 5%

W/R Neutron Flux - LESS THAN 5%

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 53 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments

I/R SUR - NEGATIVE.

CRS (Step 10) GO TO Step 17.

RO (Step 17) Ensure adequate shutdown margin as follows:

Obtain current NC boron concentration NOTE: The CRS/RO may from Primary Chemistry. call Chemistry.

If so, Booth Instructor acknowledge as Chemistry.

WHEN current NC boron concentration is NOTE: The CRS may ask obtained, THEN perform shutdown the U2 RO to perform this margin calculation PER action.

OP/0/A/6100/006 (Reactivity Balance If so, Floor Instructor Calculation). acknowledge as U2 RO.

WHEN following conditions satisfied, NOTE: This is a Continuous THEN NC System boration may be Action. The CRS will make stopped: one or more board operators aware.

Adequate shutdown margin is obtained.

Uncontrolled cooldown has been stopped.

CRS (Step 18) Ensure the following have been NOTE: The CRS may ask implemented: SM to address.

If so, Floor Instructor acknowledge as SM.

RP/0/A/5700/000 (Classification of Emergency).

RP/0/A/5700/010 (NRC Immediate Notification Requirements).

CRS (Step 19) RETURN TO procedure and step NOTE: The CRS will in effect. transition back to E-0.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 54 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments EP/1/A/5000/E-0, REACTOR TRIP OR SAFETY INJECTION RO/ (Step 1) Monitor Foldout page.

BOP NC Pump Trip Criteria (Not Expected)

CA Suction Sources (CA storage tank (water tower) goes below 1.5 ft - Not expected)

Position Criteria for 1NV-150B and 1NV-151A (U1 NV Pump Recird Isol)

IF NV S/I flowpath aligned AND NC pressure is less than 1500 PSIG, THEN CLOSE 1NV-150B and 1NV-151A.

IF NC pressure is greater than 2000 PSIG, THEN OPEN 1NV-150B and 1NV-151A.

Ruptured S/G Aux Feedwater Isolation NOTE: The Crew may meet Criteria (IF both of the following conditions this criterion.

met, THEN stop CA flow to affected S/G(s):

(1) Level going up in an uncontrolled manner or radiation level in that S/G is abnormal and (2) N/R level - GREATER THAN 11% (32%

ACC).)

Faulted S/G Aux Feedwater Isolation Criteria NOTE: The Crew is (IF all of the following conditions met, THEN expected to meet this stop CA flow to affected S/G: (1) S/G criterion.

pressure going down in an uncontrolled manner or completely depressurized, (2)

Only one S/G is diagnosed as faulted, and (3) Secondary heat sink: is available [NR level in one SG > 11% or > 450 gpm CA flow].)

RO (Step 2) Check Reactor Trip: Immediate Action

All rod bottom lights - LIT

Reactor trip and bypass breakers -

OPEN

I/R power - GOING DOWN.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 55 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments RO (Step 3) Check Turbine Trip: Immediate Action

All throttle valves - CLOSED.

BOP (Step 4) Check 1ETA and 1ETB - Immediate Action ENERGIZED.

RO/ (Step 5) Check if S/I is actuated: Immediate Action BOP

SAFETY INJECTION ACTUATED status light (1SI-18) - LIT.

Both LOCA Sequencer Actuated status Examiner NOTE: SI will lights (1SI-14) - LIT. most likely NOT be actuated at this time, however, plant conditions will not permit SI to be avoided.

If the crew transitions to ES-0.1, observe crew activities and continue with the script when SI is actuated.

NOTE that upon return to E-0 from ES-0.1 the CRS will start at Step 1.

CRS (Step 6) Announce Unit 1 Safety Injection. NOTE: The CRS may ask U2 RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

BOP (Step 7) Check all Feedwater Isolation status lights (1SI-4) - LIT.

BOP (Step 8) Check Phase A RESET lights -

DARK.

BOP (Step 9) Check ESF Monitor Light Panel on Energized train(s):

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 56 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments

Groups 1, 2, 5 - DARK.

Group 3 - LIT.

Group 4 - LIT AS REQUIRED.

Group 6 - LIT. NOTE: Group 6 lights may NOT be LIT due to the previously failed RN Pump Suction Valve.

CRS (Step 9.d RNO) GO TO Step 9.f.

RO/ (Step 9.f) Check the following:

BOP

OAC - IN SERVICE

LOCA Sequencer Actuated status light (1SI-14) on energized train(s) - LIT.

Perform the following on energized train(s):

Check OAC Monitor Light Program

("MONL") for Group 6 windows that are dark.

Align valves as required, while continuing in this EP.

RO (Step 10) Check proper CA pump status:

MD CA pumps - ON. NOTE: Although both MDCA Pumps failed to auto start they should be running by now.

N/R level in at least 3 S/Gs - GREATER NOTE: Although NR level in THAN 17%. 3 S/Gs may not exist the TDCA Pump has failed and cannot be started.

BOP (Step 11) Check all KC pumps - ON.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 57 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments BOP (Step 12) Check both RN pumps - ON. NOTE: The 1B RN Pump may have been rendered inoperable due to a previous malfunction.

If not, the CRS may contact the WCCS/dispatch an AO to stop the pump by opening the breaker.

If so, Booth Instructor acknowledge as WCC, and indicate that the 1B RN Pump Breaker will be Racked Out. Use:

LOA-RN006 = Racked_Out (1B RN Pump BKR)

LOA-RN006A =

Racked_Out (1B RN Pump Cntrl Pwr)

BOP (Step 12 RNO) Perform the following:

Start pump(s). NOTE: the 1B RN Pump cannot be started.

IF 1A RN pump is off, THEN.

IF affected train is deenergized, AND its NOTE: the 1B D/G is D/G is off, THEN running.

Reset the following on affected train:

S/I.

Sequencer.

Dispatch operator to stop affected D/G NOTE: The CRS may using emergency stop pushbutton. dispatch an AO.

If so, Booth Instructor acknowledge as the AO, and use LOA_DG004 =

STOP_DG to stop the 1B D/G.

Monitor affected RN cooled components and shut down as necessary.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 58 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments CRS (Step 13) Notify Unit 2 to perform the Floor Instructor: As U2 following: RO report 2A RN Pump is running.

Start 2A RN pump.

THROTTLE Unit 2 RN flow to minimum Booth Instructor:

for existing plant condition. insert LOA_RN087 (Start 2A RN Pump) insert LOA_RN083 8050.000000 delay=0 ramp=10 (Unit 2 Train A Demand Flow)

RO (Step 14) Check all S/G pressures - NOTE: 1C S/G is faulted GREATER THAN 775 PSIG. and may be less than 775 psig (Crew may perform RNO. If NOT, proceed to Step 15).

RO (Step 14 RNO) Perform the following:

Check the following valves closed:

All MSIVs

All MSIV Bypass Valves

All SM PORVs.

IF any valve open, THEN..

BOP (Step 15) Check Containment Pressure - NOTE: Containment HAS REMAINED LESS THAN 3 PSIG. Pressure is normal.

BOP (Step 16) Check S/I flow:

Check NV PMPS TO COLD LEG FLOW gauge - INDICATING FLOW.

Check NC pressure - LESS THAN 1600 PSIG.

BOP (Step 16b RNO) Perform the following:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 59 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments

Ensure ND pump miniflow valve on running pump(s) OPEN:

1ND-68A (1A ND Pump & Hx Mini Flow Isol)

1ND-67B (1B ND Pump & Hx Mini Flow Isol).

CRS

IF valve(s) open on all running ND pumps, THEN GO TO Step 17.

CRS (Step 17) Notify Shift Manager or other SRO NOTE: The CRS may ask to perform EP/1/A/5000/G-1 (Generic SM to address.

Enclosures), Enclosure 22 (Shift Manager If so, Floor Instructor Actions Following an S/I) within 10 minutes.

acknowledge as SM.

RO/ (Step 18) Check CA flow: NOTE: The CA flow to the BOP 1C S/G should be isolated.

E-0 Foldout Page item 5 is expected to be met by this time.

Total CA flow - GREATER THAN 450 GPM.

RO/ (Step 18.a RNO) Perform the following:

BOP

IF N/R level in all S/Gs is less than 11%

(32% ACC), THEN..

IF N/R level in all S/Gs is less than 11%

(32% ACC) AND feed flow greater than 450 GPM cannot be established, THEN.

BOP

Check VI header pressure - GREATER THAN 60 PSIG.

RO/

WHEN each S/G N/R level is greater NOTE: This is a Continuous BOP than 11% (32% ACC), THEN control CA Action. The CRS will make flow to maintain that S/G N/R level one or more board operators between 11% (32% ACC) and 50%. aware.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 60 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments RO (Step 19) Check NC temperatures:

IF any NC pumps on OR

IF all NC pumps off, THEN check NC T-Colds - STABLE OR TRENDING TO 557°F.

(Step 19 RNO) Perform the following based on plant conditions:

IF temperature less than 557°F AND NOTE: The CRS may going down, THEN attempt to stop assign the RO (BOP) to Cooldown PER Enclosure 3 perform this action.

(Uncontrolled NC System Cooldown). If so, RO (BOP) Examiner follow actions of Enclosure 3.

Other Examiners follow E-0 Actions, Step 20, on Page 61.

EP/1/A/5000/E-0, REACTOR TRIP OR SAFETY INJECTION ENCLOSURE 3, UNCONTROLLED NC SYSTEM COOLDOWN RO/ (Step 1) Check steam dump valves -

(BOP) CLOSED.

RO/ (Step 2) Check all SM PORVs - CLOSED.

(BOP)

RO/ (Step 3) Check MSR RESET light - LIT (BOP)

RO/ (Step 4) Check any NC pump - ON.

(BOP)

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 61 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments RO/ (Step 5) Check NC TAvg GOING DOWN.

(BOP)

RO/ (Step 6) Control feed flow as follows:

(BOP)

IF S/G N/R level is less than 11% (32%

ACC) in all S/Gs, THEN

WHEN N/R level is greater than 11%

(32% ACC) in at least one S/G, THEN THROTTLE feed flow further to:

Minimize cooldown

Maintain at least one S/G N/R level greater than 11% (32%ACC).

RO/ (Step 7) Check MSIVs - ANY OPEN. NOTE: All MSIVs are (BOP) expected to be CLOSED.

RO/ (Step 7 RNO) Perform the following:

(BOP)

CLOSE MSIV Bypass Valves

Exit this enclosure EP/1/A/5000/E-0, REACTOR TRIP OR SAFETY INJECTION BOP (Step 20) Check Pzr PORV and spray Examiner NOTE:

(RO) valves: Examiners following the CRS/RO(BOP) continue HERE.

All Pzr PORVs - CLOSED.

Normal Pzr spray valves - CLOSED. NOTE: 1NC-27 is most likely closed using the Emergency CLOSE Switch.

At least one Pzr PORV isolation valve-OPEN.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 62 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments BOP (Step 21) Check NC subcooling based on (RO) core exit T/Cs - GREATER THAN 0°F.

BOP (Step 22) Check if main steamlines intact:

(RO)

All S/G pressures - STABLE OR GOING UP

All S/Gs - PRESSURIZED.

CRS (Step 22 RNO) IF any S/G is faulted, THEN NOTE: The 1C S/G is perform the following: faulted.

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

GO TO EP/1/A/5000/E-2 (Faulted Steam Generator Isolation).

NOTE: The CRS will transition to E-2.

EP/1/A/5000/E-2, FAULTED STEAM GENERATOR ISOLATION RO/ (Step 1) Monitor Foldout page.

BOP Cold Leg Recirc Switchover Criteria CA Suction Sources Position Criteria for 1NV-150B and 1NV-151A (U1 NV Pump Recird Isol)

IF NV S/I flowpath aligned AND NC pressure is less than 1500 PSIG, THEN CLOSE 1NV-150B and 1NV-151A.

IF NC pressure is greater than 2000 PSIG, THEN OPEN 1NV-150B and 1NV-151A.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 63 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments CRS (Step 2) Maintain any faulted S/G or secondary break isolated during subsequent recovery actions unless needed for NC System cooldown.

RO (Step 3) Check the following - CLOSED:

All MSIVs

All MSIV bypass valves.

RO (Step 4) Check at least one S/G pressure - NOTE: Although all SG STABLE OR GOING UP. pressures may be decreasing slowly, the operator will report stable based on plant conditions (i.e. faulted SG). Otherwise a transition to ECA-2.1 will be made.

RO/ (Step 5) Identify faulted S/G(s): NOTE: The 1C SG is BOP Faulted.

Any S/G pressure - GOING DOWN IN AN UNCONTROLLED MANNER OR

Any S/G - DEPRESSURIZED.

RO (Step 6) Maintain at least one S/G available for NC System cooldown in subsequent steps.

RO (Step 7) Check faulted S/G(s) SM PORV -

CLOSED.

BOP (Step 8) Reset CA modulating valves.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 64 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments RO/ (Step 9) Isolate faulted S/G(s) as follows:

BOP RO/

For 1C S/G:

BOP

Check S/G C FDW ISOLATED status light (1SI-4) - LIT.

Close 1CA-50B (U1 TD CA Pump Disch To 1C S/G Isol).

Close 1CA-46B (1B CA Pump Disch To 1C S/G Isol).

Check at least one MD CA pump -

RUNNING

Dispatch operator to unlock and NOTE: If not already done, CLOSE the following valves: the CRS will dispatch an AO to close these valves.

If so, Booth Instructor:

Insert REM_SA0001 = 0 Insert REM_SA0077 = 0 Within 3 minutes, as AO report that steam has been isolated to the TD CA Pump from the 1C SG.

1SA-1 (1C S/G SM Supply to Unit 1 TD CA Pump Turb Maint Isol) (Unit 1 interior doghouse, 767+10, FF-53, above ladder)

1SA-77 (1C S/G SM Supply to Unit 1 TD CA Pump Turb Loop Seal Isol) (Unit 1 interior doghouse, 767+10, FF-53).

Check BB valves - CLOSED:

1BB-3B (1C S/G Blowdown Cont Outside Isol Control)

1BB-7A (C S/G BB Cont Inside Isol).

BOP

Close 1SM-95 (C SM Line Drain Isol).

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 65 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments RO (Step 10) Close 1AS-12 (U1 SM To AS Hdr Control Inlet Isol).

RO/ (Step 11) Check S/G tubes intact as follows:

BOP

Check the following EMFs - NORMAL: NOTE: 1EMF-26 is likely in TRIP 1 or 2.

1EMF-33 (Condenser Air Ejector Exhaust)

1EMF-24 (S/G A)

1EMF-25 (S/G B)

1EMF-26 (S/G C)

1EMF-27 (S/G D).

CRS (Step 11.a RNO) GO TO EP/1/A/5000/E-3 (Steam Generator Tube Rupture)

NOTE: The CRS will transition to E-3.

EP/1/A/5000/E-3, STEAM GENERATOR TUBE RUPTURE RO/ (Step 1) Monitor Foldout page.

BOP NC Pump Trip Criteria S/I Reinitiation Criteria Secondary Integrity Criteria Cold Leg Switchover Criteria CA Suction Sources Multiple Tube Rupture Criteria:

BOP (Step 2) Identify ruptured S/G(s):

Any S/G N/R level - GOING UP IN AN UNCONTROLLED MANNER

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 66 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments OR

Chemistry or RP has determined NOTE: The CRS may ruptured S/G. contact Chemistry for sampling.

Booth Instructor:

Acknowledge as appropriate.

OR

Any of the following EMFs - ABOVE NOTE: 1EMF-26 is likely in NORMAL: TRIP 1 or 2.

1EMF-24 (S/G A)

1EMF-25 (S/G B)

1EMF-26 (S/G C)

1EMF-27 (S/G D)

RO (Step 3) Check at least one S/G -

AVAILABLE FOR NC SYSTEM COOLDOWN.

RO (Step 4) Isolate flow from ruptured S/G(s) as follows:

Check ruptured S/G(s) PORV -

CLOSED.

Check S/Gs 1B and 1C - INTACT. NOTE: The 1C SG is NOT Intact.

RO/ (Step 4.B RNO) Isolate TD CA pump steam BOP supply from ruptured S/G as follows:

IF TD CA pump is the only source of feedwater, THEN

Ensure operators dispatched in next step immediately notify Control Room Supervisor when valves are closed.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 67 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments For 1C S/G: NOTE: If not already done, the CRS will dispatch an AO to close these valves.

If so, Booth Instructor:

Insert REM_SA0001 = 0 Insert REM_SA0077 = 0 Within 3 minutes, as AO report that steam has been isolated to the TD CA Pump from the 1C SG.

1SA-77 (1C S/G SM Supply to Unit 1 TD CA Pump Turb Loop Seal Isol) (Unit 1 interior doghouse, 767+10, FF-53)

1SA-1 (1C S/G SM Supply to Unit 1 TD CA Pump Turb Maint Isol) (Unit 1 interior doghouse, 767+10, FF-53, above ladder).

IF AT ANY TIME local closure of SA valves NOTE: This is a Continuous takes over 8 minutes,THEN isolate TD CA Action. The CRS will make pump steam supply PER Enclosure 2 one or more board operators (Tripping TD CA Pump Stop Valve or aware.

Alternate Steam Isolation).

RO

Check blowdown isolation valves on ruptured S/G/(s) - CLOSED.

For 1C S/G:

1BB-3B (1C S/G Blowdown Cont Outside Isol Control)

1BB-7A (C S/G BB Cont Inside Isol).

BOP

CLOSE steam drain on ruptured S/G(s)

1SM-95 (C SM Line Drain Isol)

RO

CLOSE the following valves on ruptured S/G(s):

MSIV

MSIV bypass valve.

RO (Step 5) Control ruptured S/G(s) level as follows:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 68 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments

Check ruptured S/G(s) N/R level -

GREATER THAN 11% (32% ACC).

BOP (Step 5 RNO A) Perform the following:

IF any ruptured S/G is also faulted, THEN NOTE: The 1C S/G is NOT do not establish feed flow to the ruptured needed for cooldown.

S/G unless needed for NC System cooldown.

IF any ruptured S/G is nonfaulted OR is required for cooldown, THEN.

CRS

GO TO Step 6.

RO (Step 6) Check ruptured S/G(s) pressure - Examiner NOTE: The 1C GREATER THAN 350 PSIG. S/G may be less than 350 psig.

IF so, the crew will transition to ECA-3.1, at which time the Exam should be terminated.

If not, continue in E-3 until the NCS cooldown is started.

BOP (Step 7) Check any NC pump - RUNNING.

BOP (Step 8) Check Pzr pressure - GREATER NOTE: Pzr pressure may be THAN 1955 PSIG. <1955. If so, the crew will perform the RNO. If not, proceed to Step 9.

BOP (Step 8 RNO) IF "P-11 PRESSURIZER S/I BLOCK PERMISSIVE" status light (1SI-18) is lit, THEN block Low Pressure Steamline Isolation as follows:

Depress "BLOCK" on Low Pressure Steamline Isolation block switches.

Maintain NC pressure less than 1955 PSIG.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 69 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments RO (Step 9) Initiate NC System cooldown as follows:

CRS

Determine required core exit temperature NOTE: The CRS will based on lowest ruptured S/G pressure: determine the target temperature ruptured S/G pressure based on the 1C SG pressure.

RO

Check the following valves on ruptured S/G(s) - CLOSED:

MSIV

MSIV bypass valve.

RO

Check ruptured S/G(s) SM PORV -

CLOSED.

RO

Check S/G(s) 1B and 1C - INTACT. NOTE: The 1C SG is ruptured.

RO/ (Step 9.D RNO) IF 1B OR 1C S/G is NOTE: If not already done, BOP ruptured, THEN perform the following: the CRS will dispatch an AO to close these valves.

If so, Booth Instructor:

Insert REM_SA0001 = 0 Insert REM_SA0077 = 0 Within 3 minutes, as AO report that steam has been isolated to the TD CA Pump from the 1C SG.

Ensure steam to TDCA pump is isolated from ruptured S/G per one of the following:

Local isolation of SA line (per Step 4.B)

OR

Tripping TD CA pump stop valve (per Step 4.B).

Do not continue until affected TDCA pump steam supply is either:

Isolated OR

Determined to be unisolable.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 70 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments NOTE

NC pump trip criteria based on subcooling does not apply after starting a controlled cooldown.

After the Low Pressure Steamline Isolation signal is blocked, maintaining steam pressure negative rate less than 2 PSIG per second will prevent a Main Steam Isolation.

RO (Step 9.E) Check condenser available:

C-9 COND AVAILABLE FOR STEAM DUMP status light (1SI-18) - LIT

MSIV on intact S/G(s) OPEN.

RO (Step 9.E RNO) GO TO RNO for Step 9.H.

CAUTION After initiating cooldown in next step, continue with subsequent steps without delay.

CRS (Step 9.H RNO) Perform the following:

RO/

Ensure at least one Pzr PORV isolation BOP valve is OPEN

IF VI is lost, OR a Phase B Isolation has NOTE: VI is NOT lost.

occurred, THEN..

IF Pzr pressure is greater than 1955 NOTE: Pzr pressure may be PSIG, THEN depressurize to 1900 PSIG greater than 1955 psig. If using Pzr PORV. NOT, no depressurization will be made.

Depress "BLOCK" on Low Pressure Steamline Isolation block switches.

Maintain NC pressure less than 1955 PSIG.

Ensure Main Steam Isolation reset.

Ensure SM PORVs reset.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 2 Event # 6-7 Page 71 of 72 Event

Description:

1C MSIV fails CLOSED/ 1C SG SV fails OPEN/ATWS/SGTR/ TD CA Pump Overspeed Trip/1A & B MD CA Pumps fail to start in AUTO Time Pos. Expected Actions/Behavior Comments

IF any intact S/G SM PORV isolation NOTE: The Cooldown will valve is closed, AND associated SM be conducted using the 1A PORV is operable, THEN perform the and 1B S/Gs.

following:

OPEN SM PORV isolation valve.

IF isolation valve will not open,

Dump steam using all intact S/G(s) SM PORVs at maximum rate as follows:

RO/

CLOSE SM PORV manual loader on BOP ruptured S/G(s).

Place intact S/G SM PORV manual loaders at 50%.

Select "MANUAL" on "SM PORV MODE SELECT".

Adjust manual loaders on intact S/G SM PORVs as required to control intact S/G depressurization rate at approximately 2 PSIG per second.

At the discretion of the Lead Examiner terminate the exam.

UNIT 1 STATUS:

Power Level: 75% NCS [B] 1065 ppm Pzr [B]: 1068 ppm Xe: Per OAC Power History: At this power level for 14 days Core Burnup: 250.1 EFPDs UNIT 2 STATUS:

Power Level: 100%

CONTROLLING PROCEDURE:

OP/1/A/6100/003 (Controlling Procedure for Unit Operation)

OTHER INFORMATION NEEDED TO ASSUME THE SHIFT:

The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The following equipment is Out-Of-Service:

The 1D S/G PORV is isolated and its actuator is currently removed for maintenance.

1KFP-5130, Spent Fuel Pool Temperature, failed last shift (IAE is investigating).

MCB Annunciator 1AD-11, L-1, ETA DEGRADED VOLTAGE, has alarmed spuriously several times over the last hour and has currently failed ON (IAE has verified that the issue is limited to an annunciator card issue).

Crew Directions:

The crew will raise power to 100% after taking the shift, starting from Step 3.37.11 of Enclosure 4.1 of OP/1/A/6100/003.

The fuel is conditioned for 100% power.

Raise power at 3 MWe/minute.

The RE recommends 100% Control Rod position of 216 steps on Control Bank D.

The RE recommends that the BOP perform a 400 gallon Simple Dilute to initiate the power increase.

RMWST Dissolved O2 is greater than 1000 ppb.

Blender content is Reactor Makeup Water.

Work Control SRO Jim Field SRO Joe (FB)

AO's AVAILABLE Unit 1 Unit 2 Aux Bldg. John Aux Bldg. Chris Turb Bldg. Bob (FB) Turb Bldg. Mike (FB)

Extra(s) Bill (FB) Ed (FB) Gus (RW) Carol

Appendix D Scenario Outline Form ES-D-1 (Rev_011420)

Facility: McGuire Scenario No.: 3 Op Test No.: N20-1 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: The plant is at 36% power (BOL). The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Turnover: The following equipment is Out-Of-Service: The 1B EDG is OOS for bearing replacement.

ACTION has been taken in accordance with Technical Specification LCO 3.8.1 ACTION B. The 1D S/G PORV is isolated and its actuator is currently removed for maintenance.

1KFP-5130, Spent Fuel Pool Temperature, failed last shift (IAE is investigating) and MCB Annunciator 1AD-9, A-7, NF SYSTEM TRACE HEATING LOSS OF POWER, has alarmed spuriously several times over the last hour (IAE is investigating). The crew will raise power to 100% after taking the shift.

Critical Tasks: See Below Event Malf. Event Type* Event No. No. Description 1 NA R-RO Power Increase w/Alternate Dilute N-BOP N-SRO 2 MAL C-RO SG 1C PORV fails OPEN SM001C C(TS)-SRO 3 REM C-BOP 1B NCP Standpipe Low Level Alarm NV0461 C-SRO 4 MAL C(TS)-SRO #1 Seal Leak on 1B NCP NCP008B 5 MAL C-RO Inadvertent Turbine Trip/Failure of Control Rods to Move in AUTO DEH001 C-SRO IRE009 6 MAL C-BOP #1 Seal Leak on 1B NCP Fails NCP008B NCP016C NCP015C 7 MAL C-BOP 4 Control Rods fail to Fully Insert on Rx Trip IRE010 C-SRO 8 MAL M-RO Loss of Switchyard to Unit 1/1A EDG fails to START EP002A M-BOP EP002B M-SRO DG001A

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 (Rev_011420)

McGuire 2020 NRC Scenario #3 The plant is at 36% power (BOL). The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The following equipment is Out-Of-Service: The 1B EDG is OOS for bearing replacement. ACTION has been taken in accordance with Technical Specification LCO 3.8.1 ACTION B. The 1D S/G PORV is isolated and its actuator is currently removed for maintenance. 1KFP-5130, Spent Fuel Pool Temperature, failed last shift (IAE is investigating) and MCB Annunciator 1AD-9, A-7, NF SYSTEM TRACE HEATING LOSS OF POWER, has alarmed spuriously several times over the last hour (IAE is investigating). The crew will raise power to 100% after taking the shift.

Shortly after taking the watch, the operator will commence a load increase to 100% starting with Step 3.35.12 of Enclosure 4.1, Power Increase, of OP/1/A/6100/003, Controlling Procedure for Unit Operation. The operator will dilute the NC System Boron concentration in accordance with .4, Alternate Dilute, of OP/1/A/6150/009, Boron Concentration Control, and raise Turbine load in accordance with OP/1/A/6300/001 A, Turbine-Generator Load Change.

Shortly after starting the power increase, the 1C Steam Generator PORV will fail OPEN. The operator will respond in accordance with AP/1/A/5500/01, Steam Leak, and isolate the PORV. The operator will address Technical Specification LCO 3.7.4, Steam Generator Power Operated Relief Valves (SG PORVs), and may enter LCO 3.4.1, RCS Pressure, Temperature and Flow Departure from Nucleate Boiling (DNB) Limits.

After this, AD-7/B-2, NC PUMP B NO. 2 SEAL S-PIPE LO LEVEL, will alarm. The operator will address the Annunciator Response Procedure, and then use Enclosure 4.3, Filling and Draining NC Pump Standpipe, of OP/1/A/6150/002A, Reactor Coolant Pump Operation, to refill the standpipe.

Subsequently, a #1 seal leak will develop on the 1B NCP such that #1 Seal leakoff flow is 5.0-5.5 gpm. The operator will respond in accordance with AP/1/A/5500/08, Malfunction of NC Pump, and address Selected Licensee Commitment 16.9.7, Standby Shutdown System. The control operators will be directed on the action to take should the #1 Seal Leakoff flow degrade to > 6 gpm (which will occur subsequently).

Shortly afterwards, the Main Turbine will inadvertently trip. The operator will respond in accordance with AP/1/A/5500/02, Turbine Generator Trip. The operator will discover that the Control Rods will not respond in AUTO and the RO will need to operate the control rods manually. The crew will stabilize the plant in accordance with AP-2 and subsequently enter AP/1/A/5500/14, Rod Control Malfunction.

While the crew is in AP-2, the 1B NC Pump Hi Vibration alarm will occur and the #1 seal leak flow on the 1B NCP will rise to 6 gpm. The operator will return to Step 8 of AP-8 (Continuous Action Step), and close the 1B NCP Pzr Spray Valve, manually trip the reactor and stop the 1B NCP when reactor power is < 5%. The crew will perform Enclosure 2, NC Pump Post Trip Actions For #1 Seal Failure, of AP8, while subsequently performing E-0.

The operator will enter EP/1/A/5000/E-0, Reactor Trip or Safety Injection, and verify reactor trip.

On the reactor trip four control rods will fail to fully insert. The operator will transition to EP/1/A/5000/ES-0.1, Reactor Trip Response, and emergency borate per AP/1/A/5500/38, Emergency Boration And Response To Inadvertent Dilution.

Appendix D Scenario Outline Form ES-D-1 (Rev_011420)

Immediately following the initiation of Emergency Boration, a loss of the Unit 1 Switchyard will occur, and the 1A Emergency Diesel Generator will fail to start. The operator will immediately transition to EP/1/A/5000/ECA-0.0, Loss of All AC Power. The operator will restore power to 1ETA per Unit 2 6900V busses through SATA or SATB per Enclosure 13 Energizing Unit 1 4160V Bus From Unit 2

- SATA or SATB.

The scenario will terminate when one ESF Bus has been re-energized.

Critical Tasks:

Trip the Reactor prior to stopping the 1B NCP during a seal failure/high vibration condition and trip the NCP only after Reactor power level has dropped to less than 5% but before the CRS starts to read the Immediate Actions of EP/1/A/5000/E-0, Reactor Trip or Safety Injection to the Control Board Operators to verify that a Reactor Trip has occurred.

Safety Significance: The transient placed on the unit when an NCP is secured at power can challenge both reactor protection and control systems. Station management has decided that the conservative approach to dealing with this transient is to trip the reactor anytime a NCP malfunction warrants stopping a pump in Mode 1. Guidance is given to wait until reactor power is less than 5%

before stopping the NC pump to ensure that the NC pump will provide adequate flow/core cooling until reactor power is sufficiently low enough to preclude a challenge to fuel integrity. If the action can be taken, and is not taken, this demonstrates mis-operation or incorrect operation that could unnecessarily challenge a fission product barrier (NCS).

Control Steam Generator Water Levels during the Station Blackout such that no Steam Generator Overfill Condition occurs (0.8 on Void Fraction SGINFO.cts) and causes Water to Enter the Steam Lines.

Safety Significance: During the Station Blackout the only source of CA flow is the TDCA Pump. If the critical task is not performed and one or more SGs are allowed to overfill, water will enter the steam line and potentially damage the only available source for CA flow (i.e. the TDCA Pump).

PROGRAM: McGuire Operations Training MODULE: Initial License Operator Training Class ILT 20-1 TOPIC: NRC Simulator Exam Scenario N20-1-3

REFERENCES:

1. Technical Specification LCO 3.8.1, AC Sources - Operating (Amendment 314/293)

2. OP/1/A/6100/003, Controlling Procedure for Unit Operation (Rev 212)

3. OP/1/A/6150/009, Boron Concentration Control (Rev 138)

4. OP/1/A/6300/001 A, Turbine-Generator Load Change (Rev 13)

5. AP/1/A/5500/01, Steam Leak (Rev 19)

6. Technical Specification LCO 3.4.1, RCS Pressure, Temperature and Flow Departure From Nucleate Boiling (DNB) Limits (Amendment 219/201)

7. MCEI -0400-379, McGuire 1 Cycle 27 Core Operating Limits Report (Rev 1)

8. Technical Specification LCO 3.7.4, Steam Generator Power Operated Relief Valves (SG PORVs) (Amendment 302/281)

9. OP/1/A/6100/010 H, Annunciator Response for Panel 1AD-7 (Rev 68)

10. OP/1/A/6150/002 A, Reactor Coolant Pump Operation (Rev 71)

11. AP/1/A/5500/08, Malfunction of NC Pump (Rev 17)

12. SLC 16.9.7, Standby Shutdown System (Rev 180)

13. AP/1/A/5500/02, Turbine Generator Trip (Rev 30)

14. AP/1/A/5500/14, Rod Control Malfunction (Rev 16)

15. AP/1/A/5500/38, Emergency Boration and Response to Inadvertent Dilution (Rev 11)

16. EP/1/A/5000/E-0, Reactor Trip or Safety Injection (Rev 36)

17. EP/1/A/5000/ES-0.1, Reactor Trip Response (Rev 47)

18. EP/1/A/5000/ECA-0.0, Loss of All AC Power (Rev 44)

Validation Time: 115 minutes Author: David Lazarony, Essential Training & Consulting, LLC Facility Review: ________________________

Rev. 011420 McGuire 2020 NRC Scenario #3 Objectives:

Given the simulator at an initial condition of 36% power with a normal power increase planned evaluate:

1. the SROs ability to supervise the control room team during the normal, abnormal, and emergency situations that arise, including compliance with all facility procedures, Technical Specifications, and other commitments.

2. each crew members ability to effectively communicate as part of a control room team during the normal, abnormal, and emergency situations that arise.

3. the RO and BOPs ability to effectively raise power in accordance with Enclosure 4.1, Power Increase, of OP/1/A/6100/003, Controlling Procedure for Unit Operation, and the Alternate Dilution process.

4. each crew members ability to effectively diagnose a failed open Steam Generator PORV and the RO and BOPs ability to respond to such an event in accordance with AP/1/A/5500/01, Steam Leak.

5. each crew members ability to effectively diagnose a low-level condition on an NC Pump

2 Seal Pipe, and the BOPs ability to respond to such a condition in accordance with OP/1/A/6150/002A, Reactor Coolant Pump Operation.

6. each crew members ability to effectively diagnose a degradation of a #1 Seal on an NC Pump and the RO and BOPs ability to respond to such an event in accordance with AP/1/A/5500/08, Malfunction of NC Pump.

7. each crew members ability to effectively diagnose an inadvertent Turbine Trip while < P-8 and a failure of the control rods to move in AUTO when required; and the ROs ability to respond to such an event in accordance with AP/1/A/5500/02, Turbine Generator Trip, including manual rod control during the transient.

8. each crew members ability to effectively diagnose a failure of the #1 NC Pump Seal and the RO and BOPs ability to respond to such an event in accordance with AP/1/A/5500/08, Malfunction of NC Pump, EP/1/A/5000/E-0, Reactor Trip or Safety Injection, EP/1/A/5000/ES-0.1, Reactor Trip Response, and emergency borate per AP/1/A/5500/38, Emergency Boration And Response To Inadvertent Dilution.

9. each crew members ability to effectively diagnose a loss of the Unit 1 Switchyard and the RO and BOPs ability to respond to such an event in accordance with EP/1/A/5000/ECA-0.0, Loss of All AC Power.

Scenario Event Description NRC Scenario 3 Facility: McGuire Scenario No.: 3 Op Test No.: N20-1 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: The plant is at 36% power (BOL). The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Turnover: The following equipment is Out-Of-Service: The 1B EDG is OOS for bearing replacement. ACTION has been taken in accordance with Technical Specification LCO 3.8.1 ACTION B. The 1D S/G PORV is isolated and its actuator is currently removed for maintenance. 1KFP-5130, Spent Fuel Pool Temperature, failed last shift (IAE is investigating) and MCB Annunciator 1AD-9, A-7, NF SYSTEM TRACE HEATING LOSS OF POWER, has alarmed spuriously several times over the last hour (IAE is investigating). The crew will raise power to 100% after taking the shift.

Critical Tasks: See Below Event Malf. Event Type* Event No. No. Description 1 NA R-RO Power Increase w/Alternate Dilute N-BOP N-SRO 2 MAL C-RO SG 1C PORV fails OPEN SM001C C(TS)-SRO 3 REM C-BOP 1B NCP Standpipe Low Level Alarm NV0461 C-SRO 4 MAL C(TS)-SRO #1 Seal Leak on 1B NCP NCP008B 5 MAL C-RO Inadvertent Turbine Trip/Failure of Control Rods to Move in AUTO DEH001 C-SRO IRE009 6 MAL C-BOP #1 Seal Leak on 1B NCP Fails NCP008B NCP016C NCP015C 7 MAL C-BOP 4 Control Rods fail to Fully Insert on Rx Trip IRE010 C-SRO 8 MAL M-RO Loss of Switchyard to Unit 1/1A EDG fails to START EP002A M-BOP EP002B M-SRO DG001A

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 3 McGuire 2020 NRC Scenario #3 The plant is at 36% power (BOL). The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The following equipment is Out-Of-Service: The 1B EDG is OOS for bearing replacement.

ACTION has been taken in accordance with Technical Specification LCO 3.8.1 ACTION B. The 1D S/G PORV is isolated and its actuator is currently removed for maintenance. 1KFP-5130, Spent Fuel Pool Temperature, failed last shift (IAE is investigating) and MCB Annunciator 1AD-9, A-7, NF SYSTEM TRACE HEATING LOSS OF POWER, has alarmed spuriously several times over the last hour (IAE is investigating). The crew will raise power to 100% after taking the shift.

Shortly after taking the watch, the operator will commence a load increase to 100% starting with Step 3.35.12 of Enclosure 4.1, Power Increase, of OP/1/A/6100/003, Controlling Procedure for Unit Operation. The operator will dilute the NC System Boron concentration in accordance with .4, Alternate Dilute, of OP/1/A/6150/009, Boron Concentration Control, and raise Turbine load in accordance with OP/1/A/6300/001 A, Turbine-Generator Load Change.

Shortly after starting the power increase, the 1C Steam Generator PORV will fail OPEN. The operator will respond in accordance with AP/1/A/5500/01, Steam Leak, and isolate the PORV.

The operator will address Technical Specification LCO 3.7.4, Steam Generator Power Operated Relief Valves (SG PORVs), and may enter LCO 3.4.1, RCS Pressure, Temperature and Flow Departure from Nucleate Boiling (DNB) Limits.

After this, AD-7/B-2, NC PUMP B NO. 2 SEAL S-PIPE LO LEVEL, will alarm. The operator will address the Annunciator Response Procedure, and then use Enclosure 4.3, Filling and Draining NC Pump Standpipe, of OP/1/A/6150/002A, Reactor Coolant Pump Operation, to refill the standpipe.

Subsequently, a #1 seal leak will develop on the 1B NCP such that #1 Seal leakoff flow is 5.0-5.5 gpm. The operator will respond in accordance with AP/1/A/5500/08, Malfunction of NC Pump, and address Selected Licensee Commitment 16.9.7, Standby Shutdown System. The control operators will be directed on the action to take should the #1 Seal Leakoff flow degrade to > 6 gpm (which will occur subsequently).

Shortly afterwards, the Main Turbine will inadvertently trip. The operator will respond in accordance with AP/1/A/5500/02, Turbine Generator Trip. The operator will discover that the Control Rods will not respond in AUTO and the RO will need to operate the control rods manually. The crew will stabilize the plant in accordance with AP-2 and subsequently enter AP/1/A/5500/14, Rod Control Malfunction.

While the crew is in AP-2, the 1B NC Pump Hi Vibration alarm will occur and the #1 seal leak flow on the 1B NCP will rise to 6 gpm. The operator will return to Step 8 of AP-8 (Continuous Action Step), and close the 1B NCP Pzr Spray Valve, manually trip the reactor and stop the 1B NCP when reactor power is < 5%. The crew will perform Enclosure 2, NC Pump Post Trip Actions For #1 Seal Failure, of AP8, while subsequently performing E-0.

The operator will enter EP/1/A/5000/E-0, Reactor Trip or Safety Injection, and verify reactor trip. On the reactor trip four control rods will fail to fully insert. The operator will transition to EP/1/A/5000/ES-0.1, Reactor Trip Response, and emergency borate per AP/1/A/5500/38, Emergency Boration And Response To Inadvertent Dilution.

Scenario Event Description NRC Scenario 3 Immediately following the initiation of Emergency Boration, a loss of the Unit 1 Switchyard will occur, and the 1A Emergency Diesel Generator will fail to start. The operator will immediately transition to EP/1/A/5000/ECA-0.0, Loss of All AC Power. The operator will restore power to 1ETA per Unit 2 6900V busses through SATA or SATB per Enclosure 13 Energizing Unit 1 4160V Bus From Unit 2 - SATA or SATB.

The scenario will terminate when one ESF Bus has been re-energized.

Critical Tasks:

Trip the Reactor prior to stopping the 1B NCP during a seal failure/high vibration condition and trip the NCP only after Reactor power level has dropped to less than 5%

but before the CRS starts to read the Immediate Actions of EP/1/A/5000/E-0, Reactor Trip or Safety Injection to the Control Board Operators to verify that a Reactor Trip has occurred.

Safety Significance: The transient placed on the unit when an NCP is secured at power can challenge both reactor protection and control systems. Station management has decided that the conservative approach to dealing with this transient is to trip the reactor anytime a NCP malfunction warrants stopping a pump in Mode 1. Guidance is given to wait until reactor power is less than 5% before stopping the NC pump to ensure that the NC pump will provide adequate flow/core cooling until reactor power is sufficiently low enough to preclude a challenge to fuel integrity. If the action can be taken, and is not taken, this demonstrates mis-operation or incorrect operation that could unnecessarily challenge a fission product barrier (NCS).

Control Steam Generator Water Levels during the Station Blackout such that no Steam Generator Overfill Condition occurs (0.8 on Void Fraction SGINFO.cts) and causes Water to Enter the Steam Lines.

Safety Significance: During the Station Blackout the only source of CA flow is the TDCA Pump.

If the critical task is not performed and one or more SGs are allowed to overfill, water will enter the steam line and potentially damage the only available source for CA flow (i.e. the TDCA Pump).

Scenario Event Description NRC Scenario 3 SIMULATOR OPERATOR INSTRUCTIONS Bench Mark ACTIVITY DESCRIPTION Reset to Temp IC 232 T = 0 Malfunctions:

(Base IC-18 [42%

BOL]) insert MAL_EPQ001B ACTIVE (Loss of D/G B Control Power) insert LOA_DG021 RACKED_OUT (1B D/G Output Breaker Control Power Fuses) insert LOA_DG012 RACKED_OUT (1B D/G Output Breaker Racked Out)

Insert REM_SV0025 = 0 (Close 1SV-25 [1D S/G PORV Isolation])

Insert LOA_SV004 = Racked_Out (SG PORV Breaker Racked Out)

H_X02_098_3 = 0 (1D PORV Controller LEFT lamp)

H_X02_098_4 = 0 (1D PORV Controller RIGHT lamp)

Insert LOA_SV020 = 0 (SM PORV D LOCAL OPERATION) insert XMT_ KFTT5130 = 0 (Spent Fuel Pool Temperature Failure) insert MAL_IRE010N9 (Shutdown Bank B-3 Stuck at original position) insert MAL_IRE010N11 (Shutdown Bank D-3 Stuck at original position) insert MAL_IRE010P10 Control Bank B-3 Stuck at original position) insert MAL_IRE010P12 Shutdown Bank A-3 Stuck at original position)

RUN Place Tagout/O-Stick on:

1B EDG (Tagout)

Reset all SLIMs

1SV-25 (Tagout)

1KFP-5130 (O-Stick)

MCB Annunciator 1AD-9, A-7 (O-stick)

Update Status Board, NOTE: RMWST DO = <1000 ppb.

Setup OAC Freeze.

Update Fresh Tech.

Spec. Log.

Scenario Event Description NRC Scenario 3 Bench Mark ACTIVITY DESCRIPTION Fill out the AO's Available section of Shift Turnover Info.

Prior to Crew RUN Briefing Crew Briefing

1. Assign Crew Positions based on evaluation requirements

2. Review the Shift Turnover Information with the crew.

3. Provide Enclosure 4.1 of OP/1/A/6100/003 marked up as required.

4. Provide the crew with OP/1/A/6150/009 (Boron Concentration Control) and OP/1/A/6300/1 A (Turbine-Generator Load Change).

5. Direct the crew to Review the Control Boards taking note of present conditions, alarms.

T-0 Begin Familiarization Period At direction of Execute Simulator examiner Scenario N20-1-3.

At direction of Event 1 Power Increase w/Alternate Dilute examiner NA After adequate Event 2 SG 1C PORV fails OPEN power insert MAL_SM001C =

increase/

100, ramp=10 direction of examiner Scenario Event Description NRC Scenario 3 Bench Mark ACTIVITY DESCRIPTION When AD-7/B- Event 3 1B NCP Standpipe Low Level Alarm 2, NC PUMP insertREM_NV0461 = NOTE: The Malfunction for this event will be B NO. 2 SEAL 1.0 (Open Standpipe inserted in Event 2.

S-PIPE LO Drain Valve)

LEVEL, is LIT delIA REM_NV0461 =

0.0 cd cd x10_152_5

=1 delay = 60 seconds (Closed Standpipe Drain Valve when MCB Annunciator 1AD-7 B-2 is LIT)

When crew Event 4 #1 Seal Leak on 1B NCP determines 1B Insert NOTE: The Malfunction for this event will be NC Pump #1 MAL_NCP008B=12, inserted in Event 3.

Seal leakoff Ramp = 10 minutes flow is rising or at the discretion of the Lead Examiner When the Event 5 Inadvertent Turbine Trip/Failure of Control Rods to CRS enters Move in AUTO Insert MAL_DEH001 AP-14 for the Insert MAL_IRE009 failure of Auto Rod Motion or at direction of examiner At direction of Event 6 #1 Seal Leak on 1B NCP Fails examiner Change Severity MAL_NCP008B=15 Ramp = 120 seconds insertMAL_NCP016C =

16 Ramp = 120 seconds (1B NCP Hi Vibration) insert MAL_NCP015C =

11 Ramp = 120 seconds (1B NCP Hi Vibration)

H_X10_171_3 EQ1 (NCP 1B Breaker Green Status light ON),

delIA MAL-NCP016C and 015C Scenario Event Description NRC Scenario 3 Bench Mark ACTIVITY DESCRIPTION Post-Rx Trip Event 7 4 Control Rods fail to Fully Insert on Rx Trip Insert MAL_IRE010N9 MAL_IRE010N11 MAL_IRE010P10 MAL_IRE010P12 Post- Event 8 Loss of Switchyard to Unit 1/1A EDG fails to Immediate START Insert MAL_EP002 Boration AND EP002B = TRIP Insert MAL_DG001A =

TRUE Terminate the scenario upon direction of Lead Examiner Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 1 Page 10 of 71 Event

Description:

Power Increase w/Alternate Dilute Shortly after taking the watch, the operator will commence a load increase to 100%

starting with Step 3.35.12 of Enclosure 4.1, Power Increase, of OP/1/A/6100/003, Controlling Procedure for Unit Operation. The operator will dilute the NC System Boron concentration in accordance with Enclosure 4.4, Alternate Dilute, of OP/1/A/6150/009, Boron Concentration Control, and raise Turbine load in accordance with OP/1/A/6300/001 A, Turbine-Generator Load Change.

Booth Operator Instructions: NA Indications Available: NA Time Pos. Expected Actions/Behavior Comments NOTE: Per Limit and Precaution 1.4 of Enclosure 4.1 of OP/1/A/6100/003 the operator will control Tavg-Tref at +/-2°F.

OP/1/A/6100/003, CONTROLLING PROCEDURE FOR UNIT OPERATIONS ENCLOSURE 4.1, POWER INCREASE NOTE: The power increase will be at 3 MWe/minute.

BOP (Step 3.35.12) WHEN Turbine load greater than 40% (370 psig Turbine Inlet Pressure),

THEN begin aligning MSRs per OP/1/B/6250/011 (Moisture Separator Reheater Operation).

OP/1/A/6300/001A, TURBINE-GENERATOR STARTUP/SHUTDOWN ENCLOSURE 4.1, TURBINE-GENERATOR LOAD CHANGE NOTE If reducing power to a level greater than 50%, it is preferable to reduce power at a rate less than 12% per hour in order to minimize sodium peaks. [NCR01574291]

RO (Step 3.4.1) IF Turbine in OPERATOR AUTO, perform the following:

(Step 3.4.1.1) Ensure desired change within Calculated Capability Curve.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 1 Page 11 of 71 Event

Description:

Power Increase w/Alternate Dilute Time Pos. Expected Actions/Behavior Comments (Step 3.4.1.2) IF turbine load will increase or NOTE: The BOP will contact decrease more than 10 MWs, notify DEC BA.

Dispatcher of expected load change. Booth Operator: As DEC BA acknowledge.

RO (Step 3.4.1.3) IF desired to change the load rate, THEN perform the following:

Depress LOAD RATE.

Enter desired load rate in VARIABLE NOTE: the RO will select 3 DISPLAY. MWe/Min loading rate.

Depress ENTER.

(Step 3.4.1.4) IF desired to change desired load, THEN perform the following:

Depress REFERENCE.

Enter desired load in VARIABLE DISPLAY.

Depress ENTER.

Depress GO (Step 3.4.1.5) IF desired to pause load change, THEN perform the following:

Depress "HOLD".

WHEN desired to resume load change, THEN depress "GO".

OP/1/A/6150/009, BORON CONCENTRATION CONTROL ENCLOSURE 4.4, ALTERNATE DILUTE NOTE: The BOP may repeat this task as needed during the power increase.

BOP (Step 3.1) Obtain RMWST Dissolved Oxygen (DO) concentration from Chemistry Daily Status Sheet.

NOTE High Oxygen concentration within the VCT makeup process can cause an increase in iron corrosion product generation within the charging supply piping (long term Crud Burst control issue). {NCR 01604415}

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 1 Page 12 of 71 Event

Description:

Power Increase w/Alternate Dilute Time Pos. Expected Actions/Behavior Comments BOP (Step 3.2) IF RMWST Dissolved Oxygen NOTE: The RMWST (DO) concentration is greater than 1000 ppb, Dissolved Oxygen (DO)

THEN. concentration is less than 1000 ppb.

BOP (Step 3.3) Evaluate all outstanding Clearances that may impact performance of this procedure.

NOTE

Large additions of cold water to the VCT (from RMWST) can cause large decreases in NC pump #1 seal leakoff flow. This creates a potential for a #1 seal rub when there is a low leaking seal (less than 2 gpm). {NCR 01632117}

A temperature decrease at the NC pump seals, will cause a short term increase (5 -

10 min) in seal leakoff flow before it goes to its new lower operating flow.

A temperature increase at the NC pump seals, will cause a short term decrease (5 -

10 min) in seal leakoff flow before it goes to its new higher operating flow.

If outside air temperature is less than 75 °F (can use OAC point M1P1484),

consideration should be given to making large cold water additions to VCT in 1000 gallon increments with time between additions to restore temperature.

BOP (Step 3.4) IF the lowest NCP seal leakoff is less than 2 gpm AND VCT makeup of greater than 1000 gallons will be made, THEN BOP (Step 3.5) Evaluate energizing additional pressurizer heaters per OP/1/A/6100/003 (Controlling Procedure For Unit Operation) to enhance system mixing when changing NC System boron concentration. (R.M.)

BOP (Step 3.6) Determine current blender contents and evaluate any potential Reactivity effects prior to performing this enclosure:

Rx Makeup Water

Blend

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 1 Page 13 of 71 Event

Description:

Power Increase w/Alternate Dilute Time Pos. Expected Actions/Behavior Comments

Boron BOP (Step 3.7) Determine amount of reactor makeup water needed to obtain desired boron concentration using McGuire Data Book, OAC, Reactor Group Guidance, or plant parameters (T-Ave, Steam Pressure, Xenon worth, etc.). (R.M.)

Total Reactor Makeup Water: NOTE: The BOP will add 300 gallons of MU Water.

BOP (Step 3.8) Ensure the following reset to zero:

(R.M.)

Total Make Up Flow Counter

Boric Acid Flow Counter BOP (Step 3.9) Set Total Make Up Flow Counter to value determined in Step 3.7. (R.M.)

BOP (Step 3.10) Select ALTERNATE DILUTE on NC Sys M/U Controller.

BOP (Step 3.11) IF desired to makeup only through 1NV-175A (U1 Boric Acid Blender To VCT Outlet Control), THEN select CLOSED on 1NV-171A (U1 Boric Acid Blender to VCT Inlet Control).

NOTE Rapidly changing reactor makeup water flow can cause a Rx Makeup Flow Deviation Annunciator Alarm.

BOP (Step 3.12) IF AT ANY TIME it is desired to NOTE: Typically, it is NOT adjust reactor makeup water flow, adjust Rx desired to adjust reactor M/U Water Flow Control setpoint to achieve makeup water flow.

desired flowrate.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 1 Page 14 of 71 Event

Description:

Power Increase w/Alternate Dilute Time Pos. Expected Actions/Behavior Comments BOP (Step 3.13) IF AT ANY TIME it is desired to manually adjust reactor makeup water flow, perform the following:

(Step 3.13.1) Place Rx M/U Water Flow Control in manual.

(Step 3.13.2) Adjust Rx M/U Water Flow Control output to control reactor makeup water flowrate.

NOTE IF desired to dilute with a constant flow rate as advised by engineering to minimize VCT temperature decrease, it is preferred to allow 1NV-137A (U1 NC Filter Otlt to VCT 3-Way Diversion Cntrl) to auto divert on high level.

BOP (Step 3.14) IF AT ANY TIME it is desired to lower VCT level, perform the following:

(Step 3.14.1) Monitor Letdown Pressure.

NOTE An increase in Letdown Pressure greater than 20 psig during diverts may be indicative of excessive NB Feed Filter DP. {NCR 01597088}

(Step 3.14.2) Select HUT on 1NV-137A NOTE: The BOP may do this (U1 NC Filters Otlt to VCT 3-Way Diversion at any time to lower VCT level.

Contrl).

(Step 3.14.3) IF Letdown Pressure increases greater than 20 psig, notify CRS.

(Step 3.14.4) AFTER desired level achieved, select AUTO on 1NV-137A (U1 NC Filters Otlt to VCT 3-Way Diversion Cntrl).

NOTE Steps 3.15 - 3.25 may be completed and then checked off as time allows.

BOP (Step 3.15) IF AT ANY TIME plant parameters require termination of dilution, THEN perform the following:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 1 Page 15 of 71 Event

Description:

Power Increase w/Alternate Dilute Time Pos. Expected Actions/Behavior Comments (Step 3.15.1) Place NC System Make Up to STOP. (R.M.)

(Step 3.15.2) IF 1NV-137A (U1 NC Filters Otlt to VCT 3-Way Diversion Cntrl) was placed to HUT, place to AUTO.

BOP (Step 3.16) IF AT ANY TIME nuisance NOTE: The plant is in Mode 1.

Reactor Makeup Flow Deviation alarms are being received AND Unit in Mode 5, 6, or NO Mode.

BOP (Step 3.17) Momentarily select START on NC System Make Up. (R.M.)

BOP (Step 3.18) Check NC System Make Up red light lit.

BOP (Step 3.19) Check 1NV-175A (U1 Boric Acid Blender To VCT Outlet Control) open.

BOP (Step 3.20) Check 1NV-252A (Rx M/U Water Supply To U1 BA Blender Cntrl) open or throttled as required.

BOP (Step 3.21) IF 1NV-171A (U1 Boric Acid NOTE: 1NV-171A is NOT in Blender To VCT Inlet Control) in AUTO, AUTO.

THEN check 1NV-171A (U1 Boric Acid Blender to VCT Inlet Control) open.

BOP (Step 3.22) Check Rx M/U Water Pump starts.

BOP (Step 3.23) Monitor Total Make Up Flow Counter. (R.M.)

BOP (Step 3.24) HOLD until one of the following occurs:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 1 Page 16 of 71 Event

Description:

Power Increase w/Alternate Dilute Time Pos. Expected Actions/Behavior Comments

Amount of reactor makeup water recorded per Step 3.7 added OR

Reactor makeup water addition manually terminated BOP (Step 3.25) Ensure dilution terminated as follows: (R.M.)

(Step 3.25.1) IF in AUTO, ensure the following off:

1A Rx M/U Water Pump

1B Rx M/U Water Pump BOP (Step 3.25.2) Ensure the following closed:

1NV-175A (U1 Boric Acid Blender To VCT Outlet Control)

1NV-252A (RX M/U Water Supply To U1 BA Blender Cntrl)

1NV-171A (U1 Boric Acid Blender To VCT Inlet Control)

BOP (Step 3.26) Ensure 1NV-171A (U1 Boric Acid Blender to VCT Inlet Control) in AUTO.

BOP (Step 3.27) Ensure Rx M/U Water Flow Control in AUTO. (R.M.)

NOTE

OAC point M1P5614 (Unit 1 Effective Boron Concentration) may be used as the desired boron concentration in the following calculations. Use of Effective Boron Concentration will account for B-10 depletion. {NCR 01641629}

Results of Boron Concentration makeups have been consistently lower than desired.

To compensate it may be necessary to use actual Boron Concentration (instead of Effective Boron Concentration) or adjustment of the "desired" Boron Concentration to obtain a desired resultant Boron Concentration. {NCR 01682204}

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 1 Page 17 of 71 Event

Description:

Power Increase w/Alternate Dilute Time Pos. Expected Actions/Behavior Comments BOP (Step 3.28) IF Rx M.U Water Flow Control NOTE: Typically, the Rx M.U adjusted per Step 3.12 or 3.13, THEN Water Flow Control was NOT adjusted.

BOP (Step 3.29) Ensure 1NV-137A (U1 NC Filters Otlt to VCT 3-Way Diversion Cntrl) in AUTO.

BOP (Step 3.30) IF Reactor Makeup Flow NOTE: These alarms are NOT Deviation alarms blocked per Step 3.16, blocked.

THEN.

NOTE CRS concurrence required if flush of blender NOT performed.

BOP (Step 3.31) IF desired to flush blender. NOTE: The BOP will likely request that the flush NOT be performed.

BOP (Step 3.32) Select AUTO for NC Sys M/U Controller.

BOP (Step 3.33) Momentarily select START on NC System Make Up.

BOP (Step 3.34) Check NC System Make Up red light lit.

BOP (Step 3.35) Ensure the following reset to zero: (R.M.)

Total Make Up Flow Counter

Boric Acid Flow Counter BOP (Step 3.36) Record in Auto Log that final blender content is Rx Makeup Water.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 1 Page 18 of 71 Event

Description:

Power Increase w/Alternate Dilute Time Pos. Expected Actions/Behavior Comments OP/1/A/6100/003, CONTROLLING PROCEDURE FOR UNIT OPERATIONS ENCLOSURE 4.1, POWER INCREASE RO (Step 3.35.13) WHEN Turbine Inlet Pressure 365 - 375 psig, THEN check "AMSAC ACTUATION BLOCK/UNBLOCK" as follows:

IF "UNBLOCK" dark, THEN reset as follows:

Check all "AMSAC S/G LOW FLOW" status lights dark.

Check "S/G PATH CLSD >30 SEC" dark.

Depress "UNBLOCK" for "AMSAC ACTUATION BLOCK/UNBLOCK".

Check "UNBLOCK" lit.

BOP (Step 3.35.14) WHEN 40% RTP, THEN notify RP to adjust setpoints for the following: {NCR 01717012}

1EMF-71 (S/G A Leakage Hi Rad)

1EMF-72 (S/G B Leakage Hi Rad)

1EMF-73 (S/G C Leakage Hi Rad)

1EMF-74 (S/G D Leakage Hi Rad)

After adequate power increase/discretion of the Lead Examiner move to Event #2.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 2 Page 19 of 71 Event

Description:

SG 1C PORV fails OPEN Shortly after starting the power increase, the 1C Steam Generator PORV will fail OPEN.

The operator will respond in accordance with AP/1/A/5500/01, Steam Leak, and isolate the PORV. The operator will address Technical Specification LCO 3.7.4, Steam Generator Power Operated Relief Valves (SG PORVs), and may enter LCO 3.4.1, RCS Pressure, Temperature and Flow Departure from Nucleate Boiling (DNB) Limits.

Booth Operator Instructions: insert MAL_SM001C 100 delay=0 ramp=10 (S/G PORV 1SV7 SGC fails OPEN)

Indications Available:

1SV-7ABC Red status light LIT

1SV-7ABC Black needle indication at 100%

OAC Alarm: TM FREEZE - MID3497-VLVSV1C SM PORV OPEN

OAC Alarm: U1 SV-PORV/SAFETY VLV OPEN -T/D CA PMP ON

OAC Alarm: 1SV-7 1C SM PORV

Core Ts rising

Rx Power rising

Steam flow on 1C steam line rising Time Pos. Expected Actions/Behavior Comments NOTE: It is likely that the operator will take actions to isolate the 1C SG PORV prior to being directed by the CRS.

(Step 13)

AP/1/A/5500/01, STEAM LEAK CRS (Step 1) Monitor Foldout page.

Manual Reactor Trip Criteria: (IF any of the NOTE: Manual Reactor Trip following occur: (1) Steam leak is Criteria is NOT expected to be jeopardizing personnel safety or plant utilized.

equipment, (2) T-Avg is less than 551°F AND going down, or (3) UST level is less than 1 ft

- NOT Expected).

RO (Step 2) Reduce turbine load to maintain the following:

Excore NIs - LESS THAN OR EQUAL TO 100%.

NC Loop D/Ts - LESS THAN 60°F D/T

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 2 Page 20 of 71 Event

Description:

SG 1C PORV fails OPEN Time Pos. Expected Actions/Behavior Comments

T-Avg - AT T-REF.

CRS (Step 3) Check containment entry - IN NOTE: A Containment Entry is PROGRESS. NOT in progress.

CRS (Step 3 RNO) GO TO Step 5.

BOP (Step 5) Check Pzr pressure prior to event -

GREATER THAN P-11 (1955 PSIG).

BOP (Step 6) Check Pzr level - STABLE OR NOTE: The CRS may direct GOING UP. the RNO to be performed depending on the timeliness of the S/G PORV closure. If not, proceed to Step 7.

BOP (Step 6 RNO) Perform the following as required to maintain level:

Maintain charging flow less than 200 GPM at all times in subsequent steps.

Ensure 1NV-238 (U1 Charging Hdr Control) OPENING.

OPEN 1NV-241 (U1 Seal Water Inj Flow Control) while maintaining NC pump seal flow greater than 6 GPM.

Reduce or isolate letdown.

Start additional NV pump.

IF Pzr level going down with maximum charging flow, THEN ..

BOP (Step 7) IF AT ANY TIME while in this NOTE: This is a Continuous procedure Pzr level cannot be maintained Action. The CRS will make stable, THEN RETURN TO Step 6. one or more board operators aware.

CRS (Step 8) GO TO Step 12.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 2 Page 21 of 71 Event

Description:

SG 1C PORV fails OPEN Time Pos. Expected Actions/Behavior Comments CRS (Step 12) Announce occurrence on paging NOTE: CRS may ask U2 RO system. to make Plant Announcement that AP-1 has been entered.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 13) Identify and isolate leak on Unit 1 as follows:

(Step 13.A) Check SM PORVs - NOTE: The 1C SG PORV is CLOSED. Open.

RO (Step 13.A RNO) IF S/G pressure is less than 1092 PSIG, THEN perform the following:

Close affected S/G SM PORV manual NOTE: Closing the Manual loader. Loader will have no effect.

IF SM PORV is still open, THEN perform NOTE: The 1C SG PORV the following: Isolation Valve will need to be closed.

Close SM PORV isolation valve.

IF SM PORV isolation valve still NOTE: The PORV Isolation open valve is closed.

RO * (Step 13.B) Check condenser dump valves - CLOSED.

BOP * (Step 13.C) Check containment conditions - NORMAL:

Containment temperature

Containment pressure

Containment humidity

Containment floor and equipment sump level.

RO / * (Step 13.D) Check TD CA pump - OFF.

BOP

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 2 Page 22 of 71 Event

Description:

SG 1C PORV fails OPEN Time Pos. Expected Actions/Behavior Comments BOP * (Step 13.E) Check valves on STEAM NOTE: One or more of these LINE DRAIN VALVES board (1MC-9) - valves may be cycling. The CLOSED. RNO will direct closing the valves.

CRS * (Step 13.F) Check opposite Unit (Unit 2) NOTE: CRS may ask U2 RO STEAM HEADER PRESSURE - for AS Header pressure.

GREATER THAN 200 PSIG. If so, Floor Instructor report as U2 RO that U2 Steam Header pressure is 1000 psig.

CRS * (Step 13.G) Dispatch operator to check NOTE: The CRS may dispatch for leaks. an AO to look for leaks.

If so, Floor Instructor:

acknowledge.

Booth Instructor: Report back in 3-5 minutes that there are no leaks.

NOTE: The CRS may NOT dispatch AOs to look for leaks because it is understood that the SM PORV opening was the reason that AP-1 was entered.

BOP (Step 14) Check UST level - STABLE OR GOING UP.

CRS (Step 15) Evaluate unit shutdown as follows:

Check unit status - IN MODE 1 OR 2.

Determine if unit shutdown or load NOTE: CRS may call reduction is warranted based on the WCC/Management to address following criteria: the startup.

If so, Booth Instructor acknowledge as WCC.

Size of leak

Location of leak

Rate of depletion of secondary inventory

IF steam is leaking from a secondary heater relief OR MSR relief valve

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 2 Page 23 of 71 Event

Description:

SG 1C PORV fails OPEN Time Pos. Expected Actions/Behavior Comments

IF turbine trip will isolate steam leak (such as feedwater heater leak or MSR leak

Check unit shutdown or load reduction - NOTE: Shutdown/Load REQUIRED. Reduction will NOT be required.

CRS (Step 15.C RNO) Perform the following:

Maintain present plant conditions until leak can be isolated or repaired.

Exit this procedure.

NOTE: The CRS may call WCC/IAE to address the Valve failure.

If so, Booth Instructor acknowledge as WCC, and using Time Compression report that 1SV7ABC is stuck fully open (and cannot be moved even using the Manual handwheel).

NOTE: The CRS will likely conduct a Focus Brief.

NOTE: The CRS will address Tech Specs based on plant response.

Booth Operator Instructions: While the CRS is checking Tech Specs, insertREM_NV0461 = 1.0 (Open Standpipe Drain Valve) (will take 3-4 min, to alarm) delIA REM_NV0461 = 0.0 cd x05_002B02_1 =1 Delay = 60 Seconds (Closed Standpipe Drain Valve when MCB Annunciator 1AD-7 B-2 is LIT)

TECHNICAL SPECIFICATION 3.7.4, STEAM GENERATOR POWER OPERATED RELIEF VALVES (SG PORVs)

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 2 Page 24 of 71 Event

Description:

SG 1C PORV fails OPEN Time Pos. Expected Actions/Behavior Comments CRS LCO 3.7.4 Three SG PORV lines shall be OPERABLE.

CRS APPLICABILITY: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.

CRS ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required SG PORV A.1 Restore required SG 7 days line inoperable. PORV line to OPERABLE status.

NOTE: The CRS will determine that Condition A is required and that ACTION A.1 must be taken.

TECHNICAL SPECIFICATION 3.4.1, RCS PRESSURE, TEMPERATURE, AND FLOW DEPARTURE FROM NUCLEATE BOILING (DNB) LIMITS CRS LCO 3.4.1 RCS DNB parameters for NOTE: According to Table pressurizer pressure, RCS average 3.4.1-1, Parameter 2, indicated temperature, and RCS total flow rate shall be Pressurizer Pressure will be within the limits specified in Table 3.4.1-1. The limit specified in the COLR.

CRS APPLICABILITY: MODE 1. NOTE: According to Table 4 of the COLR, indicated Pressurizer Pressure (with four channels available) must be 2212.3 psig via the meter indication and 2209.1 psig via the OAC.

During this failure Pressurizer Pressure will lower below these values.

CRS ACTIONS

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 2 Page 25 of 71 Event

Description:

SG 1C PORV fails OPEN Time Pos. Expected Actions/Behavior Comments CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer pressure or A.1 Restore DNB parameter(s) 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months RCS average temperature to within limit.

DNB parameters not within limits.

NOTE: When Pressurizer Pressure drops to < 2209.1 psig (OAC) on the failure, the CRS will determine that Condition A is required and that ACTION A.1 must be taken.

NOTE: Floor Instructor if the crew attempts to continue the power increase as Shift Manager direct that the crew await further direction to raise power.

When AD-7/B-2, NC PUMP B NO. 2 SEAL S-PIPE LO LEVEL, move to Event 3.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 3 Page 26 of 71 Event

Description:

1B NCP Standpipe Low Level Alarm After this, AD-7/B-2, NC PUMP B NO. 2 SEAL S-PIPE LO LEVEL, will alarm. The operator will address the Annunciator Response Procedure, and then use Enclosure 4.3, Filling and Draining NC Pump Standpipe, of OP/1/A/6150/002A, Reactor Coolant Pump Operation, to refill the standpipe.

Booth Operator Instructions: insertREM_NV0461 = 1.0 (Open Standpipe Drain Valve) (will take 3-4 min, to alarm) delIA REM_NV0461 = 0.0 cd x05_002B02_1 =1 delay = 60 seconds (Closed Standpipe Drain Valve when MCB Annunciator 1AD-7 B-2 is LIT)

Indications Available:

OAC Alarm M1D1496: 1B NC Pump Standpipe Level Low

MCB Annunciator 1AD-7/B-2 NC PUMP B NO.2 SEAL S-PIPE LOW LEVEL Time Pos. Expected Actions/Behavior Comments OP/1/A/6100/010 H, ANNUNCIATOR RESPONSE FOR PANEL 1AD-7 B2, NC PUMP B NO. 2 SEAL S-PIPE LO LVL BOP (Step 1) IF drain was inadvertently opened, ensure it is closed.

BOP (Step 2) Check the following NC pump parameters stable:

Lower bearing Temperature

Number 1 seal outlet temperature

Number 1 seal leakoff flow BOP (Step 3) IF any NC pump parameter listed in NOTE: All listed parameters Step 2 abnormal, are normal.

BOP (Step 4) Make up to standpipe as necessary NOTE: The CRS will transition per OP/1/A/6150/002A (Reactor Coolant to the OP to refill the Pump Operation). standpipe.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 3 Page 27 of 71 Event

Description:

1B NCP Standpipe Low Level Alarm Time Pos. Expected Actions/Behavior Comments When BOP addresses OP/1/A/6150/002 A to refill the 1B NC Pump Standpipe:

Booth Operator Instructions: insert MAL_NCP008B=12 Ramp = 10 minutes (Event 4)

(NOTE: This malfunction will require several minutes to diagnose).

OP/1/A/6150/002 A, REACTOR COOLANT PUMP OPERATION ATTACHMENT 3, FILLING AND DRAINING NC PUMP STANDPIPE BOP (Step 3.1.1) Evaluate all outstanding CLEARANCES that may impact performance of this procedure.

BOP (Step 3.1.2) IF Containment Closure in NOTE: Containment Closure is effect, THEN.. NOT in effect.

BOP (Step 3.1.3) Perform the following sections, as applicable:

Section 3.2, Filling NC Pump Standpipes BOP (Step 3.2) Filling NC Pump Standpipes

Check Reactor Makeup Water System aligned per OP/1/A/6200/012 (Reactor Makeup Water System).

Check 1NC-56B (PRT Spray Cont Outside Isol) OPEN.

NOTE

NC Pump Standpipe volume needed to clear applicable "NC Pump No. 2 Seal S-pipe Lo Lvl" alarm is approximately seven gallons. The preferred method to clear the alarm is to allow RMWST gravity feed to fill the affected NC Pump Standpipe.

[8.7.9]

Only one NC Pump Standpipe fill valve should be opened at a time and closed immediately when the low standpipe alarm clears. [8.7.9]

Minimal NC Pump Standpipe volume is required to reduce flow through the standpipe and reduce debris entering No. 2 and No. 3 seals. [8.7.9]

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 3 Page 28 of 71 Event

Description:

1B NCP Standpipe Low Level Alarm Time Pos. Expected Actions/Behavior Comments BOP

Open Applicable valve(s):

1NV-55B (B NC Pump Standpipe Fill)

IF required, THEN start one of the NOTE: It is likely that the BOP following: will need to start a Rx M/U Water Pump.

1A Rx M/U Water Pump OR

1B Rx M/U Water Pump

WHEN applicable NC Pump No. 2 Seal S-pipe Lo Lvl alarm clears, THEN perform the following:

IF pump started in Step 4, stop applicable pump:

1A Rx M/U Water Pump OR

1B Rx M/U Water Pump

Close applicable valve.

1NV-55B (B NC Pump Standpipe Fill)

NOTE: The CRS may call WCC to address the failure.

If so, Booth Instructor acknowledge as WCC.

NOTE: The CRS will likely conduct a Focus Brief.

When the crew has determined that the 1B NC Pump #1 Seal Leakoff flow is rising or at the discretion of the Lead Examiner, move to Event #4.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 4 Page 29 of 71 Event

Description:

1 Seal Leak on 1B NCP Subsequently, a #1 seal leak will develop on the 1B NCP such that #1 Seal leakoff flow is 5.0-5.5 gpm. The operator will respond in accordance with AP/1/A/5500/08, Malfunction of NC Pump, and address Selected Licensee Commitment 16.9.7, Standby Shutdown System. The control operators will be directed on the action to take should the #1 Seal Leakoff flow degrade to > 6 gpm (which will occur subsequently).

Booth Operator Instructions: insert MAL_NCP008B=12 Ramp = 10 minutes (NOTE: This malfunction was mostly likely inserted during the completion of Event 3).

Indications Available:

1B NC Pump #1 Seal leakoff flow is rising on the OAC.

OAC Alarm: 1B NCP Seal Flow > SSF Limit.

MCB Annunciator 1AD-7/E3, NCP PMP CNTRL LEKAGE HI FLOW Time Pos. Expected Actions/Behavior Comments AP/1/A/5500/08, MALFUNCTION OF NC PUMP CASE I, NC PUMP SEAL OR PUMP LOWER BEARING MALFUNCTION NOTE Step 1 RNO should be used to validate the abnormal parameter unless it has been previously validated or is clearly known to be valid.

BOP (Step 1) Check abnormal NC pump NOTE: The operator may parameter - KNOWN TO BE VALID. address Enclosure 1 per the RNO (Not Scripted).

BOP (Step 2) Check NC pump parameters within operating limits:

All NC pump lower radial bearing temperatures - LESS THAN 225°F

All NC pump number 1 seal outlet temperatures - LESS THAN 235°F

All NC pump number 1 seal D/Ps -

GREATER THAN 200 PSID.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 4 Page 30 of 71 Event

Description:

1 Seal Leak on 1B NCP Time Pos. Expected Actions/Behavior Comments BOP (Step 3) IF AT ANY TIME, any operating limit NOTE: This is a Continuous in Step 2 is exceeded, THEN GO TO Step 5. Action. The CRS will make one or more board operators aware.

CRS (Step 4) GO TO Step 6.

BOP (Step 6) Check if seal cooling available to affected NC pump as follows:

Seal injection (normal or SSF Supply) -

ESTABLISHED OR

KC to Thermal Barrier - ESTABLISHED.

NOTE Up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of NC Pump operation may be required before seals seat and operate normally after seal maintenance or startup.

BOP (Step 7) Check any NC pump number one NOTE: It is likely that by the seal leakoff - GREATER THAN OR EQUAL time the crew arrives at this TO 6 GPM. step the leakoff flow will be rising but will NOT have exceeded 6 GPM.

BOP (Step 7 RNO) Perform the following:

NOTE OP/1/A/6200/001 B (Chemical and Volume Control System Charging), Enclosure 4.10 (Maintaining NC Pump Seal Leakoff) gives guidance on actions used to change seal leakoff flow.

IF seal leakoff slowly going up, THEN NOTE: The CRS may call contact station management for further WCC/SM to address the guidance. seal failure with station management.

If so, Booth Instructor acknowledge as WCC/SM.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 4 Page 31 of 71 Event

Description:

1 Seal Leak on 1B NCP Time Pos. Expected Actions/Behavior Comments

Continue to monitor NC pump seal leakoff flow.

CRS

IF AT ANY TIME seal leakoff flow goes NOTE: This is a Continuous up to 6 GPM, THEN GO TO Step 8. Action. The CRS will make one or more board operators aware.

CRS

GO TO Step 9.

BOP (Step 9) Check affected NC pump(s) Seal Return Valve - OPEN:

1NV-50B (1B NC Pump Seal Return Isol)

BOP (Step 10) Check NC pressure - GREATER THAN 2000 PSIG.

BOP (Step 11) Check any NC Pump number one seal leakoff - LESS THAN 0.8 GPM.

CRS (Step 11 RNO) Perform the following:

NOTE OP/1/A/6200/001 B (Chemical and Volume Control System Charging), Enclosure 4.10 (Maintaining NC Pump Seal Leakoff) gives guidance on actions used to change seal leakoff flow.

BOP

IF seal leakoff slowly going down, THEN.

Continue to monitor NC Pump seal leakoff flow.

IF AT ANY TIME seal leakoff flow goes NOTE: This is a Continuous below 0.8 GPM, THEN RETURN TO Action. The CRS will make Step 10. one or more board operators aware.

CRS

GO TO Step 17.

BOP (Step 17) Check for number two seal failure without a number one seal failure as follows:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 4 Page 32 of 71 Event

Description:

1 Seal Leak on 1B NCP Time Pos. Expected Actions/Behavior Comments

Number one seal leakoff - LESS THAN NOTE: #1 Seal Leak off NORMAL OR GOING DOWN. Flow is higher than Normal.

CRS (Step 17 RNO) GO TO Step 18.

CRS (Step 18) Check for number three seal failure as follows:

Frequent filling of seal standpipe with standpipe drains closed - HAS OCCURRED.

CRS (Step 18 RNO) GO TO Step 19.

CRS (Step 19) Announce occurrence on paging NOTE: CRS may ask U2 system. RO to make Plant Announcement.

If so, Floor Instructor acknowledge as U2 RO.

BOP (Step 20) Check NC Pumps - ANY NOTE: All NCPs are RUNNING. running.

BOP (Step 21) Check the following NC Pump temperatures - STABLE OR GOING DOWN:

All NC Pump lower radial bearing temperatures

All NC Pump number one seal outlet temperatures.

CRS (Step 22) Have another SRO evaluate if NOTE: The CRS may ask leakage exceeds SLC 16.9.7 Condition C the SM to evaluate SLC limit and immediately notify security if SSF is 16.9.7.

inoperable.

If so, Floor Instructor, indicate that another SRO is NOT available.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 4 Page 33 of 71 Event

Description:

1 Seal Leak on 1B NCP Time Pos. Expected Actions/Behavior Comments SELECTED LICENSEE COMMITMENT 16.9.7, STANDBY SHUTDOWN SYSTEM CRS COMMITMENT The Standby Shutdown System (SSS) shall be operable.

CRS APPLICABILITY: MODES 1, 2, and 3.

CRS REMEDIAL ACTIONS The SRO should ensure that security is NOTE: The CRS may call notified 10 minutes prior to declaring the SSS WCC/Security to implement inoperable. Immediately upon discovery of compensatory measures the SSS inoperability, Security must be within 10 minutes of notified to implement compensatory discovery.

measures within 10 minutes of discovery. If so, Booth Instructor acknowledge as WCC/Security.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 4 Page 34 of 71 Event

Description:

1 Seal Leak on 1B NCP Time Pos. Expected Actions/Behavior Comments CONDITION REQUIRED ACTION COMPLETION TIME C. Total Unidentified C.1 Declare the Standby Immediately LEAKAGE, Identified Makeup Pump inoperable.

LEAKAGE, and reactor AND coolant pump seal leakoff >

C.2 Enter Condition A.

20 gpm.

OR Total reactor coolant pump seal leakoff > 16.3 gpm.

OR Any reactor coolant pump No.

1 seal leakoff > 4.0 gpm.

A. One or more required SSS A.1 Verify the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months components identified in FUNCTIONALITY of fire Table 16.9.7-1. detection and suppression systems in the associated areas identified in Table 16.9.7-1 AND 7 days A.2 Restore the component to FUNCTIONAL status.

The CRS will identify that Condition C is required and that Actions C.1 and C.2 must be taken immediately; and that C.2 requires Condition A and Actions A.1 and A.2 must be taken.

At the discretion of the Lead Examiner, move to Event #5.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 5 Page 35 of 71 Event

Description:

Inadvertent Turbine Trip/Failure of Control Rods to Move in AUTO Shortly afterwards, the Main Turbine will inadvertently trip. The operator will respond in accordance with AP/1/A/5500/02, Turbine Generator Trip. The operator will discover that the Control Rods will not respond in AUTO and the RO will need to operate the control rods manually. The crew will stabilize the plant in accordance with AP-2 and subsequently enter AP/1/A/5500/14, Rod Control Malfunction.

Booth Operator Instructions: insert MAL_DEH001/IRE009 Indications Available:

Turbine Trip Valves closed

Turbine Governor Valves closed

Rx does NOT trip (Rx Trip Breakers closed)

Steam Dump Valves open

No Automatic Rod Motion Time Pos. Expected Actions/Behavior Comments NOTE: The CRS will enter AP-02.

AP/1/A/5000/02, TURBINE GENERATOR TRIP RO (Step 1) Check Turbine Trip:

All throttle valves - CLOSED.

RO (Step 2) Check P/R meters - LESS THAN NOTE: PR indication is >

20%. 20%.

RO (Step 2 RNO) Perform the following:

Ensure control rods moving in to reduce NOTE: The rods must be T-Avg. moved in MANUAL.

Designate an operator to continuously NOTE: The CRS will monitor reactor power. designate the RO.

WHEN reactor power is less than 20%, NOTE: This is a Continuous THEN perform the following: Action. The CRS will make one or more board operators aware.

Place control rods in manual.

Perform Step 3 to stabilize reactor NOTE: The RO will stabilize power. reactor power at about 12-15%.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 5 Page 36 of 71 Event

Description:

Inadvertent Turbine Trip/Failure of Control Rods to Move in AUTO Time Pos. Expected Actions/Behavior Comments CRS

GO TO Step 4.

RO (Step 4) IF AT ANY TIME reactor power NOTE: This is a Continuous goes below 5%, THEN perform the following: Action. The CRS will make one or more board operators aware.

RO

Do not pull control rods.

Insert control rods as necessary to maintain negative SUR on I/R startup rate meters.

RO (Step 5) Check C-9 COND AVAILABLE FOR STEAM DUMP status light (1SI-18) -

LIT.

BOP (Step 6) Check any CF pump - IN SERVICE. NOTE: The 1A CF Pump is in service.

RO (Step 7) Check both generator breakers -

OPEN.

RO (Step 8) Check EXCITATION - OFF.

RO (Step 9) IF AT ANY TIME T-Avg is less than NOTE: This is a Continuous 551°F AND going down, THEN perform the Action. The CRS will make following: one or more board operators aware.

Trip reactor.

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

RO (Step 10) Check all control rods - ALIGNED WITH ASSOCIATED BANK.

RO (Step 11) Check MSR RESET light - LIT.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 5 Page 37 of 71 Event

Description:

Inadvertent Turbine Trip/Failure of Control Rods to Move in AUTO Time Pos. Expected Actions/Behavior Comments CRS (Step 12) Announce the following: Unit 1 NOTE: CRS may ask U2 Turbine trip, non-essential personnel stay out RO to make Plant of Unit 1 turbine bldg. Announcement.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 13) Check UNBLOCK light for AMSAC ACTUATION BLOCK/UNBLOCK switch (1MC-2) - DARK.

RO (Step 14) Check condenser dump valves -

MODULATING OPEN.

BOP (Step 15) Check Pzr pressure control response as follows:

Ensure Pzr heaters are in auto.

Ensure Pzr spray control valves are in auto.

Check Pzr PORVs - CLOSED.

Check Pzr spray control valves -

CLOSED.

BOP (Step 16) Check Pzr level -TRENDING TO PROGRAM.

RO (Step 17) Ensure Bearing Lift pump in AUTO.

RO (Step 18) WHEN bearing oil pressure goes down to 11-12 PSIG, THEN ensure AC Bearing Oil pump starts.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 5 Page 38 of 71 Event

Description:

Inadvertent Turbine Trip/Failure of Control Rods to Move in AUTO Time Pos. Expected Actions/Behavior Comments RO (Step 19) Perform applicable steps of OP/1/A/6300/001 (Turbine Generator Startup/Shutdown), Enclosure 4.3 (Shutdown).

When the CRS enters AP-14 for the failure of Automatic Rod Motion or at the discretion of the Lead Examiner move to Events #6-8.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 39 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START While the crew is in AP-2, the 1B NC Pump Hi Vibration alarm will occur and the #1 seal leak flow on the 1B NCP will rise to 6 gpm. The operator will return to Step 8 of AP-8 (Continuous Action Step), and close the 1B NCP Pzr Spray Valve, manually trip the reactor and stop the 1B NCP when reactor power is < 5%. The crew will perform , NC Pump Post Trip Actions For #1 Seal Failure, of AP8, while subsequently performing E-0. The operator will enter EP/1/A/5000/E-0, Reactor Trip or Safety Injection, and verify reactor trip. On the reactor trip four control rods will fail to fully insert. The operator will transition to EP/1/A/5000/ES-0.1, Reactor Trip Response, and emergency borate per AP/1/A/5500/38, Emergency Boration And Response To Inadvertent Dilution. Immediately following the initiation of Emergency Boration, a loss of the Unit 1 Switchyard will occur, and the 1A Emergency Diesel Generator will fail to start. The operator will immediately transition to EP/1/A/5000/ECA-0.0, Loss of All AC Power. The operator will restore power to 1ETA per Unit 2 6900V busses through SATA or SATB per Enclosure 13 Energizing Unit 1 4160V Bus From Unit 2 - SATA or SATB. The scenario will terminate when one ESF Bus has been re-energized.

Booth Operator Instructions: Change Severity MAL_NCP008B=15 Ramp =

120 seconds insertMAL_NCP016C = 16 Ramp = 120 seconds (1B NCP Hi Vibration) insert MAL_NCP015C = 11 Ramp = 120 seconds (1B NCP Hi Vibration)

H_X10_171_3 EQ1 (NCP 1B Breaker Green Status light ON), delIA MAL_NCP016C and 015C Indications Available:

MCB Annunciator 1AD6/E-11, NC PUMP HI VIBRATION

1B NC Pump #1 Seal leakoff flow is rising on the OAC to 6 gpm.

Time Pos. Expected Actions/Behavior Comments NOTE: The CRS will go back and implement Step 8 of AP-8.

AP/1/A/5500/08, MALFUNCTION OF NC PUMP CASE I, NC PUMP SEAL OR PUMP LOWER BEARING MALFUNCTION CRS (Step 8) Stop affected NC pump as follows:

IF A or B NC pump is the affected pump, Then CLOSE associated spray valve:

BOP

1NC-29C (B NC Loop PZR Spray Control).

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 40 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments CAUTION (NC Pump Post Trip Actions For #1 Seal Failure) contains actions that must be performed 3 to 5 minutes after stopping the NC Pump. This enclosure must be performed even after transition to EPs.

CRS

Have any available RO perform NOTE: The CRS may direct Enclosure 2 (NC Post Trip Actions for #1 the Unit 2 BOP to perform Seal Failure as crew performs the this action.

following steps. If so, Floor Instructor:

report that the U2 BOP (or any other RO) is NOT available.

Check unit status - IN MODE 1 OR 2.

RO

Trip reactor BOP

WHEN reactor power less than 5%,

THEN stop affected NC pump.

Critical Task:

Trip the Reactor prior to stopping the 1B NCP during a seal failure/high vibration condition and trip the NCP only after Reactor power level has dropped to less than 5% but before the CRS starts to read the Immediate Actions of EP/1/A/5000/E-0, Reactor Trip or Safety Injection to the Control Board Operators to verify that a Reactor Trip has occurred.

Safety Significance: The transient placed on the unit when an NCP is secured at power can challenge both reactor protection and control systems. Station management has decided that the conservative approach to dealing with this transient is to trip the reactor anytime a NCP malfunction warrants stopping a pump in Mode 1.

Guidance is given to wait until reactor power is less than 5% before stopping the NC pump to ensure that the NC pump will provide adequate flow/core cooling until reactor power is sufficiently low enough to preclude a challenge to fuel integrity. If the action can be taken, and is not taken, this demonstrates mis-operation or incorrect operation that could unnecessarily challenge a fission product barrier (NCS).

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 41 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments NOTE: The CRS will direct the BOP to perform Enclosure 2, and continue in AP-8 with the RO.

If so, BOP Examiner follow actions of Enclosure 2.

Other Examiners follow AP-8 Actions on Page 42.

AP/1/A/5500/08, MALFUNCTION OF NC PUMP ENCLOSURE 2, NC PUMP POST TRIP ACTIONS FOR #1 SEAL FAILURE Examiner NOTE: Follow the actions associated with Enclosure 2 if BOP is assigned by CRS to perform.

CAUTION Failure of number two and three seals may occur unless the affected NC Pump Seal Return Valve is closed immediately after the pump has coasted down to zero speed (3-5 min). This enclosure must be completed even after transition to EPs.

BOP (Step 1) Record time of NC pump shutdown.

BOP (Step 2) Check if seal cooling available to affected pump as follows:

Seal injection from normal charging (NV pump or PD Pump) - ESTABLISHED

KC to Thermal Barrier - ESTABLISHED.

BOP (Step 3) Check if any NC Pump number one seal leakoff flow - GREATER THAN OR EQUAL TO 6 GPM.

BOP (Step 4) Maintain seal injection flow greater NOTE: The BOP will need than 9 GPM to affected pump(s). to adjust Sealwater Injection flow.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 42 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments BOP (Step 5) Check all NC Pumps - OFF. NOTE: All NC Pumps are running.

BOP (Step 5 RNO) IF any NC Pump continues to run, THEN perform the following:

WHEN affected NC pump has been off 3 minutes, THEN immediately perform the following:

CLOSE affected NC pump seal return valve:

1NV-50B (B NC Pump Seal NOTE: The BOP will close Return Isol) this valve approximately three minutes after stopping the 1B NC Pump.

OPEN all of the following valves:

OPEN 1KC-394A (A NC Pump Therm Bar Otlt)

OPEN 1KC-345A (C NC Pump Therm Bar Otlt)

OPEN 1KC-364B (B NC Pump Therm Bar Otlt)

OPEN 1KC-413B (D NC Pump Therm Bar Otlt)

Exit this enclosure AP/1/A/5500/08, MALFUNCTION OF NC PUMP CASE I, NC PUMP SEAL OR PUMP LOWER BEARING MALFUNCTION Examiner NOTE:

Examiners following the CRS/RO continue HERE.

CRS

Continue with this AP as time allows.

CRS

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

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 43 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments EP/1/A/5000/E-0, REACTOR TRIP OR SAFETY INJECTION RO/ (Step 1) Monitor Foldout page.

BOP NC Pump Trip Criteria (Not Expected)

CA Suction Sources (CA storage tank (water tower) goes below 1.5 ft - Not expected)

Position Criteria for 1NV-150B and 1NV-151A (U1 NV Pump Recird Isol)

IF NV S/I flowpath aligned AND NC NOTE: The BOP will pressure is less than 1500 PSIG, THEN monitor these conditions.

CLOSE 1NV-150B and 1NV-151A.

IF NC pressure is greater than 2000 PSIG, THEN OPEN 1NV-150B and 1NV-151A.

Ruptured S/G Aux Feedwater Isolation Criteria (Not expected)

Faulted S/G Aux Feedwater Isolation Criteria (Not expected)

RO (Step 2) Check Reactor Trip: Immediate Action

All rod bottom lights - LIT NOTE: There will be four rods that failed to fully insert on the Rx Trip.

Reactor trip and bypass breakers -

OPEN

I/R power - GOING DOWN.

RO (Step 2 RNO) Perform the following:

Trip reactor.

IF reactor will not trip RO (Step 3) Check Turbine Trip: Immediate Action

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 44 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments

All throttle valves - CLOSED.

BOP (Step 4) Check 1ETA and 1ETB - Immediate Action ENERGIZED.

RO/ (Step 5) Check if S/I is actuated: Immediate Action BOP

SAFETY INJECTION ACTUATED NOTE: SI will NOT be status light (1SI-18) - LIT. actuated.

RO/ (Step 5 RNO) Perform the following: Immediate Action BOP Check if S/I is required:

Pzr pressure less than 1845 PSIG OR

Containment pressure greater than 1 PSIG.

IF S/I is required,.. NOTE: SI will NOT be required.

RO/ IF S/I is not required, THEN perform the BOP following:

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

CRS GO TO EP/1/A/5000/ES-0.1 (Reactor Trip Response).

NOTE: The CRS will transition to ES-0.1.

EP/1/A/5000/ES-0.1, REACTOR TRIP RESPONSE RO/ (Step 1) Monitor Foldout page.

BOP S/I Actuation Criteria CA Suction Sources

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 45 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments BOP (Step 2) Check the following:

VI pressure - GREATER THAN 85 PSIG.

Any Unit 1 6900V bus - ENERGIZED.

CRS (Step 3) Announce: "Unit 1 Reactor trip, non- NOTE: The CRS may ask essential personnel stay out of Unit 1 turbine U2 RO to make Plant bldg". Announcement.

If so, Floor Instructor acknowledge as U2 RO.

RO (Step 4) Check any NC Pump ON. NOTE: The 1A, 1C and 1D NCPs will be ON.

RO (Step 5) Check NC temperatures as follows:

IF any NC Pump on, THEN check NC T Avg STABLE OR TRENDING TO 557°F.

RO (Step 6) Continue to monitor NC temperature as follows:

Check any NC Pump ON. NOTE: The 1A, 1C and 1D NCPs will be ON.

IF AT ANY TIME while in this procedure NOTE: This is a Continuous either of the following occurs, THEN Action. The CRS will make perform Step 5: one or more board operators aware.

NC TAvg is less than 557°F and going down OR

NC TAvg is greater than 557°F and going up.

CRS (Step 7) REFER TO the following: NOTE: The CRS may ask SM to address.

If so, Floor Instructor acknowledge as SM.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 46 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments

RP/0/A/5700/000 (Classification of Emergency)

RP/0/A/5700/010 (NRC Immediate Notification Requirements).

RO (Step 8) Check Main Generator as follows:

Check both generator breakers OPEN.

Check "EXCITATION" OFF.

RO (Step 9) Check MSR "RESET" light LIT.

RO (Step 10) Check NC TAvg GREATER THAN 553°F.

RO/ (Step 11) Check feedwater status:

BOP

Check any CA Pump ON.

Check total feed flow to S/Gs GREATER THAN 450 GPM.

CRS (Step 12) WHEN time and manpower allow, NOTE: The CRS may THEN dispatch operator to perform dispatch an AO to look for Enclosure 5 (MSR Second Stage Drain Tank leaks.

Isolation).

If so, Floor Instructor:

acknowledge.

RO (Step 13) Check if shutdown margin adequate:

All control rods FULLY INSERTED. NOTE: There will be four rods that failed to fully insert on the Rx Trip.

BOP (Step 13 RNO) Perform the following:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 47 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments

IF all rod position indication is lost, OR NOTE: The BOP will borate greater than 2 rods not fully inserted, 8000 gallons of Boric Acid THEN emergency borate total of 8,000 per AP/1/A/5500/38, while gallons of 7000 PPM boron solution PER the crew continues with ES-AP/1/A/5500/38 (Emergency Boration 0.1.

And Response To Inadvertent Dilution).

IF 2 rods not fully inserted, THEN..

NOTE: The CRS may assign the BOP to perform this action.

If so, BOP Examiner follow actions of Enclosure AP38.

Other Examiners follow ES-0.1 Actions, Step 13.B, on Page 50.

NOTE: The CRS may these actions to the BOP.

AP/1/A/5500/38, EMERGNCY BORATION AND RESPONSE TO INADVERTENT DILUTION Examiner NOTE: Follow the actions associated with AP38 if BOP is assigned by CRS to perform.

BOP (Step 1) Check if boron dilution -

SUSPECTED.

BOP (Step 1 RNO) Perform the following:

IF unit in Mode 1 or 2, THEN..

GO TO Step 12.

BOP (Step 12) Initiate emergency boration as follows:

Check 1A or 1B NV pump - AVAILABLE.

Check any NV pump - ON.

Check the following boric acid system components - AVAILABLE.

Boric Acid Storage Tank

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 48 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments BOP

Boric Acid Transfer pump.

OPEN 1NV-265B (U1 NV Pump Boric Acid Sup Isol).

Ensure a boric acid transfer pump is running.

Check boration flow using one of the following methods:

IF 1NV-265B is open, THEN check "EMERGENCY BORATION FLOW" -

ESTABLISHED.

OR

IF 1NV-269 is open, THEN..

NOTE If 1NV-265B opened for emergency boration, OAC point M1P0785 provides the gallons of boric acid added.

BOP (Step 13) IF AT ANY TIME boration no NOTE: This is a Continuous longer required, THEN GO TO Step 20. Action.

BOP (Step 14) IF AT ANY TIME a higher boration NOTE: This is a Continuous flowrate is desired, THEN evaluate Action.

performing the following as required:

Start a second boric acid transfer pump.

Align NV pump suction to FWST as follows:

OPEN the following valves:

1NV-221A (U1 NV Pump Suct From FWST Isol)

1NV-222B (U1 NV Pump Suct From FWST Isol).

CLOSE the following valves:

1NV-141A (U1 VCT Outlet Isol)

1NV-142B (U1 VCT Outlet Isol).

BOP (Step 15) Align Normal Charging flowpath as follows:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 49 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments

Ensure one of the following NC loop isolation valves is OPEN:

1NV-13B (U1 NV Supply To 1A NC Loop Isol)

OR

1NV-16A (U1 NV Supply To 1D NC Loop Isol).

Check both of the following valves -

OPEN:

1NV-244A (U1 Charging Hdr Cont Outside Isol)

1NV-245B (U1 Charging Hdr Cont Outside Isol).

BOP (Step 16) Establish desired charging flowrate to the NC System as follows:

THROTTLE OPEN 1NV-238 (U1 Charging Hdr Control) and 1NV-241 (U1 Seal Water Inj Flow Control) to establish desired charging flow, not to exceed 200 GPM.

IF required to compensate for higher charging flowrate, THEN raise letdown to a maximum of 120 GPM.

NOTE A time delay of up to 3-5 minutes can be expected before indication of negative reactivity insertion is obtained on excore instrumentation.

BOP (Step 17) Check if boric acid flow to NC System is adequate:

Reactor power - STABLE OR GOING DOWN

NC temperature - STABLE OR GOING DOWN

Control Rods - STABLE OR STEPPING OUT.

BOP (Step 18) Check NV pump suction -

ALIGNED TO VCT.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 50 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments BOP (Step 19) IF AT ANY TIME VCT level approaches water solid, THEN evaluate performing the following:

Raise charging flow.

Raise letdown flow as required to compensate for higher charging flow.

Ensure 1NV-137A (U1 NC Filter Otlt To VCT 3-Way Diversion Cntrl) diverts to the RHT as required.

BOP (Step 20) WHEN emergency boration no longer required, THEN EP/1/A/5000/ES-0.1, REACTOR TRIP RESPONSE Examiner NOTE:

Examiners following the CRS/RO continue HERE.

RO (Step 13.B-D) Stop any dilutions in progress.

Check all NC TColds GREATER THAN 540°F.

IF AT ANY TIME any NC TCold goes NOTE: This is a Continuous below 540°F, THEN perform Step 13.C. Action. The CRS will make the RO aware.

RO/ (Step 14) Check Pzr level control:

BOP

Check VI pressure GREATER THAN 60 PSIG.

Pzr level GREATER THAN 17%.

Check charging and letdown IN SERVICE.

Check Pzr level trending to program NOTE: The RO or BOP may "PZR LEVEL SETPOINT". adjust Letdown flow as needed.

RO/ (Step 15) Check Pzr pressure GREATER BOP THAN 1845 PSIG.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 51 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments RO (Step 16) Check NC loop flow instruments on NOTE: The 1B NC Pump is 1MC5 ALL LOOPS INDICATING OFF.

GREATER THAN 90% FLOW.

RO/ (Step 16 RNO) Perform the following:

BOP

IF 1A OR 1B NC pump is off, THEN place Pzr spray valve in manual and CLOSE for stopped NC Pump.

IF loss of offsite power has occurred, THEN.

NOTE The following enclosure will place Outside Air Pressure Filter train in service to pressurize the Control Room. This is a 30 minute time critical action to minimize Control Room dose if NC pump locked rotor event has occurred.

Place Outside Air Pressure Filter train in NOTE: The BOP may go to service PER Enclosure 7 (Control Room perform Enclosure 7 but will Pressurization). return when the LOP occurs and ECA-0.0 is entered.

RO/ (Step 17) Check Pzr pressure STABLE AT BOP OR TRENDING TO 2235 PSIG.

RO (Step 18) Control S/G levels as follows:

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

THROTTLE feed flow to maintain S/G N/R levels between 11% and 50%.

Booth Operator Instructions: Insert MAL_EP002A AND EP002B =

Insert MAL_DG001A = TRUE Indications Available:

Control Room lights dim.

1A EDG does NOT start as required.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 52 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments NOTE: The CRS will transition to ECA-0.0.

EP/1/A/5000/ECA-0.0, LOSS OF ALL AC POWER NOTE: Crew will carry out Immediate Actions of ECA-0.0, prior to the CRS addressing the EP.

CRS (Step 1) CSF Status trees should be monitored for information only. EPs referenced by them should not be implemented.

RO (Step 2) Check Reactor Trip: IMMEDIATE ACTION

All rod bottom lights - LIT NOTE: DRPI is NOT available on the LOOP.

Reactor trip and bypass breakers -

OPEN

I/R power - GOING DOWN.

RO (Step 3) Check Turbine Trip: IMMEDIATE ACTION

All throttle valves - CLOSED.

CRS (Step 4) Establish NC pump seal injection from the SSF as follows:

CRS

Immediately dispatch operator to SSF to NOTE: The CRS will perform the following: dispatch an AO to complete Enclosure 2.

Floor/Booth Instructor acknowledge as appropriate, after ten minutes insert ECA-0.0 (Enclosure 2 SSF Actions) and report that Enclosure 2 is complete.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 53 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments

Obtain Brown Folder at SSF and complete Enclosure 2 (Unit 1 SSF -

ECA-0.0 Actions).

NOTE The fastest pathway to 1ETA room is to emergency egress into the aux bldg from the Unit 1 MG set room.

CRS

Dispatch operator to 1ETA room as follows:

Check if operator will enter aux bldg

- FROM MG SET ROOM.

Give operator dosimeter from Unit 2 SRO desk.

CRS

Dispatch operator to perform NOTE: The CRS will Enclosure 3 (Unit 1 ETA And ETB dispatch an AO to complete Rooms - ECA-0.0 Actions). Enclosure 3.

If so, Floor/Booth Instructor acknowledge as appropriate.

Booth Instructor: wait 3 minutes, then insert ECA-0.0 ENCLOSURE 3, then report that Enclosure 3 is complete.

CRS

Use any of the following to notify security NOTE: The CRS will to immediately dispatch officer with key dispatch a Security Officer to SSF to ensure operator can access to the SSF.

SSF: Booth Instructor:

Acknowledge as Security.

Security ringdown phone (located on Unit 2 SRO desk)

1941 (Same line as ringdown phone)

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 54 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments

4900. Floor Instructor: If asked, U2 does NOT have normal power, and both DGs are running.

RO/ (Step 5) Monitor Foldout Page BOP Alternate Low Pressure Feedwater (applies after Step 8 in body of the procedure)

Loss of Vital Instrumentation or Control Power Low Decay Heat Temperature Control CA Suction Sources (applies after Step 15 in body of the procedure)

BOP (Step 6) Check NC System - ISOLATED:

BOP

Check the following letdown orifice isolation valves - CLOSED.

1NV-458A (U1 75 GPM L/D Orifice Outlet Cont Isol).

1NV-457A (U1 45 GPM L/D Orifice Outlet Cont Isol).

1NV-35A (U1 Variable L/D Orifice Outlet Cont Isol).

BOP

CLOSE the following valves:

1NV-1A (U1 NC L/D Isol To Regenerative Hx)

1NV-2A (U1 NC L/D Isol To Regenerative Hx).

BOP

Check Pzr PORVs - CLOSED.

BOP

Check the following excess letdown isolation valves - CLOSED:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 55 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments

1NV-24B (1C NC Loop To Excess L/D Hx Isol)

1NV-25B (1C NC Loop To Excess L/D Hx Isol).

BOP

Check 1NV-121 (U1 ND Letdown Control) - CLOSED.

RO (Step 7) Check total CA flow - GREATER THAN 450 GPM.

RO (Step 7 RNO) Perform the following:

Ensure TD CA pump on.

CRS

IF flow is less than 450 GPM due to operator action to control CA flow, THEN GO TO Step 8.

Control Steam Generator Water Levels during the Station Blackout such that no Steam Generator Overfill Condition occurs (0.8 on Void Fraction SGINFO.cts) and causes Water to Enter the Steam Lines.

Safety Significance: During the Station Blackout the only source of CA flow is the TDCA Pump. If the critical task is not performed and one or more SGs are allowed to overfill, water will enter the steam line and potentially damage the only available source for CA flow (i.e. the TDCA Pump).

BOP (Step 8) Try to restore power to 1ETA or 1ETB as follows:

Check both D/Gs - RUNNING.

BOP (Step 8.A RNO) Perform the following:

Initiate S/I

Notify Unit 2 to immediately perform NOTE: The CRS will notify Enclosure 5 (Unit 2 Actions) (enclosure U2.

ensures 2B RN pump has suction Floor Instructor:

flowpath, which may have isolated on S/I Acknowledge as U2 RO.

signal).

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 56 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments CRS

IF at least one D/G starts, THEN NOTE: The 1B D/G is OOS, and the 1A D/G will NOT start.

CRS

GO TO Step 9 RO/ (Step 9) Stabilize S/G pressures using SM NOTE: The 1C S/G PORV PORVs as follows: has previously failed and is BOP isolated; while the 1D S/G PORV is OOS.

Reset Main Steam Isolation.

Reset SM PORVs.

CLOSE all SM PORV manual loaders.

Place SM PORVs in manual.

Control S/G pressures at 1000 PSIG.

CRS (Step 10) Ensure the following have been NOTE: The CRS may ask implemented: SM to address.

If so, Floor Instructor acknowledge as SM.

RP/0/A/5700/000 (Classification of Emergency)

RP/0/A/5700/010 (NRC Immediate Notification Requirements).

RO/ (Step 11) Control intact S/G levels as follows:

BOP

Check N/R level in any intact S/G -

GREATER THAN 11% (32% ACC).

THROTTLE CA control valves to maintain all intact S/G N/R levels between 11% (32% ACC) and 50%.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 57 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments NOTE If normal VI supply is lost, the Blackout Header FLEX Air Tank should automatically maintain normal control of CA flow. 1EVDA and 1EVDD are also required for TD CA control valves to work, unless TD CA solenoid valves are bypassed.

IF AT ANY TIME CA flow control is lost, NOTE: This is a Continuous THEN perform RNO for Step 11.B. Action. The CRS will make one or more board operators aware.

CRS (Step 12) Ensure Unit 2 performs Enclosure NOTE: The CRS will ask 5 (Unit 2 Actions). U2 to address.

If so, Floor Instructor acknowledge as U2 BOP.

RO (Step 13) Check Unit 1 status IN MODE 3.

NOTE If operating train of VC/YC has failed, it is time critical to swap operating VC/YC trains.

BOP (Step 14) Ensure VC/YC cooling available as follows:

Check VC/YC alignment using Unit 1 status board AT LEAST ONE OPERABLE VC/YC TRAIN ALIGNED TO AN ENERGIZED UNIT 2 4160V BUS.

Notify an available operator to initiate NOTE: The CRS may EP/1/A/5000/G1 (Generic Enclosures), assign the BOP to perform Enclosure 13 (VC and VA System this action.

Operation) within 30 minutes of loss of If so, BOP Examiner follow power. actions of Enclosure 13.

Other Examiners follow ECA-0.0 Actions, Step 15, on Page 63.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 58 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments EP/1/A/5000/G-1, GENERIC ENCLOSURES ENCLOSURE 13, VC AND VA OPERATION Examiner NOTE: Follow the actions associated with Enclosure 13 if BOP is assigned by CRS to perform.

BOP (Step 1) Check the following HVAC NOTE: The B Train alarm is annunciator alarms - LIT: LIT.

"VC/YC TRAIN A SAFETY ACTUATION" (0AD-11, G-1)

"VC/YC TRAIN B SAFETY ACTUATION" (0AD-11, G-2).

BOP (Step 1 RNO) Depress VC/YC Safety Actuation "INITIATE" pushbutton(s).

BOP (Step 2) Check the following VC equipment -

ON:

"B CONTROL ROOM AHU" NOTE: The B Train equipment is ON.

"A CONTROL ROOM AHU"

Train selected YC pump.

BOP (Step 2 RNO) Start equipment.

BOP (Step 3) Check train selected Control Room NOTE: The selected Train Area Chiller - ON. is NOT ON.

BOP (Step 3 RNO) Perform the following:

IF the "STOP" pushbutton is depressed NOTE: The STOP on selected train, THEN.. pushbutton on the selected Train is NOT depressed.

IF train selected chiller is off, THEN start opposite train chiller as follows:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 59 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments

Ensure RN pump aligned to desired NOTE: The BOP will direct chiller is running. the Unit 2 BOP to start the 2B RN Pump.

Floor Instructor:

Acknowledge as U2 RO.

Perform one of the following:

IF desired to start A VC/YC chiller, THEN.

OR

IF desired to start B VC/YC chiller, THEN place the "VC/YC TRN B MODE SELECT" switch to "TRN B".

Depress "START" on chiller to be started.

Check chiller starts within 2 minutes.

IF neither chiller can be started, THEN.

Stop undesired train by performing the following:

Depress "STOP" on chiller to be stopped.

WHEN chiller "ON" indication dark, THEN select "OFF" on associated VC/YC mode select switch.

BOP (Step 4) Check the following VC fans - ON:

"B TRAIN CR OUTSIDE AIR PRESS FAN"

"A TRAIN CR OUTSIDE AIR PRESS NOTE: The A Train Fan is FAN". NOT running.

(Step 4 RNO) Start equipment NOTE: The A Train Fan will NOT start.

BOP (Step 5) Check "OPEN" lights on the following dampers - DARK:

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 60 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments

CRA-OAD-4 (CR Area Otsd Air Fans Damper)

CRA-OAD-3 (CR Area Otsd Air Fans NOTE: The CRA-OAD-3 Damper). light is LIT.

BOP (Step 5 RNO) CLOSE dampers.

BOP (Step 6) Check the following fans - OFF.

"#1 CRA OTSD AIR FAN"

"#2 CRA OTSD AIR FAN".

BOP (Step 7) Check the following VC equipment for train selected - ON:

A Train: NOTE: The A Train is NOT selected.

1A SWGR AHU (1ETA Supply)

2A SWGR AHU (2ETA Supply)

1C SWGR AHU (1ETB Supply)

2C SWGR AHU (2ETB Supply)

"A CR AREA AHU"

"BATT ROOM A EXH FAN".

OR

B Train: NOTE: The B Train is selected.

1B SWGR AHU (1ETA Supply) NOTE: The AHU is NOT ON.

2B SWGR AHU (2ETA Supply)

1D SWGR AHU (1ETB Supply) NOTE: The AHU is NOT ON.

2D SWGR AHU (2ETB Supply)

"B CR AREA AHU"

"BATT ROOM B EXH FAN".

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 61 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments BOP (Step 7 RNO) Perform the following:

Start equipment on train selected.

IF SWGR AHU or CR Area AHU is not available on selected train, THEN evaluate swapping VC trains PER OP/0/A/6450/011 (Control Area Ventilation/Chilled Water System),

Enclosure 4.2 (Operational Alignment Change of VC/YC System) (copy of procedure located in satellite file in VC/YC chiller area).

IF battery room exhaust fan is off on selected train, THEN..

IF switchgear room cooling is not NOTE: The BOP will available, THEN contact station contact Station management to evaluate opening the Management.

following essential 4160 V switchgear Floor Instructor:

room doors to establish cooling: Acknowledge as Station Management and indicate that they will evaluate.

Auxiliary Bldg Doors

Turbine Bldg Doors.

BOP (Step 8) Check the following AHUs - ON: NOTE: All AHUs are OFF.

1B NS AHU

1B ND AHU

1B KF AHU

1A NS AHU

1A ND AHU

1A KF AHU.

BOP (Step 8 RNO) IF S/I has occurred, THEN start AHUs.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 62 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments BOP (Step 9) Ensure VA filter units remain in filter mode as follows:

Place the following switches in "TEST":

"1B VA FILTER UNITS TEST"

"1A VA FILTER UNITS TEST"

"2B VA FILTER UNITS TEST"

"2A VA FILTER UNITS TEST".

Check the following - CLOSED:

1ABF-D-3 (1B VA Filter Exh Bypass Damper) - CLOSED

1ABF-D-3 (1A VA Filter Exh Bypass Damper) - CLOSED

2ABF-D-3 (2B VA Filter Exh Bypass Damper) - CLOSED

2ABF-D-3 (2A VA Filter Exh Bypass Damper) - CLOSED.

BOP (Step 9.b RNO) Notify station management NOTE: The BOP will to evaluate PER "Evaluations by Station contact Station Management in the TSC, Volume 1" (section Management.

titled "Generic Enclosure (G-1) Specified Floor Instructor:

Actions"). Acknowledge as Station Management and indicate that they will evaluate.

BOP (Step 10) Restart the following EMF Sample Blowers as required:

EMF 41 (Aux Bldg Ventilation) EMF-43A (Control Room Air Intake Loc A)

1EMF-35, 36, 37 (Unit Vent Particulate, Gas, Iodine)

1EMF-42 (Fuel Bldg Ventilation)

EMF-43B (Control Room Air Intake Loc B).

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 63 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments BOP (Step 11) WHEN time and manpower allow, NOTE: The BOP will inform THEN dispatch operator to ensure VA the CRS of this step.

System remains in proper alignment.

EP/1/A/5000/ECA-0.0, LOSS OF ALL AC POWER Examiner NOTE:

Examiners following the CRS/RO continue HERE.

RO (Step 15) Monitor CA Storage Tank (water tower) level and ensure CA suction source as follows:

Check if external event that has the NOTE: The CRS may ask potential to damage CA Storage Tank the OSM to evaluate.

(water tower) (such as seismic or If so, Floor Instructor:

tornado) - HAS OCCURRED.

Acknowledge and indicate that no such event has occurred.

CRS (Step 15.A RNO) Observe Note prior to Step 15.C and GO TO Step 15.C.

NOTE Control Room indication of CA Storage Tank (water tower) level should be used if available. It will be lost when aux control power is lost or if instrument damaged by external event. If operator is dispatched for periodic local monitoring, he can be used for other tasks.

(Step 15.C-E) Monitor CA Storage Tank (water tower) level using available Control Room indication.

IF AT ANY TIME CA Storage Tank NOTE: This is a Continuous (water tower) level indication is lost Action. The CRS will make (invalid reading), THEN dispatch one or more board operators operator to locally monitor level PER aware.

EP/1/A/5000/G-1 (Generic Enclosures),

Enclosure 31 (Local CA Storage Tank (Water Tower) Level Monitoring).

Ensure CA Suction Sources is monitored on Foldout Page.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 64 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments CRS (Step 16) Check for plant damage as follows:

Check if event that could have caused NOTE: No such event has damage to mechanical systems internal occurred.

to plant (seismic, tornado, etc) - HAS OCCURRED.

CRS (Step 16 RNO) GO TO Step 17.

RO (Step 17) Check if S/I is actuated as follows: NOTE: SI was actuated in an attempt to start the 1A D/G.

"SAFETY INJECTION ACTUATED" status light (1SI18) LIT.

Reset S/I.

CRS (Step 18) Dispatch operator to open the NOTE: The CRS will following breakers to sequencer DC control dispatch an AO.

power:

Booth Instructor acknowledge as appropriate, after three minutes insert MAL_EQB002A and EQB002B = FAILURE and report that the Sequencer DC Control Breakers have been opened.

A Train 1EVDA Breaker 6

B Train 1EVDD Breaker 8.

CRS (Step 19) IF AT ANY TIME operator NOTE: This is a Continuous dispatched to perform Enclosure 3 (Unit 1 Action. The CRS will make ETA And ETB Rooms ECA0.0 Actions) one or more board operators determines that lockout exists, THEN aware.

perform the following:

Have IAE clear or isolate fault from bus.

WHEN fault cleared or isolated from bus, THEN reset lockout.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 65 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments NOTE Consider the following when selecting power restoration options:

If problem with D/G is easily correctable, Enclosure 12 (Energizing Unit 1 4160V Bus With 1A OR 1B D/G) may restore power the quickest.

If Unit 2 6900V busses are energized, Enclosure 13 (Energizing Unit 1 4160V Bus From Unit 2 - SATA or SATB) can be performed within an hour and should be the preferred option.

If cause of loss of Unit 1 offsite power is known, and grid available, Enclosure 14 (Energizing Unit 1 4160V Bus From Unit 1) may be preferred, but could take 2-3 hours.

EPSP can restore one essential bus within an hour, but complicates restoration of offsite power later in the event. If ESPS is being used on Unit 2, it shall not be used on Unit 1.

CRS (Step 20) Restore power to 1ETA or 1ETB NOTE: The CRS may using any of the following while continuing dispatch an AO to evaluate with this procedure: lockouts on 1ETA and 1ETB.

Booth Instructor acknowledge as appropriate, after two minutes report that there are no Lockouts on 1ETA but that Lockouts do exist on 1ETB.

Local reset and start of 1A or 1B D/G PER Enclosure 12 (Energizing Unit 1 4160V Bus With 1A or 1B D/G)

OR

Unit 2 6900V busses through SATA or NOTE: This is the only SATB PER Enclosure 13 (Energizing Unit option for re-powering either 1 4160V Bus From Unit 2 SATA or 1ETA or 1ETB.

SATB).

OR

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 66 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments

Unit 1 offsite power PER Enclosure 14 (Energizing Unit 1 4160V Bus From Unit 1)

OR

ESPS PER Enclosure 65 (Energizing Unit 1 4160V Bus With ESPS).

NOTE: The CRS will address Enclosure 13.

EP/1/A/5000/ECA-0.0, LOSS OF ALL AC POWER ENCLOSURE 13, ENERGIZING UNIT 1 4160V BUS FROM UNIT 2 - SATA OR SATB NOTE

Unit 2 6900V bus 2TB must already be energized for this enclosure to restore power to 1ETB.

Unit 2 6900V bus 2TC must already be energized for this enclosure to restore power to 1ETA.

Available equipment on 1ETA or 1ETB bus should be considered when choosing bus to energize.

CRS (Step 1) Perform one of the following: NOTE: The CRS may dispatch an AO to evaluate lockouts on 1ETA and 1ETB.

Booth Instructor acknowledge as appropriate, after two minutes report that there are no Lockouts on 1ETA but that Lockouts do exist on 1ETB.

IF 1ETA is to be energized from Unit 2, THEN observe Note prior to Step 18 and GO TO Step 18.

OR

IF 1ETB is to be energized from Unit 2, THEN observe Note prior to Step 2 and GO TO Step 2.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 67 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments NOTE Steps 18 through 32 will align power from Unit 2 2TC through SATA to Unit 1 1ETA.

(Step 18) Have Unit 2 RO check 2ETA NOTE: The CRS/BOP will Standby Breaker control switch - DARK. ask U2 to address.

If so, Floor Instructor acknowledge as U2 BOP, and report that 2ETA Standby Breaker control switch - DARK.

NOTE Either the 1ETA Normal or 1ETA Standby Breaker control switch will be dark, indicating that it is racked out and open.

RO/ (Step 19) Check the following 4160V BOP breakers OPEN.

1ETA Normal Breaker

1ETA Standby Breaker

1ETA Emergency Breaker.

RO/ (Step 20) Ensure breakers are racked in as BOP required to power 1ETA from Unit 2 2TC (via SATA) as follows:

Check 1ETA Normal Breaker control switch - LIT (indicates that breaker is racked in).

Dispatch operator to perform Enclosure NOTE: The CRS will 68 (Shifting 1ETA from Normal (1ATC) to dispatch an AO to complete Standby (SATA)). Enclosure 68.

Booth Instructor acknowledge as appropriate, after two minutes insert LOA_EP134=RACKOUT and LOA_EP136=RACKIN and report that Enclosure 68 is complete.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 68 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments

Check Unit 1 SATA Feeder Breaker control switch - LIT (indicates that breaker is racked in).

OPEN Unit 1 SATA Feeder Breaker.

NOTE If enclosure was initiated in Step 20.B, then enclosures in Steps 20.B and 20.E can be performed concurrently.

Dispatch operator to perform Enclosure NOTE: The CRS will 72 (Shifting SATA from 1TC to Unit 2 dispatch an AO to complete 2TC). Enclosure 72.

Booth Instructor acknowledge as appropriate, after two minutes report that Enclosure 72 is complete (No Field Action is required).

CRS (Step 21) Do not continue until the following is performed:

Ensure Steps 18 through 20 are completed.

Ensure operators are away from breakers.

CRS (Step 22) Have Unit 2 RO check Unit 2 SATA NOTE: The CRS will ask Feeder Breaker CLOSED. U2 to address.

If so, Floor Instructor acknowledge as U2 BOP, and report that Unit 2 SATA Feeder Breaker is CLOSED.

RO/ (Step 23) Check if S/I is actuated as follows:

BOP

"SAFETY INJECTION ACTUATED" NOTE: SI was previously status light (1SI18) LIT. reset.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 69 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments CRS (Step 23.A RNO) GO TO Step 24.

CRS (Step 24) Check "SEQ A LOSS OF CONTROL PWR" alarm (1AD11, B2)

LIT.

RO/ (Step 25) Open 1A CA pump breaker.

BOP RO/ (Step 25 RNO) Open breaker by depressing BOP 1A CA pump "START" and "STOP" at same time.

RO/ (Step 26) Open the remaining pump BOP breakers:

1A NV pump

1A ND pump

1A NI pump

1A1 KC pump

1A2 KC pump

1A RN pump

1A KF pump

1A NS pump RO/ (Step 27) Open the following 600 V essential BOP load center feeder breakers:

1ELXA

1ELXC

1ELXE RO/ (Step 28) Check 1A D/G Mode Select switch BOP IN CONTROL ROOM POSITION.

Appendix D Operator Action Form ES-D-2 Op Test No.: N20-1 Scenario # 3 Event # 6, 7 & 8 Page 70 of 71 Event

Description:

1 Seal Leak on 1B NCP Degrades/4 Control Rods fail to Fully Insert on Rx Trip/ Loss of Switchyard to Unit 1/1A EDG fails to START Time Pos. Expected Actions/Behavior Comments RO/ (Step 28 RNO) Place 1A D/G Mode Select BOP switch to Control Room position.

RO/ (Step 29) Close 1ETA Standby Breaker.

BOP RO/ (Step 30) Place 1A D/G Mode Select switch BOP to "AUTO" position.

RO/ (Step 31) Check 1ETA bus ENERGIZED.

BOP RO/ (Step 32) Notify Control Room Supervisor to BOP GO TO Step 47 in body of this procedure.

Control Steam Generator Water Levels during the Station Blackout such that no Steam Generator Overfill Condition occurs (0.8 on Void Fraction SGINFO.cts) and causes Water to Enter the Steam Lines.

Safety Significance: During the Station Blackout the only source of CA flow is the TDCA Pump. If the critical task is not performed and one or more SGs are allowed to overfill, water will enter the steam line and potentially damage the only available source for CA flow (i.e. the TDCA Pump).

At the discretion of the Lead Examiner terminate the exam.

UNIT 1 STATUS:

Power Level: 36% NCS [B] 1888 ppm Pzr [B]: 1884 ppm Xe: Per OAC Power History: At this power level for 20 days Core Burnup: 25.1 EFPDs UNIT 2 STATUS:

Power Level: 100%

CONTROLLING PROCEDURE:

OP/1/A/6100/003 (Controlling Procedure for Unit Operation)

OTHER INFORMATION NEEDED TO ASSUME THE SHIFT:

The area has experienced snow and freezing rain for the last 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and this is expected to continue for the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The following equipment is Out-Of-Service:

The 1B EDG is OOS for bearing replacement. ACTION has been taken in accordance with Technical Specification LCO 3.8.1 ACTION B.

The 1D S/G PORV is isolated and its actuator is currently removed for maintenance.

1KFP-5130, Spent Fuel Pool Temperature, failed last shift (IAE is investigating).

MCB Annunciator 1AD-9, A-7, NF SYSTEM TRACE HEATING LOSS OF POWER, has alarmed spuriously several times over the last hour (IAE is investigating).

Crew Directions:

The crew will raise power to 100% on this shift, starting with Step 3.35.12 of Enclosure 4.1 of OP/1/A/6100/003 Controlling Procedure for Unit Operation.

The loading rate will be 3 MWe/minute.

The RE recommends 100% Control Rod position of 215 steps on Control Bank D.

RE has recommended a 300-gallon initial dilution using Enclosure 4.4 (Alternate Dilute) of OP/1/A/6150/009 (Boron Concentration Control).

RMWST Dissolved O2 is less than 1000 ppb.

Blender content is Reactor Makeup Water.

Work Control SRO Jim Field SRO Joe (FB)

AO's AVAILABLE Unit 1 Unit 2 Aux Bldg. John Aux Bldg. Chris Turb Bldg. Bob (FB) Turb Bldg. Mike (FB)

Extra(s) Bill (FB) Ed (FB) Gus (RW) Carol

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIM JPM A 2020 Systems - Control Room JPM A (Rev_011320) NUREG 1021, Revision 11

Appendix C Page 2 of 11 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Restoring Charging Flow with Hot JPM No.: 2020 Systems - Control NC Pump Seals Room JPM A (Alternate Path)

K/A

Reference:

APE 022 AA1.04 (3.3/3.2)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

Initial Conditions:

Unit 1 was at 100% power when the 1A NV Pump tripped on overcurrent.

The 1B NV Pump was Out-Of-Service for maintenance.

The crew entered AP/1/A/5500/12, Loss of Letdown, Charging or Seal Injection, and tripped the reactor on high bearing temperatures on the 1A NC Pump.

The crew entered EP/1/A/5000/E-0, Reactor Trip or Safety Injection, and transitioned to EP/1/A/5000/ES-0.1, Reactor Trip Response.

Maintenance has returned 1B NV pump to Operations and all clearances have been restored.

The crew has returned to AP/1/A/5500/12, Loss of Letdown, Charging or Seal Injection, to restore charging flow.

All NC Pump lower bearing temperature are greater than 225°F.

2020 Systems - Control Room JPM A NUREG 1021, Revision 11

Appendix C Page 3 of 11 Form ES-C-1 Job Performance Measure Worksheet Initiating Cue: The CRS has directed you to perform Enclosure 4 (Restoring Charging Flow With Hot NC Pump Seals) of AP/1/A/5500/12, Loss of Letdown, Charging or Seal Injection, and establish approximately 50 gpm charging flow.

Task Standard: The operator will isolate the NC Pumps seals, attempt to start the 1B NV Pump to re-establish Charging Flow, then start the PD Pump when the 1B NV Pump fails to start and complete the restoration of approximately 50 gpm charging flow per Enclosure 4 of AP/1/A/5500/12.

Required Materials: None General

References:

EP/1/A/5000/E-0 (Reactor Trip or Safety Injection), Rev 36 EP/1/A/5000/ES-0.1 (Reactor Trip Response), Rev 47 AP/1/A/5500/12 (Loss of Letdown, Charging or Seal Injection), Rev 24 OMP 4-3 (Use of Emergency and Abnormal Procedures and FLEX Support Guidelines), Rev 48 Handouts: Handout 1: Blank copy of Enclosure 4 (Restoring Charging Flow With Hot NC Pump Seals) of AP/1/A/5500/12, Loss of Letdown, Charging or Seal Injection.

Time Critical Task: NO Validation Time: 15 minutes 2020 Systems - Control Room JPM A NUREG 1021, Revision 11

Appendix C Page 4 of 11 Form ES-C-1 Job Performance Measure Worksheet Critical Step Justification Step 1 This step is critical because initially isolating sealwater flow to the NC Pumps is necessary to complete the restoration of charging flow per Enclosure 4 of AP/1/A/5500/12.

Step 2 This step is critical because sealwater flow to the NC Pumps must be isolated before action is taken to re-establish charging flow to the NC Pumps per Enclosure 4 of AP/1/A/5500/12.

Step 3 This step is critical because pressing the 1B NV Lube Oil Pump MAN pushbutton (White PB) and then pressing the START pushbutton is necessary to start the 1B NV Pump to re-establish Charging Flow.

Step 4 This step is critical because depressing the 1B NV Start pushbutton is necessary to start the 1B NV Pump to re-establish Charging Flow.

Alternate Path Critical Step Justification Step 7 This step is critical because depressing the 1RN-64A OPEN pushbutton is necessary to start the PD Pump to complete the restoration of charging flow per Enclosure 4 of AP/1/A/5500/12.

Step 8 This step is critical because selecting the SLIMS output to be displayed on the PD Pump SLIMS and using the DOWN arrow to adjust the SLIMS Output to 0% is necessary to start the PD Pump to complete the restoration of charging flow per Enclosure 4 of AP/1/A/5500/12.

Step 10 This step is critical because depresses the PD Pump START pushbutton is necessary to start the PD Pump to complete the restoration of charging flow per Enclosure 4 of AP/1/A/5500/12.

Step 14 This step is critical because using the UP arrow on the PD Pump SLIMs, over at least a 45 second period is necessary to complete the restoration of 50 gpm charging flow per Enclosure 4 of AP/1/A/5500/12.

2020 Systems - Control Room JPM A NUREG 1021, Revision 11

Appendix C Page 5 of 11 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

1. Reset simulator to IC-21 (100% Power, Any Time in Life).

2. Place in RUN.

3. INSERT MAL_NV029A (NV Pump A Trips Due To Overcurrent).

4. INSERT MAL_NV006B (NV Pump fails to START)

5. Respond in accordance with AP-12 (The goal is to have all four NC Pumps Lower Bearing temperatures rise above 225°F which will require a plant trip. It may be necessary to close the KC flow to the thermal barrier while doing this, but flow should be restored with bearing temperature above setpoint and stable when the IC is snapped.).

6. Ensure that Simulator reflects that AP-12 was performed to some point, E-0 was entered the when the NC Pumps high bearing temperatures occur and the NC Pumps are stopped, ES-0.1 was entered and performed to step 14.c, and AP-12 is now complete through the Step 23 RNO.

7. Insert the following LOAs:

REM_NV0028 EQ 0 (NC Pump 1A Seal Water Manual Control)

REM_NV0044 EQ 0 (NC Pump 1B Seal Water Manual Control)

REM_NV0060 EQ 0 (NC Pump 1C Seal Water Manual Control)

REM_NV0076 EQ 0 (NC Pump 1D Seal Water Manual Control)

8. Freeze the Simulator OR

1. Reset to IC-239 (August, 2019)

2. Momentarily go to RUN to acknowledge Alarms then place Simulator in FREEZE.

3. Leave Simulator in FREEZE until operator is ready to begin.

NOTE: During the performance of this JPM, the simulator operator may need to control CF flow to the SGs.

2020 Systems - Control Room JPM A NUREG 1021, Revision 11

Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT Simulator Instructor NOTE: Leave Simulator in FREEZE until operator is ready to begin.

1 (Step 1) Dispatch operator The operator contacts AO to CLOSE the following and directs that they valves on the NC pump(s) CLOSE 1NV-28.

with hot seals:

1NV-28 (1A NC Pump The operator contacts AO Seal Water Injection and directs that they Throttle) (aux bldg, 733, CLOSE 1NV-44.

VCT hallway at reactor The operator contacts AO bldg wall) and directs that they

1NV-44 (1B NC Pump CLOSE 1NV-60.

Seal Water Injection The operator contacts AO Throttle) (aux bldg, and directs that they 733+2, HH-52, VCT CLOSE 1NV-76.

hallway at reactor bldg wall)

BOOTH OPERATOR:

1NV-60 (1C NC Pump Seal Water Injection As AO acknowledge Throttle) (aux bldg, direction and state Using 733+2, JJ-51, VCT Time Compression, all NC hallway 15 ft southwest Pump Sealwater Injection of BIT) Throttle Valves are

1NV-76 (1D NC Pump CLOSED.

Seal Water Injection Throttle) (aux bldg, 716+14, JJ-51, room 603, 4 ft from reactor building wall).

2 (Step 2) Do not continue The operator ensure that until Step 1 complete. Step 1 is complete and proceeds to Step 3.

2020 Systems - Control Room JPM A NUREG 1021, Revision 11

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

3 (Step 3) Start 1A or 1B NV The operator presses the pump as follows: 1B NV Lube Oil Pump MAN pushbutton (White PB) and (Step 3.a) Start associated then presses the START NV Lube Oil pump. pushbutton observing the Red status light is LIT and the Green status light is OFF.

4 (Step 3.b) Start 1A or 1B The operator depresses the NV pump. 1B NV Pump Start pushbutton and observed Red status remains OFF, and the Green status light is LIT. (Alternate Path)

The operator proceeds to the Step 3RNO.

5 (Step 3RNO a) IF PD pump The operator observes the is available, THEN start PD 1SI-18 SAFETY pump as follows: INJECTION ACTUATED status light is OFF (Or IF SI has occurred OR Equivalent) and recognizes 1ETA is deenergized, that SI has not occurred or THEN. observes that the 1SI-14 LOSS/UNDERVOLTAGE Phase A, B, and C status lights are OFF and recognizes that 1ETA is energized; and proceeds to Step 3RNO b.

6 (Step 3RNO b) Ensure The operator observes the 1RN-42A (AB Non Ess 1RN-42A Red status light Supply Isol) is OPEN. LIT, Green status light OFF.

2020 Systems - Control Room JPM A NUREG 1021, Revision 11

Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

7 (Step 3RNO c) OPEN the The operator depresses the following valves: 1RN-64A OPEN pushbutton

1RN-64A (AB Non Ess and observes Red status Return Isol) light LIT, Green status light OFF.

1RN-63B (AB Non Ess Return Isol).

The operator observes the 1RN-63B Red status light LIT, Green status light OFF.

8 (Step 3RNO d) Ensure PD The operator selects the pump speed controller SLIMS output to be output set to 0%. displayed on the PD Pump SLIMS and uses the DOWN arrow to adjust the SLIMS Output to 0%.

9 (Step 3RNO e) OPEN 1NV- The operator depresses the 1047A (U1 NV PD Pump 1NV-1047A OPEN Recirc Isol). pushbutton and observes Red status light LIT, Green status light OFF.

10 (Step 3RNO f) Start the PD The operator depresses the pump. PD Pump START pushbutton and observes the Red status light LIT, Green status light OFF.

11 (Step 3RNO g) Ensure After two minutes, the 1NV-1047A CLOSES after operator observes that the 2 minutes. 1NV-1047A Green status light is LIT, Red status light is OFF.

12 (Step 4) Check any of the The operator observes the following charging pumps - PD Pump Red status light is ON. LIT, Green status light is

1A NV pump OFF and concludes that the OR PD Pump is running.

1B NV pump OR

PD pump 2020 Systems - Control Room JPM A NUREG 1021, Revision 11

Appendix C Page 9 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 13 (Step 5) Check all four NC The operator recognizes pump seals - ISOLATED that all four valves were PER STEP 1. closed and proceeds to Step 6.

14 (Step 6) Slowly establish The operator uses the UP desired charging flow by arrow on the PD Pump performing one of the SLIMs, over at least a 45 following: second period, and

THROTTLE OPEN observes Charging flow 1NV-238 (U1 Charging (1NVP5630) is rising to 50 Hdr Control) gpm.

OR

WHEN 1NV-1047A (U1 NV PD Pump Recirc Isol) is closed, THEN raise PD pump speed, taking at least 45 seconds to reach desired flow.

15 (Step 7) GO TO Step 37 in The operator informs the the body of this procedure. CRS of required AP12 action.

Cue:

Another operator will continue with this procedure.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Systems - Control Room JPM A NUREG 1021, Revision 11

Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Systems - Control Room JPM A Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Systems - Control Room JPM A NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

Unit 1 was at 100% power when the 1A NV Pump tripped on overcurrent.

The 1B NV Pump was Out-Of-Service for maintenance.

The crew entered AP/1/A/5500/12, Loss of Letdown, Charging or Seal Injection, and tripped the reactor on high bearing temperatures on the 1A NC Pump.

The crew entered EP/1/A/5000/E-0, Reactor Trip or Safety Injection, and transitioned to EP/1/A/5000/ES-0.1, Reactor Trip Response.

Maintenance has returned 1B NV pump to Operations and all clearances have been restored.

The crew has returned to AP/1/A/5500/12, Loss of Letdown, Charging or Seal Injection, to restore charging flow.

All NC Pump lower bearing temperature are greater than 225°F.

INITIATING CUE: The CRS has directed you to perform Enclosure 4 (Restoring Charging Flow With Hot NC Pump Seals) of AP/1/A/5500/12, Loss of Letdown, Charging or Seal Injection, and establish approximately 50 gpm charging flow.

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIM JPM B 2020 Systems - Control Room JPM B (Rev_011520) NUREG 1021, Revision 11

Appendix C Page 2 of 14 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Auxiliary Feedwater Flow Control JPM No.: 2020 Systems - Control with a Loss of Instrument Air Room JPM B (Alternate Path)

K/A

Reference:

APE 065 AA2.07 (2.8/3.2)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

Initial Conditions:

With Unit 1 at 100% power, a seismic event results in a loss of VI and a reactor trip.

The crew is in EP/1/A/5000/ES-0.1, Reactor Trip Response, and continuing with AP/1/A/5500/22, Loss of VI, as time allows.

The crew has just determined that VI Header pressure is less than 85 psig at Step 2 of ES-0.1.

Initiating Cue: The CRS has directed you to perform the ES-0.1 Step 2 RNO to control NC System Cooldown.

Task Standard: The operator will initiate the Step 2 RNO of ES-0.1, determine that all S/G levels are greater than 11% and rising in an uncontrolled manner, then implement Generic Enclosure 16 (CA Flow Control with a Loss of VI) to minimize cooldown and stabilize all Steam Generator levels prior to Steam Generator Narrow Range level in any Steam Generator rising to greater than 92%.

2020 Systems - Control Room JPM B NUREG 1021, Revision 11

Appendix C Page 3 of 14 Form ES-C-1 Job Performance Measure Worksheet Required Materials: None General

References:

EP/1/A/5000/E-0 (Reactor Trip or Safety Injection), Rev 36 EP/1/A/5000/ES-0.1 (Reactor Trip Response), Rev 47 AP/1/A/5500/22 (Loss of VI), Rev 39 EP/1/A/500/G-1 (Generic Enclosures), Rev 41 OMP 4-3 (Use of Emergency and Abnormal Procedures and FLEX Support Guidelines), Rev 48 Handouts: Handout 1: Pages 2-3 of 79 of EP/1/A/5000/ES-0.1 (Reactor Trip Response) marked up for place-keeping through Step 2.

Handout 2: EP/1/A/500/G-1 (Generic Enclosures); Generic Enclosure 16 (CA Flow Control With Loss Of VI).

Time Critical Task: NO Validation Time: 15 minutes Critical Step Justification Step 5 This step is critical because resetting and attempting to control CA flow to the Steam Generators using the CA throttle Valves for both the TDCA and the MDCA Pumps is necessary to determine that SG levels are rising uncontrollably and that Generic Enclosure 16 (CA Flow Control with a Loss of VI) must be implemented.

Step 9 This step is critical because controlling flow from the TDCA Pump into all four Steam Generators is necessary to stabilize all Steam Generator levels prior to Steam Generator Narrow Range level in any Steam Generator rising to greater than 92%.

Step 13 This step is critical because controlling flow from the MD CA Pumps into three of the four Steam Generators is necessary to stabilize all Steam Generator levels prior to Steam Generator Narrow Range level in any Steam Generator rising to greater than 92%.

Alternate Path Critical Step Justification Step 16 This step is critical because dispatching an AO to control flow from the MD CA Pump into 1D Steam Generator is necessary to stabilize the 1D Steam Generator level prior to Narrow Range level rising to greater than 92%.

2020 Systems - Control Room JPM B NUREG 1021, Revision 11

Appendix C Page 4 of 14 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

1. Reset simulator to IC-39 (100% power, Any Time In Life).

2. Place in RUN.

3. Insert MAL-VI001B (INSTR AIR SYS LEAK:AUX-A ESS HDR) and VI001C (INSTR AIR SYS LEAK:AUX-B ESS HDR) [The goal is to have a loss of VI such that a reactor trip is required by AP-22].

4. Create a Scenario Manger File N20 JPM B.sce as follows:

Insert LOA_VI108 0.0 Ramp = 0, Delay = 5 Seconds

Insert LOA_VI109 0.0 Ramp = 8, Delay = 5 Seconds

Label CPJEM1A0001INP 0 (OAC Point)

Insert REM-CA0042B = 1 (1CA-42B [1B CA Pump Disch To 1D S/G Isol] will not move from position from the Control Room)

5. RUN Scenario Manger File N20 JPM B.sce

6. Perform AP-22 through Step 14 RNO.

7. Perform E-0 and ES-0.1 such that all CA Control valves are open delivering flow to all four Steam Generators such that Narrow Range Level for all S/Gs are greater than 11% and rising uncontrollably.

8. Freeze the Simulator OR

1. Reset to IC-240 (August, 2019)

2. RUN Scenario Manager File N20 JPM B.sce

3. Momentarily go to RUN to acknowledge Alarms then place Simulator in FREEZE.

4. Leave Simulator in FREEZE until operator is ready to begin.

NOTE: During the performance of this JPM, the simulator operator may need to control all plant alarms and processes not associated with the control of CA flow and Steam Generator Narrow Range Levels.

2020 Systems - Control Room JPM B NUREG 1021, Revision 11

Appendix C Page 5 of 14 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT Simulator Instructor NOTE: Leave Simulator in FREEZE until operator is ready to begin.

1 (ES-0.1, Step 2RNO) The operator observes Perform the following: voltage on the 6900V Busses (Or Equivalent) and determines that a loss of (ES-0.1, Step 2RNO A) IF offsite power has NOT loss of offsite power has occurred, and proceeds.

occurred, THEN 2 (ES-0.1, Step 2RNO B) IF The operator observes VI AT ANY TIME VI pressure pressure on 1MC13 to be is less than 60 PSIG, THEN less than 60 psig (35 psig).

CLOSE the following The operator observes valves: Green status lights are LIT

All MSIVs Red status lights are OFF

All MSIV Bypass for all four MSIVs.

Valves.

The operator observes all four MSIVs Bypass valves are closed using the OAC.

3 (ES-0.1, Step 2RNO C) IF The operator reads the CA control valves cannot be Continuous Action Step and throttled in subsequent proceeds.

steps, THEN control flow PER EP/1/A/5000/G-1 (Generic Enclosures),

Enclosure 16 (CA Flow Control With Loss Of VI).

4 (ES-0.1, Step 2RNO D) IF The operator observes all S/G N/R level is less than four S/G Narrow Range 11% in all S/Gs, THEN.. levels and determines that all levels are NOT less than 11% and proceeds.

2020 Systems - Control Room JPM B NUREG 1021, Revision 11

Appendix C Page 6 of 14 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

5 (ES-0.1, Step 2RNO E) The operator observes all WHEN N/R level is greater four S/G Narrow Range than 11% in at least one levels and determines that S/G, THEN THROTTLE level is greater than 11% in feed flow further to achieve at least one S/G.

the following:

The operator will reset and

Minimize cooldown attempt to control CA flow

Maintain at least one to the Steam Generators S/G N/R level greater using the CA throttle Valves than 11%. for both the TDCA and the MDCA Pumps and determine that these valves have failed OPEN.

NOTE:

The operator may attempt to regain control of these valves throughout the JPM.

The operator addresses Generic Enclosure 16.

NOTE:

When the operator locates Generic Enclosure 16, PROVIDE the operator with Handout 2.

2020 Systems - Control Room JPM B NUREG 1021, Revision 11

Appendix C Page 7 of 14 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6 (Generic Enclosure 16, The operator reads the NOTE prior to Step 1) This Note and proceeds.

enclosure may be required if the Unit 1 VI Blackout Header FLEX Air Tank is not providing adequate air supply or if control of CA valves is lost for any other reason such as loss of vital DC control power (1EVDA or 1EVDD). The Unit 1 VI Blackout Header FLEX Air Tank should provide air for CA control valves for 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months if normal VI supply is lost.

7 (Step 1) Continue to use The operator reads the any normal CA flow control Continuous Action Step and valve that works instead of proceeds.

associated S/G motor operator isolation valve.

8 (Step 2) Check TD CA The operator observes flow pump - ON. from the TDCA Pump into all four Steam Generators (Or Equivalent) and determines that the TD CA Pump is ON.

2020 Systems - Control Room JPM B NUREG 1021, Revision 11

Appendix C Page 8 of 14 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

9 (Step 3) Control TD CA The operator presses the pump flow by operating the 1CA-66AC CLOSE following TD CA pump to pushbutton and observes S/G motor operated the Green status light is LIT, isolation valves as required: and the Red status light is

1CA-66AC (U1 TD CA OFF.

Pump Disch To 1A S/G Isol) The operator presses the

1CA-54AC (U1 TD CA 1CA-54AC CLOSE Pump Disch To 1B S/G pushbutton and observes Isol) the Green status light is LIT, and the Red status light is

1CA-50B (U1 TD CA OFF.

Pump Disch To 1C S/G Isol) The operator presses the 1CA-50B CLOSE

1CA-38B (U1 TD CA pushbutton and observes Pump Disch To 1D S/G the Green status light is LIT, Isol).

and the Red status light is OFF.

The operator presses the 1CA-38B CLOSE pushbutton and observes the Green status light is LIT, and the Red status light is OFF.

10 (Step 4) Check 1A or 1B CA The operator observes flow pump - ON. from the 1A and 1B MD CA Pump into all four Steam Generators (Or Equivalent) and determines that both MD CA Pumps are ON.

11 (Note prior to Step 5) At The operator reads the S/G pressures less than Note and proceeds.

600 PSIG, only one S/G is fed at a time from each MD CA pump through an unthrottled discharge path, to ensure adequate margin to pump runout and overcurrent trip setpoint.

2020 Systems - Control Room JPM B NUREG 1021, Revision 11

Appendix C Page 9 of 14 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 12 (Step 5) IF AT ANY TIME The operator observes S/G S/G pressure is less than pressure to be greater than 600 PSIG, THEN perform 600 psig.

the following:

The operator reads the

Only feed one S/G at a Continuous Action Step and time from each MD CA proceeds.

pump until flow is throttled in subsequent steps.

Ensure each MD CA pump flow is maintained less than 600 GPM.

2020 Systems - Control Room JPM B NUREG 1021, Revision 11

Appendix C Page 10 of 14 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

13 (Step 6) Control MD CA The operator presses the pump flow by operating the 1CA-62A CLOSE following CA to S/G motor pushbutton and observes operated isolation valves as the Green status light is LIT, required: and the Red status light is OFF.

1A CA pump:

1CA-62A (1A CA Pump The operator presses the Disch To 1A S/G Isol) 1CA-58A CLOSE

1CA-58A (1A CA Pump pushbutton and observes Disch To 1B S/G Isol). the Green status light is LIT, 1B CA pump: and the Red status light is OFF.

1CA-46B (1B CA Pump Disch To 1C S/G Isol) The operator presses the 1CA-46B CLOSE

1CA-42B (1B CA Pump pushbutton and observes Disch To 1D S/G Isol).

the Green status light is LIT, and the Red status light is OFF.

The operator presses the 1CA-42B CLOSE pushbutton and observes the Red status light remains LIT, and the Green status light remains OFF.

NOTE:

When the operator attempts to close 1CA-42B the valve will not move from position.

(Alternate Path)

The operator will recognize that 1CA-42B cannot be controlled from the MCB and proceed to the RNO.

2020 Systems - Control Room JPM B NUREG 1021, Revision 11

Appendix C Page 11 of 14 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 14 (Step 6 RNO A) Control MD The operator recognizes CA pump flow as follows: that the motor operator IF any of the CA to S/G isolation valves for all CA motor operator isolation flow loops with the valves OR air operated exception of the MD CA control valves work, THEN Pump to the 1D Steam continue to control that S/G Generator are operating level from the Control and proceeds with the Room. RNO.

15 (Note prior to Step 6 RNO The operator reads the B) Valves take 20-22 turns Note and proceeds.

to stroke. Most of the throttling occurs in the first 4 turns from closed seat.

2020 Systems - Control Room JPM B NUREG 1021, Revision 11

Appendix C Page 12 of 14 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

16 (Step 6 RNO B) Dispatch The operator contacts an operator to unlock and AO to unlock and THROTTLE the following THROTTLE 1CA-39 valve(s) on just the S/G(s) that flow cannot be controlled from the Control BOOTH OPERATOR:

Room:

Close 1CA-39 using REM-1D S/G: 1CA-39 (1B CA CA0039 and report that Pump Disch To 1D S/G the valve has been Control Inlet Isol) (Unit 1 CA closed.

pump rm, 716+12, CC-50, 6 ft north of 1B CA Pump near reactor bldg wall).

The operator determines that all four Steam Generator Narrow Range levels are under control between 11-92%.

NOTE:

The operator will continue with Enclosure 16 until feedback is provided from the AO.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Systems - Control Room JPM B NUREG 1021, Revision 11

Appendix C Page 13 of 14 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Systems - Control Room JPM B Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Systems - Control Room JPM B NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

With Unit 1 at 100% power, a seismic event results in a loss of VI and a reactor trip.

The crew is in EP/1/A/5000/ES-0.1, Reactor Trip Response, and continuing with AP/1/A/5500/22, Loss of VI, as time allows.

The crew has just determined that VI Header pressure is less than 85 psig at Step 2 of ES-0.1.

INITIATING CUE: The CRS has directed you to perform the ES-0.1 Step 2 RNO to control NC System Cooldown.

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIM JPM C 2020 Systems - Control Room JPM C (Rev_011520) NUREG 1021, Revision 11

Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

CA Suction Source Realignment JPM No.: 2020 Systems - Control Room JPM C (Alternate Path)

K/A

Reference:

061 A2.07 (3.4/3.5)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

Initial Conditions:

Unit 1 has just tripped from 100% power, due to seismic activity.

The crew is now implementing EP/1/A/5000/ES-0.1 (Reactor Trip Response).

The CA Storage Tank has developed a leak, and level has lowered to 1.5 feet.

Initiating Cue: The CRS has directed you to perform EP/1/A/5000/G-1, Generic Enclosure 20 (CA Suction Source Realignment), while the crew continues with ES-0.1.

Task Standard: The operator will realign the suction of the CA Pumps from the non-safety related to the safety-related source (RN). During this action, the operator will recognize that RN Supply to the 1B MDCA Pump cannot be established and stop the pump.

Required Materials: None 2020 Systems - Control Room JPM C NUREG 1021, Revision 11

Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet General

References:

EP/1/A/5000/E-0 (Reactor Trip or Safety Injection), Rev 36 EP/1/A/5000/ES-0.1 (Reactor Trip Response), Rev 47 EP/1/A/5000/G-1 (Generic Enclosures), Rev 41 OMP 4-3 (Use of Emergency and Abnormal Procedures and FLEX Support Guidelines Procedures), Rev 48 Handouts: Handout 1: Blank copy of Enclosure 20 (CA Suction Source Realignment) of EP/1/A/5000/G-1 (Generic Enclosures).

Time Critical Task: NO Validation Time: 8 minutes 2020 Systems - Control Room JPM C NUREG 1021, Revision 11

Appendix C Page 4 of 12 Form ES-C-1 Job Performance Measure Worksheet Critical Step Justification Step 4 This step is critical because pressing the 1RN-69A OPEN pushbutton is necessary to realign the suction of the CA Pumps from the non-safety related to the safety-related source.

Step 5 This step is critical because pressing the 1CA-15A OPEN pushbutton is necessary to realign the suction of the CA Pumps from the non-safety related to the safety-related source.

Step 6 This step is critical because pressing the 1CA-86A OPEN pushbutton is necessary to realign the suction of the CA Pumps from the non-safety related to the safety-related source.

Alternate Path Critical Step Justification Step 12 This step is critical because pressing the STOP pushbutton for the 1B MDCA Pump is necessary to stop the 1B MDCA pump.

Step 15 This step is critical because pressing the 1CA-11A CLOSE pushbutton is necessary to realign the suction of the CA Pumps from the non-safety related to the safety-related source.

Step 19 This step is critical because pressing the 1CA-7AC CLOSE is necessary to realign the suction of the CA Pumps from the non-safety related to the safety-related source.

2020 Systems - Control Room JPM C NUREG 1021, Revision 11

Appendix C Page 5 of 12 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

1. Reset simulator to IC-39 (100%).

2. Place Simulator in RUN.

3. Ensure that the B Train of RN is in operation.

4. Insert REM_CA0018B=0 to ensure that 1CA-18B (1B CA Pump Suction from 1B RN Isol) will not OPEN.

5. Insert (CA) PLP_078 = 1.00 - (Simulates Leak in CAST).

6. Override ON OBE Exceeded Annunciator (1AD-13 E-7). (1AD13_E07 = ON)

7. Manually trip the reactor and perform the actions of EP/1/A/5000/E-0, and transition to EP/1/A/5000/ES-01.

8. Ensure both MDCA Pumps are running, acknowledge and silence all annunciators, and Freeze the Simulator.

OR

1. Reset to IC-241 (August, 2019)

2. Run Scenario Manager file N20 JPM C.sce.

3. Momentarily go to RUN to acknowledge Alarms then place Simulator in FREEZE.

4. Leave Simulator in FREEZE until operator is ready to begin.

NOTE: The Booth/Floor Instructor will need to control BOP during the performance of this JPM and ENSURE that SI Actuation is NOT needed.

2020 Systems - Control Room JPM C NUREG 1021, Revision 11

Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT Simulator Instructor NOTE: Leave Simulator in FREEZE until operator is ready to begin.

1 (Enclosure 20, Step 1/1.A) The operator recognizes Check if RN assured CA from the Initial Conditions suction should be that a CAST leak exists, immediately aligned as and proceeds.

follows:

Check if failure (causing leak) of CA Storage Tank (water tower) or associated CA suction piping KNOWN TO EXIST.

2 (Step 1.B) GO TO Step 4. The operator proceeds to Step 4.

3 (Step 4) Align A train RN to The operator observes the CA suction as follows: 1A RN Pump Red status light LIT, Green status light (Step 4.A) Start 1A RN OFF; and motor amps at pump. 88 amps and determines the 1A RN Pump is running.

4 (Step 4.B) OPEN 1RN-69A The operator presses the (1A RN Assured Supply To 1RN-69A OPEN pushbutton Unit 1 CA Isol). and observes the Red status light LIT, Green status light OFF.

The operator will acknowledge alarm on 1AD-5.

2020 Systems - Control Room JPM C NUREG 1021, Revision 11

Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

5 (Step 4.C) OPEN 1CA-15A The operator presses the (1A CA Pump Suction From 1CA-15A OPEN pushbutton 1A RN Isol) and observes the Red status light LIT, Green status light OFF.

The operator will acknowledge alarm on 1AD-5.

6 (Step 4.D) OPEN 1CA-86A The operator presses the (U1 TD CA Pump Suction 1CA-86A OPEN pushbutton From 1A RN Isol). and observes the Red status light LIT, Green status light OFF.

The operator will acknowledge alarm on 1AD-5.

7 (Step 5) Align B train RN to CA suction as follows:

(Step 5.A) Start 1B RN The operator observes the pump. 1B RN Pump Red status light LIT, Green status light OFF; and motor amps at 88 amps and determines the 1B RN Pump is running.

8 (Step 5.B) OPEN 1RN- The operator presses the 162B (1B RN Assured 1RN-162B OPEN Supply To Unit 1 CA Isol). pushbutton and observes the Red status light LIT, Green status light OFF.

The operator will acknowledge alarm on 1AD-5.

2020 Systems - Control Room JPM C NUREG 1021, Revision 11

Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 9 (Step 5.C) OPEN 1CA-18B The operator presses the (1B CA Pump Suction From 1CA-18B OPEN pushbutton 1B RN Isol). and observes the Green status light remains LIT, Red status light OFF (Alternate Path).

The operator proceeds to the RNO.

10 (Step 5.C RNO) IF 1B CA The operator may press the pump is on, THEN stop 1B RESET Pushbuttons and MD CA pump as follows: observes RESET status lights LIT for both Train A (Step 5.C RNO 1) Reset and B SI. (Already RESET)

S/I.

11 (Step 5.C RNO 2) Reset 1B The operator may press the Sequencer. Sequencer RESET and observes RESET status lights LIT Pushbuttons for both Train A and B.

(Already RESET)

12 (Step 5.C RNO 3) Stop 1B The operator presses the CA pump. STOP pushbutton for the 1B MDCA Pump and observes the Green status light LIT, Red status light OFF; and that motor amps drop to 0.

The operator will acknowledge alarm on 1AD-5.

13 (Step 5.C RNO 4) IF 1B CA The operator observes that pump still on,. the 1B MDCA Pump is OFF, and proceeds.

2020 Systems - Control Room JPM C NUREG 1021, Revision 11

Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 14 (Step 5.D) OPEN 1CA- The operator presses the 116B (U1 TD CA Pump 1CA-116B OPEN Suction From 1B RN Isol). pushbutton and observes the Red status light LIT, Green status light OFF.

The operator will acknowledge alarm on 1AD-5.

15 (Step 6) Isolate nonsafety The operator presses the CA suction sources from 1CA-11A CLOSE MD CA pumps as follows: pushbutton and observes the Green status light LIT, Red status light OFF.

(Step 6.A) CLOSE 1CA-11A (1A CA Pump Suction Isol).

16 (Step 6.B) CLOSE 1CA-9B The operator presses the (1B CA Pump Suction Isol). 1CA-9B CLOSE pushbutton and observes the Green status light LIT, Red status light OFF.

17 (Step 7) Isolate non-safety CA suction sources from TD CA pump as follows:

(Step 7.A) Check the following valves - OPEN:

1RN-69A (1A RN Assured The operator observes the Supply To Unit 1 CA Isol) 1RN-69A Red status light LIT, Green status light OFF.

1CA-86A (U1 TD CA Pump The operator observes the Suction From 1A RN Isol). 1CA-86A Red status light LIT, Green status light OFF.

18 (Step 7.B) GO TO Step 7.D. The operator proceeds to Step 7.D.

2020 Systems - Control Room JPM C NUREG 1021, Revision 11

Appendix C Page 10 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

19 (Step 7.D) CLOSE 1CA- The operator presses the 7AC (U1 TD CA Pump 1CA-7AC CLOSE Suction Isol). pushbutton and observes the Green status light LIT, Red status light OFF.

20 (Step 8) WHEN time allows, THEN. Cue:

Another operator will complete the remaining steps.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Systems - Control Room JPM C NUREG 1021, Revision 11

Appendix C Page 11 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Systems - Control Room JPM C Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Systems - Control Room JPM C NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

Unit 1 has just tripped from 100% power, due to seismic activity.

The crew is now implementing EP/1/A/5000/ES-0.1 (Reactor Trip Response).

The CA Storage Tank has developed a leak, and level has lowered to 1.5 feet.

INITIATING CUE: The CRS has directed you to perform EP/1/A/5000/G-1, Generic Enclosure 20 (CA Suction Source Realignment), while the crew continues with ES-0.1.

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIM JPM D 2020 Systems - Control Room JPM D (Rev_011520) NUREG 1021, Revision 11

Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Place LTOP in Service and JPM No.: 2020 Systems - Control Respond to a Failed PORV Room JPM D (Alternate Path)

K/A

Reference:

010 A4.03 (4.0/3.8)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

Initial Conditions:

A Unit 1 NC cooldown and depressurization is in progress in accordance with OP/1/A/6100/SD-4 (Cooldown to 240 Degrees F).

Attachment 2 (Cooldown to 240°F (Control Room Activities)) is in progress.

The 1A and 1B NCPs are operating.

NC System pressure is 320 psig and NC System temperature is 310-320oF.

NC Pressure control via normal spray and PZR heaters.

NC pressure is being controlled using 1NC-29C, 1B NC Loop Pzr Spray Control, in MANUAL.

Attachment 1 of OP/1/A/6100/SO-10 (Controlling Procedure for LTOP Operation) has been completed through Step 3.13.a.

LTOP vent requirements are to be satisfied by Pzr PORVs 1NC-32B and 1NC-34A.

2020 Systems - Control Room JPM D NUREG 1021, Revision 11

Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet Initiating Cue: The CRS has directed you to place the LTOP System in operation beginning with Step 3.13.b - of Attachment 1 of OP/1/A/6100/SO-10 (Controlling Procedure for LTOP Operation) and monitor for proper operation.

Task Standard: The operator will place LTOP in service by first placing 1NC-32B in service per procedure; and then respond to a failed open Pzr PORV (1NC-34A) by closing the failed open Pzr PORV Block Valve.

Required Materials: None General

References:

OP/1/A/6100/SD-4 (Cooldown to 240 Degrees F), Rev 73 OP/1/A/6100/SO-10 (Controlling Procedure for LTOP Operation), Rev 43 AP/1/A/5500/11 (Pressurizer Pressure Anomalies), Rev 12 AD-OP-ALL-1001 (Conduct of Abnormal Operations), Rev 3 OMP 4-3 (Use of Emergency And Abnormal Procedures And FLEX Support Guidelines), Rev 48 Handouts: Handout 1: Enclosure 4.1 (Placing LTOP System in Service per OP/1/A/6100/SO-10 (Cooldown to 240 Degrees F)) marked up for place-keeping through Step 3.13.a.

Time Critical Task: NO Validation Time: 10 minutes NOTE: This JPM should be pre-briefed in the Briefing Room.

2020 Systems - Control Room JPM D NUREG 1021, Revision 11

Appendix C Page 4 of 12 Form ES-C-1 Job Performance Measure Worksheet Critical Step Justification Step 7 This step is critical because placing the PORV Overpress Protection Select Switch in LOW PRESS is necessary to change the Pzr PORV mode of operation from Normal mode to the Low Temperature Overpressure Protection (LTOP) mode.

Step 13 This step is critical because placing the PORV Overpress Protection Select Switch in LOW PRESS is necessary to change the Pzr PORV mode of operation from Normal mode to the Low Temperature Overpressure Protection (LTOP) mode.

Alternate Path Critical Step Justification Step 17 This step is critical because placing the 1NC-33A Control Switch in the CLSD position is necessary to respond to a failed open Pzr PORV (1NC-34A) by closing the failed open Pzr PORV Block Valve.

2020 Systems - Control Room JPM D NUREG 1021, Revision 11

Appendix C Page 5 of 12 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

1. Reset simulator to IC-45.

2. Place in RUN

3. Adjust NCS Temperature to 300-320oF, and NCS Pressure to 320-330 psig.

4. Place LTOP PORV switches in NORMAL

5. When NCS Temperature/Pressure in range place Steam Dump System in AUTO (SG Pressure 70 psig)

6. Ensure that Simulator reflects that Attachment 2 of OP/1/A/6100/SD-4 is complete through Step 3.19 and Attachment 1 of OP/1/A/6100/SO-10 is completed through Step 3.13.a.

7. Insert REM_NC0034A=1 cd X10_162_1EQ1 (Conditional on the LOW PRESS position of the PORV Overpress Protection Select 1NC-34A)

8. Freeze the Simulator OR

1. Reset to IC-242 (August, 2019)

2. Run Scenario Manager file N20 JPM D.sce.

3. Momentarily go to RUN to acknowledge Alarms then place Simulator in FREEZE.

4. Ensure that the AFD Computer screen displays the C/D Tab panel and that the BOP screen displays the NCLTOP panel.

5. Place Info Stickers on PORV Controls.

6. Leave Simulator in FREEZE until operator is ready to begin.

NOTE: During the performance of this JPM, the simulator operator may need to control CF flow to the SGs (Monitor Wide Range Levels).

2020 Systems - Control Room JPM D NUREG 1021, Revision 11

Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT Simulator Instructor NOTE: Leave Simulator in FREEZE until operator is ready to begin.

1 (Step 3.13.b) Ensure in The operator calls up both service:

points on OAC.

M1A1359 (NC NR Pressure for 1NC-32B actuation).

M1A1365 (NC NR Pressure for 1NC-34A actuation).

2 (Step 3.13.c) Monitor: The operator monitors both points and observes NC NR M1A1359 (NC NR pressure Pressure to be between for 1NC-32B actuation).

320-330 psig.

M1A1365 (NC NR pressure for 1NC-34A actuation).

3 (Step 3.13.d) Ensure the following for A Cold Leg Accumulator:

The operator observes Pressure greater than 200 1NIP-5050 and 1NIP-5040 psig. and determines A CLA pressure to be 610 psig.

Level less than 38.7% The operator observes (7342 gallons maximum). 1NIP-5051 and 1NIP-5041 and determines A CLA Level to be 30%.

2020 Systems - Control Room JPM D NUREG 1021, Revision 11

Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 4 (Step 3.13.e) Ensure the following for B Cold Leg Accumulator:

The operator observes Pressure greater than 200 1NIP-5070 and 1NIP-5060 psig. and determines B CLA pressure to be 610 psig.

Level less than 38.7% The operator observes (7342 gallons maximum). 1NIP-5071 and 1NIP-5061 and determines B CLA Level to be 25%.

5 (Step 3.13.f) Ensure OPEN: The operator observes Red status light LIT, Green 1NC-31B (Pzr PORV Isol). status light OFF for 1NC-31B.

1NC-33A (Pzr PORV Isol). The operator observes Red status light LIT, Green status light OFF for 1NC-33A.

6 (Note prior to Step 3.13.g) The operator reads the For NC Loop in which an Note, and proceeds to Step NC Pump is operating, NR 3.13.g.

pressure may indicate up to 30 psig lower than NR pressure for NC Loop in which an NC Pump is NOT operating.

7 (Step 3.13.g) When The operator observes M1A1359 indicates 320-330 M1A1359 is between 320-psig, perform the following:

330 psig and selects LOW (Step 3.13.g.1) Select PRESS on PORV LOW PRESS on PORV Overpress Protection Select Overpress Protection Select 1NC-32B.

1NC-32B. NOTE: 1AD-6/F-10 will alarm.

2020 Systems - Control Room JPM D NUREG 1021, Revision 11

Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 8 (Step 3.13.g.2) Ensure 1NI- The operator observes that 431B (Emerg N2 from CLA Red status light is LIT, to 1NC-32B & 36B) OPEN. Green status light OFF for 1NI-431B.

NOTE: If CLOSED, the operator presses the OPEN Pushbutton and Observes Red status light is LIT, Green status light OFF for 1NI-431B.

9 (Step 3.13.g.3) Check lit The operator observes that 1AD-6, F10 (PORV NC-32B 1AD-6, F-10 is LIT.

Emerg CLA N2 Enabled) 10 (Note prior to Step 3.13.g.4) The operator reads the Continue with the rest of the Note, and proceeds to Step procedure while performing 3.13.g.4.

Step 3.13.g.4.

11 (Step 3.13.g.4) Place Info Sticker on control switch for Cue:

1NI-431B stating: Do NOT operate, N2 aligned to 1NC- Another operator has 32B for LTOP. filled out and placed an Info Sticker for 1NI-431B The operator acknowledges and proceeds to Step 3.13.g.5.

12 (Step 3.13.g.5) Ensure The operator observes that 1NC-32B (Pzr PORV) in Control Switch for 1NC-32B AUTO. is in AUTO.

2020 Systems - Control Room JPM D NUREG 1021, Revision 11

Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

13 (Step 3.13.h) WHEN The operator observes M1A1365 indicates 320-330 M1A1365 is between 320-psig, THEN perform the 330 psig and selects LOW following:

PRESS on PORV (Step 3.13.h.1) Select Overpress Protection Select LOW PRESS on PORV 1NC-34A (Alternate Path).

Overpress Protection Select 1NC-34A. NOTE:

When this occurs 1NC-34A will fail full open, causing NCS pressure to lower, and creating the plant conditions need to enter AP/1/A/500/11, Pressurizer Pressure Anomalies.

The operator will carry out the Immediate Actions of AP11.

NOTE:

The operator may take the immediate actions without addressing AP11 first. (Section 5.2.5 of OMP 4-3 and Section 3.12, 5.1.4.1, and 5.7.3 of AD-OP-ALL-1001).

14 (AP11 Immediate Action The operator observes NCS Step 1) Check Pzr pressure pressure to be lowering

- HAS GONE DOWN. rapidly.

2020 Systems - Control Room JPM D NUREG 1021, Revision 11

Appendix C Page 10 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 15 (Immediate Action Step 2) The operator observes the Check Pzr PORVs -

1NC-34A Red status light is CLOSED.

LIT and determines that the valve is OPEN.

16 (Immediate Action Step 2 The operator rotates the RNO) Perform the following: 1NC-34A control Switch to CLOSE.

(Immediate Action Step 2 RNO A) CLOSE PORVs.

17 (Immediate Action Step 2 RNO) Perform the following:

(Immediate Action Step 2 The operator observes that RNO B) IF PORV will not 1NC-34A is still OPEN and close, THEN CLOSE places the 1NC-33A Control PORV isolation valve. Switch in the CLSD position; and observes the 1NC-33A Green status light is LIT, and the Red status light is OFF.

18 (Immediate Action Step 3) The operator observes that Check Pzr spray valves -

only the 1NC-27C SLIM CLOSED.

CLOSED window light is LIT.

The operator observes that only the 1NC-29C SLIM CLOSED window light is LIT.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Systems - Control Room JPM D NUREG 1021, Revision 11

Appendix C Page 11 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Systems - Control Room JPM D Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Systems - Control Room JPM D NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

A Unit 1 NC cooldown and depressurization is in progress in accordance with OP/1/A/6100/SD-4 (Cooldown to 240 Degrees F).

Attachment 2 (Cooldown to 240°F (Control Room Activities)) is in progress.

The 1A and 1B NCPs are operating.

NC System pressure is 320 psig and NC System temperature is 310-320oF.

NC Pressure control via normal spray and PZR heaters.

NC pressure is being controlled using 1NC-29C, 1B NC Loop Pzr Spray Control, in MANUAL.

Attachment 1 of OP/1/A/6100/SO-10 (Controlling Procedure for LTOP Operation) has been completed through Step 3.13.a.

LTOP vent requirements are to be satisfied by Pzr PORVs 1NC-32B and 1NC-34A.

INITIATING CUE: The CRS has directed you to place the LTOP System in operation beginning with Step 3.13.b - of Attachment 1 of OP/1/A/6100/SO-10 (Controlling Procedure for LTOP Operation) and monitor for proper operation.

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIM JPM E 2020 Systems - Control Room JPM E (Rev_011520) NUREG 1021, Revision 11

Appendix C Page 2 of 14 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Restore Normal Power to 1ETB and JPM No.: 2020 Systems - Control Unload the 1B EDG/Respond to Room JPM E 1ETB Lockout (Alternate Path)

K/A

Reference:

056 AA1.02 (4.0/3.9)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

Initial Conditions:

Unit 1 was operating at 100% power when the normal power breaker to 1ETB was inadvertently opened.

The 1B EDG started and re-energized the bus and sequenced loads onto 1ETB as expected.

The crew entered AP/1/A/5500/07, Loss of Electrical Power, Case II, Loss of Normal Power to Either 1ETA or 1ETB; and are currently at Step 86.

An investigation has revealed that the breaker was inadvertently opened, and that the breaker is ready to be re-closed.

The crew is attempting to return 1ETB to normal power and shutdown the 1B D/G.

AO John is standing by in the field to support this activity.

Initiating Cue: The CRS has directed you to restore 1ETB to normal power and separate the 1B D/G from the Grid from the Control Room per OP/1/A/6350/002 (Diesel Generator), Enclosure 4.4 (1B D/G Shutdown).

2020 Systems - Control Room JPM E NUREG 1021, Revision 11

Appendix C Page 3 of 14 Form ES-C-1 Job Performance Measure Worksheet Task Standard: While 1ETB is being powered by the 1B D/G, the operator will parallel 1ETB, with 1ATD, and then unload the 1B D/G. Once the 1ETB Emergency Breaker is opened, Bus 1ETA will experience an overcurrent lockout, and the operator will carry out the immediate actions of AP/1/A/5500/07 by starting the 1B NV Pump and the 1B KC Pumps manually.

Required Materials: None General

References:

EP/1/A/5000/E-0 (Reactor Trip or Safety Injection), Rev 36 EP/1/A/5000/ES-0.1 (Reactor Trip Response), Rev 47 AP/1/A/5500/07 (Loss of Electrical Power), Rev 40 OP/1/A/6350/002 (Diesel Generator), Rev 130 OMP 4-3 (Use of Emergency And Abnormal Procedures And FLEX Support Guidelines), Rev 48 AD-OP-ALL-1001 (Conduct of Abnormal Operations), Rev 3 Handouts: Handout 1: Enclosure 4.4 of OP/1/A/6350/002 (Diesel Generator) marked up through Step 3.1.

Time Critical Task: NO Validation Time: 15 minutes NOTE: The JPM should be pre-briefed in the Briefing Room.

2020 Systems - Control Room JPM E NUREG 1021, Revision 11

Appendix C Page 4 of 14 Form ES-C-1 Job Performance Measure Worksheet Critical Step Justification Step 1 This step is critical because rotating the 1B D/G Mode Select switch counter-clockwise to the C/R position is necessary for the Control Room operator to control the 1B D/G.

Step 4 This step is critical because rotating "1B D/G Volt Adjust" switch clockwise and/or counterclockwise as necessary to match voltages is necessary to parallel 1ETB (powered by the 1B D/G), with 1ATD.

Step 5 This step is critical because rotating the 1B D/G Sync Scope Switch to ON is necessary to parallel 1ETB (powered by the 1B D/G), with 1ATD.

Step 7 This step is critical because depressing the RAISE/LOWER pushbutton causing the synchroscope to move slowly in the FAST direction is necessary to parallel 1ETB (powered by the 1B D/G), with 1ATD.

Step 8 This step is critical because depressing the 1ETB Normal Breaker CLOSE pushbutton with the synchroscope pointer is 3 minutes before vertical is necessary to parallel 1ETB (powered by the 1B D/G), with 1ATD.

Step 9 This step is critical because pressing the Raise pushbutton to raise DG load after paralleling and rotating the Voltage Adjust handle to raise power factor within band are necessary to parallel 1ETB (powered by the 1B D/G), with 1ATD.

Step 14 This step is critical because depressing the 1B D/G Gov Control LOWER pushbutton until load meter indicates < 200 KW is necessary to unload the 1B D/G.

Step 15 This step is critical because depressing the 1ETB Emergency Breaker OPEN pushbutton is necessary to unload the 1B D/G.

Alternate Path Critical Step Justification Step 19 This step is critical because pressing the 1B NV Pump, 1B1 KC Pump and 1B2 KC Pump START Pushbutton is necessary to carry out the immediate actions of AP/1/A/5500/07.

2020 Systems - Control Room JPM E NUREG 1021, Revision 11

Appendix C Page 5 of 14 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

1. Reset simulator to IC-21, 100% Power (or equivalent at power IC).

2. Ensure that Train A Pumps are in service.

3. Place Simulator in RUN and allow time to stabilize.

4. Open the 1ETB Normal Power Breaker (Simulating an inadvertent opening of the breaker).

5. Insert MAL_EP008A on Trigger #1 and establish a condition such that when the 1ETB Emergency Breaker is opened the malfunction will go active (H_X11_229_3_1 [Emergency Breaker OPEN light is LIT]).

6. Perform the actions of Case II AP/1/A/5500/07 up through step 86.B.

7. Freeze the Simulator OR

1. Reset to IC-243 (August, 2019) 2020 Systems - Control Room JPM E NUREG 1021, Revision 11

Appendix C Page 6 of 14 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT Simulator Instructor NOTE: Leave Simulator in FREEZE until operator is ready to begin.

1 (Step 3.2) Place Control The operator rotates the 1B Room 1B D/G Mode D/G Mode Select switch Select switch to the counter-clockwise to C/R for applicable position: the 1B D/G.

LOCAL to operate D/G from local panel.

OR C/R to operate D/G from Control Room.

2 (Step 3.3) If D/G is The operator observes operating Unloaded,.. Emergency Breaker status (Red light LIT) and determines that the D/G is not running unloaded (Or Equivalent).

3 (Step 3.4) IF D/G is carrying The operator observes 1ETB separated from the Normal and Emergency Duke Grid, THEN parallel Breaker status and D/G to Grid as follows: determines that the D/G is separated from the Duke Grid.

(Step 3.4.1) Check Line Volts 3960-4360 V. The operator observes Line Volts Meter at 4175V.

2020 Systems - Control Room JPM E NUREG 1021, Revision 11

Appendix C Page 7 of 14 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

4 (Step 3.4.2) Match D/G The operator rotates "1B voltage with line voltage D/G Voltage Adjust" switch using "1B D/G Voltage clockwise and/or Adjust." counterclockwise as necessary and observes voltage meters are matched.

5 (Step 3.4.3) Place the 1B The operator rotates the 1B D/G Sync Switch to ON. D/G Sync Scope Switch to ON.

The operator observes synch scope meter dial is NOT moving or moving slowly in the SLOW direction.

6 (Note prior to Step 3.4.4) As The operator reads the a guide, have synchroscope NOTE and proceeds.

traveling no faster than one revolution in 20 seconds.

7 (Step 3.4.4) Using "1B D/G The operator depresses the Gov Control," adjust D/G RAISE/LOWER pushbutton speed to allow causing the synchroscope to synchroscope to move move slowly in the FAST slowly and smoothly in direction.

"FAST" direction.

2020 Systems - Control Room JPM E NUREG 1021, Revision 11

Appendix C Page 8 of 14 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

8 (Step 3.4.5) IF desired to The operator determines align 1ETB to normal supply from initial conditions that it (1ATD), perform the is desired to align 1ETB to following: 1ATD.

(Notes prior to Step 3.4.5.1): The operator reads the

D/G load will drop to 0 NOTES and proceeds.

amps when bus is paralleled to Duke Grid.

D/G load shall be quickly raised after breaker closed to prevent reverse power condition. IF a reverse power condition occurs, the D/G Emergency Breaker will trip after a short time delay.

Steps 3.4.5.1 and 3.4.5.2 may be completed and then signed off as time allows.

(Step 3.4.5.1) HOLD until synchroscope pointer is The operator observes within 3 minutes before the pointer is 3 minutes before 12 oclock position, THEN vertical, then depresses the firmly depress AND release 1ETB Normal Breaker CLOSE on 1ETB Normal CLOSE pushbutton and Breaker. observes Red Status light is LIT.

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Appendix C Page 9 of 14 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

9 (Step 3.4.5.2) Perform concurrently:

Quickly raise D/G load to The operator presses Raise 800 - 1000 KW using "1B pushbutton and observes D/G Gov Control." KW meter indicates 800-1000KW.

Adjust power factor to 0.90 The operator rotates Voltage

- 0.92 lagging using "1B Adjust handle and observes D/G Voltage Adjust." meter indication reads 0.9 Lagging.

10 (Step 3.4.5.3) Place 1B The operator turns the 1B D/G Sync Switch to OFF. D/G Sync scope to OFF.

11 (Step 3.4.5.4) Evaluate The operator has the CRS Offsite Power sign for offsite power OPERABILITY. operability.

Cue:

As CRS, initial Step 3.4.5.4.

12 (Step 3.4.5.5) Go to Step The operator proceeds to 3.5.9. Step 3.5.9.

2020 Systems - Control Room JPM E NUREG 1021, Revision 11

Appendix C Page 10 of 14 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 13 (Step 3.5.9) HOLD for 10 The operator waits for 10 minutes minutes.

Cue:

Using TIME COMPRESSION, the 1B D/G has been at the current load for 10 minutes.

14 (Step 3.5.10) Perform the following: The operator depresses the (Step 3.5.10.1) Lower D/G 1B D/G Gov Control load to less than 200 kW LOWER pushbutton until using 1B D/G Gov Control. load meter indicates < 200 KW.

The operator observes that meter indicates < 200KW.

15 (Step 3.5.10.2) Open 1ETB The operator depresses the Emergency Breaker. 1ETB Emergency Breaker OPEN pushbutton and observes the Green Status light is LIT.

Simulator Instructor NOTE: Trigger #1 is set up to cause an Overcurrent Lockout on Bus 1ETA when the 1ETB Emergency Breaker is OPEN. (Alternate Path) 2020 Systems - Control Room JPM E NUREG 1021, Revision 11

Appendix C Page 11 of 14 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 16 (Note prior to Step 3.6) IF The operator will recognize D/G has been loaded less that an Overcurrent Lockout than full load (3600 - 4000 has occurred on 1ETA and kW) for an extended event, perform the Immediate performing a full load run for Actions of Case II of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months essentially AP/1/A/5500/07.

reconfirms McGuire Tech Spec SR 3.8.1.3 AND conforms to industry practices. NOTE:

The operator may take the immediate actions without addressing AP7 first.

(Section 5.2.5 of OMP 4-3 and Section 3.12, 5.1.4.1, and 5.7.3 of AD-OP-ALL-1001).

17 (AP/1/A/5500/07 IA Step 1) The operator observes Check affected bus(s) 1ETA remains de-energized, ENERGIZED AND and proceeds to the RNO.

SEQUENCER APPLYING LOADS.

18 (AP/1/A/5500/07 IA Step The operator observes that 1RNO.A) Perform the 1ETB is energized, and following: proceeds.

IF both busses deenergized, THEN.

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Appendix C Page 12 of 14 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

19 (AP/1/A/5500/07 IA Step The operator presses the 1B 1RNO.B) Perform the NV Pump START following: Pushbutton and observes the Red status light is LIT, Ensure the following pumps and the Green status light is running on energized bus: OFF.

NV pump The operator presses the

KC pumps 1B1 KC Pump START Pushbutton and observes

RN pump.

the Red status light is LIT, and the Green status light is OFF.

The operator presses the 1B2 KC Pump START Pushbutton and observes the Red status light is LIT, and the Green status light is OFF.

The operator observes the 1B RN Pump Red status light is LIT, and the Green status light is OFF.

Cue:

Another operator will continue with this procedure.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

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Appendix C Page 13 of 14 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Systems - Control Room JPM E Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Systems - Control Room JPM E NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

Unit 1 was operating at 100% power when the normal power breaker to 1ETB was inadvertently opened.

The 1B EDG started and re-energized the bus and sequenced loads onto 1ETB as expected.

The crew entered AP/1/A/5500/07, Loss of Electrical Power, Case II, Loss of Normal Power to Either 1ETA or 1ETB; and are currently at Step 86.

An investigation has revealed that the breaker was inadvertently opened, and that the breaker is ready to be re-closed.

The crew is attempting to return 1ETB to normal power and shutdown the 1B D/G.

AO John is standing by in the field to support this activity.

INITIATING CUE: The CRS has directed you to restore 1ETB to normal power and separate the 1B D/G from the Grid from the Control Room per OP/1/A/6350/002 (Diesel Generator), Enclosure 4.4 (1B D/G Shutdown).

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIM JPM F 2020 Systems - Control Room JPM F (Rev_011520) NUREG 1021, Revision 11

Appendix C Page 2 of 16 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Control Room Air Intake High JPM No.: 2020 Systems - Control Radiation Alarms Room JPM F K/A

Reference:

061 AA2.01 (3.5/3.7)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM).

Initial Conditions:

Units 1 and 2 are operating at 100% power.

Annunciator 1RAD-2 B2, EMF 43B CR AIR INTAKE B HI RAD, alarmed 45 seconds ago.

Annunciator 1RAD-1 B2, EMF 43A CR AIR INTAKE A HI RAD, alarmed 15 seconds ago.

Initiating Cue: The CRS has directed you to perform the Annunciator Response Procedures for both alarms.

Task Standard: The operator will determine that the Unit 2 intake presents a greater threat than Unit 1 and align the VC inlet to take suction on Unit 1 only; and then pressurize the Control Room from the B Train Outside Air Pressure Fan.

Required Materials: None General

References:

OP/1/A/6100/010 Q (Annunciator Response for Panel 1RAD-1), Rev 68 OP/1/A/6100/010 R (Annunciator Response for Panel 1RAD-2), Rev 42 2020 Systems - Control Room JPM F NUREG 1021, Revision 11

Appendix C Page 3 of 16 Form ES-C-1 Job Performance Measure Worksheet OP/0/A/6450/011 (Control Area Ventilation/Chilled Water System), Rev 107 AD-HU-ALL-004 (Procedure And Work Instruction Use and Adherence),

Rev 10 Handouts: Handout 1: OP/0/A/6450/011 (Control Area Ventilation/Chilled Water System)

Time Critical Task: NO Validation Time: 10 minutes Critical Step Justification Step 8 This step is critical because observing EMF 43A and EMF 43B and determining that EMF 43B has the highest reading is necessary to determine that the operator must align the VC inlet to take suction on Unit 1 only.

Step 13 This step is critical because pressing the 1VC-9A, 10A, 11B and 12B CLOSE pushbutton is necessary to align the VC inlet to take suction on Unit 1 only.

Step 14 This step is critical because determining that both EMF 43A and EMF 43B are valid alarms is necessary to pressurize the Control Room from the B Train Outside Air Pressure Fan.

Step 21 This step is critical because rotating the B Train CR Outside Air Press Fan Control Switch to the ON position is necessary to pressurize the Control Room from the B Train Outside Air Pressure Fan.

Step 22 This step is critical because pressing the MAN pushbutton for #1 & #2 CRA Otsd Air Fan is necessary to pressurize the Control Room from the B Train Outside Air Pressure Fan.

Step 23 This step is critical because pressing the OFF pushbutton for CRA-OAD-3 and 4 is necessary to pressurize the Control Room from the B Train Outside Air Pressure Fan.

2020 Systems - Control Room JPM F NUREG 1021, Revision 11

Appendix C Page 4 of 16 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

1. Reset simulator to IC-39 (100%).

2. Place in RUN

3. Adjust the output of EMF 43B to greater than the Trip II setpoint (Insert MAL_EMF-43B = 5400).

4. Adjust the output of EMF 43A to greater than the Trip II setpoint, but less than the value of EMF 43B (Insert MAL_EMF-43A = 4100).

5. Ensure 1RAD-1 B2 and 1RAD-2 B2 are both LIT.

6. Ensure Air Intake Valves from BOTH Units are OPEN.

7. Ensure that the B Train of VC/YC is operating.

8. Acknowledge all alarms.

9. Freeze the Simulator OR

1. Reset to IC-244 (August, 2019)

2. Momentarily go to RUN to acknowledge Alarms then place Simulator in FREEZE.

3. Leave Simulator in FREEZE until operator is ready to begin.

2020 Systems - Control Room JPM F NUREG 1021, Revision 11

Appendix C Page 5 of 16 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM).

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT Simulator Instructor NOTE: Leave Simulator in FREEZE until operator is ready to begin.

1 (OP/1/A/6100/010 Q, After checking the other 1RAD-1 B2 IA) Perform ARP, the operator proceeds OP/0/A/6450/011 (Control to OP/0/A/6450/011 Area Ventilation / Chilled Enclosure 4.14.

Water System) Enclosure 4.14 (Response When EMF Examiner Note:

43A and/or EMF 43B In Trip 2 or Non-Functional). The Immediate Actions for both ARPs are the same. The operator can address in either order (Step 1 and 2 can be done in any order).

When operator seeks Enclosure 4.14, provide Handout 1.

2 (OP/1/A/6100/010 R, After checking the other 1RAD-2 B2 IA) Perform ARP, the operator proceeds OP/0/A/6450/011 (Control to OP/0/A/6450/011 Area Ventilation / Chilled Enclosure 4.14.

Water System) Enclosure 4.14 (Response When EMF 43A and/or EMF 43B In Trip 2 or Non-Functional).

3 (OP/0/A/6450/011 The operator observes that Enclosure 4.14, Step 2.1) EMF-43A is in TRIP II.

EMF43A or EMF43B in Trip 2 Alarm or Non-Functional. The operator observes that EMF-43B is in TRIP II.

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Appendix C Page 6 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 4 (Step 3.1) Evaluate all The operator requests this outstanding Clearances that information from the CRS.

may impact performance of this procedure.

Cue:

There are no outstanding Clearances on this equipment.

5 (Step 3.2) Perform the The operator observes that following sections, as EMF-43A is in TRIP II.

applicable:

Section 3.3, Response The operator observes that for EMF43A or EMF43B EMF-43B is in TRIP II.

Non Functional

Section 3.4, Response The operator proceeds to for Trip 2 on EMF43A Section 3.6.

(Control Rm Air Intake Loc A) Examiner Note:

Section 3.5, Response for Trip 2 on EMF43B The operator may go to (Control Rm Air Intake Section 3.4 or 3.5. If so, Loc B) the first step of both

Section 3.6, Response sections will direct the for Trip 2 on EMF43A use of Section 3.6.

(Control Rm Air Intake Loc A) AND EMF43B (Control Rm Air Intake Loc B) 6 (Step 3.6) Response for The operator calls and Trip 2 on EMF43A (Control notifies RP of the situation, Rm Air Intake Loc A) AND and records.

EMF43B (Control Rm Air Intake Loc B)

Cue:

(Step 3.6.1) Notify RP of Trip 2 on both EMF43A and RP Technician Don Smith EMF43B. acknowledges.

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Appendix C Page 7 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 7 (Note prior to Step 3.6.2) The operator reads the Both sets of air intakes Note and proceeds.

should never be closed at same time.

8 (Step 3.6.2) IF both Unit 1 The operator observes that and Unit 2 intake valves both Unit 1 and Unit 2 open, perform the following: intake valves are OPEN.

(Step 3.6.2.1) Determine The operator observes EMF location with highest 43A and EMF 43B and radiation hazard per one or determines that EMF 43B both of the following: has the highest reading and records EMF 43B in the (Step 3.6.2.1.A) Check EMF space provided.

readings in Control Room and determine location with highest radiation hazard.

Record Location:

9 (Note prior to Step The operator reads the 3.6.2.1.B) Each unit's intake Note and proceeds.

can be accessed from associated unit's D/G building roof. The intake is 2 candy cane shaped 18" pipes on Aux building roof, next to Reactor building.

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Appendix C Page 8 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 10 (Step 3.6.2.1.B) Notify RP The operator calls requests to check VC intake radiation RP to survey the areas.

and determine location with highest radiation hazard.

Record Location: Cue:

The CRS directs you to continue with your task.

11 (Step 3.6.2.2) IF both intake The operator recognizes radiation hazards are the that the threat at Unit 2 is same,.. higher and that this step is NA.

12 (Step 3.6.2.3) IF Unit 1 The operator recognizes intake (monitored by that the threat at Unit 2 is EMF43A) is intake with higher and that this step is highest radiation hazard. NA.

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Appendix C Page 9 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

13 (Step 3.6.2.4) IF Unit 2 intake (monitored by EMF43B) is intake with highest radiation hazard ensure the following closed: The operator presses the

1VC-9A (VC Outside Air 1VC-9A CLOSE Intake From Unit 2 Isol) pushbutton, and observes the Green status light LIT, Red status light OFF.

1VC-10A (VC Outside The operator presses the Air Intake From Unit 2 1VC-10A CLOSE Isol) pushbutton, and observes the Green status light LIT, Red status light OFF.

1VC-11B (VC Outside The operator presses the Air Intake From Unit 2 1VC-11B CLOSE Isol) pushbutton, and observes the Green status light LIT, Red status light OFF.

1VC-12B (VC Outside The operator presses the Air Intake From Unit 2 1VC-12B CLOSE Isol) pushbutton, and observes the Green status light LIT, Red status light OFF.

Cue:

If asked, indicate that a Concurrent Verification (CV) has been completed.

Examiner NOTE:

HVAC OAD-11 H-8 and H-9 are expected alarms.

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Appendix C Page 10 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

14 (Step 3.6.3) IF EMF43A The operator observes both (Control Rm Air Intake Loc instruments and determines A) AND EMF43B (Control that both EMF 43A and Rm Air Intake Loc B) Trip 2 EMF 43B are valid alarms; alarm valid (no loss of and proceeds to Enclosure power), perform the 4.4.

following:

(Step 3.6.3.1) Pressurize Examiner Note:

Control Room per Enclosure 4.4 (Control Handout 1 also contains Room Atmosphere Enclosure 4.4.

Pressurization During Abnormal Conditions).

15 (OP/0/A/6450/011 The operator recognizes Enclosure 4.4, Step 2.1) that this Initial Condition has Control Room atmosphere been satisfied during the has been determined to be performance of the in need of pressurization to Immediate Actions.

protect Control Room personnel.

16 (Step 2.2) VC / YC Train A The operator observes that OR B is selected and is in the VC/YC Train B Mode operation per this Select Switch is in B, and procedure. that the VC/YC Train A Mode Select Switch is in OFF, and determines that the Train B is selected and in operation.

17 (Step 3.1) Evaluate all The operator requests this outstanding Clearances that information from the CRS.

may impact performance of this procedure.

Cue:

There are no outstanding Clearances on this equipment.

2020 Systems - Control Room JPM F NUREG 1021, Revision 11

Appendix C Page 11 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 18 (Step 3.2) Perform the The operator recognizes following sections as that Section 3.3 is required applicable: and proceeds.

Section 3.3, Pressurize Control Room Using Outside Air Pressure Fans

Section 3.4, Securing Pressurization Of Control Room 19 (Step 3.3) Pressurize The operator observes the Control Room using Red status lights LIT for the Outside Air Pressure Fans Unit 1 valves.

(Step 3.3.1) Ensure at least one the following groups of Cue:

intake valves open:

1VC-1A (VC Outside Air If asked, indicate that a Intake From Unit 1 Isol) Concurrent Verification

1VC-2A (VC Outside Air (CV) has been completed.

Intake From Unit 1 Isol)

1VC-3B (VC Outside Air Intake From Unit 1 Isol)

1VC-4B (VC Outside Air Intake From Unit 1 Isol)

OR

1VC-9A (VC Outside Air Intake From Unit 2 Isol)

1VC-10A (VC Outside Air Intake From Unit 2 Isol)

1VC-11B (VC Outside Air Intake From Unit 2 Isol)

1VC-12B (VC Outside Air Intake From Unit 2 Isol) 20 (Step 3.3.2) IF A Train VC/ The operator observes that YC operating, .. the A Train of VC/YC is OFF.

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Appendix C Page 12 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

21 (Step 3.3.3) IF B Train VC / The operator rotates the B YC operating, place "B Train CR Outside Air Press Train CR Outside Air Press Fan Control Switch to the Fan" to "ON". ON position.

The operator will observe the Red B Train CR Outside Air Press Fan status light is LIT. (Not Critical)

The operator will observe the White B Train CR Filter Preheat Enabled status light is LIT. (Not Critical)

The operator observes the CRA-OAPFT-2 Dampers Red status light is LIT, and the Green status light is OFF. (Not Critical)

Cue:

If asked, indicate that a Concurrent Verification (CV) has been completed.

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Appendix C Page 13 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 22 (Step 3.3.4) Depress "MAN" The operator presses the for the following (to ensure MAN pushbutton for #1 fans off): CRA Otsd Air Fan, and

#1 CRA Otsd Air Fan observes the Green status

#2 CRA Otsd Air Fan light is LIT, Red status light is OFF.

The operator presses the MAN pushbutton for #2 CRA Otsd Air Fan, and observes the Green status light is LIT, Red status light is OFF.

Cue:

If asked, indicate that a Concurrent Verification (CV) has been completed.

23 (Step 3.3.5) Depress "OFF" The operator presses the for the following: OFF pushbutton for CRA-

CRA-OAD-4 (CR Area OAD-4 and observes the Otsd Air Fans Damper) Red status light is OFF.

CRA-OAD-3 (CR Area Otsd Air Fans Damper) The operator presses the OFF pushbutton for CRA-OAD-3 and observes the Red status light is OFF.

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Appendix C Page 14 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 24 (Step 3.3.6) Check the following dark:

CRA-OAD-4 (CR Area The operator observes Otsd Air Fans Damper) CRA-OAD-4 light is OFF.

"OPEN" light

CRA-OAD-3 (CR Area The operator observes Otsd Air Fans Damper) CRA-OAD-3 light is OFF.

"OPEN" light 25 (Note prior to Step 3.4) CR The operator starts to read Outside Air Press Fan is the Note.

credited to minimize Control Room dose for events such Cue:

as:

Another operator will complete this task.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Systems - Control Room JPM F NUREG 1021, Revision 11

Appendix C Page 15 of 16 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Systems - Control Room JPM F Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Systems - Control Room JPM F NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

Units 1 and 2 are operating at 100% power.

Annunciator 1RAD-2 B2, EMF 43B CR AIR INTAKE B HI RAD, alarmed 45 seconds ago.

Annunciator 1RAD-1 B2, EMF 43A CR AIR INTAKE A HI RAD, alarmed 15 seconds ago.

INITIATING CUE: The CRS has directed you to perform the Annunciator Response Procedures for both alarms.

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIM JPM G 2020 Systems - Control Room JPM G (Rev_011520) NUREG 1021, Revision 11

Appendix C Page 2 of 11 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Control Pressurizer Relief Tank JPM No.: 2020 Systems - Control Parameters Room JPM G K/A

Reference:

007 A1.03 (2.6/2.7)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

Initial Conditions:

Unit 1 is operating at power.

A transient has resulted in a discharge to the Pressurizer Relief Tank from the Pressurizer PORVs.

The plant has stabilized and all Pressurizer PORVs are closed.

Previous PRT cooling operations have lowered PRT Temperature, however, MCB Annunciator 1AD-6, C9, PRT HI TEMP, is still LIT.

The following PRT parameters are observed:

PRT Level is 76%.

PRT Pressure is 4 psig.

PRT Temperature 112°F.

Steps 3.1 through 3.5 of Enclosure 4.3 (PRT Cooling) of OP/1/A/6150/004 (Pressurizer Relief Tank), have been completed.

Initiating Cue: The CRS has directed you to perform Enclosure 4.3 (PRT Cooling) of OP/1/A/6150/004 (Pressurizer Relief Tank), starting with Step 3.6, to lower PRT Temperature to clear 1AD-6, C9, PRT HI TEMP.

2020 Systems - Control Room JPM G NUREG 1021, Revision 11

Appendix C Page 3 of 11 Form ES-C-1 Job Performance Measure Worksheet Task Standard: The operator will complete Enclosure 4.3 (PRT Cooling) of OP/1/A/6150/004 (Pressurizer Relief Tank) such that PRT Temperature is less than 110°F, and 1AD-6, C9, PRT HI TEMP, is EXTINGUISHED.

Required Materials: None General

References:

OP/1/A/6150/004 (Pressurizer Relief Tank), Rev 60 OP/1/A/6100/010G (Annunciator Response for Panel 1AD-6) Rev 77 AD-HU-ALL-004 (Procedure And Work Instruction Use and Adherence),

Rev 10 Handouts: Handout 1: Enclosure 4.3 (PRT Cooling) of OP/1/A/6150/004 (Pressurizer Relief Tank) marked up for place-keeping through Step 3.5.

Time Critical Task: NO Validation Time: 12 minutes NOTE: The JPM should be pre-briefed in the Briefing Room.

2020 Systems - Control Room JPM G NUREG 1021, Revision 11

Appendix C Page 4 of 11 Form ES-C-1 Job Performance Measure Worksheet Critical Step Justification Step 4 This step is critical because pressing the 1NC-107A OPEN pushbutton is necessary to cool the PRT per Enclosure 4.3 of OP/1/A/6150/004 (Pressurizer Relief Tank).

Step 5 This step is critical because pressing the 1WL-33 OPEN pushbutton is necessary to cool the PRT per Enclosure 4.3 of OP/1/A/6150/004 (Pressurizer Relief Tank).

Step 6 This step is critical because pressing the 1WL-3 and 1WL-36 CLOSE pushbutton is necessary to cool the PRT per Enclosure 4.3 of OP/1/A/6150/004 (Pressurizer Relief Tank).

Step 7 This step is critical because rotating the 1WL-23 Control Switch clockwise to MAN is necessary to cool the PRT per Enclosure 4.3 of OP/1/A/6150/004 (Pressurizer Relief Tank).

Step 11 This step is critical because pressing the 1WL-3 and 1WL-36 OPEN pushbutton is necessary to cool the PRT per Enclosure 4.3 of OP/1/A/6150/004 (Pressurizer Relief Tank).

Step 12 This step is critical because pressing 1WL-33 and the 1NC-107A CLS pushbutton is necessary to cool the PRT per Enclosure 4.3 of OP/1/A/6150/004 (Pressurizer Relief Tank).

Step 16 This step is critical because rotating the 1WL-23 Control Switch counter-clockwise to AUTO is necessary to restore NCDT Level Control per Enclosure 4.3 of OP/1/A/6150/004 (Pressurizer Relief Tank).

2020 Systems - Control Room JPM G NUREG 1021, Revision 11

Appendix C Page 5 of 11 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

1. Reset simulator to IC-39 (100%).

2. Place Simulator in RUN.

3. Lower reactor power to 97% by manually adjusting Turbine load, or some other convenient means.

4. Open one Pressurizer PORV until PRT Temperature is 114°F, and THEN Close.

5. Ensure that PRT Level is < 88% and that PRT Rupture Disc does NOT fail.

6. Ensure 1WL-41B is Open.

7. Ensure that PRT and NCDT pressures are approximately equal.

8. If necessary, use NCPLP90 = 4, to raise PRT pressure to 4 psig.

9. Ensure 1AD-6, C-9, PRT HI TEMP, is LIT.

10. Since 1AD-6, C-9, PRT HI TEMP, alarms at 114°F and does NOT clear until 110°F, cool the PRT to 112°F to lower the time commitment of the JPM.

OR

1. Reset to IC-245 (August, 2019)

2. Momentarily go to RUN to acknowledge Alarms then place Simulator in FREEZE.

3. Leave Simulator in FREEZE until operator is ready to begin.

NOTE: The Booth/Floor Instructor will need to control BOP during the performance of this JPM.

2020 Systems - Control Room JPM G NUREG 1021, Revision 11

Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT Simulator Instructor NOTE: Leave Simulator in FREEZE until operator is ready to begin.

1 (Caution prior to Step 3.6) The operator reads the NCDT pressure will rise Caution and proceeds.

rapidly to PRT pressure. IF NCDT pressure goes above VCT pressure, NC Pump #2 and #3 seals will be adversely affected.

2 (Step 3.6) IF 1NV-94AC (U1 The operator observes the NC Pumps Seal Water 1NV-94AC and 1NV-95B Return Cont Inside Isol) Red status lights are LIT, AND 1NV-95B (U1 NC and Green status lights are Pump Seal Water Return OFF.

Cont Outside Isol) open, check VCT pressure is The operator observes greater than PRT pressure. 1NVP5500 (VCT pressure) and 1NCP-5130 (PRT pressure) and determines that VCT pressure is greater than PRT pressure.

3 (Note prior to Step 3.7) IF The operator reads the 1WL-41B (NCDT Vent Cont Note and proceeds.

Outside Isol) open, Steps 3.7 - 3.9 should be performed without delay.

4 (Step 3.7) Open 1NC-107A The operator presses the (Unit 1 PRT To NCDT 1NC-107A OPEN Pump Drn Isol). pushbutton and observes the Red status light LIT, Green status light is OFF.

2020 Systems - Control Room JPM G NUREG 1021, Revision 11

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

5 (Step 3.8) Open 1WL-33 The operator presses the (NCDT Pumps to PRT). 1WL-33 OPEN pushbutton and observes the Red status light LIT, Green status light is OFF.

6 (Step 3.9) Close: The operator presses the 1WL-3 CLOSE pushbutton

1WL-3 (Unit 1 NCDT and observes the Green Outlet Isol) status light LIT, Red status

1WL-36 (NCDT Pumps light is OFF.

Recirc)

The operator presses the 1WL-36 CLOSE pushbutton and observes the Green status light LIT, Red status light is OFF.

7 (Step 3.10) Align 1WL-23 The operator rotates the (NCDT Pumps Disch 1WL-23 Control Switch Control) as follows: clockwise to MAN.

(Step 3.10.1) Select "MAN" on "1WL-23 Mode Select".

8 (Step 3.10.2) Close 1WL-23 The operator observes the (NCDT Pumps Disch 1WLM0230 controller Control). output to be 0.

9 (Step 3.11) IF 1WL-41B The operator observes the (NCDT Vent Cont Outside 1WL-41B Red status light is Isol) open, perform the LIT, Green status light is following: OFF.

(Step 3.11.1) Monitor NCDT The operator observes level. 1WLP-5153 (NCDT Level) to be 48%.

10 (Step 3.11.2) IF NCDT level The operator reads the Step approaches 90%, close and proceeds.

1WL-41B (NCDT Vent Cont Outside Isol).

2020 Systems - Control Room JPM G NUREG 1021, Revision 11

Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

11 (Step 3.12) WHEN PRT at The operator desired temperature OR observes1NCP-5350 (PRT necessary to stop and lower Temperature) to be NCDT level, perform the lowering.

following:

The operator observes that (Step 3.12.1) Open: 1AD-6, C9, is DARK.

1WL-3 (Unit 1 NCDT The operator presses the Outlet Isol) 1WL-3 OPEN pushbutton

1WL-36 (NCDT Pumps and observes the Red Recirc) status light LIT, Green status light is OFF.

The operator presses the 1WL-36 OPEN pushbutton and observes the Red status light LIT, Green status light is OFF.

NOTE:

MCB Annunciator 1AD-6, C9 will clear at 110°F.

12 (Step 3.12.2): Close: The operator presses the 1WL-33 CLS pushbutton

1WL-33 (NCDT Pumps and observes the Green to PRT) status light LIT, Red status

1NC-107A (Unit 1 PRT light is OFF.

To NCDT Pump Drn Isol) The operator presses the 1NC-107A CLS pushbutton and observes the Green status light LIT, Red status light is OFF.

2020 Systems - Control Room JPM G NUREG 1021, Revision 11

Appendix C Page 9 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 13 (Step 3.12.3) IF PRT over The operator recognizes pressure initiated, THEN that the PRT is not notify Radwaste to isolate overpressurized, and PRT over pressure per proceeds.

OP/0/A/6200/518 (Waste Gas Operation).

14 (Step 3.12.4) Align 1WL-23 The operator observes (NCDT Pumps Disch 1WLP-5153 (NCDT Level)

Control) as follows: is lowering to 42-46%.

(Step 3.12.4.1) IF NCDT level greater than 48%,

lower NCDT level to 48%

using 1WL-23 (NCDT Pumps Disch Control).

15 (Step 3.12.4.2) Ensure The operator observes the 1WL-23 (NCDT Pumps 1WLM0230 controller Disch Control) closed. output to be 0.

16 (Step 3.12.4.3) Select The operator rotates the "AUTO" on "1WL-23 Mode 1WL-23 Control Switch Select". counter-clockwise to AUTO.

17 (Step 3.12.5) WHEN NCDT The operator observes the level AND pressure normal, 1WL-41B the Red status ensure 1WL-41B (NCDT light is LIT, Green status Vent Cont Outside Isol) light is OFF.

open.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Systems - Control Room JPM G NUREG 1021, Revision 11

Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Systems - Control Room JPM G Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Systems - Control Room JPM G NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

Unit 1 is operating at power.

A transient has resulted in a discharge to the Pressurizer Relief Tank from the Pressurizer PORVs.

The plant has stabilized and all Pressurizer PORVs are closed.

Previous PRT cooling operations have lowered PRT Temperature, however, MCB Annunciator 1AD-6, C9, PRT HI TEMP, is still LIT.

The following PRT parameters are observed:

PRT Level is 76%.

PRT Pressure is 4 psig.

PRT Temperature 112°F.

Steps 3.1 through 3.5 of Enclosure 4.3 (PRT Cooling) of OP/1/A/6150/004 (Pressurizer Relief Tank), have been completed.

INITIATING CUE: The CRS has directed you to perform Enclosure 4.3 (PRT Cooling) of OP/1/A/6150/004 (Pressurizer Relief Tank), starting with Step 3.6, to lower PRT Temperature to clear 1AD-6, C9, PRT HI TEMP.

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIM JPM H 2020 Systems - Control Room JPM H (Rev_011620) NUREG 1021, Revision 11

Appendix C Page 2 of 13 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Start and Stop the 1B NCP for NCS JPM No.: 2020 Systems - Control Venting Room JPM H K/A

Reference:

003 A4.01 (3.3/3.2)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

Initial Conditions:

A plant startup is in progress per OP/1/A/6100/001 (Controlling Procedure For Unit Startup).

The crew is implementing Attachment 2 (Venting the NC System (Control Room Activities)) of OP/1/A/6100/SU-6 (Venting the NC System).

The NC System is water solid.

NC System pressure is being maintained between 320-350 psig.

During the NC System pressure increase to the current system pressure, it was noted that the 1B NCP Seal Leakoff flow increased 0.2 gpm.

The crew is ready to conduct an initial 60 second run of the 1B NC Pump.

Attachment 1 (Startup and Operation) of OP/1/A/6150/002 A (Reactor Coolant Pump Operation) has been completed through step 3.1.3 to support NC Pump operation.

Another operator has been assigned to control and maintain NCS pressure during the NCP run.

AOs are standing by in the field to assist.

2020 Systems - Control Room JPM H NUREG 1021, Revision 11

Appendix C Page 3 of 13 Form ES-C-1 Job Performance Measure Worksheet Initiating Cue: The CRS has directed you to start the 1B NCP per Section 3.3 of Attachment 1 (Startup and Operation) of OP/1/A/6150/002 A (Reactor Coolant Pump Operation); and then stop the 1B NCP under either of the following conditions:

The LOWEST NC Tcold lowers to 74°F.

The 1B NCP has operated for 60 seconds.

Task Standard: The operator will conduct a 60 second run of the 1B NC Pump in accordance with Attachment 1 of OP/1/A/6150/002 A. The pump should be immediately stopped if the applicant notices the bearing temperature spike (simulator issue).

Required Materials: None General

References:

OP/1/A/6100/001 (Controlling Procedure For Unit Startup), Rev 186 OP/1/A/6100/SU-6 (Venting the NC System), Rev 38 OP/1/A/6150/002 A (Reactor Coolant Pump Operation), Rev 71 OP/1/A/6100/022 (Unit 1 Data Book), Rev 481 AD-HU-ALL-004 (Procedure And Work Instruction Use and Adherence),

Rev 10 Handouts: Handout 1: Attachment 1 (Startup and Operation) of OP/1/A/6150/002 A (Reactor Coolant Pump Operation) marked up for place-keeping.

Time Critical Task: NO Validation Time: 15 minutes NOTE: The JPM should be pre-briefed in the Briefing Room.

Critical Step Justification Step 16 This step is critical because pressing the START pushbutton for either 1B1 or 1B2 Oil Lift Pumps is necessary to conduct a 60 second run of the 1B NC Pump in accordance with Attachment 1 of OP/1/A/6150/002 A.

Step 19 This step is critical because pressing the 1B NC Pump START pushbutton is necessary to conduct a 60 second run of the 1B NC Pump in accordance with Attachment 1 of OP/1/A/6150/002 A.

Step 22 This step is critical because pressing the 1B NC Pump STOP pushbutton is necessary to conduct a 60 second run of the 1B NC Pump in accordance with Attachment 1 of OP/1/A/6150/002 A.

2020 Systems - Control Room JPM H NUREG 1021, Revision 11

Appendix C Page 4 of 13 Form ES-C-1 Job Performance Measure Worksheet 2020 Systems - Control Room JPM H NUREG 1021, Revision 11

Appendix C Page 5 of 13 Form ES-C-1 Job Performance Measure Worksheet SIMULATOR OPERATIONAL GUIDELINES

1. Reset simulator to IC-5 (Mode 5, water solid).

2. Place Simulator in RUN.

3. Take actions through Step 3.3.9 of Attachment 2 (Venting the NC System (Control Room Activities)) of OP/1/A/6100/SU-6 (Venting the NC System)

4. Ensure NC System pressure adjusted between 320-350 psig.

5. Ensure that Seal Water Injection flow to each NCP is 8-12 gpm.

6. Ensure that 1NV-127A is aligned to the VCT.

7. Ensure that plant conditions permit the startup of the 1B NC Pump per Attachment 1 of OP/1/A/6150/002 A (Reactor Coolant Pump Operation).

8. Allow plant conditions to stabilize.

9. Freeze the Simulator.

OR

1. Reset to IC-246 (August, 2019) [It may be necessary to run the CTS file to defeat the NCP overcurrent relay: CTS-SET_NCP_51_RELAYDISABLED.CTS]

2. Ensure that Seal Water Injection flow to each NCP is 8-12 gpm.

3. Momentarily go to RUN to acknowledge Alarms then place Simulator in FREEZE.

4. Leave Simulator in FREEZE until operator is ready to begin.

NOTE: During the performance of this JPM, the Simulator Instructor will need to control NCS pressure between 325-350 psig and monitor unrelated alarms and silence as needed.

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Appendix C Page 6 of 13 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT Simulator Instructor NOTE: Leave Simulator in FREEZE until operator is ready to begin.

1 (Step 3.3.1) Check the The operator observes the associated 6900 V supply 1B NC Pump supply breaker closed.

breaker Red status light lit, Green status light OFF.

2 (Step 3.3.2) Check reactor The operator observes that power less than 25%.

the Reactor Trip Breakers are OPEN (or equivalent).

3 (Step 3.3.3) Check 1B NC The operator observes 1B Pump No. 1 Seal D/P is NC Seal P, 1NVP-5220, greater than 200 psid.

and notes P is 300 psid.

4 (Step 3.3.4) Check VCT The operator observes VCT pressure equal to OR Pressure, 1NVP-5500, and greater than 15 psig.

notes pressure is approximately 30 psig.

5 (Step 3.3.5) Check 8 gpm The operator observes 1B seal injection flow NC Pump Seal Flow, 1NVP-established to 1B NC 5320, and notes flow is Pump.

approximately 9.0 gpm.

6 (Notes prior to Step 3.3.6) The operator reads the NORMAL is described as Notes and proceeds.

ZERO static level.

The preferred method to check NC Pump oil level is by visual inspection.

2020 Systems - Control Room JPM H NUREG 1021, Revision 11

Appendix C Page 7 of 13 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 7 (Caution prior to Step 3.3.6) The operator reads the Starting an NC motor with Caution and proceeds.

LOW oil has the risk of an immediate bearing wipe.

8 (Step 3.3.6) Check the The operator uses OAC, following Normal via OAC NCPMPALL (or equivalent),

OR by visual inspection of and notes that lower and 1B NC Pump. upper oil levels - all green.

Upper oil pot level Lower oil pot level Cue:

IF asked, AO reports that all lower and upper oil pot levels are satisfactory.

9 (Step 3.3.7) Check 1NC-29 The operator observes the (B Loop Pzr Spray Control)

B Loop Pzr Spray SLIMS CLOSED.

Red closed light (or equivalent) is LIT.

2020 Systems - Control Room JPM H NUREG 1021, Revision 11

Appendix C Page 8 of 13 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 10 (Notes prior to Step 3.3.8) The operator reads the Effective spray flow can be Notes and proceeds.

achieved with any of the following:

1B NC Pump using 1NC-29 (B Loop Spray Control)

1A, 1C and 1D NC Pumps using 1NC-27 (A Loop Pzr Spray Control)

ND System in RHR Mode using 1NV-840A (ND to Pzr Aux Spray Control)

ND System not in RHR Mode using 1NV-21A (NV Spray to Pzr Isol) 11 (Caution prior to Step 3.3.8) The operator reads the Starting an NC Pump with Caution and proceeds.

either Pressurizer Spray Valve open will increase spray flow and affect NC System pressure.

12 (Step 3.3.8) IF 1A NC Pump The operator observes the OFF, THEN ensure 1NC-27 A Loop Pzr Spray SLIMS (A Loop Pzr Spray Control)

CLOSED. Red closed light (or equivalent) is LIT.

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Appendix C Page 9 of 13 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 13 (Step 3.3.9) IF 1B NC Pump The operator recognizes No. 1 seal leakoff NOT that a 0.2 gpm increase on greater than or equal to the the 1B NC Pump seal minimum leakoff required leakoff flow occurred during per Unit 1 Data Book, pressurization; and perform one of the continues.

following:

(Step 3.3.9.a) Check that a 0.2 gpm increase occurred during pressurization.

OR (Step 3.3.9.b) Perform Attachment 4 (Operator Action for Low No.1 Seal Leakoff Flow) to locally measure flow.

14 (Step 3.3.10) IF either 1B The operator observes that NC Pump Standpipe alarm AD-7/A-2, NC Pump B No.

lit,.. 2 Seal S-Pipe Hi Level, and AD-7/B-2, NC Pump B No.

2 Seal S-Pipe Lo Level, annunciators are EXTINGUISHED.

15 (Step 3.3.11) Ensure all The operator contacts AO personnel are clear of 1B and directs that they ensure NCP Safety Breaker by at that all personnel are clear least 10 feet.

of the 1B NC Pump Safety Breaker by at least 10 feet.

Cue:

AO reports that all personnel are clear of the 1B NC Pump Safety Breaker by at least 10 feet.

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Appendix C Page 10 of 13 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

16 (Step 3.3.12) Two minutes The operator presses the prior to starting 1B NC START pushbutton for Pump, start one of the associated oil lift pumps. either 1B1 or 1B2 Oil Lift Pumps, and observes Red status light LIT, Green status light OFF.

17 (Step 3.3.13) Announce The operator announces starting of 1B NC Pump.

that the 1B NC Pump will be started.

18 (Caution prior Step 3.3.14) The operator reads the In Low Pressure Mode, Caution and proceeds.

PORVs will open on NC Narrow Range Pressure of 378 - 382 psig.

19 (Step 3.3.14) Start 1B NC The operator presses the Pump.

1B NC Pump START pushbutton and observes Red status light LIT, Green status light OFF.

The operator observes Motor amps increase, spike high, and then stabilize lower.

The operator observes NC System flow for the 1B NC Loop increases to 100%.

If the operator notices that bearing temperatures have spiked, it is acceptable to trip the NCP immediately.

20 (Step 3.3.15) Record time The operator records the 1B NC Pump started: time the pump is started in the space provided.

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Appendix C Page 11 of 13 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 21 (Step 3.3.16) IF desired to The operator recognizes stop 1B NC Pump in less that the CRS direction is to than one minute after run the 1B NC Pump until start, either the LOWEST NC Tcold lowers to 74°F, (Not Expected) or the 1B NCP has operated for 60 seconds; and proceeds.

22 (CRS Directed Action) The 60 seconds after pump CRS has directed you to start, the operator presses start the 1B NCP per the 1B NC Pump STOP Section 3.3 of Attachment 1 (Startup and Operation) of pushbutton and observes OP/1/A/6150/002 A Green status light LIT, Red (Reactor Coolant Pump status light OFF.

Operation); and then stop The operator observes the 1B NCP under either of Motor amps lower to 0.

the following conditions:

The operator observes NC

The LOWEST NC Tcold System flow for the 1B NC lowers to 74°F. Loop decrease to 0%.

The 1B NCP has operated for 60 seconds.

23 (Step 3.3.17) WHEN two The operator observes the minutes have elapsed from running Oil Lift Pump Green 1B NC Pump start, THEN status light is LIT Red check the oil lift pump that status light is OFF.

was started has stopped.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Systems - Control Room JPM H NUREG 1021, Revision 11

Appendix C Page 12 of 13 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Systems - Control Room JPM H Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Systems - Control Room JPM H NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

A plant startup is in progress per OP/1/A/6100/001 (Controlling Procedure For Unit Startup).

The crew is implementing Attachment 2 (Venting the NC System (Control Room Activities)) of OP/1/A/6100/SU-6 (Venting the NC System).

The NC System is water solid.

NC System pressure is being maintained between 320-350 psig.

During the NC System pressure increase to the current system pressure, it was noted that the 1B NCP Seal Leakoff flow increased 0.2 gpm.

The crew is ready to conduct an initial 60 second run of the 1B NC Pump.

Attachment 1 (Startup and Operation) of OP/1/A/6150/002 A (Reactor Coolant Pump Operation) has been completed through step 3.1.3 to support NC Pump operation.

Another operator has been assigned to control and maintain NCS pressure during the NCP run.

AOs are standing by in the field to assist.

INITIATING CUE: The CRS has directed you to start the 1B NCP per Section 3.3 of Attachment 1 (Startup and Operation) of OP/1/A/6150/002 A (Reactor Coolant Pump Operation); and then stop the 1B NCP under either of the following conditions:

The LOWEST NC Tcold lowers to 74°F.

The 1B NCP has operated for 60 seconds.

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet IN-PLANT JPM I 2020 Systems - In-Plant JPM I (Rev_011620) NUREG 1021, Revision 11

Appendix C Page 2 of 8 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Emergency Borate the Reactor JPM No.: 2020 Systems - In-Coolant System Locally Using 2NV- Plant JPM I 269 K/A

Reference:

APE 024 AA1.04 (3.6/3.7)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: X Actual Performance:

Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

Initial Conditions:

Unit 2 was at 100% power when a Boron dilution event occurred.

AP/2/A/5500/38 (Emergency Boration and Response to Inadvertent Dilution) was entered.

While attempting to open 2NV-265B (Boric Acid To NV Pumps), the BOP discovered that 2NV-265B was de-energized.

Initiating Cue: The CRS has directed you to emergency borate the NC System by performing Step 12.d RNO of AP/2/A/5500/38 (Emergency Boration and Response to Inadvertent Dilution).

A Portion of this JPM is TIME CRITICAL Task Standard: The operator will attempt to open 2NV-265B, and then open 2NV-269 within ten (10) minutes of dispatch minus transit time from the Control Room to the RCA Entry Point.

2020 Systems - In-Plant JPM I NUREG 1021, Revision 11

Appendix C Page 3 of 8 Form ES-C-1 Job Performance Measure Worksheet Required Materials: PPE (Hardhat, Safety Glasses, Hearing Protection, Safety Shoes etc.)

Dosimetry General

References:

AP/2/A/5500/38 (Emergency Boration and Response to Inadvertent Dilution), Rev 10 OMP 4-3 (Use of Emergency and Abnormal Procedures and FLEX Guidelines), Rev 48 PT/0/A/4600/113 (McGuire Time Critical Actions/Time Sensitive Actions), Enclosure 13.3 (Stop Dilution and Borate During a Dilution Event), Rev 28 Handouts: Handout 1: Step 12.d RNO (Page 8 of 19) of AP/2/A/5500/38 (Emergency Boration and Response to Inadvertent Dilution) marked up for place-keeping.

Time Critical Task: YES - Enclosure 13.3 of PT/0/A/4600/113 Modes 1 and 2: Operators will stop dilution and initiate boration within 15 minutes. This may involve time critical local actions to open NV-265 or NV-269 (10 minutes from dispatch) per AP-38. Time starts when rods reach insertion limit (automatic rod control), or when reactor trips (manual rod control). (If you stop the dilution prior to going below rod insertion limit or reactor trip, emergency boration is not required.)

Only securing dilution within times above is required by the safety analysis, but UFSAR 15.4.6 states that operators can also initiate boration in these stated times. Operators will therefore be required to meet times for both securing dilution and initiating boration. The stated times are long enough for operators to perform actions. Note that UFSAR Section 15.4.6 states that operators have "at least 15 minutes" (Modes 1 and 2). The actual limiting times per UFSAR Table 15-19 are 16.6 minutes when rods are in manual (after trip), and 25.9 minutes when rods are in auto (after reaching rod insertion limit).

Validation Time: 8 minutes NOTE: Start this JPM from the RCA Control Point. Record the Time Critical Completion Time (in JPM step number 2) when 2NV-269 is open.

Critical Step Justification Step 1 This step is critical because locating 2NV-265B, pressing downward on the Motor handwheel clutch, and rotating the handwheel in the counter-clockwise direction is necessary to attempt to open 2NV-265B.

Step 2 This step is critical because locating 2NV-269, removing the locking device, and rotating the handwheel in the counter-clockwise direction is necessary to manually open 2NV-269.

2020 Systems - In-Plant JPM I NUREG 1021, Revision 11

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

1 (Step 12.d RNO) Perform The operator locates 2NV-the following: 265B, presses downward on the Motor handwheel clutch, (Step 12.d RNO 1) Dispatch and rotates the handwheel operator to OPEN 2NV- in the counter-clockwise 265B (aux bldg, 733+3, JJ- direction.

57, near chemical addition tank). Cue:

Handwheel clutch engaged Force applied in the counter-clockwise direction Handwheel is NOT moving The operator recognizes that valve cannot be opened and continues.

2020 Systems - In-Plant JPM I NUREG 1021, Revision 11

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 2 (Step 12.d RNO 2) IF 2NV- The operator locates 2NV-265B cannot be opened, 269, removes the locking THEN perform the device, and rotates the following: handwheel in the counter-

clockwise direction within (Step 12.d RNO 2.a) ten minutes of dispatch.

Dispatch operator to unlock and OPEN 2NV-269 (Unit 2 NV Pump Boric Acid Supply Cue:

Isol (Emergency Boration Valve)) (aux bldg, 733+4, Lock removed, Handwheel JJ-58, near chemical rotated fully counter-addition tank). clockwise.

Stop Time for Time Critical Task:

3 (Step 12.d RNO 2.b) OPEN The operator calls the 2NV-267A (Boric Acid To Control Room to report 2NV-Blender Control). 269 Open and requests that the BOP Open 2NV-267A.

Cue:

The Control Room operator acknowledges that 2NV-269 and 2NV-267A is open.

2020 Systems - In-Plant JPM I NUREG 1021, Revision 11

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 4 (Step 12.d RNO 3) Do not The operator recognizes that continue until 2NV-265B or 2NV-269 is OPEN and 2NV-269 flowpath above is indicates that the task is aligned. complete.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Systems - In-Plant JPM I NUREG 1021, Revision 11

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Systems - In-Plant JPM I Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Systems - In-Plant JPM I NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

Unit 2 was at 100% power when a Boron dilution event occurred.

AP/2/A/5500/38 (Emergency Boration and Response to Inadvertent Dilution) was entered.

While attempting to open 2NV-265B (Boric Acid To NV Pumps), the BOP discovered that 2NV-265B was de-energized.

INITIATING CUE: The CRS has directed you to emergency borate the NC System by performing Step 12.d RNO of AP/2/A/5500/38 (Emergency Boration and Response to Inadvertent Dilution).

A Portion of this JPM is TIME CRITICAL NOTE: No plant equipment should be operated during the performance of this JPM. All actions must be SIMULATED.

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet IN-PLANT JPM J 2020 Systems - In-Plant JPM J (Rev_011620) NUREG 1021, Revision 11

Appendix C Page 2 of 10 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Start the Hydrogen Analyzers JPM No.: 2020 Systems - In-Plant JPM J K/A

Reference:

069 AA1.03 (2.8/3.0)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: X Actual Performance:

Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1.

Initial Conditions:

Unit 1 has tripped from 100% power due to an accident.

The crew is in EP/1/A/5000/FR-Z.1 (Response to High Containment Pressure).

The crew is checking Containment Hydrogen Concentration.

Initiating Cue: The CRS has directed you to place the Hydrogen Analyzers in service in accordance with Enclosure 5 (Placing H2 Analyzers In Service) of EP/1/A/5000/G-1 (Generic Enclosures).

Task Standard: The operator will place the 1A Hydrogen Analyzer in service.

Required Materials: PPE (Hardhat, Safety Glasses, Hearing Protection, Safety Shoes etc.)

Dosimetry KEY #172 (Key 178 will be Simulated)

General

References:

EP/1/A/5000/FR-Z.1 (Response to High Containment Pressure), Rev 19 EP/1/A/5000/G-1 (Generic Enclosures), Rev 41 2020 Systems - In-Plant JPM J NUREG 1021, Revision 11

Appendix C Page 3 of 10 Form ES-C-1 Job Performance Measure Worksheet OMP 4-3 (Use of Emergency and Abnormal Procedures and FLEX Support Guidelines), Rev 48 Handouts: Handout 1: Enclosure 5 (Placing H2 Analyzers In Service) of EP/1/A/5000/G-1 (Generic Enclosures).

Time Critical Task: NO Validation Time: 20 minutes NOTE: The Examiner will need to sign out Key 172 from the WCC before using this JPM.

Critical Step Justification Step 2 This step is critical because going to the 1MICA6851 1A VX HYDROGEN ANALYZER REMOTE CABINET is necessary to place the 1A Hydrogen Analyzer in service.

Step 3 This step is critical because using Key 172 to Open the 1MICA6851 1A VX HYDROGEN ANALYZER REMOTE CABINET is necessary to place the 1A Hydrogen Analyzer in service.

Step 4 This step is critical because is placing Key 178 in the ISOLATION VALVES OPEN switch, and rotating the switch clockwise is necessary to place the 1A Hydrogen Analyzer in service.

Step 6 This step is critical because rotating the "HYDROGEN ANALYZER SAMPLE ENABLE SWITCH" clockwise is necessary to place the 1A Hydrogen Analyzer in service.

Step 7 This step is critical because rotating the "HYDROGEN ANALYZER SAMPLE SELECT" switch counter-clockwise is necessary to place the 1A Hydrogen Analyzer in service.

Step 8 This step is critical because pressing the "OFF" pushbutton for SAMPLE ROUTED TO PAMS PANEL switch is necessary to place the 1A Hydrogen Analyzer in service.

Step 9 This step is critical because rotating the OFF-STANDBY /ANALYZE switch clockwise is necessary to place the 1A Hydrogen Analyzer in service.

Step 10 This step is critical because pressing the "LOCAL/REMOTE SELECTOR" pushbutton is necessary to place the 1A Hydrogen Analyzer in service.

Step 12 This step is critical because rotating the FUNCTION SELECTOR counterclockwise is necessary to place the 1A Hydrogen Analyzer in service.

2020 Systems - In-Plant JPM J NUREG 1021, Revision 11

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1 (Step 1) Obtain one key 172 The operator seeks to find and two keys 178 from "Unit the Keys.

1 EP/AP Keys" on Unit 1 SRO desk.

Cue:

Hand Key 172 to Operator.

The Use of the 178 Key will be simulated during this JPM.

The operator proceeds.

2 (Step 2) Start 1A H2 The operator proceeds to Analyzer as follows: cabinet.

(Step 2.A) Proceed to 1MICA6851 1A VX HYDROGEN ANALYZER REMOTE CABINET (750' elevation in cable spreading room).

3 (Step 2.B) Use key 172 to The operator uses Key 172 access remote panel. to Open Cabinet.

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Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

4 (Step 2.C) Inside remote The operator places Key panel, use key 178 to place 178 in the ISOLATION ISOLATION VALVES VALVES OPEN switch and OPEN switch to ON. rotates the switch clockwise.

Cue:

The Switch is in the ON position.

5 (Step 2.D) Check "POWER The operator observes the ON" light above POWER ON" light.

ISOLATION VALVES OPEN switch - LIT. Cue:

The POWER ON light is LIT.

6 (Step 2.E) Place The operator rotates the "HYDROGEN ANALYZER "HYDROGEN ANALYZER SAMPLE ENABLE SAMPLE ENABLE SWITCH" to "SAMPLE". SWITCH" clockwise.

Cue:

The Switch is in SAMPLE.

2020 Systems - In-Plant JPM J NUREG 1021, Revision 11

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

7 (Step 2.F) Select sample The operator rotates the location as follows: "HYDROGEN ANALYZER SAMPLE SELECT" switch (Step 2.F.1) Place counter-clockwise.

"HYDROGEN ANALYZER SAMPLE SELECT" switch Cue:

to UPPER CONT The Switch is in UPPER (Step 2.F.2) Check CONT.

POWER ON light for selected location - OFF The operator observes the POWER ON" light.

Cue:

The POWER ON light is OFF.

8 (Step 2.G) Depress "OFF The operator presses the pushbutton on SAMPLE "OFF" pushbutton for ROUTED TO PAMS SAMPLE ROUTED TO PANEL switch. PAMS PANEL switch.

9 (Step 2.H) Place OFF- The operator rotates the STANDBY/ANALYZE OFF-STANDBY switch to "ANALYZE" /ANALYZE switch clockwise.

Cue:

The Switch is in Analyze.

10 (Step 2.I) Depress The operator presses the "LOCAL/REMOTE "LOCAL/REMOTE SELECTOR" pushbutton. SELECTOR" pushbutton.

2020 Systems - In-Plant JPM J NUREG 1021, Revision 11

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 11 (Step 2.J) Ensure H2 The operator observes the DUAL RANGE SW is in 0- position of the H2 DUAL 30% range. RANGE SW.

Cue:

The Switch is in the 0-30%

range.

12 (Step 2.K) Place The operator rotates the FUNCTION SELECTOR FUNCTION SELECTOR to SAMPLE. counterclockwise.

Cue:

The Function Selector is in the SAMPLE position.

13 (Step 2.L) Do not continue The operator waits for five until 5 minutes have minutes.

elapsed.

Cue:

Using Time Compression, five minutes have elapsed.

2020 Systems - In-Plant JPM J NUREG 1021, Revision 11

Appendix C Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 14 (Step 2.M) IF COMMON The operator observes the ALARM lit, THEN . COMMON ALARM.

Cue:

The COMMON ALARM light is NOT LIT.

15 (Step 2.N) Notify Control The operator calls the Room that 1A H2 Analyzer control room and reports.

is in service.

Cue:

As the BOP, acknowledge report.

16 (Step 3) Start 1B H2 The operator starts to place Analyzer as follows..... the 1B Hydrogen Analyzer in service.

Cue:

Another Operator will start 1B H2 Analyzer and complete the Enclosure.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Systems - In-Plant JPM J NUREG 1021, Revision 11

Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Systems - In-Plant JPM J Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Systems - In-Plant JPM J NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

Unit 1 has tripped from 100% power due to an accident.

The crew is in EP/1/A/5000/FR-Z.1 (Response to High Containment Pressure).

The crew is checking Containment Hydrogen Concentration.

INITIATING CUE: The CRS has directed you to place the Hydrogen Analyzers in service in accordance with Enclosure 5 (Placing H2 Analyzers In Service) of EP/1/A/5000/G-1 (Generic Enclosures).

NOTE: No plant equipment should be operated during the performance of this JPM. All actions must be SIMULATED.

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet IN-PLANT JPM K 2020 Systems - In-Plant JPM K (Rev_011620) NUREG 1021, Revision 11

Appendix C Page 2 of 16 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Establish NC Pump Seal Injection JPM No.: 2020 Systems - In-From the SSF Plant JPM K K/A

Reference:

EPE 055 EK3.02 (4.3/4.6)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: X Actual Performance:

Classroom Simulator Plant X READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and WHEN the operator locates the Brown Folder at the SSF, provide Handout 1.

Initial Conditions:

A Loss of All AC has occurred on Unit 1.

EP/1/A/5000/ECA-0.0 (Loss of All AC Power) has been implemented.

The CRS has dispatched an operator to complete Enclosure 3 (Unit 1 ETA And ETB Rooms - ECA-0.0 Actions).

Initiating Cue: The CRS has directed you to obtain the Brown Folder at SSF and complete Enclosure 2 (Unit 1 SSF-ECA-0.0 Actions).

A Portion of the JPM is TIME CRITICAL.

Task Standard: The operator will place the SSF Diesel in operation and supply power to 1SLXG, start the Standby Makeup Pump and ensure that it is supplying NCP seal injection within seven (7) minutes of dispatch, ensure that 1SLXG is supplying power to SMXG and SMXG-1, and that Battery Chargers SDSP-1 and SDSP-2 supply breakers are closed.

2020 Systems - In-Plant JPM K NUREG 1021, Revision 11

Appendix C Page 3 of 16 Form ES-C-1 Job Performance Measure Worksheet Required Materials: PPE (Hardhat, Safety Glasses, Hearing Protection, Safety Shoes etc.)

General

References:

EP/1/A/5000/ECA-0.0 (Loss of All AC Power), Rev 44 OMP 4-3 (Use of Emergency And Abnormal Procedures And FLEX Support Guidelines), Rev 48 PT/0/A/4600/113 (McGuire Time Critical Actions/Time Sensitive Actions), Enclosure 13.9 (Initiate SSF NCP Seal Injection and Swap to the SSF), Rev 28 Handouts: Handout 1: Blank copy of Enclosure 2 (Unit 1 SSF - ECA-0.0 Actions) of EP/1/A/5000/ECA-0.0 (Loss of All AC Power)

Time Critical Task: YES: According to PT/0/A/4600/113 (Operator Time Critical Task Verification), Enclosure 13.9 (Initiate SSF NCP Seal Injection and Swap to the SSF): NO Expectation: Seal injection from standby makeup pump can be initiated within 10 minutes of a loss of all AC power event or an NFPA 805 fire event. This requires completion of actions at SSF to start SBMUP within 7 minutes of dispatch, and completion of actions in ETA room to swap EMXA-4 within 4 minutes of dispatch. To support the local actions, the following dispatches must be initiated:

Operator dispatched to SSF within 3 minutes of loss of all NCP seal cooling. (Total time = 7 min + 3 min = 10 min to initiate NCP seal injection from SBMUP).

Consequently, the operator must place the SSF Diesel in operation and supply power to 1SLXG, start the Standby Makeup Pump and ensure that it is supplying NCP seal injection within 7 minutes of dispatch.

This JPM should be timed starting from the OPS Kitchen. Once flow from the standby makeup pump is verified, the critical time stops.

Validation Time: 15 minutes 2020 Systems - In-Plant JPM K NUREG 1021, Revision 11

Appendix C Page 4 of 16 Form ES-C-1 Job Performance Measure Worksheet Critical Step Justification Step 4 This step is critical because rotating the SSF DIESEL TEST/EMERG switch clockwise to EMER is necessary to place the SSF Diesel in operation and supply power to 1SLXG.

Step 6 This step is critical because placing the SSF DIESEL START CONTROL switch to ON is necessary to place the SSF Diesel in operation and supply power to 1SLXG.

Step 8 This step is critical because pressing TRIP for NORMAL INCOMING BREAKER CONTROL and for the two breaker control switches on far right of bottom row holding for two seconds is necessary to place the SSF Diesel in operation and supply power to 1SLXG.

Step 9 This step is critical because pressing CLOSE for GENERATOR BREAKER CONTROL is necessary to place the SSF Diesel in operation and supply power to 1SLXG.

Step 10 This step is critical because pressing CLOSE for 1SLXG-5C CTRL SW is necessary to place the SSF Diesel in operation and supply power to the SBMUP.

Step 12 This step is critical because pressing CLOSE for 1SLXG-4C CTRL SW is necessary to place the SSF Diesel in operation and supply power to the SBMUP.

Step 13 This step is critical because pressing the 1NV-842AC OPEN pushbutton and 1NV-849 AC is necessary to start the Standby Makeup Pump and ensure that it is supplying NCP seal injection within 7 minutes.

Step 15 This step is critical because pressing the 1NV-94AC CLOSE pushbutton is necessary to start the Standby Makeup Pump and ensure that it is supplying NCP seal injection within 7 minutes.

Step 16 This step is critical because pressing the SBMUP START pushbutton is necessary to start the Standby Makeup Pump and ensure that it is supplying NCP seal injection within 7 minutes.

Step 25 This step is critical because resetting the shunt trip and closing breaker SMXG1-FAE is necessary to ensure that 1SLXG is supplying power to SMXG.

Step 28 This step is critical because resetting the shunt trip and closing breaker SMXG1-RAD is necessary to ensure that 1SLXG is supplying power to SMXG-1, and that Battery Chargers SDSP-1 and SDSP-2 supply breakers are closed.

Step 30 This step is critical because pressing the "CLOSE" pushbutton on "1SLXG-5D CTRL SW is necessary to ensure that Battery Chargers SDSP-1 and SDSP-2 supply breakers are closed.

2020 Systems - In-Plant JPM K NUREG 1021, Revision 11

Appendix C Page 5 of 16 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and WHEN the operator locates the Brown Folder at the SSF, provide Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1 (Note prior to Step 1) The The operator reads the following steps are NOTE and proceeds.

performed at SSF Control Panel until stated otherwise.

2 (Step 1) Check LINE The operator observes the VOLTAGE - line voltage meter.

APPROXIMATELY 600V.

Cue:

Meter reads 0 Volts.

3 (Step 1 RNO) GO TO Step Operator goes to Step 3.

3.

4 (Step 3) Place SSF The operator rotates SSF DIESEL DIESEL TEST/EMERG TEST/EMERGENCY switch clockwise to EMER switch to EMER Cue:

Switch rotated clockwise to EMER position.

2020 Systems - In-Plant JPM K NUREG 1021, Revision 11

Appendix C Page 6 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 5 (Step 4) Check SSF The operator observes the DIESEL START SSF DIESEL START CONTROL switch - OFF CONTROL.

Cue:

Switch is in "OFF" position.

6 (Step 5) Place SSF The operator places SSF DIESEL START DIESEL START CONTROL CONTROL switch to ON switch to ON.

Cue:

Switch is rotated clockwise to "ON" position.

7 (Step 6) Check D/G - The operator observes STARTS WITHIN 30 Diesel condition.

SECONDS Cue:

Background noise level has increased, various gage indications are up.

2020 Systems - In-Plant JPM K NUREG 1021, Revision 11

Appendix C Page 7 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

8 (Step 7) Open the following For all nine breakers inside breakers: the yellow time critical border the operator presses TRIP. For the two breaker (Step 7.A) Depress "TRIP" control switches on the far on all nine breaker control right of the bottom row they switches inside yellow time will hold for 2 seconds.

critical border.

Cue:

Pushbuttons depressed, Green lights are LIT.

If the operator did not (Step 7.B) Ensure two already perform on previous breaker control switches on bullet they will depress far right of bottom row were TRIP and hold for two depressed for 2 seconds. seconds for the two breaker control switches on the far right of bottom row. There are no lights for these pushbuttons.

Cue:

Pushbuttons depressed.

9 (Step 8) Depress "CLOSE" The operator presses on "GENERATOR CLOSE for GENERATOR BREAKER CONTROL". BREAKER CONTROL.

Cue:

Pushbutton depressed, Red light is LIT.

2020 Systems - In-Plant JPM K NUREG 1021, Revision 11

Appendix C Page 8 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

10 (Step 9) Depress "CLOSE" The operator presses on "1SLXG-5C CTRL SW". CLOSE for 1SLXG-5C CTRL SW.

Cue:

Pushbutton depressed, Red light is LIT.

11 (Step 10) Wait 10 seconds. The operator waits 10 seconds.

12 (Step 11) Depress "CLOSE" The operator presses on "1SLXG-4C CTRL SW". CLOSE for 1SLXG-4C CTRL SW.

Cue:

Pushbutton depressed, Red light is LIT.

13 (Step 12) Open the The operator presses the following valves: 1NV-842AC OPEN pushbutton, observes Red 1NV-842AC (U1 Standby status light LIT.

Makeup Pump Suction Isol)

The operator presses the 1NV-849AC (U1 Standby 1NV-849AC OPEN Makeup Pump Cont pushbutton, observes Red Outside Isol) status light LIT.

Cue:

As each valve is repositioned, pushbutton depressed, red light is LIT.

2020 Systems - In-Plant JPM K NUREG 1021, Revision 11

Appendix C Page 9 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 14 (Step 13) Check 1NV- The operator observes Red 1013C (Standby M/U Pump status light LIT.

to NC Pmp Seals Isol) -

OPEN Cue:

Red light is LIT.

15 (Step 14) CLOSE 1NV- The operator presses the 94AC (U1 NC Pumps Seal 1NV-94AC CLOSE Water Return Cont Inside pushbutton, and observes Isol) Green status light LIT.

Cue:

Pushbutton depressed, Green light is LIT.

16 (Step 15) Start Unit 1 The operator presses the Standby Makeup pump. SBMUP START pushbutton, observes Red status light LIT.

Cue:

Pushbutton depressed, Red light is LIT.

2020 Systems - In-Plant JPM K NUREG 1021, Revision 11

Appendix C Page 10 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 17 (Step 16) Check Unit 1 The operator observes Standby Makeup pump flow meter (1NVP6420) - GREATER THAN OR EQUAL TO 26 Cue:

GPM.

Meter indicates 28 gpm.

Stop Time for Time Critical Task:

NOTE: This time must be 7 minutes.

18 (Note prior to Step 17) The operator reads the Remaining steps in this NOTE and proceeds.

enclosure are not time critical, but must be completed in a timely manner.

19 (Step 17) Check 1NV- The operator observes 1012C (Standby M/U Pump Green status light LIT.

Disch to Cont Sump) -

CLOSED Cue:

Green light is LIT.

20 (Step 18) Check SSF D/G - The operator observes RUNNING Diesel condition.

Cue:

Background noise level is heard, various gage indications are up.

2020 Systems - In-Plant JPM K NUREG 1021, Revision 11

Appendix C Page 11 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 21 (Step 19) Check SSF D/G The operator observes FREQUENCY - AT 60 Hz. frequency meter.

Cue:

Meter indicates 60 Hz.

22 (Step 20) Check SSF D/G The operator observes VOLTAGE - AT 600V. meter.

Cue:

Meter indicates 600 Volts.

23 (Note prior to Step 21) If The operator reads the SMXG1-FAE and SMXG1- NOTE and proceeds.

RAD were previously shunt tripped from the SSF Control Panel, they will be in their intermediate position.

24 (Step 21) At SMXG1: The operator observes breaker SMXG1-FAE.

(Step 21.A) Check breaker SMXG1-FAE (SDSP1 BATTERY CHARGER) - IN Cue:

INTERMEDIATE POSITION. Breaker is in the Tripped/Intermediate position.

2020 Systems - In-Plant JPM K NUREG 1021, Revision 11

Appendix C Page 12 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

25 (Step 21.B) Reset shunt trip The operator resets the and close breaker SMXG1- shunt trip by sliding the FAE as follows: breaker down to the fully Open position.

(Step 21.B.1) Slide breaker fully to OPEN position. Cue:

(Step 21.B.2) CLOSE breaker. Breaker is down in Open position.

The operator closes the breaker by pushing the breaker up into the Closed position.

Cue:

Breaker is up in the Closed position.

26 (Step 21.C) Wait 10 The operator waits 10 seconds. seconds.

27 (Step 21.D) Check breaker The operator observes SMXG1RAD (SDSP2 breaker SMXG-1 RAD.

BATTERY CHARGER) IN INTERMEDIATE POSITION. Cue:

Breaker is in the Tripped/Intermediate position.

2020 Systems - In-Plant JPM K NUREG 1021, Revision 11

Appendix C Page 13 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

28 (Step 21.E) Reset shunt trip The operator resets the and close breaker SMXG1- shunt trip by sliding the RAD (SDSP2 BATTERY breaker down to the fully CHARGER) as follows: Open position.

(Step 21.E.1) Slide breaker Cue:

fully to OPEN position.

(Step 21.E.2) CLOSE Breaker is down in Open breaker. position.

The operator closes the breaker by pushing the breaker up into the Closed position.

Cue:

Breaker is up in the Closed position.

29 (Step 22) At SMXG: The operator observes breaker position.

(Step 22.A) Ensure SMXG-F5A (UNIT 1 Cue:

PRESSURIZER HEATERS 28/55/56 FEEDER) is Breaker is closed.

CLOSED.

30 (Step 23) At SSF Control The operator presses the Panel: CLOSE pushbutton and observes the Red status (Step 23.A) Depress light.

"CLOSE" on "1SLXG-5D CTRL SW (SDSS Cue:

BATTERY CHARGER FDR BKR CONTROL)". Pushbutton depressed, Red light is LIT.

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Appendix C Page 14 of 16 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 31 (Step 23.B) Check SSF D/G The operator observes SSF FREQUENCY - AT 60 HZ D/G Frequency Meter.

Cue:

Meter indicates 60 Hz.

32 (Step 23.C) Check SSF D/G The operator observes SSF VOLTAGE - AT 600V. D/G Voltage Meter.

Cue:

Meter indicates 600 volts.

33 (Step 23.D) Check SSF The operator observes SSF Generator Load - LESS Generator Load Meter.

THAN OR EQUAL TO 700 KW.

Cue:

Meter indicates 500 KW.

34 (Step 24) Check proper The operator moves toward operation of SSF battery SDSP1 Battery Charger.

chargers in upper level of SSF as follows:

Cue:

Another operator will continue with this procedure.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Systems - In-Plant JPM K NUREG 1021, Revision 11

Appendix C Page 15 of 16 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Systems - In-Plant JPM K Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Systems - In-Plant JPM K NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

A Loss of All AC has occurred on Unit 1.

EP/1/A/5000/ECA-0.0 (Loss of All AC Power) has been implemented.

The CRS has dispatched an operator to complete Enclosure 3 (Unit 1 ETA And ETB Rooms - ECA-0.0 Actions).

INITIATING CUE: The CRS has directed you to obtain the Brown Folder at SSF and complete Enclosure 2 (Unit 1 SSF-ECA-0.0 Actions).

A Portion of the JPM is TIME CRITICAL.

NOTE: No plant equipment should be operated during the performance of this JPM. All actions must be SIMULATED.

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A1a RO 2020 Admin - JPM A1a RO (Rev_011620) NUREG 1021, Revision 11

Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Complete a Surveillance for Mode JPM No.: 2020 Admin - JPM A1a Change RO K/A

Reference:

2.1.20 (4.6)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

Initial Conditions:

Unit 1 is in Mode 4 during a plant startup.

Current EFPD is 348.

NC System pressure has stabilized at 1600 psig.

Chemistry has reported that the CLA Boron Concentrations are as follows:

CLA 1A - 2485 ppm

CLA 1B - 2482 ppm

CLA 1C - 2491 ppm

CLA 1D - 2349 ppm

It has become necessary to perform Enclosure 13.4, NC Boron Concentration Checklist, of PT/1/A/4600/003D, Monthly Surveillance Items, in order to continue with the plant startup.

Initiating Cue:

The CRS has directed you to complete Enclosure 13.4, NC Boron Concentration Checklist, of PT/1/A/4600/003D, Monthly Surveillance Items.

Identify Flex Strategy Administrative Limits and/or Technical Specification LCOs that are not met (if any).

2020 Admin - JPM A1a RO NUREG 1021, Revision 11

Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet Task Standard: The operator will complete Enclosure 13.4 of PT/1/A/4600/003D in accordance with the attached KEY, determine that all Flex Strategy Administrative Limits are met, and determine that LCO 3.5.1 is not currently met.

Required Materials: Calculator General

References:

PT/1/A/4600/003D (Monthly Surveillance Items), Rev 95 MCEI-0400-379 (McGuire Unit 1 Cycle 27 Core Operating Limits Report), Rev 1 McGuire Technical Specification LCO 3.5.1 (Accumulators), Amendment 218/200 Handouts: Handout 1: PT/1/A/4600/003D, Monthly Surveillance Items and Enclosure 13.4, Boron Concentration Checklist marked up for JPM.

Time Critical Task: NO Validation Time: 15 minutes 2020 Admin - JPM A1a RO NUREG 1021, Revision 11

Appendix C Page 4 of 12 Form ES-C-1 Job Performance Measure Worksheet Critical Step Justification Step 3 This step is critical because recording Mode 3 on Enclosure 13.4 is necessary to complete Enclosure 13.4 of PT/1/A/4600/003D in accordance with the attached KEY.

Step 5 This step is critical because using the COLR to determine the minimum required and maximum permitted Accumulator Boron Concentration is necessary to complete Enclosure 13.4 of PT/1/A/4600/003D in accordance with the attached KEY.

Step 8 This step is critical because identifying that CLA 1D is <2400ppm Boron is necessary to complete Enclosure 13.4 of PT/1/A/4600/003D in accordance with the attached KEY.

Step 9 This step is critical because identifying that CLA 1D is <2400ppm Boron is necessary to complete Enclosure 13.4 of PT/1/A/4600/003D in accordance with the attached KEY.

Step 10 This step is critical because determining the average boron concentration of the three CLAs >2400 ppm boron is necessary to complete Enclosure 13.4 of PT/1/A/4600/003D in accordance with the attached KEY.

Step 11 This step is critical because determining the average boron concentration of the four CLAs is necessary to complete Enclosure 13.4 of PT/1/A/4600/003D in accordance with the attached KEY.

Step 12 This step is critical because this step is necessary to determine that all Flex Strategy Administrative Limits are met.

Step 17 This step is critical because this step is necessary to determine that LCO 3.5.1 is not currently met for entry into Mode 3.

Additionally, this step is critical that LCO 3.5.1 is not required in Mode 4.

2020 Admin - JPM A1a RO NUREG 1021, Revision 11

Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1 (Step 1) Prerequisites: The operator recognizes (Step 1.1) IF performing that the Surveillance is NOT routine monthly being performed for the surveillances, THEN Monthly Surveillance and proceeds.

2 (Note prior to Step 1.2) IF The operator reads the performing this procedure in Note and proceeds.

preparation for mode change, Enclosure 13.4 may be performed prior to Mode 3 however, this surveillance shall be met in Mode 3 prior to NC System pressure increasing to greater than 1000 psig.

3 (Step 1.2) IF performing this The operator records Mode procedure prior to entering 3 and Today (or Mode 3 OR Unit in Mode 3 Equivalent), and proceeds.

prior to NC System pressure increasing greater than 1000 psig, THEN NOTE: The Date recorded record the following: is NOT critical.

Mode to be entered: _____

Date: _____

2020 Admin - JPM A1a RO NUREG 1021, Revision 11

Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 4 (Step 2) Check Boron Concentration of Cold Leg Accumulators within limits specified in COLR (Step 2.1) Record the following: The operator records 2485 in the 1A CLA space Cold Leg Accumulator 1A provided.

Cold Leg Accumulator 1B The operator records 2482 Cold Leg Accumulator 1C in the 1B CLA space Cold Leg Accumulator 1D provided.

The operator records 2491 in the 1C CLA space provided.

The operator records 2349 in the 1D CLA space provided.

5 (Step 2.2) Record Cold Leg The operator reviews the Accumulator limits as procedure and Section specified in COLR: 2.11.1 of the Unit 1 COLR and determines that based on a current EFPD of 348, (Min) ____________ ppmB the minimum required (Max) ____________ ppmB Accumulator Boron Concentration is 2350 ppm, and records this in the space provided.

The operator recognizes that the 1D CLA is less than that required by Tech Spec LCO 3.5.1.

The operator reviews the procedure and Section 2.11.1 of the Unit 1 COLR and determines that the maximum allowable Accumulator Boron Concentration is 2875 ppm, and records this in the space provided.

2020 Admin - JPM A1a RO NUREG 1021, Revision 11

Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 6 (Notes prior to Step 3) The The operator reads the FLEX Strategy CLA Notes and proceeds.

minimum Boron Concentration limit is a Beyond Design Basis External Event administrative limit and does NOT affect Tech Spec operability.

The FLEX Strategy Boron Concentration administrative limit for Cold Leg Accumulators is greater than 2400 ppmB.

7 (Step 3) Check FLEX CLA The operator recognizes Boron Concentration that the 1D CLA Boron administrative limit met Concentration is NOT greater than 2400 ppm, and (Step 3.1) IF all Cold Leg proceeds.

Accumulators Boron Concentration greater than 2400 ppmB, THEN.

8 (Step 3.2) IF only one Cold The operator records 1D in Leg Accumulator below the space provided.

2400 ppmB, THEN perform the following:

(Step 3.2.1) Record affected CLA: __________

9 (Step 3.2.2) Record The operator records 2349 affected CLA Boron in the space provided.

Concentration: __________

ppmB 2020 Admin - JPM A1a RO NUREG 1021, Revision 11

Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

10 (Step 3.2.3) Determine The operator records 2485 average Boron in one space provided.

Concentration of the The operator records 2482 other three CLAs: in a second space provided.

[(__________ ppmB [1st The operator records 2491 CLA]) + (__________ in the third space provided.

ppmB [2nd CLA]) + The operator performs the

(__________ ppmB [3rd calculation and determines CLA])] ÷ 3 = ____ that the Average of the

[Avg of other CLAs] Other CLAs is 2486 ppm, and this value is recorded.

11 (Step 3.2.4) Determine The operator records 2349 average CLA Boron in the space provided for Concentration: the Affected CLA.

(_____________ ppmB The operator records 2486

[Affected CLA] + in the space provided for

______________ ppmB the Average of the Other

[Average of other CLAs]) ÷ 2 = CLAs.

_____________ ppmB The operator performs the

[Average CLA Boron Conc] calculation and determines that the Average CLA Boron Concentration is 2417.5-2418 ppm, and this value is recorded.

12 (Step 3.2.5) IF Average The operator recognizes CLA Boron Concentration is that the Average CLA Boron greater than 2400 ppmB, Concentration is greater THEN this surveillance is than 2400 ppm and met. concludes that the Surveillance (i.e. All Flex Strategy Administrative Limits) is met, and proceeds.

13 (Step 3.2.6) IF above The operator recognizes calculation is less than 2400 that this step is NOT ppmB, THEN. applicable, and proceeds.

14 (Note prior to Step 3.3) The operator reads the Steps 3.3.1 and 3.3.2 may Note and proceeds.

be performed concurrently.

2020 Admin - JPM A1a RO NUREG 1021, Revision 11

Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 15 (Step 3.3) IF more than one The operator recognizes CLA is less than 2400 that CLA 1A, 1B and 1C are ppmB, THEN. all greater than 2400 ppm, that this step is NOT applicable, and proceeds.

16 (Step 4) Initial one of the The operator leaves both following: bullets unsigned and hands off the Enclosure to the

No Discrepancy CRS.

Discrepancy Sheet Attached (IF any Acceptance Criteria NOT met, THEN it is identified as a discrepancy, evaluated per Tech Spec/SLC and appropriate corrective action taken.)

17 (Directed Action) Complete The operator recognizes Enclosure 13.4, NC Boron that the 1D CLA is less than Concentration Checklist, of that required by Tech Spec PT/1/A/4600/003D, Monthly LCO 3.5.1 and entry into Surveillance Items. Mode 3 is not allowed.

OR Identify any Flex Strategy LCO 3.5.1 is not applicable Administrative Limits and/or in Mode 4.

Technical Specification LCOs that are not met. The operator recognizes that all Flex Strategy Administrative Limits are met.

NOTE: See Key on Page 11 of JPM and separate document.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Admin - JPM A1a RO NUREG 1021, Revision 11

Appendix C Page 10 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Admin - JPM A1a RO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Admin - JPM A1a RO NUREG 1021, Revision 11

Appendix C Page 11 of 12 Form ES-C-1 VERIFICATION OF COMPLETION KEY:

Are ALL Flex Strategy Administrative Limits met? YES Are ALL Technical Specification LCOs met? NO If NOT, identify requirements NOT met: LCO 3.5.1 See also separate KEY of completed Enclosure 13.4.

2020 Admin - JPM A1a RO NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

Unit 1 is in Mode 4 during a plant startup.

Current EFPD is 348.

NC System pressure has stabilized at 1600 psig.

Chemistry has reported that the CLA Boron Concentrations are as follows:

CLA 1A - 2485 ppm

CLA 1B - 2482 ppm

CLA 1C - 2491 ppm

CLA 1D - 2349 ppm

It has become necessary to perform Enclosure 13.4, NC Boron Concentration Checklist, of PT/1/A/4600/003D, Monthly Surveillance Items, in order to continue with the plant startup.

INITIATING CUE:

The CRS has directed you to complete Enclosure 13.4, NC Boron Concentration Checklist, of PT/1/A/4600/003D, Monthly Surveillance Items.

Identify Flex Strategy Administrative Limits and/or Technical Specification LCOs that are not met (if any).

Are ALL Flex Strategy Administrative Limits met?

Are ALL Technical Specification LCOs met?

If NOT, identify requirements NOT met:

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A1b RO 2020 Admin - JPM A1b RO (Rev_011620) NUREG 1021, Revision 11

Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Verification of Keff <0.99 with JPM No.: 2020 Admin - JPM A1b Shutdown Banks Withdrawn RO K/A

Reference:

2.1.37 (4.3)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

Initial Conditions:

Unit 1 was shutdown 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months ago after having run at 100% power for the previous three weeks.

A Unit 1 startup is in progress per OP/1/A/6100/001 (Controlling Procedure for Unit Startup) and PT/0/A/4150/047 (1/M Monitoring During Startup).

However, all control banks have just been reinserted because the extrapolated critical rod position indicated that criticality would occur below the lower ECP band.

Criticality is now scheduled for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months from now.

The following Cycle 27 conditions exist currently:

EFPD = 25

NC Boron = 1966 PPM

Xenon Worth = 0 PCM

Differential Samarium worth = - 150 PCM

The OAC and REACT Program are unavailable.

It is expected that Tavg will be maintained at its current value of 557°F 2020 Admin - JPM A1b RO NUREG 1021, Revision 11

Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet Initiating Cue: The CRS has directed you to perform Enclosure 4.7 (Verification of Keff

<0.99 with Shutdown Banks Withdrawn) of OP/0/A/6100/006 (Reactivity Balance Calculation) to determine Mode 2 Boron Deficit.

Task Standard: The operator determines that under the current plant conditions there is a 2.6-2.7 ppm Mode 2 Effective Boron Deficit, and that there is sufficient NCS boron concentration to maintain Mode 2. (See attached KEY).

Required Materials: Calculator General

References:

OP/1/A/6100/001 (Controlling Procedure for Unit Startup), Rev 186 PT/0/A/4150/047 (1/M Monitoring During Startup), Rev 7 OP/0/A/6100/006 (Reactivity Balance Calculation), Rev 81 MCEI-0400-380 (McGuire 1 Cycle Startup and Operational Report), Rev 0

MCEI-0400-379 (McGuire 1 Cycle 27 Core Operating Limits Report),

Rev 1 AD-OP-ALL-0203 (Reactivity Management), Rev 11 Handouts: Handout 1: Blank Copy of OP/0/A/6100/006 (Reactivity Balance Calculation)

Time Critical Task: NO Validation Time: 20 minutes 2020 Admin - JPM A1b RO NUREG 1021, Revision 11

Appendix C Page 4 of 12 Form ES-C-1 Job Performance Measure Worksheet Critical Step Justification Step 17 This step is critical because determining the Fission Product Correction is necessary to determine that under the current plant conditions there is a 2.6-2.7 ppm Mode 2 Effective Boron Deficit.

Step 19 This step is critical because selecting and using SOR Table 15 properly is necessary to determine that under the current plant conditions there is a 2.6-2.7 ppm Mode 2 Effective Boron Deficit.

Step 20 This step is critical because selecting and using SOR Table 1 properly is necessary to determine that under the current plant conditions there is a 2.6-2.7 ppm Mode 2 Effective Boron Deficit.

Step 21 This step is critical because completing Table 4.7.1 of Enclosure 4.7 of OP/0/A/6100/006 is necessary to determine that under the current plant conditions there is a 2.6-2.7 ppm Mode 2 Effective Boron Deficit.

Step 22 This step is critical because determining the Mode 2 Effective Boron Deficit is greater than 0 is necessary to determine that under the current plant conditions there is sufficient NCS boron concentration to maintain Mode 2.

2020 Admin - JPM A1b RO NUREG 1021, Revision 11

Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1 (Note prior top Step 3.1) All The operator reads the curves/tables used in this NOTE and proceeds.

procedure, except for the Table referenced in Step 3.1.5, are found in the Control Room Data section of each units Startup and Operational Report (SOR).

2 (Step 3.1) Record the The operator records Unit 1 following: and Cycle 27, and (Step 3.1.1) Unit ___ Cycle proceeds.

3 (Step 3.1.2) Burnup The operator records 25 (P1457) ___________ EFPD.

EFPD 4 (Step 3.1.3) Present/

Desired NC System Effective Boron Concentration:

(Step 3.1.3.1) IF OAC is unavailable: The operator recognizes that the OAC is unavailable, (Step 3.1.3.1.A) Record and records 1966 ppm as Present/Desired NC Boron the present Boron Concentration: Concentration.

(Step 3.1.3.1.B ) Apply 100 The operator applies the ppm B-10 correction 100 ppm B-10 correction penalty:

penalty and records 1866 (Step 3.1.3.1A - 100 ppm) =

ppm as the present Boron

(____________ - 100) = Concentration.

2020 Admin - JPM A1b RO NUREG 1021, Revision 11

Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 5 (Note prior to Step 3.1.3.2) The operator reads the If performing this enclosure NOTE and proceeds.

prior to a dilution and wish to use a desired boron concentration instead of a current boron concentration, Step 3.1.3.2 shall be marked N/A.

6 (Step 3.1.3.2) IF desired to The operator recognizes calculate effective boron that the OAC is unavailable, using the OAC:.. and proceeds.

7 (Step 3.1.3.3) IF desired to The operator recognizes calculate effective boron that it is not desired to manually:.. calculate the effective boron manually, and proceeds.

8 (Step 3.1.3.4) Record the The operator records 1866 Effective Boron ppm as the Effective Boron Concentration: (Step Concentration.

3.1.3.1B or 3.1.3.2C or Step 3.1.3.3C) =

9 (Note prior to Step 3.1.4) If The operator reads the performing this enclosure NOTE and proceeds.

prior to a temperature change, the limiting temperature as described in L&P 1.1.2.3 shall be used for Step 3.1.4. Otherwise, use the present temperature.

10 (Step 3.1.4) Present OR The operator recognizes limiting NC system from initial conditions that temperature: Tavg is 557°F and records.

2020 Admin - JPM A1b RO NUREG 1021, Revision 11

Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 11 (Step 3.1.5) IF EFPD = 0 The operator recognizes AND boron concentration from the initial conditions from Step 3.1.3.4 is greater that EFPD is NOT = 0 or than the Rod Drop boron compares the Rod Drop concentration specified in boron concentration the SOR Table SOR-2:. specified in the SOR Table SOR-2 (1963 ppm) with the Effective Boron Concentration (1866) and recognizes that this step is NA and proceeds.

12 (Step 3.1.6) IF burnup from The operator recognizes step 3.1.2 is > 0 EFPD, that burnup is > 0 EFPD record the difference and records -150 pcm from between equilibrium and initial conditions.

present samarium worth (P1475, OAC Program Xenon Samarium-XESM, or REACT program).

13 (Step 3.1.7) IF burnup from The operator recognizes Step 3.1.2 is > 12 EFPD, that burnup is > 12 EFPD perform Enclosure 4.8 to and that fission product determine the fission correction is needed.

product correction.

14 (Enclosure 4.8, Notes prior The operator reads the to Step 3.1) NOTEs and proceeds.

The values in Table 4.8 (found at the end of this Enclosure) are pulled from MCEI-0400-268, Table 3.

Number of hours shutdown is the difference in time between the time the reactor went subcritical and the expected time of criticality.

2020 Admin - JPM A1b RO NUREG 1021, Revision 11

Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 15 (Step 3.1) Shutdown The operator recognizes Fission Product Correction that Unit 1 operated for >3 Calculation: EFPD from previous (Step 3.1.1) IF Unit shutdown to current operated > 3 EFPD from shutdown and addresses previous shutdown to Table 4.8.

current shutdown:

(Step 3.1.1.1) Use Table 4.8 to determine the shutdown fission product correction:

16 (Step 3.1.1.2) Number of The operator recognizes hours shutdown that the difference in time between the time the reactor went subcritical and the expected time of criticality is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

17 (Step 3.1.1.3) Shutdown The operator records the Fission Product Correction: Fission Product Correction as 10 ppmb and returns to Step 3.1.7 of Enclosure 4.7.

18 (Enclosure 4.7, Step 3.2) IF The operator recognizes desired, perform automated from the initial conditions calculations using REACT that the REACT Program is (Reactivity Balance - Mode NOT available, and places 3 Verification module).. NA in Step 3.2.

2020 Admin - JPM A1b RO NUREG 1021, Revision 11

Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

19 (Step 3.3) Manual The operator uses Table 15 Calculations: (Handout 2) and determines (Step 3.3.1) Mode 2 Boron Mode 2 boron concentration Concentration: with shutdown banks withdrawn, control banks (Step 3.3.1.1) Determine inserted, no xenon for 25 Mode 2 boron concentration EFPD and 557°F is 1877 with shutdown banks PPMB.

withdrawn, control banks inserted, no xenon at the burnup recorded in Step The operator records 1877 3.1.2 and temperature of on Line A of Table 4.7.1.

Step 3.1.4 (Table 15 in the SOR).

(Step 3.3.1.2) Record value in Table 4.7.1 Line A

20 (Step 3.3.2) ARI Differential The operator uses Table 1 boron worth: (Handout 2) and determines (Step 3.3.2.1) Determine that the ARI Differential ARI Differential Boron Boron Worth at 25 EFPD at Worth at burnup recorded in 557°F is -6.34 PCM/PPM.

Step 3.1.2 and temperature of Step 3.1.4 (Table 1 in the The operator records -6.34 SOR). on Line B of Table 4.7.1.

(Step 3.3.2.2) Record value in Table 4.7.1 Line B 2020 Admin - JPM A1b RO NUREG 1021, Revision 11

Appendix C Page 10 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

21 (Step 3.3.3) Mode 2 boron The operator records 1866 deficit: ppm in Line C Table 4.7.1.

(Step 3.3.3.1) Record values of Steps 3.1.3.4, The operator records -150 3.1.6 and 3.1.7 in Table pcm in Line D Table 4.7.1.

4.7.1.

(Step 3.3.3.2) Complete Table 4.7.1, recording 0 The operator records 10 for any reference steps N/A. ppmb in Line E Table 4.7.1.

The operator calculates F on Table 4.7.1 to be 23.66 (23.6 to 23.7) ppm (F = D/B or -150 pcm/-6.34 pcm/ppm

= 23.66 ppm [23.6 to 23.7])

The operator calculates Mode 2 Effective Boron Deficit on Table 4.7.1 to be 2.6-2.7 ppm (M2 EBD = C-A-E+F or 1866 ppm -1877 ppm - 10 + 23.66 (23.6 to 23.7) = 2.6-2.7 ppm)

22 (Step 3.3.4) IF Mode 2 The operator determines Effective Boron Deficit from that the current NC Table 4.7.1 > 0: conditions are sufficient in a (Step 3.3.4.1) Sufficient NC xenon free condition to boron is present in xenon prevent entering Mode 2, free condition to prevent and marks all remaining entering Mode 2. Steps NA.

(Step 3.3.4.2) Mark remainder of Enclosure N/A.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Admin - JPM A1b RO NUREG 1021, Revision 11

Appendix C Page 11 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Admin - JPM A1b RO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Admin - JPM A1b RO NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET Initial Conditions:

Unit 1 was shutdown 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months ago after having run at 100%

power for the previous three weeks.

A Unit 1 startup is in progress per OP/1/A/6100/001 (Controlling Procedure for Unit Startup) and PT/0/A/4150/047 (1/M Monitoring During Startup).

However, all control banks have just been reinserted because the extrapolated critical rod position indicated that criticality would occur below the lower ECP band.

Criticality is now scheduled for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months from now.

The following Cycle 27 conditions exist currently:

EFPD = 25

NC Boron = 1966 PPM

Xenon Worth = 0 PCM

Differential Samarium worth = - 150 PCM

The OAC and REACT Program are unavailable.

It is expected that Tavg will be maintained at its current value of 557°F INITIATING CUE: The CRS has directed you to perform Enclosure 4.7 (Verification of Keff <0.99 with Shutdown Banks Withdrawn) of OP/0/A/6100/006 (Reactivity Balance Calculation) to determine Mode 2 Boron Deficit.

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A2 RO 2020 Admin - JPM A2 RO (Rev_011620) NUREG 1021, Revision 11

Appendix C Page 2 of 12 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Partial Loss of Annunciators JPM No.: 2020 Admin - JPM A2 RO K/A

Reference:

GK/A 2.2.43 (3.0)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1-2.

Initial Conditions:

Unit 1 is operating at 100% power.

Due to a lightning strike several of the Unit 1 Control Room Annunciators have failed.

The crew entered PT/1/A4600/033 (Loss of Control Room Annunciators) and has completed Attachment 2 (Partial Loss of Annunciator Panels) through Step 3.8.

Several Operators are reviewing the Annunciator Response Procedures for each failed annunciator.

All other annunciators have been tested satisfactorily.

The IAE Supervisor has been notified and is investigating.

Initiating Cue: The CRS has directed you to perform step 3.9 of Attachment 2 for the failed Annunciators on 1AD-13 (Marked in YELLOW on Attached Handout).

2020 Admin - JPM A2 RO NUREG 1021, Revision 11

Appendix C Page 3 of 12 Form ES-C-1 Job Performance Measure Worksheet

The CRS has directed you to determine:

IF any AP or EP that has a Time Critical Task has been affected

IF any Technical Specification or Selected Licensee Commitment surveillance has been affected

IF any proceduralized Alternate Action must be taken Task Standard: The operator will determine that there are Alternative Methods procedurally identified for Surveillance associated with three of these annunciators, that one failure impacts the Semi-Daily Surveillance associated with TS SR 3.6.4.1, that one failure impacts the Daily Surveillance associated with SLC 16.7.3, that one failure impacts the Daily Surveillance associated with SLC 16.9.26, and that one failure impacts an AP/EP Time Critical Task per the attached KEY.

Required Materials: None General

References:

PT/1/A/4600/033 (Loss of Control Room Annunciators), Rev 11 PT/1/A/4600/003 A (Semi-Daily Surveillance Items), Rev 170 PT/1/A/4600/003 B (Daily Surveillance Items), Rev 172 OP/1/A/6100/010 N (Annunciator Response For Panel 1AD-13), Rev 80 PT/0/A/4600/113 (McGuire Time Critical Actions/Time Sensitive Actions), Rev 28 AP/0/A/5500/44 (Plant Flooding), Rev 21 Handouts: Handout 1: PT/1/A4600/033 (Loss of Control Room Annunciators) marked up for place-keeping.

Handout 2: Failed Annunciators Time Critical Task: NO Validation Time: 25 minutes 2020 Admin - JPM A2 RO NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet Critical Step Justification Step 1 This step is critical because determining that 1AD-13, B1 has no Alternate Method of Surveillance, that an AP/EP Time Critical Action is NOT affected, and that this alarm failure has no bearing on the surveillances of Enclosure 13.1 of PT/1/A/4600/003 A & Enclosure 13.1 of PT/1/A/4600/003 B is necessary to complete the assigned task.

Step 2 This step is critical because determining the Alternate Method of Surveillance and determining that an 1AD-13, B3 alarm failure affects Enclosure 13.1 of PT/1/A/4600/003 A (Semi-Daily Surveillance Items), specifically the surveillance associated with TS SR 3.6.4.1; and has no other impact, is necessary to complete the assigned task.

Step 3 This step is critical because determining the Alternate Method of Surveillance and determining that an 1AD-13, C1 alarm failure affects the performance of an AP/EP Time Critical Task is necessary to complete the assigned task.

Step 4 This step is critical because determining the Alternate Method of Surveillance and determining that an 1AD-13, C4 alarm failure affects Enclosure 13.1 of PT/1/A/4600/003 B (Daily Surveillance Items), specifically the surveillance associated with SLC 16.7.3; and has no other impact, is necessary to complete the assigned task.

Step 5 This step is critical because determining that 1AD-13, E7 has no Alternate Method of Surveillance, that an AP/EP Time Critical Action is NOT affected, and that this alarm failure has no bearing on the surveillances of Enclosure 13.1 of PT/1/A/4600/003 A & Enclosure 13.1 of PT/1/A/4600/003 B is necessary to complete the assigned task.

2020 Admin - JPM A2 RO (Rev_011620) NUREG 1021, Revision 11

Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1-2.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT NOTE: The operator may desire to review the Annunciator Response Procedure for any of the five Annunciators. A copy of OP/1/A/6100/010 N (Annunciator Response For Panel 1AD-13) should be available for this review.

1 (PT/1/A/4600/033, The operator addresses Attachment 2, Step 3.9) Attachment 3 of Perform Attachment 3, PT/1/A/4600/033 and Annunciator Panel recognizes that this Reference to evaluate the Annunciator has no following: Alternate Method of Surveillance and that an

Alternate indications AP/EP Time Critical Action available for affected is NOT affected.

alarms The operator reviews

Impact to Ops PTs Enclosure 13.1 of (Semi Daily, Daily, etc.) PT/1/A/4600/003 A &

Enclosure 13.1 of 1AD-13, B1, FWST YARD PT/1/A/4600/003 B and LINE CONTENTS LO determines that this alarm TEMP failure has no bearing on these surveillances.

NOTE:

The evaluation of the Annunciators may be performed in ANY order.

NOTE:

See KEY on Page 11.

2020 Admin - JPM A2 RO NUREG 1021, Revision 11

Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

2 (PT/1/A/4600/033, The operator addresses Attachment 2, Step 3.9) Attachment 3 of Perform Attachment 3, PT/1/A/4600/033 and Annunciator Panel determines that the Reference to evaluate the Alternate Method of following: Surveillance requires that OAC alarm for M1P4295 be

Alternate indications set at +0.2 psig.

available for affected alarms The operator addresses Attachment 3 of

Impact to Ops PTs PT/1/A/4600/033 and (Semi Daily, Daily, etc.) determines that an AP/EP Time Critical Action is NOT 1AD-13, B3, CONT PRESS affected.

ALERT HI The operator reviews Enclosure 13.1 of PT/1/A/4600/003 A and determines that this alarm failure affects Enclosure 13.1, specifically the surveillance associated with TS SR 3.6.4.1.

The operator reviews Enclosure 13.1 of PT/1/A/4600/003 B and determines that this alarm failure has no bearing on these surveillances.

NOTE:

See KEY on Page 11.

2020 Admin - JPM A2 RO NUREG 1021, Revision 11

Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

3 (PT/1/A/4600/033, The operator addresses Attachment 2, Step 3.9) Attachment 3 of Perform Attachment 3, PT/1/A/4600/033 and Annunciator Panel determines that the Reference to evaluate the Alternate Method of following: Surveillance requires that the operator monitor the

Alternate indications ND/NS sump levels locally.

available for affected alarms The operator addresses Attachment 3 of

Impact to Ops PTs PT/1/A/4600/033 and (Semi Daily, Daily, etc.) determines that the failure of this alarm will affect the 1AD-13, C1, ND & NS performance of a Time ROOM SUMP HI-HI LVL Critical Task in an AP or EP.

The operator reviews Enclosure 13.1 of PT/1/A/4600/003 A &

Enclosure 13.1 of PT/1/A/4600/003 B and determines that this alarm failure impacts the performance of Enclosure 13.1, specifically the surveillance associated with SLC 16.9.26.

NOTE:

See KEY on Page 11.

2020 Admin - JPM A2 RO NUREG 1021, Revision 11

Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

4 (PT/1/A/4600/033, The operator addresses Attachment 2, Step 3.9) Attachment 3 of Perform Attachment 3, PT/1/A/4600/033 and Annunciator Panel determines that the Reference to evaluate the Alternate Method of following: Surveillance requires that the operator verify that the

Alternate indications chart recorders readout is available for affected updating.

alarms The operator addresses

Impact to Ops PTs Attachment 3 of (Semi Daily, Daily, etc.) PT/1/A/4600/033 and determines that an AP/EP 1AD-13, C4, Time Critical Action is NOT ENVIRONMENT SYSTEM affected.

TROUBLE The operator reviews Enclosure 13.1 of PT/1/A/4600/003 and determines that this alarm failure has no bearing on these surveillances.

The operator reviews Enclosure 13.1 of PT/1/A/4600/003 B and determines that this alarm failure impacts the performance of Enclosure 13.1, specifically the surveillance associated with SLC 16.7.3.

NOTE:

See KEY on Page 11.

2020 Admin - JPM A2 RO NUREG 1021, Revision 11

Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 5 (PT/1/A/4600/033, The operator addresses Attachment 2, Step 3.9) Attachment 3 of Perform Attachment 3, PT/1/A/4600/033 and Annunciator Panel recognizes that this Reference to evaluate the Annunciator has no following: Alternate Method of Surveillance and that an

Alternate indications AP/EP Time Critical Action available for affected is NOT affected.

alarms The operator reviews

Impact to Ops PTs Enclosure 13.1 of (Semi Daily, Daily, etc.) PT/1/A/4600/003 A &

Enclosure 13.1 of 1AD-13, E7, O.B.E. PT/1/A/4600/003 B and EXCEEDED determines that this alarm failure has no bearing on these surveillances.

NOTE:

See KEY on Page 11.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Admin - JPM A2 RO NUREG 1021, Revision 11

Appendix C Page 10 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Admin - JPM A2 RO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Admin - JPM A2 RO NUREG 1021, Revision 11

Appendix C Page 11 of 12 Form ES-C-1 VERIFICATION OF COMPLETION KEY:

Failed Annunciator AP/EP w/TC Task TS/SLC Affected Alternate Action 1AD-13, B1, FWST YARD LINE NO None None CONTENTS LO TEMP 1AD-13, B3, CONT NO TS SR 3.6.4.1 OAC alarm for PRESS ALERT HI M1P4295 be set at

+0.2 psig 1AD-13, C1, ND & YES SLC 16.9.26 The operator will NS ROOM SUMP HI- (New critical Task) monitor the ND/NS HI LVL sump levels locally 1AD-13, C4, NO SLC 16.7.3 The operator verify ENVIRONMENT that the chart SYSTEM TROUBLE recorders readout is updating.

1AD-13, E7, O.B.E. NO None None EXCEEDED RED = Critical NOTE: Annunciators may be listed in ANY order.

2020 Admin - JPM A2 RO NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET Initial Conditions:

Unit 1 is operating at 100% power.

Due to a lightning strike several of the Unit 1 Control Room Annunciators have failed.

The crew entered PT/1/A4600/033 (Loss of Control Room Annunciators) and has completed Attachment 2 (Partial Loss of Annunciator Panels) through Step 3.8.

Several Operators are reviewing the Annunciator Response Procedures for each failed annunciator.

All other annunciators have been tested satisfactorily.

The IAE Supervisor has been notified and is investigating.

INITIATING CUE:

The CRS has directed you to perform step 3.9 of Attachment 2 for the failed Annunciators on 1AD-13 (Marked in YELLOW on Attached Handout).

The CRS has directed you to determine:

IF any AP or EP that has a Time Critical Task has been affected

IF any Technical Specification or Selected Licensee Commitment surveillance has been affected

IF any proceduralized Alternate Action must be taken Failed Annunciator AP/EP w/TC Task TS/SLC Affected Alternate Action YES / NO YES / NO YES / NO YES / NO YES / NO (Use Back if More Space Needed)

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A3 RO 2020 Admin - JPM A3 RO (Rev_011620) NUREG 1021, Revision 11

Appendix C Page 2 of 7 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Evaluate Stay Time with Lowered JPM No.: 2020 Admin - JPM A3 SFP Level RO K/A

Reference:

2.3.7 (3.5)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

Initial Conditions:

A station wide accident has occurred due to an Earthquake.

Unit 1 is in Mode 6 with a complete core off-load.

The Unit 1 Spent Fuel Pool level has lowered to 10 feet above the top of the fuel and has stabilized at this level.

The crew is implementing AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level) and EP/1/A/5000/G-1 Generic Enclosures),

Enclosure 32 (Monitoring Unit 1 SFP Level and Temperature).

No installed radiation monitors are operable in the Unit 1 Spent Fuel Building.

A dose limit of 500 mrem has been placed on all personnel performing emergency tasks within the building.

You have been assigned a repetitive task within Generic Enclosure 32 which will require you to enter the Unit 1 Spent Fuel Building and proceed to the area around the Spent Fuel Pool, and remain there for 8 minutes, before exiting the building.

The exposure traveling to and from the Unit 1 Spent Fuel Pool area results in no appreciable exposure.

2020 Admin - JPM A3 RO NUREG 1021, Revision 11

Appendix C Page 3 of 7 Form ES-C-1 Job Performance Measure Worksheet Initiating Cue: The CRS has directed you to use Enclosure 13 (Spent Fuel Pool Radiation Level Vs. Water Level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level), and determine the number of times you will be able to perform this repetitive task before you must be replaced by another operator.

Task Standard: The operator will use Enclosure 13 of AP/1/A/5500/41 to determine that the dose rate around the Spent Fuel Pool area is 649 mrem/hour and based on this the operator will determine that the repetitive task can be performed 5 times before another operator will need to perform the task.

Required Materials: Calculator General

References:

AP/1/A/5500/41 (Loss of Spent Fuel Pool Cooling or Level), Rev 15 EP/1/A/5000/G-1 (Generic Enclosures), Rev 41 MNS SLC 16.9.21 (Water Level - Spent Fuel Storage Pool), Rev 155 PD-RP-ALL-0001 (Radiation Worker Responsibilities), Rev 11 Handouts: Handout 1: Enclosure 13 (Spent Fuel Pool Radiation Level Vs. Water Level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level)

Time Critical Task: NO Validation Time: 7 minutes Critical Step Justification Step 1 This step is critical because using Enclosure 13 and determining that the dose rate around the pool area is 649 mrem/hour is necessary to complete the assigned task.

Step 2 This step is critical because determining the dose received for one performance of the task is necessary to complete the assigned task.

Step 3 This step is critical because determining the number of times the operator will be able to perform this repetitive task before they must be replaced by another operator is necessary to complete the assigned task.

2020 Admin - JPM A3 RO NUREG 1021, Revision 11

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

1 (AP/1/A/5500/41, The operator uses Enclosure 13) Determine Enclosure 13 and the Dose Rate around the determines that the dose Spent Fuel Pool area with rate around the pool water level at 10 feet. area is 649 mrem/hour.

6.49E-01R/hr OR (6.49 x 10-1 R/hr) x 103 mrem/R = 649 mrem/hr

2 Determine Dose received The operator recognizes each time task is that the task requires performed eight minutes.

The operator determines that the dose received in that eight-minute period is 86.53 mrem (86-87 mrem).

Dose = 649 mrem/hr x 1hr/60 minutes x 8 minutes 2020 Admin - JPM A3 RO NUREG 1021, Revision 11

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

3 Determine the number of The operator recognizes times that the repetitive that the maximum task can be performed allowable dose received while remaining within is 500 mrem, and that allowable RWP dose limit. 86.53 (86-87 mrem) mrem will be received on each occasion the task is performed.

The operator identifies that the task can be performed 5 times, before another operator will be required to perform the task.

Task performances =

500 mrem/86.53 (86-87 mrem) mrem/task = 5.78 tasks, or 5 tasks.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Admin - JPM A3 RO NUREG 1021, Revision 11

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Admin - JPM A3 RO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Admin - JPM A3 RO NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

A station wide accident has occurred due to an Earthquake.

Unit 1 is in Mode 6 with a complete core off-load.

The Unit 1 Spent Fuel Pool level has lowered to 10 feet above the top of the fuel and has stabilized at this level.

The crew is implementing AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level) and EP/1/A/5000/G-1 Generic Enclosures),

Enclosure 32 (Monitoring Unit 1 SFP Level and Temperature).

No installed radiation monitors are operable in the Unit 1 Spent Fuel Building.

A dose limit of 500 mrem has been placed on all personnel performing emergency tasks within the building.

You have been assigned a repetitive task within Generic Enclosure 32 which will require you to enter the Unit 1 Spent Fuel Building and proceed to the area around the Spent Fuel Pool, and remain there for 8 minutes, before exiting the building.

The exposure traveling to and from the Unit 1 Spent Fuel Pool area results in no appreciable exposure.

INITIATING CUE: The CRS has directed you to use Enclosure 13 (Spent Fuel Pool Radiation Level Vs. Water Level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level), and determine the number of times you will be able to perform this repetitive task before you must be replaced by another operator.

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A1a SRO 2020 Admin - JPM A1a SRO (Rev_011620) NUREG 1021, Revision 11

Appendix C Page 2 of 9 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Determine Reportability JPM No.: 2020 Admin - JPM A1a Requirements SRO K/A

Reference:

2.1.18 (3.8)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

Initial Conditions:

With Unit 1 at 100% power, the following event occurred at 0400 today:

The crew was removing Pzr Heater Groups A, B and D from service when an automatic plant trip on low pressurizer pressure occurred due to an operational error.

The crew entered EP/1/A/5000/E-0, Reactor Trip or Safety Injection, and quickly stabilized pressurizer pressure before transitioning to EP/1/A/5000/ES-0.1, Reactor Trip Response, where the plant was stabilized.

The SM has verified that this event has NOT exceeded an Emergency Action Level (EAL).

The SM and the STA believe that this event is reportable to the NRC.

No external persons and/or agencies have been notified of this event, nor have any actions other than those identified been taken.

Initiating Cue: Ten minutes after the event the SM directs you to determine reportability requirements per RP/0/A/5700/010 (NRC Immediate Notification Requirements), including completion of any necessary paperwork (Provide to Examiner when ready to Transmit).

2020 Admin - JPM A1a SRO NUREG 1021, Revision 11

Appendix C Page 3 of 9 Form ES-C-1 Job Performance Measure Worksheet Task Standard: The operator will identify that this condition requires a 4-hour notification to the NRC in accordance with RP/0/A/5700/010 (NRC Immediate Notification Requirements), and complete Attachment 2 (NRC Event Notification Worksheet) in accordance with the attached Key.

Required Materials: None General

References:

RP/0/A/5700/010 (NRC Immediate Notification Requirements), Rev. 31 RP/0/A/5700/014 (Emergency Telephone Directory), Rev. 39 AD-OP-ALL-0101 (Event Response and Notifications), Rev. 11 Handouts: Handout 1: Blank copy of RP/0/A/5700/010.

Time Critical Task: NO Validation Time: 20 minutes Critical Step Justification Step 3 This step is critical because determining that Event Condition 4.1.3.3 is applicable and that this event must be reported as soon as practical and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the occurrence is necessary to complete the assigned task.

Step 6 This step is critical because Completing Attachment 2 of RP/0/A/5700/010 (NRC Immediate Notification Requirements) is necessary to complete the assigned task in accordance with the attached Key.

2020 Admin - JPM A1a SRO NUREG 1021, Revision 11

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

START TIME:

S TEPS ELEMENTS S TANDARD S /U COMMENTS REQUIRED FOR UNS AT 1 (Step 6.1) Notify the NRC The operator places initials Operations Center in in block and proceeds.

accordance with this procedure.

2 (Step 6.2) Ensure the Shift The operator recognizes Technical Advisor is aware that the STA is aware of the of the pending NRC pending NRC notification notification. (Initial Conditions), checks the block and proceeds.

2020 Admin - JPM A1a SRO NUREG 1021, Revision 11

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION S TEPS ELEMENTS S TANDARD S /U COMMENTS REQUIRED FOR UNS AT

3 (Step 6.3) Determine The operator addresses appropriate notification AND Attachment 1.

time requirements using Attachment 1, Events The operator recognizes Requiring NRC Notification. that Event Condition 4.1.3.3 is applicable and that this event must be reported as soon as practical and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the occurrence.

4.1.3.3:

Any event OR condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from AND is part of a pre-planned sequence during testing OR reactor operation.

The operator may check

[(50.72(b)(3)(IV)(A)] Valid Actuation of System listed in Attachment 3 Block (8-hour report) - Not Critical.

4 (Note prior to Step 6.4) The operator reads the Sections of Attachment 2 Note, checks the block and that are not applicable proceeds.

should be marked (N/A).

5 (Step 6.4) IF Attachment 2, The operator records that NRC Event Notification this is a drill, and proceeds.

Worksheet being completed OR for a drill, THEN write: "This The operator does not is a Drill" on the first line of record that this is a drill, and event description. proceeds.

2020 Admin - JPM A1a SRO NUREG 1021, Revision 11

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION S TEPS ELEMENTS S TANDARD S /U COMMENTS REQUIRED FOR UNS AT 6 (Step 6.5) Complete The operator completes

applicable portions of Attachment 2 in accordance (As shown on Attachment 2 using with the Attached Key.

KEY) information from Attachment 1.

Cue:

After the Attachment 2 is presented for transmittal, indicate that another operator will complete the required actions.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Admin - JPM A1a SRO NUREG 1021, Revision 11

Appendix C Page 7 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Admin - JPM A1a SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Admin - JPM A1a SRO NUREG 1021, Revision 11

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION KEY: NRC Event Notification Worksheet Page 1 of 3 All blocks left blank except as follows:

Notification Time/Date: (Left Blank)

Unit 1 Callers Name Operators Name NRC Operations Officer (Left Blank)

Contacted Event Time and Zone 0400 (time)

Event Date Present Date Power/Mode Before 100%/Mode 1 Power/Mode After 0%/Mode 3 4-Hr Non-Emergency Check Mark in [(50.72(b)(2)(IV)(B)] RPS Actuation -

Critical Scram Block. The operator may check

[(50.72(b)(3)(IV)(A)] Valid Actuation of System listed in Attachment 3 Block (8-hour report) - Not Critical. NRC Event Notification Worksheet Page 2 of 3 All blocks left blank except as follows:

Event Description The crew was removing Pzr Heater Groups A, B and D from service when an automatic plant trip on low pressurizer pressure occurred due to an operational error. The crew entered EP/1/A/5000/E-0, Reactor Trip or Safety Injection, and quickly stabilized pressurizer pressure before transitioning to EP/1/A/5000/ES-0.1, Reactor Trip Response, where the plant was stabilized (Or Equivalent).

Notifications: NRC Resident Will Be is checked Notifications: State NO or Will Be is checked Notifications: Local NO or Will Be is checked Notifications: Other Gov NO or Will Be is checked Agencies Notifications: Media/Press NO or Will Be is checked Release Anything Unusual or NOT NO is checked understood?

Did all Systems Function as YES is checked.

required Approved By: Operators Name Time/Date: Estimated Time and Date NRC Event Notification Worksheet Page 3 of 3 - All blocks lined out with NA and Initials.

CRITICAL Information is in BOLD 2020 Admin - JPM A1a SRO NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET Initial Conditions:

With Unit 1 at 100% power, the following event occurred at 0400 today:

The crew was removing Pzr Heater Groups A, B and D from service when an automatic plant trip on low pressurizer pressure occurred due to an operational error.

The crew entered EP/1/A/5000/E-0, Reactor Trip or Safety Injection, and quickly stabilized pressurizer pressure before transitioning to EP/1/A/5000/ES-0.1, Reactor Trip Response, where the plant was stabilized.

The SM has verified that this event has NOT exceeded an Emergency Action Level (EAL).

The SM and the STA believe that this event is reportable to the NRC.

No external persons and/or agencies have been notified of this event, nor have any actions other than those identified been taken.

INITIATING CUE: Ten minutes after the event the SM directs you to determine reportability requirements per RP/0/A/5700/010 (NRC Immediate Notification Requirements), including completion of any necessary paperwork (Provide to Examiner when ready to Transmit).

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A1b SRO 2020 Admin - JPM A1b SRO (Rev_011620) NUREG 1021, Revision 11

Appendix C Page 2 of 11 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Perform Daily Surveillance Items JPM No.: 2020 Admin - JPM A1b Checklist SRO K/A

Reference:

2.1.1 (4.2)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

Initial Conditions:

Unit 1 is in Mode 1 at 100% power.

Fire Hydrant 10 (W of Main Shop) is OOS and all other equipment is operable and/or functional.

Enclosure 13.1, Daily Surveillance Items Checklist, of PT/1/A/4600/003B, Daily Surveillance Items, has been completed.

Enclosure 13.3, Cask Monitoring, is still in progress and will be provided when complete.

The Unit 1 VA System is undergoing scheduled maintenance (i.e.

VA Down Day)

Initiating Cue:

Evaluate the completed Enclosure 13.1 of PT/1/A/4600/003B (Daily Surveillance Items Checklist) per Step 12.

Identify all Technical Specification/SLC required ACTION, as well as all other actions that must be taken so that an ESOMS entry can be prepared.

2020 Admin - JPM A1b SRO NUREG 1021, Revision 11

Appendix C Page 3 of 11 Form ES-C-1 Job Performance Measure Worksheet Task Standard: The operator will review the completed Enclosure 13.1, Daily Surveillance Items Checklist and associated Equipment Problem Identification Form and verify that the applicable surveillance items meet specified acceptance criteria. For surveillance items NOT meeting Acceptance Criteria, all required action will be identified per the attached KEY.

Required Materials: None General

References:

PT/1/A/4600/003B, (Daily Surveillance Items), Rev 172 AD-HU-ALL-0004, (Procedure and Work Instruction Use and Adherence), Rev 10 McGuire Technical Specifications LCO 3.5.4 (Refueling Water Storage Tank (RWST)), Amendment 184/166 McGuire Selected Licensee Commitments (SLC) 16.9.11 (Borated Water Sources (Operating)) Rev 22 McGuire Selected Licensee Commitments (SLC) 16.9.14 (Borated Water Sources (Shutdown)) Rev 177 McGuire Selected Licensee Commitments (SLC) 16.11.2 (Radioactive Liquid Effluent Monitoring Instrumentation) Rev 134 McGuire Selected Licensee Commitments (SLC) 16.11.7 (Radioactive Gaseous Effluent Monitoring Instrumentation) Rev 134 Handouts: Handout 1: Enclosure 13.1 (Daily Surveillance Items Checklist) of PT/1/A/4600/003 B (Daily Surveillance Items) and an associated Equipment Problem Evaluation Form, marked up for this JPM.

Time Critical Task: NO Validation Time: 25 minutes 2020 Admin - JPM A1b SRO NUREG 1021, Revision 11

Appendix C Page 4 of 11 Form ES-C-1 Job Performance Measure Worksheet Critical Step Justification Step 1 This step is critical because assessing the difference between the two VCT level instruments is necessary to ensure that all required action is identified per the attached KEY for surveillance items NOT meeting Acceptance Criteria.

Step 2 This step is critical because assessing the low FWST temperature is necessary to ensure that all required action is identified per the attached KEY for surveillance items NOT meeting Acceptance Criteria.

Step 3 This step is critical because assessing the unsuccessful source check on 1EMF31 is necessary to ensure that all required action is identified per the attached KEY for surveillance items NOT meeting Acceptance Criteria.

Step 4 This step is critical because assessing the low reading on the Unit Vent Flowrate Monitor is necessary to ensure that all required action is identified per the attached KEY for surveillance items NOT meeting Acceptance Criteria.

2020 Admin - JPM A1b SRO NUREG 1021, Revision 11

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT NOTE: Equipment problems may be evaluated in ANY order.

1 (Step 12.2.2) IF The operator reviews the performing Enclosure 13.1 completed Enclosure (Daily Surveillance Items 13.1 and Equipment Checklist), THEN check Problem Evaluation each applicable Form.

surveillance item in Enclosure 13.1 meets its The operator recognizes Acceptance Criteria. that Control Room indicators 1NVP5760 (Step 12.2.5) IF a and 1NVP5763 (VCT surveillance item was NOT Level) are NOT within completed due to Unit 5% of each other.

"Applicable Mode", THEN identify surveillance item The operator recognizes by writing "NA" in that there are no TS/SLC appropriate initial blank. requirements associated with the VCT level instruments, but that (Step 12.2.6) IF a they are required to be surveillance item within 5% of each other Acceptance Criteria NOT based on SOER 97-1 met, perform the following: requirements.

(Step 12.2.6.1) Identify The operator notifies surveillance item as a the WCC or directs that discrepancy in appropriate a work request be initials blank. created.

(Step 12.2.6.2) Note (See KEY on Page 10) surveillance item on a discrepancy sheet (JPM Cue Sheet).

2020 Admin - JPM A1b SRO NUREG 1021, Revision 11

Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

2 (Step 12.2.2) IF The operator reviews the performing Enclosure 13.1 completed Enclosure (Daily Surveillance Items 13.1 and Equipment Checklist), THEN check Problem Evaluation each applicable Form.

surveillance item in Enclosure 13.1 meets its The operator recognizes Acceptance Criteria. that FWST Solution Temperature (Minimum)

(Step 12.2.5) IF a is < 70oF as read on surveillance item was NOT 1FWP-5030 (which is completed due to Unit operable).

"Applicable Mode", THEN identify surveillance item The operator addresses by writing "NA" in TS LCO 3.5.4, Refueling appropriate initial blank. Water Storage Tank, and determines that ACTION A.1 applies.

(Step 12.2.6) IF a surveillance item The operator addresses Acceptance Criteria NOT SLC 16.9.11, Borated met, perform the following: Water Sources (Operating), and (Step 12.2.6.1) Identify determines that ACTION surveillance item as a D.1 applies.

discrepancy in appropriate initials blank. The operator addresses SLC 16.9.14, Borated (Step 12.2.6.2) Note Water Sources surveillance item on a (Shutdown), and discrepancy sheet (JPM determines that this SLC Cue Sheet). does not apply under the current plant conditions.

The operator identifies LCO 3.5.4 ACTION A and SLC 16.9.11 ACTION D.

(See KEY on Page 10) 2020 Admin - JPM A1b SRO NUREG 1021, Revision 11

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

3 (Step 12.2.2) IF The operator reviews the performing Enclosure 13.1 completed Enclosure (Daily Surveillance Items 13.1 and Equipment Checklist), THEN check Problem Evaluation each applicable Form.

surveillance item in Enclosure 13.1 meets its The operator recognizes Acceptance Criteria. that the operate light is NOT LIT for 1EMF-31 (Step 12.2.5) IF a (Turbine Bldg Sump surveillance item was NOT Disch) the loss of sample completed due to Unit flow annunciator is NOT "Applicable Mode", THEN in alarm status, and the identify surveillance item source check was by writing "NA" in unsuccessful.

appropriate initial blank.

The operator addresses SLC 16.11.2, (Step 12.2.6) IF a Radioactive Liquid surveillance item Effluent Monitoring Acceptance Criteria NOT Instrumentation, and met, perform the following: enters Condition B immediately.

(Step 12.2.6.1) Identify surveillance item as a The operator addresses discrepancy in appropriate Table 16.11.2-1, initials blank. Instrument 2.a and determines that since TR (Step 12.2.6.2) Note 16.11.2.1 is NOT met surveillance item on a and Instrument 2.a is discrepancy sheet (JPM NOT OPERABLE, Cue Sheet). ACTION D is required.

The operator determines that SLC 16.11.2 ACTION B and D are required and notifies the WCC or directs that a work request be created.

(See KEY on Page 10) 2020 Admin - JPM A1b SRO NUREG 1021, Revision 11

Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

4 (Step 12.2.2) IF The operator reviews the performing Enclosure 13.1 completed Enclosure (Daily Surveillance Items 13.1 and Equipment Checklist), THEN check Problem Evaluation each applicable Form.

surveillance item in Enclosure 13.1 meets its The operator recognizes Acceptance Criteria. that Unit Vent Flow Rate Monitor(1VALP-5120) is (Step 12.2.5) IF a reading < 15%.

surveillance item was NOT completed due to Unit The operator addresses "Applicable Mode", THEN SLC 16.11.7-1 and identify surveillance item enters Condition B by writing "NA" in immediately.

appropriate initial blank.

The operator addresses Table 16.11.7-1, (Step 12.2.6) IF a Instrument 3.d and surveillance item determines that since TR Acceptance Criteria NOT 16.11.7.3 is NOT met met, perform the following: Instrument 3.d is NOT OPERABLE, and that (Step 12.2.6.1) Identify ACTION D is required.

surveillance item as a discrepancy in appropriate The operator initials blank. determines that SLC 16.11.7 ACTION B and (Step 12.2.6.2) Note D are required.

surveillance item on a discrepancy sheet (JPM (See KEY on Page 10)

Cue Sheet).

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Admin - JPM A1b SRO NUREG 1021, Revision 11

Appendix C Page 9 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Admin - JPM A1b SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Admin - JPM A1b SRO NUREG 1021, Revision 11

Appendix C Page 10 of 11 Form ES-C-1 VERIFICATION OF COMPLETION KEY:

Problem Identify all Technical Specification/SLC required ACTION, as well as all other actions that must be taken Control Room indicators 1NVP5760 and The operator notifies the WCC or directs that 1NVP5763 (VCT Level) are NOT within 5% of a work request be created.

each other FWST Solution Temperature (Minimum) is < The operator identifies LCO 3.5.4 ACTION A 70oF as read on 1FWP-5030 and SLC 16.9.11 ACTION D are required.

Operate light is NOT LIT for 1EMF-31 The operator determines that SLC 16.11.2 (Turbine Bldg Sump Disch) the loss of ACTION B and D are required.

sample flow annunciator is NOT in alarm status, and the source check was The operator notifies the WCC or directs that unsuccessful a work request be created.

NOTE: The Identification of ACTION B is NOT Critical.

Unit Vent Flow Rate Monitor(1VALP-5120) is The operator determines that SLC 16.11.7 reading < 15% ACTION B and D are required.

NOTE: The Identification of ACTION B is NOT Critical.

2020 Admin - JPM A1b SRO NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET Initial Conditions:

Unit 1 is in Mode 1 at 100% power.

Fire Hydrant 10 (W of Main Shop) is OOS and all other equipment is operable and/or functional.

Enclosure 13.1, Daily Surveillance Items Checklist, of PT/1/A/4600/003B, Daily Surveillance Items, has been completed.

Enclosure 13.3, Cask Monitoring, is still in progress and will be provided when complete.

The Unit 1 VA System is undergoing scheduled maintenance (i.e. VA Down Day)

INITIATING CUE:

Evaluate the completed Enclosure 13.1 of PT/1/A/4600/003B (Daily Surveillance Items Checklist) per Step 12.

Identify all Technical Specification/SLC required ACTION, as well as all other actions that must be taken so that an ESOMS entry can be prepared.

Problem Identify all Technical Specification/SLC required ACTION, as well as all other actions that must be taken (If additional space is needed use back of page)

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A2 SRO 2020 Admin - JPM A2 SRO (Rev_011620) NUREG 1021, Revision 11

Appendix C Page 2 of 10 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Perform a Thermal Margin JPM No.: 2020 Admin - JPM A2 Determination SRO K/A

Reference:

2.2.18 (3.9)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1.

Initial Conditions:

Unit 1 was shutdown 16 days ago for a mid-cycle outage after 200 days of operation.

Unit 1 is currently in Mode 5.

No Core Offload will occur.

The NC system is 125°F with A Train ND in service.

Preparations are being made to lower NC system level to 67 inches above Hot Leg Centerline per Enclosure 4.1 (Draining the NC System) of OP/1/A/6100/SD-20 (Draining the NC System).

Initiating Cue:

Complete Attachment 12.6 of OMP 5-8 (Shift Supervision Turnovers) to determine the new thermal margin with NC system level at 67 inches above Hot Leg Centerline (Complete all required paperwork).

Identify the individuals that must be notified and/or actions that must be taken.

Task Standard: The operator will determine the Thermal Margin and complete Attachment 12.6 (Thermal Margin Determination) and Attachment 12.7 (Shutdown Assessment Status) of OMP 5-8 (Shift Supervision Turnovers) in accordance with the provided KEY.

2020 Admin - JPM A2 SRO NUREG 1021, Revision 11

Appendix C Page 3 of 10 Form ES-C-1 Job Performance Measure Worksheet Required Materials: Calculator General

References:

OP/1/A/6100/SD-20 (Draining the NC System), Rev 71 OMP 5-8 (Shift Supervision Turnovers), Rev 74 OP/1/A/6100/022 (Unit 1 Data Book), Rev 481 MCEI-0400-379 (McGuire 1 Cycle 27 Core Operating Limits Report),

Rev 1 Handouts: Handout 1: Blank copy of OMP 5-8 (Shift Supervision Turnovers)

Time Critical Task: NO Validation Time: 15 minutes NOTE: An Answer KEY is provided on a separate document.

Critical Step Justification Step 2 This step is critical because selecting and using Curve 2.10.1 B (Or Curve 2.10.1.B(1)) is necessary to determine the Thermal Margin.

Step 3 This step is critical because documenting the thermal margin time and maximum NC Temperature allowed is necessary to complete Attachment 12.6 (Thermal Margin Determination) of OMP 5-8 (Shift Supervision Turnovers) in accordance with the provided KEY.

Step 4 This step is critical because completing Attachment 12.7 of OMP 5-8 is necessary to complete the assigned task in accordance with the provided KEY.

Step 5 This step is critical because notifying the Containment Closure Coordinator (CCC) of the thermal margin time determined is necessary to complete the assigned task in accordance with the provided KEY.

Step 6 This step is critical because notifying the Shift Technical Advisor (STA) of the thermal margin time determined is necessary to complete the assigned task in accordance with the provided KEY.

Step 7 This step is critical because writing the thermal margin time on MC-6 and updating MLOG is necessary to complete the assigned task in accordance with the provided KEY.

2020 Admin - JPM A2 SRO NUREG 1021, Revision 11

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM) and Handout 1.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1 (Attachment 12.6) The operator places a Applicable to: check in the Unit 1 checkbox.

Unit 1 Unit 2 2020 Admin - JPM A2 SRO NUREG 1021, Revision 11

Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 2 (Attachment 12.6, Step 1) The operator obtains the Refer to Core Data Book and OP/1(2)/A/6100/22, Unit 1 locates Section 2.10.

(2) Databook, Enclosure 4.3, Section 2.10 Thermal The operator recognizes Margin Curves, to that since the Loops will determine appropriate be drained and the section and/or curve to Vessel Head has NOT use. been removed, the Curves of Section 2.10.1 are applicable.

SECTION/CURVE USED__________ The operator determines that from the Initial Conditions given, INITIAL_________ Enclosure 4.3 Section/Curve 2.10.1 B or B (1) is to be used, and records this, placing their initial in the appropriate Block.

Using Curve 2.10.1 B,

the operator intersects the point of 16 days after shutdown and the 140oF temperature Curve and determines that the new Thermal Margin is 30-35 minutes.

OR Using Curve 2.10.1 B (1), the operator intersects the point of 16 days after shutdown and the 140oF temperature Curve and determines that the new Thermal Margin is 32 minutes.

2020 Admin - JPM A2 SRO NUREG 1021, Revision 11

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

3 (Attachment 12.6, Step 2) The operator records the Document thermal margin date in the chart on time and maximum NC Attachment 12.6.

Temperature allowed (for curve used) in the table The operator records the below and initial. time in the chart on Attachment 12.6.

The operator records 30-35 minutes in the Thermal Margin MIN block on the chart on Attachment 12.6.

The operator records 140oF in the Max NC Temp oF block on the chart on Attachment 12.6.

2020 Admin - JPM A2 SRO NUREG 1021, Revision 11

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

4 (Attachment 12.6, Step 3)

Communicate Thermal Margin as follows: The operator records 30-35 minutes in the (Attachment 12.6, Step Thermal Margin Column 3.a) Write thermal margin TM Minutes block on time and max NC Temp on Attachment 12.7.

the Shutdown Assessment/Status The operator records (Attachment 12.7). 140oF in the Thermal Include any data Book 4.3 Margin Column Max NC Section 2.10 support Temp block on parameters (S/G Lvls, Pzr Attachment 12.7.

Lvl, etc.) Initial in Table below. The operator records 67 (60-84 is acceptable) in the Thermal Margin Column NCS Level block on Attachment 12.7.

The operator places their initial in the Thermal Margin Data Written on Shutdown Assessment/Status (Attachment 12.7) block on the chart on Attachment 12.6.

5 (Attachment 12.6, Step The operator contacts 3.b) Notify the the CCC and notifies that Containment Closure TM is 30-35 minutes.

Coordinator (CCC) of the thermal margin time The operator places their determined. Initial in the initial in the CCC table below. Notified block on the chart on Attachment 12.6.

2020 Admin - JPM A2 SRO NUREG 1021, Revision 11

Appendix C Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

6 (Attachment 12.6, Step 3.c) Notify the Shift The operator contacts Technical Advisor (STA) of the STA and notifies that the thermal margin time TM is 30-35 minutes.

determined. Initial in the table below. The operator places their initial in the STA Notified block on the chart on Attachment 12.6.

7 (Attachment 12.6, Step The operator directs the 3.d) Write thermal margin OATC to write 30-35 time on MC-6 and update minutes in the TM Block MLOG on SDS (OAC). on MC-6 and enter into Initial in the table below. MLOG.

The operator places their initial in the Thermal Margin Time Written on MC-6 and MLOG block on the chart on Attachment 12.6.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Admin - JPM A2 SRO NUREG 1021, Revision 11

Appendix C Page 9 of 10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Admin - JPM A2 SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Admin - JPM A2 SRO NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET Initial Conditions:

Unit 1 was shutdown 16 days ago for a mid-cycle outage after 200 days of operation.

Unit 1 is currently in Mode 5.

No Core Offload will occur.

The NC system is 125°F with A Train ND in service.

Preparations are being made to lower NC system level to 67 inches above Hot Leg Centerline per Enclosure 4.1 (Draining the NC System) of OP/1/A/6100/SD-20 (Draining the NC System).

INITIATING CUE:

Complete Attachment 12.6 of OMP 5-8 (Shift Supervision Turnovers) to determine the new thermal margin with NC system level at 67 inches above Hot Leg Centerline (Complete all required paperwork).

Identify the individuals that must be notified and/or actions that must be taken.

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A3 SRO 2020 Admin - JPM A3 SRO (Rev_011620) NUREG 1021, Revision 11

Appendix C Page 2 of 9 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Approve a Liquid Release Permit JPM No.: 2020 Admin - JPM A3 SRO K/A

Reference:

G KA 2.3.6 (3.8)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue and List of Out-of-Service Equipment (Last Two Pages of this JPM), and Handouts 1-2.

Initial Conditions:

Unit 1 and Unit 2 are in Mode 1 at 100% power.

There are no on-going liquid radiation releases.

Attachment 10 ('B' WMT Release Authorization) of OP/0/B/6200/607 (Liquid Waste Release - WMT B with WMT Pump B) has been initiated.

Attachment 1 ('B' WMT Release Using 'B' WMT Pump) of OP/0/B/6200/607 (Liquid Waste Release - WMT B with WMT Pump B) is in progress in preparation for release of the B Waste Monitor Tank.

RP has just delivered the LWR package # 2020067 to the Control Room.

All available RC Pumps are running.

Initiating Cue:

You are directed to review and approve LWR Package # 2020067 by performing Steps 9-12 of Attachment 10 (B WMT Release Authorization) of OP/0/B/6200/607.

If LWR Package # 2020067 cannot be approved, identify why not.

2020 Admin - JPM A3 SRO NUREG 1021, Revision 11

Appendix C Page 3 of 9 Form ES-C-1 Job Performance Measure Worksheet Task Standard: The operator will determine that LWR Package # 2020067 cannot be approved because the recommended Release Rate is GREATER THAN the Allowable Release Rate and 0EMF49 has NOT been source checked.

Required Materials: Calculator General

References:

OP/0/B/6200/607 (Liquid Waste Release - WMT B With WMT Pump B),

Rev 12 OP/1/A/6500/001 (Liquid Waste System), Rev 103 Handouts: Handout 1: Attachment 10 (B WMT Release Authorization) of OP/0/B/6200/607 (Liquid Waste Release - WMT B With WMT Pump B) marked up through Step 8.

Handout 2: LWR Discharge Document (Adjusted such that Recommended Release Rate is > Allowable Release Rate (Reversed),

and 0EMF49 Source Check Block is BLANK).

Key: A separate KEY is provided to show the portions of Attachment 10 (B WMT Release Authorization) of OP/0/B/6200/607 (Liquid Waste Release - WMT B With WMT Pump B) completed by the applicant during the performance of the JPM.

Time Critical Task: NO Validation Time: 15 minutes Critical Step Justification Step 1 This step is critical because determining the operability/functionality of release instrumentation is necessary to determine whether or not LWR Package #

2020067 can be approved.

Step 3 This step is critical because evaluating LWR 2020067 is necessary to determine whether or not LWR Package # 2020067 can be approved.

Step 4 This step is critical because identifying the reasons why LWR 2020067 cannot be approved is necessary to complete the task.

2020 Admin - JPM A3 SRO NUREG 1021, Revision 11

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue and List of Out-of-Service Equipment (Last Two Pages of this JPM), and Handouts 1-2.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

1 (Attachment 10, Step 9)

Determine functionality status of the following components: The operator reviews the equipment OOS List and 0WMLP5140 (B WMT determines that Pump Disch Flow) Yes 0WMLP5140 is OPERABLE No and checks YES.

The operator reviews the equipment OOS List and 1WP-35 (WMT & VUCDT to determines that 1WP-35 is RC Cntrl) Yes No OPERABLE and checks YES.

The operator reviews the 1WP-37 (Liquid Waste to equipment OOS List and RC Cntrl) Yes No determines that 1WP-37 is OPERABLE and checks YES.

The operator reviews the 0EMF-49 (Liquid Waste equipment OOS List and Disch Radiation Monitor) determines that 0EMF49 is Yes No OPERABLE and checks YES.

0WMFS5440 (0EMF49 The operator reviews the Outlet Flow) [8.7.4] Yes equipment OOS List and No determines that 0WMFS5440 is OPERABLE and checks YES.

2 (Step 10) IF any component The operator recognizes listed in Step 9 is NON- that all required equipment FUNCTIONAL, THEN.. is OPERABLE, and that this step is NA.

2020 Admin - JPM A3 SRO NUREG 1021, Revision 11

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

3 (Step 11) Ensure the following items on LWR Document are complete: The operator recognizes

Number of "RC Pumps that there are 7 RC Pumps Running" is greater operating which is greater than OR equal to "RC than the 1RC pump Pumps Assigned To required by LWR Package #

This Release 2020067.

Number of "RC Pumps The operator recognizes Running" is greater that there are NO than OR equal to "Total concurrent releases.

RC Pumps Required The operator recognizes (all concurrent that the "Recommended releases)" Release Rate (gpm)" is

"Recommended GREATER THAN Release Rate (GPM)" is "Allowable Release Rate less than "Allowable (gpm)" and determines that Release Rate (GPM)" this must be corrected.

The operator reviews the

0EMF-49L (Waste equipment OOS List and Liquid Low Range determines that 0EMF49 is Radiation Monitor OPERABLE.

Module) is FUNCTIONAL AND in The operator reviews LWR service. Package #202067 and

0EMF-49 (Liquid Waste determines that 0EMF49 is Disch Radiation in service.

Monitor) source check The operator reviews LWR performed. paperwork and determines

"Expected CPM" is less that 0EMF49 has NOT been than "TRIP 1 source checked.

SETPOINT" AND "TRIP The operator observes that 2 SETPOINT".

the "Expected CPM" is less

Review of Special than "Trip 1 Setpoint" and Instructions provided on "Trip 2 Setpoint".

LWR Permit. [8.7.12] The operator reviews the Special Instructions provided on the LWR Permit and determines that all Special Instructions are met (None).

2020 Admin - JPM A3 SRO NUREG 1021, Revision 11

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

4 (Step 12) WHEN approved The operator does NOT for release, THEN place initial Step 12 and identifies signature, date, AND time that LWR Package #

of Control Room Supervisor 2020067 can NOT be authorization on LWR approved until the Document. "Recommended Release Rate (gpm)" is less than the "Allowable Release Rate (gpm)" and 0EMF49 has been source checked.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

2020 Admin - JPM A3 SRO NUREG 1021, Revision 11

Appendix C Page 7 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Admin - JPM A3 SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Admin - JPM A3 SRO NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET Out-of-Service Equipment Common Unit Equipment:

Fire Alarm Control Panel (FACP) - 2 (Admin Building) - Ongoing Testing

'A' NB Evaporator Feed Pump - Failed Bearing 0EMF43A (CR Air Intake A Rad Monitor) - Circuit Failure SKSS Inverter - Ongoing Maintenance 0WMFT5130 (A Waste Monitor Tank Pump Disch Flow) - Failed transmitter Fire Hydrant 10 (W of Main Shop) - Will Not Operate 0VSWT0001 (A VS Compressor Water Separator Water Trap) - Leaking Petcock Unit 1:

Glycol Pump B - Ongoing Maintenance MCB Annunciator 1AD-2, A8 (OTDT Runback / Rod Stop Alert) - Alarm does NOT function 1RNP 5360 (1A Component Cooling HX Outlet Flow) - Failed High 1B LLI Pump - Oil Level in Reduction Gear Low Unit 2:

2RWS-13 (Raw Water Skid Coupon Rack A Influent) - Packing Leak Fireworks FDS Zone 24 Smoke Detector (Unit 2 Seal Oil System) - Failed 2EMF44 (Cont Vent Drn Tank Rad Monitor) - Detector Failure 2C RC Pump - Motor Replacement 2TLP5010 (Stm Seal Header Press) - Failed Low Note: All other equipment is OPERABLE/FUNCTIONAL.

NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

Unit 1 and Unit 2 are in Mode 1 at 100% power.

There are no on-going liquid radiation releases.

Attachment 10 ('B' WMT Release Authorization) of OP/0/B/6200/607 (Liquid Waste Release - WMT B with WMT Pump B) has been initiated.

Attachment 1 ('B' WMT Release Using 'B' WMT Pump) of OP/0/B/6200/607 (Liquid Waste Release - WMT B with WMT Pump B) is in progress in preparation for release of the B Waste Monitor Tank.

RP has just delivered the LWR package # 2020067 to the Control Room.

All available RC Pumps are running.

INITIATING CUE:

You are directed to review and approve LWR Package #

2020067 by performing Steps 9-12 of Attachment 10 (B WMT Release Authorization) of OP/0/B/6200/607.

If LWR Package # 2020067 cannot be approved, identify why not.

NUREG 1021, Revision 11

Appendix C Job Performance Measure Form ES-C-1 Worksheet JPM A4 SRO 2020 Admin - JPM A4 SRO (Rev_011620) NUREG 1021, Revision 11

Appendix C Page 2 of 13 Form ES-C-1 Job Performance Measure Worksheet Facility: McGuire Task No.:

Task

Title:

Classify an Emergency Event JPM No.: 2020 Admin - JPM A4 SRO K/A

Reference:

G KA 2.4.41 (4.6)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1-3.

Initial Conditions: Unit 1 was operating at 100% power and Unit 2 was in No Mode when a Loss of Offsite Power occurred to the site.

The 1A EDG is OOS and unavailable to start.

The following timeline of events is observed:

0800:00 Loss of Offsite Power due an electrical grid disturbance 0800:20 The 1B EDG failed to start automatically 0800:45 An AO is dispatched to manually start the 1B EDG 0801:00 The crew entered EP/1/A/5000/ECA-0.0, Loss of All AC Power.

0806:00 DEC BA reports that the switchyard is unavailable, however that power should be restored to at least the Mecklenburg line within 45 minutes.

0808:00 The AO reports that the 1B EDG has tripped on overspeed and IAE reports restoration will take about 25 minutes.

ALL Critical Safety Function Status Trees are Yellow or Green.

2020 Admin - JPM A4 SRO NUREG 1021, Revision 11

Appendix C Page 3 of 13 Form ES-C-1 Job Performance Measure Worksheet Initiating Cue:

Classify the Event in accordance with RP/0/A/5700/000 (Classification of Emergency).

If more than one Emergency Action Level (EAL) has been exceeded, identify the EAL resulting in the Highest Emergency Classification.

(Raise your hand and alert the Examiner when complete)

Then, prepare a Nuclear Power Plant Emergency Notification Form for the event, and present to the Emergency Coordinator for approval. (Raise your hand and alert the Examiner when complete)

This is a Time Critical JPM Task Standard: The operator will declare a SITE AREA EMERGENCY (SAE) based on SS1.1, Loss of all offsite and all onsite AC power capability to essential 4160V buses 1(2)ETA and 1(2)ETB for 15 min; and complete the Emergency Notification Form in accordance with the provided KEY within the following 15 minutes.

Required Materials: None General

References:

RP/0/A/5700/000 (Classification of Emergency), Rev 30 RP/0/A/5700/001 (Notification of Unusual Event), Rev 36 RP/0/A/5700/002 (Alert), Rev 37 RP/0/A/5700/003 (Site Area Emergency), Rev 37 RP/0/A/5700/004 (General Emergency), Rev 35 RP/0/B/5700/029 (Notifications to Offsite Agencies From the Control Room), Rev 25 EP/1/A/5000/ECA-0.0 (Loss of All AC Power), Rev 44 OMP 4-3 (Use of Emergency And Abnormal Procedures And FLEX Support Guidelines), Rev 48 FAD-MC-EP-EAL-WALLCHARTS, (McGuire Nuclear Station Classification of Emergency) Rev 2 Nuclear Power Plant Emergency Notification Form Handouts: Handout 1: RP/0/A/5700/000 (Classification of Emergency)

Handout 2: RP/0/B/5700/029 (Notifications to Offsite Agencies From the Control Room)

Handout 3: EAL Wallchart, Rev 2 Handout 4: Blank copies of Nuclear Power Plant Emergency Notification Forms or the Book of Pre-Printed Forms Time Critical Task: YES - 15 minutes to make classification, and THEN 15 minutes to complete ENF.

2020 Admin - JPM A4 SRO NUREG 1021, Revision 11

Appendix C Page 4 of 13 Form ES-C-1 Job Performance Measure Worksheet Validation Time: 30 minutes Critical Step Justification Step 5 This step is critical because using the EAL Wallchart is necessary to obtain the correct emergency classification.

Step 6 This step is critical because recording the classification time is necessary to establish the correct notification time.

Step 12 This step is critical because recording the correct Message Number is necessary to complete the Emergency Notification Form in accordance with the provided KEY within the 15 minutes.

Step 13 This step is critical because recording the correct Phone Number is necessary to complete the Emergency Notification Form in accordance with the provided KEY within the 15 minutes.

Step 14 This step is critical because checking the DRILL or the ACTUAL DECLARATION checkbox is necessary to complete the Emergency Notification Form in accordance with the provided KEY within the 15 minutes.

Step 16 This step is critical because checking the SAE checkbox is necessary to complete the Emergency Notification Form in accordance with the provided KEY within the 15 minutes.

Step 17 This step is critical because recording the correct EAL #, Declaration Date and Time and EAL DESCRIPTION is necessary to complete the Emergency Notification Form in accordance with the provided KEY within the 15 minutes.

Step 19 This step is critical because checking the NONE checkbox in Line 5 is necessary to complete the Emergency Notification Form in accordance with the provided KEY within the 15 minutes.

Step 20 This step is critical because checking the NONE checkbox in Line 6 is necessary to complete the Emergency Notification Form in accordance with the provided KEY within the 15 minutes.

2020 Admin - JPM A4 SRO NUREG 1021, Revision 11

Appendix C Page 5 of 13 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with an asterisk*)

Provide Candidate with Initial Conditions/Cue (Last Page of this JPM), and Handouts 1-3.

START TIME:

STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 1 (RP/0/A/5700/000, Step Using the Timeline of 6.1.1) Determine operating Events the operator MODE that existed at time determines that Unit 1 was event occurred AND prior to in Mode 1 and Unit 2 is in any protection system OR No Mode at the start of the operator action initiated in event.

response to event.

2 (Step 6.1.2) IF valid Using the Timeline of Security Condition OR Events the operator Hostile Action, THEN. determines that a valid Security Condition OR Hostile Action does NOT exist.

3 (Notes prior to Step 6.1.3) The operator reads the

EAL Wallchart created Notes and proceeds.

from MNS EPLAN Section D per NEI 99-01 rev. 006.

Wallchart ID is FAD-MC-EP-EAL-WALLCHARTS located on bottom right corner of EAL Wallchart beside Duke Energy emblem.

4 (Step 6.1.3) Verify EAL The operator locates the Wallchart has current Rev number located on revision of Classification of bottom right corner of EAL Emergency, FAD-MC-EP- Wallchart beside Duke EAL-WALLCHARTS, Energy emblem and Classification of determines that the Wall Emergency, Rev. 002 Chart is Revision 2 (Handout 3) and proceeds and proceeds.

2020 Admin - JPM A4 SRO NUREG 1021, Revision 11

Appendix C Page 6 of 13 Form ES-C-1 VERIFICATION OF COMPLETION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

5 (Step 6.1.4) Perform The operator reviews the Classification per EAL EAL Wall Chart, and Wallchart. determines the following:

The operator determines that an SAE exists on Unit 1, based on SS1.1, Loss of all offsite and all onsite AC power capability to essential 4160V buses 1(2) ETA and 1(2) ETB for 15 min.

The operator applies Note 1: The Emergency Coordinator/EOF Director should declare the event promptly upon determining that time limit has been exceeded, or will likely be exceeded, and determines that the SAE should be declared now based on projections for restoration of power.

6 (Step 6.1.5) IF Emergency The operator determines Action Level threshold has that an SAE exists, based been exceeded, THEN on based on SS1.1.

declare the appropriate Emergency Classification. The operator records the Event Declaration time: event declaration time in the space provided.

Examiner Note: Record Time Critical Stop Time __________

NOTE that this time is also the Start Time for the 2nd Time Critical action of completing the ENFS1.1.

Provide the operator with Handout 4 (BLANK ENF or the Book of Pre-Printed Forms from which the operator can select the appropriate form).

2020 Admin - JPM A4 SRO NUREG 1021, Revision 11

Appendix C Page 7 of 13 Form ES-C-1 VERIFICATION OF COMPLETION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 7 (RP/0/A/5700/000, Step The operator proceeds to 6.1.6) Implement the RP/0/A/5700/003.

applicable Emergency Response Procedure (RP) for that classification and continue with subsequent steps of this procedure.

Notification of Unusual Event RP/0/A/5700/001

Alert RP/0/A/5700/002

Site Area Emergency RP/0/A/5700/003

General Emergency RP/0/A/5700/004.

8 (RP/0/A/5700/003, Note The operator reads the prior to Step 6.1.1) The Notes and proceeds.

following actions have been separated into position specific attachments to enhance timely completion and consistent execution.

Site Assembly is required to be complete within 30 minutes of the declaration of Alert, Site Area Emergency or General Emergency.

9 (Step 6.1.1) The operator proceeds to Assign the following RP/0/B/5700/029.

actions:

Notify the Offsite Agency Communicator to make initial notifications to the offsite agencies per RP/0/B/5700/029, Notifications to Offsite Agencies from the Control Room:

2020 Admin - JPM A4 SRO NUREG 1021, Revision 11

Appendix C Page 8 of 13 Form ES-C-1 VERIFICATION OF COMPLETION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT 10 (RP/0/B/5700/029, Step The operator recognizes 6.1.1) Complete ENF by that an ENF has been using one of the following: provided, and proceeds.

Preprinted ENF.

OR

Blank ENF.

11 (Note prior to Step 6.1.2) The operator reads the Messages are sequentially Note and proceeds.

numbered throughout the drill or event beginning with message number 1 and continues until termination of the drill or event.

12 (Step 6.1.2) Record The operator records the message number. Message Number as 1, per provided KEY.

13 (Step 6.1.3) Ensure "(704) The operator records the 875-6044" recorded as Phone Number as "(704) confirmation telephone 875-6044, or ensures that number. it already exists, per provided KEY.

14 (Step 6.1.4) Complete Line The operator checks the 1 by checking 'DRILL' OR DRILL or the ACTUAL

'ACTUAL DECLARATION'. DECLARATION checkbox, per provided KEY.

15 (Step 6.1.5) Complete Line The operator ensures that 2 by verifying that the AFFECTED SITE states MCGUIRE is printed on the McGuire, per provided form. KEY.

16 (Step 6.1.6) Complete Line The operator checks the 3 by checking correct SAE checkbox, per emergency classification. provided KEY.

2020 Admin - JPM A4 SRO NUREG 1021, Revision 11

Appendix C Page 9 of 13 Form ES-C-1 VERIFICATION OF COMPLETION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

17 (Step 6.1.7) Complete Line The operator records the 4 by recording the following: EAL Number as SS1.1,

EAL #. the Declaration Date and

Declaration Date and Time as the current Date Time. and Time, and the EAL

EAL DESCRIPTION. Description as Loss of all offsite and all onsite AC power capability to essential 4160V buses 1(2)ETA and 1(2)ETB for 15 min., (Or Equivalent) per provided KEY.

18 (Note prior to Step 6.1.8) The operator reads the The "Release to the Note and proceeds.

Environment" being evaluated in Step 8 must be caused by the emergency.

2020 Admin - JPM A4 SRO NUREG 1021, Revision 11

Appendix C Page 10 of 13 Form ES-C-1 VERIFICATION OF COMPLETION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

19 (Step 6.1.8) Complete Line The operator checks the 5 as follows: NONE checkbox, per IF any of the following provided KEY.

exists, THEN check 'IS OCCURRING' OR 'HAS OCCURRED' as appropriate:

EMF 38, 39 or 40 readings indicate an increase AND containment pressure greater than 0.3 psig.

EMF 38, 39 or 40 readings indicate an increase AND a known leak path exists from containment.

EMF 35, 36 or 37 readings indicate an increase in activity.

EMF 33 or other alternate means indicate Steam Generator tube leakage.

A known release path exists.

Alternate methods of release determination are as follows:

Greater than 0.3 psig containment pressure with a LOCA.

Positive field monitoring team results.

Known Steam Generator Tube Rupture.

IF NO emergency release exists, THEN check 'NONE' 2020 Admin - JPM A4 SRO NUREG 1021, Revision 11

Appendix C Page 11 of 13 Form ES-C-1 VERIFICATION OF COMPLETION STEPS ELEMENTS STANDARD S/U COMMENTS REQUIRED FOR UNSAT

20 (Step 6.1.9) Complete Line The operator checks the 6 as follows: NONE checkbox per

IF Notification of provided KEY and goes to Unusual Event, Alert, Step 6.10.

OR Site Area Emergency, THEN check 'NONE'

Go to Step 10 21 (Step 6.1.10) Complete Line The operator leaves blank 12 by recording any and proceeds, per provided additional 'REMARKS' as KEY.

directed by the Emergency Coordinator.

22 (Step 6.1.11) Complete Line The operator completes the 13 by ensuring the SAE ENF accordance with Emergency Coordinator the provided KEY (Separate performs the following: Document) within 15

Sign 'APPROVED BY' Minutes of the SAE

Enter 'TITLE' Declaration time.

Record date and time.

The operator presents the completed ENF Form to the Emergency Coordinator.

Terminating Cue: Evaluation on this JPM is complete.

STOP TIME:

Critical TIME 1:

Critical TIME 2:

2020 Admin - JPM A4 SRO NUREG 1021, Revision 11

Appendix C Page 12 of 13 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: 2020 Admin - JPM A4 SRO Examinees Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Result: SAT UNSAT Examiners Signature: Date:

2020 Admin - JPM A4 SRO NUREG 1021, Revision 11

Appendix C Form ES-C-1 JPM CUE SHEET Initial Conditions: Unit 1 was operating at 100% power and Unit 2 was in No Mode when a Loss of Offsite Power occurred to the site.

The 1A EDG is OOS and unavailable to start.

The following timeline of events is observed:

0800:00 Loss of Offsite Power due an electrical grid disturbance 0800:20 The 1B EDG failed to start automatically 0800:45 An AO is dispatched to manually start the 1B EDG 0801:00 The crew entered EP/1/A/5000/ECA-0.0, Loss of All AC Power.

0806:00 DEC BA reports that the switchyard is unavailable, however that power should be restored to at least the Mecklenburg line within 45 minutes.

0808:00 The AO reports that the 1B EDG has tripped on overspeed and IAE reports restoration will take about 25 minutes.

ALL Critical Safety Function Status Trees are Yellow or Green.

INITIATING CUE:

Classify the Event in accordance with RP/0/A/5700/000 (Classification of Emergency).

If more than one Emergency Action Level (EAL) has been exceeded, identify the EAL resulting in the Highest Emergency Classification.

(Raise your hand and alert the Examiner when complete)

Then, prepare a Nuclear Power Plant Emergency Notification Form for the event, and present to the Emergency Coordinator for approval.

(Raise your hand and alert the Examiner when complete)

This is a Time Critical JPM NUREG 1021, Revision 11

ML20140A065

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