ML17233A135

Final Operating Exam (Sections a, B, and C) (Folder 3)

ML17233A135
Person / Time
Site:	Three Mile Island
Issue date:	06/26/2017
From:	D'Antonio J Operations Branch I
To:	Exelon Generation Co
Shared Package
ML16210A446	List: IR 05000289/2017301 ML17230A294 ML17230A316 ML17230A327 ML17233A133 ML17233A134 ML17233A135 ML18081A807 ML18081A808 ML18081A811
References
CAC U01944
Download: ML17233A135 (277)

Text

Appendix D Scenario Outline Form ES-D-1 Facility: Three Mile Island Scenario No.: 1 Op Test No.: TMl-2017-1 Examiners: Operators:

Initial Conditions:

• 100% power, MOL

• EG-Y-1A "A" Diesel Generator Out of Service

• Generator output meter GN-OM-1 is out of service for repair. Put computer points A0099 and A0098 on data trend to monitor MVAR and MW's.

Turnover: EG-Y-1A 7 day LCO has expired. Plant is beginning a shutdown. Directed rate of change of reactor power is 1%/minute Critical Tasks:

• Control RCS Inventory (CT-30)

• Natural Circulation RCS Flow (CT-12)

Event No. Malf. No. Event Type* Event Description 1 RCRS Shutdown reactor in 1102-4 (Allow power to lower >10%)

RURO (ICS in Auto, ULD in Hand) 2 TSCRS EF-P-1 oil bubbler empty, EF-P-1 inoperable 3 TSCRS NR-P-1A Trips, NR-P-18 Fails to Auto-Start, entry into OP-TM-RW02A CARO MAP-80105, and OP-TM-MAP-80205 (ARO: Starts NR-P-18 from CR) 4 IC09 ICRS ICS Malfunction, entry into OP-TM-AOP-070 IC53 IURO (Main Generator Megawatts fails to 50%, SASS fails to actuate)

IARO 5 ICRS Loss of ICS AUTO Subfeed Power (MU), entry into OP-TM-MAP-ED22C IURO H0108 IARO (URO: Operate MU-V-32 in HAND, ARO: Restore letdown) 6 MCRS Loss of Offsite power with one Emergency Diesel available, Entry ED01 into OP-TM-AOP-020 MURO MARO 7 CCRS EF-P-28 trips, Entry into OP-TM-EOP-004, Lack of Heat Tranfer FW62C CARO 8 CCRS Places the S80 diesel on the 1D 4KV bus, starts EF-P-2A CARO

• (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Scenario Set-up NRC Scenario 1 Three Mile Island NRC Scenario #1 Event #1: Diesel generator, EG-Y-1A, was out of service for a system outage. Due to complications, the outage lasted longer than 7 days, and the plant is commencing a shutdown in accordance with 1102-4, Power Operations. The Shift Manager has ordered a 1%/minute ULD load rate of change.

After the shutdown has commenced, the lead examiner can continue the scemario.

Event #2: When directed the booth operator will call the control room over the plant page. He will notify the CRO/CRS that EF-U-1 turbine oil bubbler is out of oil, and that there is oil on the floor in the EF-P-1 cubicle.

The CRS should declare EF-P-1 inoperable and order the MS-V-13A/B hand wheel closed and EF-P-1 tripped. The CRS should review TS 3.4.1.1.a.2:

With one EFW Pump or any EFW flowpath inoperable, restore the inoperable pump or flowpath to OPERABLE status within 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> or be in COLD SHUTDOWN within the next 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br />.

Once the tech spec is declared, the scenario can continue.

Event #3: The Lead Examiner will cue the trip of the "A" Nuclear River Pump. "B" Nuclear River Pump fails to auto-start in standby, leaving only one (1) Nuclear River Pump running. One Nuclear River Pump may not be sufficient to cool both the Nuclear Service Closed Cooling System (NSCCW) and the Intermediate Closed Cooling System (ICCW).

It is considered a loss of NSCCW if NSCCW temperatures reach 100°F, and the following Critical Safety Functions are affected:

CSF 4, Core Heat Removal: Provide the capability to remove core heat production at all times: Loss of Nuclear Services cooling function: RC pumps must shutdown. Natural Circulation will be used RCS heat removal.

CSF 8, Auxiliary Emergency Systems: Provide equipment cooling (closed cooling and ventilation), and other support requirements to accomplish the other Critical Safety Functions. Provide Instrument Air for operation of EFW, ADVs, RCP Support Systems, and some containment isolation valves: Loss of Nuclear Services cooling function: Other CSFs are affected as follows: (1) the reliability of safety related power sources and instrumentation system is degraded by the loss of the control building chillers and (2) the reliability of the decay closed pump motors and emergency feed pump motors is degraded by the loss of cooling to the area ventilation coolers.

CSF 10, Chemistry Control: Provide the means to monitor and control primary and secondary water chemistry in order to ensure the long term reliability of plant Scenario Set-up NRC Scenario 1 systems and limit the potential release of radioactive materials: Loss of Nuclear Services cooling function would result in the loss of the capability to obtain an RCS or OTSG sample.

It is considered a loss of ICCW if ICCW temperatures reach 120°F, and the following Critical Safety Functions are affected:

CSF 1, Reactivity and Reactor Power Control: Maintain control of the fission process, maintain the capability to shutdown the reactor and the capability to maintain the reactor in a shutdown condition. Control energy production and reactor power distribution based on design limits and current core heat removal capability. Loss of Intermediate Component Cooling: The reactor is tripped in the event of loss of cooling to the CRD stators in order to prevent stator damage.

Loss of CRD stator cooling would not prevent CRD insertion on RPS actuation.

Maintaining reactor shutdown is not affected by loss of IC component cooling.

CSF 3, RCS Integrity: Maintain the capability to control heatup and cooldown rates and control RCS pressure prevent reactor vessel brittle fracture or LTOP events. Maintain RCP seal cooling to prevent excessive loss of RCS inventory through RCP seals. Loss of Intermediate Component Cooling: One of two RCP seal cooling methods is lost. Loss of seal injection would require RCP shutdown.

If SI is lost, overheating of RCP seals is likely. If seal injection maintained, solid operation may be required due to the loss of letdown.

The crew will diagnose the trip of NR-P-1A by an amber disagreement light on the NR-P-1A control switch and Annunciator alarms B-1-5 and B-2-5. The ARO will manually start "B" Nuclear River Pump to provide sufficient cooling for NSCCW and ICCW. The CRS will identify and declare the following Tech Spec: 3.3.2.

When NR-P-1 Bis running and the Tech Spec has been declared, the scenario can continue.

Event #4: When directed by the lead examiner, insert event #4 for and ICS Failure.

The MW Generated Input to ICS Fails to 0 Volts. A cross-limit may occur as a result of the feed flow reduction caused by the BTU limit. This transient could occur if an open circuit occurs in MW Generated input to the ICS.

The crew will enter OP-TM-AOP-070 and place ICS stations placed in manual as necessary. Plant will be stabilized at 100% power or hot shutdown.

The console left digital indicator will indicate 500 MWe. A large megawatt error signal will be developed which will be used for developing the header pressure modified setpoint and for developing the megawatt calibrating integral. The modified header pressure signal will cause the Turbine Control Valves to open and cause the Main Turbine to trip to manual. Steam Generator and Reactor Demand will both increase.

After the plan is stabilized, the scenario can continue.

Scenario Set-up NRC Scenario 1 Event #5: The Lead Examiner will cue the Loss of ICS AUTO Power (Makeup Subfeed only). The following Critical Safety Functions are affected by the Loss of ICS AUTO Makeup Subfeed:

CSF 2: Reactor Vessel Inventory Control: Provide the means to maintain the core covered with sub cooled water. Loss of ATA or ICS auto power: Letdown is isolated by closure of MU-V-3, MU-V-1A and MU-V-1 B. Letdown can be recovered when resources are available. Lifted leads are required to remotely operate some Makeup Valves.

CSF 3: RCS Integrity: Maintain the capability to control heatup and cooldown rates and control RCS pressure prevent reactor vessel brittle fracture or LTOP events. Maintain RCP seal cooling to prevent excessive loss of RCS inventory through RCP seals. Loss of ATA or ICS auto power: MU-V-32 transfers to hand control.

The crew will diagnose the loss of ICS Auto Power to the Makeup Subfeed by Annunciators H-1-8 and D-2-1 in alarm, multiple PPC points in alarm, and MU-V-3 and MU-V-5 indicating midscale.

The Loss of ICS MU Auto power will cause MU-V-5, LETDOWN FLOW CONTROL BYPASS VALVE, to fail to 50% open, which will raise letdown flow. Since the cooling water for letdown remains the same with increased letdown flow, MU-V-3, RCS LETDOWN RB ISOL VALVE, will close on High Temperature interlock, thereby creating an isolation of Letdown.

The URO will control Seal Injection flow with MU-V-32 in Hand. The ARO will restore letdown IAW OP-TM-211-950 (performing the appropriate portion of the procedure when restoring from isolation following a High Temperature isolation).

Once Letdown is restored, the scenario can continue.

Event #6/7/8: When directed by the lead examiner, initiate event #6 for the loss of offsite power and EF-P-2B breaker failing to close.

When offsite power is lost, all main feedwater pumps, condensate pumps, and condensate booster pumps are lost. Due to EF-P-1 (Steam Driven Emergency Feedwater Pump) being inoperable from earlier in the scenario, EF-P-2B (Motor driven emergency feedwater pump) breaker not closing, and the loss of 1D 4160V ES bus (due to EG-Y-1A being inoperable), the crew should enter OP-TM-EOP-004, LACK OF PRIMARY TO SECONDARY HEAT TRANSFER, based on incore temperatures rising and no feedwater available.

The crew will also enter OP-TM-AOP-020, LOSS OF STATION POWER. The crew will should initiate OP-TM-864-901, SBO DIESEL GENERATOR (EG-Y-4) OPERATIONS, and power the 1D 4160V bus from EG-Y-4.

Scenario Set-up NRC Scenario 1 Once the SBO diesel, EG-Y-4, is powering the 10 4160V ES bus, emergency feedwater pump, EF-P-2A can be started to provide cooling to both OTSG's.

Termination: Once EF-P-2A is running and feeding the both OTSG's the scenario can be terminated.

Scenario Set-up NRC Scenario 1 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Control RCS Inventory - During a reactor trip, appropriate control of pressurizer level contributes to proper RCS pressure/inventory control. During this reactor trip, all power will be temporarily lost, then only the 1E 4kV bus gets repowered automatically. Since the normally running makeup pump is not ES selected, when power is returned there will be no makeup pump running.

Safety Significance: To be able to control RCS inventory, the crew must start a makeup pump. Failure to control RCS inventory after heat transfer and natural circulation are established could result in the pressurizer heaters to become uncovered and unavailable due to a low level interlock and/or unnecessary ES actuations.

Cues:

- Mismatch lights for MU-P-1 B

- Off lights for MU-P-1A and MU-P-1 B.

- No RCS MU flow.

- No RCS Seal Injection flow.

Performance Indicators:

- Operation of MU-P-1A (if the 1D 4kV bus has been restored)

- Operation of MU-P-1 C (if the 1D 4kV bus is still in the process of being restored)

- MU header pressure MU2-PI is above RCS pressure.

Feedback:

- Seal injection flow rises.

- Makeup flow rises if level is below setpoint.

CT Establish Natural Circulation RC Flow - Whenever forced RC flow is not available, NC flow should be established. Maintaining primary to secondary heat transfer via NC eliminates the need to add RC to the RB as would occur with the back up feed and bleed HPI core cooling mode.

o If primary to secondary heat transfer has been lost, then establish and maintain appropriate SG levels in accordance with Rule 4.0.

o Reduce SG pressure using the TBVs/ADVs to establish a positive primary to secondary side OT of - 50°F.

o RCS pressure should be maintained constant or slightly increasing using MU or HPI. RCS pressure should not be increased if PTS guidance is invoked.

o Trying to establish Natural Circulation RC flow outside of the following limits should be considered grounds for failure of the critical task:

Scenario Set-up NRC Scenario 1

• Establish Natural Circulation prior to transitioning into OP-TM-EOP-009, HPI Cooling.

Safety Significance: Enhances the transient mitigation capability of the plant by maintaining SGs operable and eliminates the need to add RC to the RB as with HPI Cooling.

Cues:

• Low RC flow alarm

• Verbal alert by plant staff that all RCPs have tripped

• SCM monitor and associated alarms

• P-T display and associated alarms Performance Indicators:

• Operation of EFW/FW pump and valve controls

• Operation of TBV/ADV controls

• Operation of MU/HPI pump and valve controls Feedback:

• Verbal verification that natural circulation has been established

• SG pressure

• RC temperature Scenario Set-up NRC Scenario 1 Event Description Procedure Support 100% power, beginning plant shutdown, Enclosure Initial setup 2A is complete, notifications and logs for shutdown are complete Commence plant shutdown 1 at 1%/min due 1102-4, Plant Operations 2 EF-P-1 oil leak Technical Specification 3.4.1.1.a.2 MAP B, MAIN ANNUNCIATOR PANEL B NR-P-1 C trips, NR-P-1 B fails 3 B-1-5, 480V ES MOTOR TRIP to auto start B-2-5, 480V ES MOTOR OVERLOAD ICS Malfunction - Generated OP-TM-AOP-070, PRIMARY TO SECONDARY 4

MW goes to 0 HEAT TRANSFER UPSET OP-TM-AOP-027, LOSS OF ATA OR ICS AUTO POWER OP-TM-MAP-D0201, LETDOWN CLRS OUTLET TEMP HI Loss of ICS AUTO Subfeed 5 OP-TM-MAP-H0108, ICS/NNI POWER LOST Power (MU)

OP-TM-211-476, SEAL INJECTION CONTROL-MU-V-32 CONSOLE OPERATIONS OP-TM-211-950, RESTORATION OF LETDOWN FLOW OP-TM-AOP-020, LOSS OF STATON POWER Loss of offsite power, Reactor Trip, Lack of OP-TM-EOP-001, REACTOR TRIP 6

Primary to Secondary Heat OP-TM-EOP-004, LACK OF PRIMARY TO Transfer SECODARY HEAT TRANSFER Place SBO diesel on the 1D OP-TM-864-901, SBO DIESEL GENERATOR 7

4160V ES bus (EG-Y-4) OPERATIONS Restore heat transfer, start 8 OP-TM-424-901, EMERGENCY FEEDWATER Emergency Feed Pump 2A Scenario Set-up NRC Scenario 1 ACTION COMMENTS/ INSTRUCTIONS DESCRIPTION IC-241 Initial setup for shutdown EG-Y-1A protected equipment Malfunction EG01A Value: Insert EG-Y-1A will not start When: Immediately Remote EGR28 Value: Insert Trip EG-Y-1A fuel rack When: Immediately Malfunction RW02A Value: Insert NR-P-1A Trips When: Event# 3 Overridde 03A6S25- Value: Off NR-P-18 fails to autostart ZDINRP18T(3) When: Immediately Malfunction IC09 Value: Insert Generated Megawatts to 500 When: Event# 4 Malfunction IC53 Value: Insert SASS fails to actuate When: Event# 4 Malfunction ED22C Value: Insert Loss of ICS Auto Power When: Event# 5 Makeup Subfeed Malfunction ED01 Value: Insert Loss of offsite power When: Event# 6 Malfunction FW62C Value: Insert EF-P-28 breaker fails to close When: Event# 6 Malfunction FWR78 Value: Manual MS-V-13A Local Manual When: Event# 10 Control Malfunction FWR79 Value: 0 MS-V-13A position to 0 When: Event# 10 Malfunction FWR80 Value: Manual MS-V-138 Local Manual When: Event #11 Control Malfunction FWR81 Value: 0 MS-V-138 position to 0 When: Event# 11 Malfunction FW17 Value: 0 Trips EF-P-1 When: Event# 12 Remote MUR59 Value: Lifted MU-V-1A/8 HI TEMP When: Event# 13 INTERLOCK LIFTED LEAD Remote MUR60 Value: Lifted MU-V-3 HI TEMP When: Event# 14 INTERLOCK LIFTED LEAD Remote RWR12 Value: NR-P-18 NR-P-18 ES selected When: Event# 15 Scenario Set-up NRC Scenario 1 Instructions:

1. Put G1-02 in PTL with info tag.

2. Place info tag on start PB for EG-Y-1

3. Ensure brief sheet is available for CRS.

4. Ensure proper CST and MUT level/pressure.

5. Ensure grid voltage monitor is off.

6. Ensure 1102-4, Enclosure 2A is complete. Ensure correct PPC points are removed from monitor.

7. Ensure copy of OP-TM-541-461 is available.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # Event#

Page 11of32 Event

Description:

Normal reactor shutdown Time I Position I Aoolicant's Actions or Behavior EXAMINER NOTE: There is no trigger for this event.

EXAMINER NOTE: This is a normal evolution to shutdown the reactor at the end of a 7 day LCO for EG-Y-1A inoperability.

EXAMINER NOTE: The crew may have briefed the shutdown prior to entering the simulator.

Crew Conduct a shutdown brief.

1102-4, POWER OPERATIONS, Section 3.3 URO Step 3.b.1 - Ensures the ULD is in Hand Step 3.b.2 - Sets the ULD Load rate of change to 1%/minute URO {which is at setting of 10 on the ULD load rate of change station)

Step 3.b.2 - Sets the ULD target load demand to the desired URO setpoint as ordered by the CRS EXAMINER NOTE: The crew will perform actions from Enclosure 28 as time permits.

EXAMINER NOTE: Once sufficient power reduction is observed, go to event #2 Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 2 Page 12 of 32 Event

Description:

EF-P-1 oil leak Time I Position I Aoolicant's Actions or Behavior BOOTH CUE: When directed by the lead examiner call into the control room as the secondary operator. Inform them that there is oil on the floor in the EF-P-1 cubicle, and that it appears that EF-P-1 outboard bearing oil bubbler is empty.

EXAMINER NOTE: The CRS should determine that EF-P-1 is inoperable and take step to ensure EF-P-1 does not automatically or manually start.

BOOTH CUE: If Maintenance is requested to investigate, report that they are unable to maintain level in the bubbler after oil was added.

Declares tech spec 3.4.1.1.a.2 Three EFW pumps, each capable of being powered from an OPERABLE emergency bus, and one EFW pump capable of being powered from two OPERABLE main steam supply paths:

CRS

• With one EFW pump or any EFW flow path inoperable, restore the inoperable pump or flowpath to OPERABLE status within 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> or be in COLD SHUTDOWN within the next 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br />.

BOOTH CUE: When ordered to place handwheel for MS-V-13A in the closed position, insert Event #10.

When ordered to place the handwheel for MS-V-13B in the closed position, insert event #11 If ordered to trip EF-P-1, insert event #12.

EXAMINER NOTE: Either or both methods (Tripping or closing the MS-V-13's) is an acceptable method of ensuring EF-P-1 doesn't start.

The CRS may order the valves closed and EF-P-1 tripped, and then choose to follow up with an alternate form of configuration control.

Dispatches an operator to close the handwheels for MS-V-ARO 13A/B, and to trip EF-P-1.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 2 Page 13 of 32 Event

Description:

EF-P-1 oil leak Time I Position I Applicant's Actions or Behavior EXAMINER NOTE: When the technical specification is declared and the steam supplies to EF-P-1 gagged closed (and/or EF-P-1 is tripped), go to Event #3.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 3 Page 14 of 32 Event

Description:

NR-P-1A Trips, NR-P-18 Fails to Auto-Start Time I Position I Applicant's Actions or Behavior BOOTH CUE: When directed by the Lead Examiner INITIATE Event #3.

INDICATIONS AVAILABLE: MAP B-1-5 and B-2-5 in alarm, NR-P-1A amber disagreement light lit on CR, PPC alarm.

EXAMINER NOTE: Crew may decide to start NR-P-1 B upon discovery of it not auto-starting IAW OS-24, Section 4.3.5.A:

Any time an automatic control or interlock functions fails to perform as designed and there is no specific procedure direction, the reactor operator should take action to compensate directly for the failure. The Reactor Operator should verbalize the actions taken to inform the Control Room team of the condition and actions taken.

BOOTH CUE: If directed, as an Auxiliary Operator and/or Maintenance, to investigate NR-P-1A and its breaker, acknowledge the order.

Nothing will be found at the pump or breaker.

Diagnose the trip of NR-P-1A and the failure of NR-P-18 to CRS automatically start on standby and direct entry into OP-TM-MAP-80105, 480V ES MOTOR TRIP OP-TM-MAP-B0105, 480V ES MOTOR TRIP EXAMINER NOTE: OP-TM-MAP-80105, Step 1 is an IAAT statement that is expected to remain N/A for the duration of the scenario.

Step 2: Ensures the start of the standby pump as follows:

ARO

• Starts NR-P-1 B by turning the Control Switch (CR) clockwise, observing red indicating light and normal running amps after initial start.

EXAMINER NOTE: The crew may match flags for NR-P-1A (place pump in Off or Pull-to-Lock to clear overhead alarm.)

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 3 Page 15 of 32 Event

Description:

NR-P-1A Trips, NR-P-1 B Fails to Auto-Start Time I Position I Aoolicant's Actions or Behavior EXAMINER NOTE: OP-TM-MAP-80105, Steps 3 and 4 are N/A Step 5: Maintain Nuclear River header IAW OP-TM-541-461, ARO "IC & NS Temperature Control".

OP-TM-541-461, IC & NS Temperature Control Step 3.2: Limitations.

3.2.1 To prevent NR pump run-out if a NR pump trips when two NR pumps were operating, maintain NR-Pl-217 pressure above the 2 PUMP OPERATION NOT PERMITTED region on Attachment 7.2.

ARO 3.2.4 To avoid clogging of the NR strainers (i.e., keep strainer pressure> 20 psig), do not operate for extended periods(> 4 HRs) with NR-Pl-217 pressure in the RESTRICTED REGION on Attachment 7.2.

3.2.5 To prevent excessive pump wear or damage, do not operate NR pumps for extended(> 4 HRs) periods with NR-PI-217 pressure in the RESTRICTED REGION on Attachment 7.2.

Step 4.1.5: Verify NR Pl-217 (CC) NR system pressure is within limits specified in Section 4.3.

Step 4.2.7: Verify NR Pl-217 (CC) NR system pressure is within the limits of Section 4.3.

EXAMINER NOTE: Nuclear River header pressure is expected to be in the proper range and therefore the steps listed to raise or lower are not scripted.

4.3.3 Maintain NR-Pl-217 between the high and low pressure limits of Attachment 7.2 ...

EXAMINER NOTE: OP-TM-MAP-80105, Step 6 is N/A CRS Step 7: Declares a 3.3.2 (72 Hour) Tech Spec clock.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRG Scenario # 1 Event# 3 Page 16 of 32 Event

Description:

NR-P-1A Trips, NR-P-18 Fails to Auto-Start Time I Position I Applicant's Actions or Behavior EXAMINER NOTE: Tech Spec 3.3.2:

Maintenance or testing shall be allowed during reactor operation on any component(s) in the makeup and purification, decay heat, RB emergency cooling water, RB spray, BWST level instrumentation, or cooling water systems which will not remove more than one train of each system from service.

Components shall not be removed from service so that the affected system train is inoperable for more than 72 consecutive hours.

If the system is not restored to meet the requirements of Specification 3.3.1 within 72 hours3 days <br />0.429 weeks <br />0.0986 months <br />, the reactor shall be placed in a HOT SHUTDOWN condition within six hours.*

I I EXAMINER NOTE: The crew may choose to enter OP-TM-541-451, Remove NR-P-1A From Service, which provides direction to swap the power supply for NR-P-1 B and ES select NR-P-1 B on the 1R 480V ES bus and also to close NR-V-1A.

EXAMINER NOTE: Once the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> tech spec is declared, go to Event #4.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 4 Page 17 of 32 Event

Description:

Generated Megawatts fail to 0 volts, Entry into OP-TM-AOP-070 Time I Position I Aoolicant's Actions or Behavior BOOTH CUE: When directed by the lead examiner, insert Event #4.

EXAMINER NOTE: The console left digital indicator will indicate 500 MWe. A large megawatt error signal will be developed which will be used for developing the header pressure modified setpoint and for developing the megawatt calibrating integral. Rods withdrawal and pressure rises.

Recognizes entry into OP-TM-AOP-070, PRIMARY TO Crew SECONDARY HEAT TRANSFER UPSET OP-TM-AOP-070, Section 2.0 Immediate Manual Actions Step 2.1: Ensures the diamond is in MAN and inserts control URO rods to match gross FW flow Step 2.2: Ensures both SG A & B FW Demand stations on in ARO HAND and stabilizes Tavq at current temperature.

Step 2.3: Verifies Turbine Header pressure between 835 and ARO 935 psiq Step 2.4: Verifies RCS pressure is lowering or less than 2205 URO psig. RNO: Fully open RC-V-1 and return to Auto OP-TM-AOP-070, Section 3.0 Follow-up actions Step 3.1: IAAT if a reactor trip setpoint is reached, to trip the Crew reactor Step 3.2: IAAT for Makeup tank level, which is NA for this CRS/URO scenario.

ARO Step 3.3: Verifies the Main Turbine is RESET Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 4 Page 18 of 32 Event

Description:

Generated Megawatts fail to 0 volts, Entry into OP-TM-AOP-070 Time I Position I Aoolicant's Actions or Behavior Step 3.4: Assigns manual control bands:

• Power within 1% of current power CRS

• Tave within 2 degrees F of current Tave

• Turbine Header Pressure within 10 psig or current pressure.

Step 3.5: Makes plant announcement for entry into OP-TM-ARO AOP-070 CRS Step 3.6: N/A 1102-4 is already initiated Step 3. 7: Ensures the following stations in HAND:

• SG/Reactor Demand CRS/URO

• Reactor Demand

• SG NB Load Ratio

• ULD Step 3.8: Verifies Main Feedwater Pump dP is greater than 30 ARO psid.

EXAMINER NOTE: Steps 3.9 and 3.10 are NA for this scenario Step 3.11: Adjusts FW flow to restore Tave to between 578F ARO and 580F ARO Step 3.12: Restores deltaTc to less than 5F BOOTH CUE: If the chooses to swap generated megawatt instruments, call in as SHIFT MANAGER, and report that the l&C supervisor reports that the plant must stay in manual to support troubleshooting. The plant shutdown can continue.

EXAMINER NOTE: When the plant is stable, the scenario can continue.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 5 Page 19 of 32 Event

Description:

Loss of ICS AUTO Power Makeup subfeed Time I Position I Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner, INITIATE Event 5.

Indications Available: Annunciators H-1-8, D-2-1, D-2-2, and D-3-3 in alarm, various Makeup related instrumentation and controls fail midscale.

BOOTH CUE: If directed, as an Auxiliary Operator and/or Maintenance, to investigate which ICS subfeed has been lost at the ICS Power Monitor Panel, report back that "the MU AUTO subfeed light is out, all other subfeed lights are lit".

Crew Diagnoses a loss of MU AUTO Subfeed.

CRS Direct entry into OP-TM-MAP-H0108, ICS/NNI POWER LOST OP-TM-MAP-H0108, ICS/NNI POWER LOST Step 4.0: Goes to OP-TM-AOP-027, Loss of ATA or ICS AUTO CRS Power EXAMINER NOTE: OP-TM-AOP-027 is not entered in its entirety since the entry conditions are not fully met. It is used only as a reference for the affected subfeed.

The CRS may also decide on using "approaching" criteria to enter MAP G-2-5 or D-2-3 for direction to restore letdown.

BOOTH CUE: If asked, maintenance is available to support the restoration of letdown OP-TM-AOP-027, Loss of ATA or ICS AUTO Power Step 3.10: If MU-V-17 is in HAND, then INITIATE OP-TM-211-URO 472 "Manual Pressurizer Level Control".

OP-TM-AOP-027, Loss of ATA or ICS AUTO Power Step 3.11: Initiates OP-TM-211-950, "Restoration Of Letdown ARO Flow".

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 5 Page 20 of 32 Event

Description:

Loss of ICS AUTO Power Makeup subfeed Time I Position I Applicant's Actions or Behavior OP-TM-211-950, RESTORATION OF LETDOWN FLOW ARO Reviews Precautions, Limitations, and Prerequisites.

BOOTH CUE: If directed as an Auxiliary Operator to report Local ICCW cooler outlet temperature, respond "Local ICCW cooler outlet temperature< 100°F". There is no Local ICCW Flow indicator, so if directed to report Local ICCW cooler outlet temperature, respond that you cannot find an indicator for ICCWflow.

I EXAMINER NOTE: OP-TM-211-950 Step 3.3.1 states to verify ICCW flow >550gpm. With ICS power to the indicator lost, the crew will need to display proper Engaged Thinking Skills to determine that flow has not changed (SOER 10-2)

I EXAMINER NOTE: OP-TM-211-950, Steps 4.1-4.3 are N/A.

EXAMINER NOTE: Role Play as Shift Manager and give concurrence to restore letdown.

Step 4.4.1: Decides that ICS AUTO power is deenergized and CRS obtains Shift Manager concurrence to lift leads.

BOOTH CUE: When directed as an l&C Technician to disconnect lead 7 3-16 in the ICS/NNI cabinet, insert EVENT #13 and report back that lead 7-3-3-16 in the ICS/NNI cabinet is disconnected and, if applicable, that another l&C Technician has performed the Concurrent Verification.

Step 4.4.2: Directs an Auxiliary Operator to disconnect lead 7-ARO 3-3-16 in the ICS/NNI cabinet.

EXAMINER NOTE: The crew may decide that Step 4.4.3 does not need to be performed because this partial loss of AUTO power has not affected MU-V-3 operations, and perform a Partial Performance of OP-TM-211-901.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRG Scenario # 1 Event# 5 Page 21of32 Event

Description:

Loss of ICS AUTO Power Makeup subfeed Time I Position I Applicant's Actions or Behavior BOOTH CUE:

If directed as an Auxiliary Operator (or l&C Technician) to disconnect lead 5-4-5-4 in the ICS/NNI cabinet, insert EVENT

1. 14 and report back that lead 5-4-5-4 in the ICS/NNI cabinet is disconnected and, if applicable, that another Auxiliary Operator (or l&C Technician) has performed the Concurrent Verification.

Step 4.4.3: Directs an Auxiliary Operator to disconnect lead 5-ARO 4-5-4 in the ICS/NNI cabinet.

EXAMINER NOTE: OP-TM-211-950, Step 4.4.4 is N/A.

Step 4.5: Verifies MU-V-5 is closed by the Control Station demand indicator reading zero (CC), closes MU-V-3 and MU-V-ARO 4, verifying green closed lights lit and the red open lights not lit (CC).

EXAMINER NOTE: Step 4.6 is N/A.

Step 4.7: Verifies MU-V-1A and MU-V-1 Bare Open by the ARO indicatinQ liqhts for each beinq red (not qreen) (CC)

Step 4.8.2: Verifies MU-V-2A and MU-V-28 are open by ARO observing lights on CC are red and PCR are amber.

BOOTH CUE: If asked, MU-V-98 is not throttled open.

Step 4.9.2: Throttles MU-V-5 to 10% open by operating the dial ARO on the MU-V-5 Control Station to the 10 position.

Step 4.10: Determines MU-V-8 is aligned to the THRU position ARO by the indication THRU TO FILTERS lit and BYPASS indication not lit (CC).

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 5 Page 22 of 32 Event

Description:

Loss of ICS AUTO Power Makeup subfeed Time I Position I Aoolicant's Actions or Behavior Step 4.11.4: Opens MU-V-3 by pressing the open pushbutton until high letdown temperature alarm (D-2-1) clears, and ARO observing the red open light lit and green closed light not lit (CC)

EXAMINER NOTE: OP-TM-211-950, Steps 4.12 and 4.13 require no action.

OP-TM-AOP-027, Loss of ATA or ICS AUTO Power Step 3.12: If MU-V-32 is in HAND, then INITIATE OP-TM-211-URO 476 "Seal Injection Control - MU-V-32 Console Operations".

OP-TM-211-476, Seal Injection Control - MU-V-32 Console Operations Step 4.2.1: Manually control SI flow using MU-V-32 H/A station URO as follows: PLACE MU-V-32 in HAND by pressing White HAND PB on the MU-V-32 Bailey Control Station (CC)

Step 4.2.2: Determines that the White HAND light and RED URO AUTO lights are not Lit on the MU-V-32 Bailey Control Station (CC).

BOOTH CUE: If contacted as an Auxiliary Operator to determine Seal Injection flow locally, go to the a RCP screen on the simulator computer, read seal injection, then multiply by 4 to report total seal injection.

Step 2.4.3: ADJUST Seal Injection Flow (MU42-Fl1 )(CC) using URO the toggle switch in the up and/or down directions, as necessary at the MU-V-32 Bailey Control Station (CC).

EXAMINER NOTE: Once letdown is being restored and Seal Injection is controlled properly, Go to Event 6.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # Event# 61718 Page 23 of 32 Event

Description:

Loss of Offsite Power, Reactor Trip, Lack of Primary to Secondary Heat Transfer Time I Position I Aoolicant's Actions or Behavior BOOTH CUE: When directed by the lead examiner, insert event 6.

Ensure EF-P-1 is tripped (EVENT 12) if not done in Event 2 EXAMINER NOTE: The crew will recognize we lost offsite power by the reactor trip, and the control room lights de-energizing.

Since only% the lights will re-energize, t.he crew will recognize that the 10 4160V bus did not repower because its associated diesel generator, EG-Y-1A is OOS.

BOOTH CUE: After the reactor trip is announced, perform the OS-24 actions that the Auxiliary Operators would normally perform.

Recognizes and diagnoses a loss of offsite power and Crew performes OP-TM-EOP-001 Immediate Actions.

OP-TM-EOP-001, Reactor Trip, Section 2.0 Immediate Actions URO Step 2.1: Presses both Reactor Trip and DSS pushbuttons URO Step 2.2: Verifies the reactor is shutdown.

URO Step 2.3: Presses the turbine trip pushbutton URO Step 2.4: Verifies the turbine stop valves are Closed.

OP-TM-EOP-001, Section 3.0 Vital System Status Verification (VSSV)

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# Event# 6/7/8 Page 24 of 32 Event

Description:

Loss of Offsite Power, Reactor Trip, Lack of Primary to Secondary Heat Transfer Time I Position I Aoolicant's Actions or Behavior EXAMINER NOTE: Entry into OP-TM-EOP-004, Lack of Primary to Secondary Heat Transfer is through the performance of a symptom check. The crew may choose to enter via the first performance, or through a subsequent symptom check based on incore temperature trends at the time of the check. Either option is acceptable.

EXAMINER NOTE: After recognition, the CRS should prioritize OP-TM-EOP-004, and OP-TM-AOP-020 actions to place the S80 diesel on the 1D 4160V ES bus. The crew may choose to attempt to start Emergency Feedwater Pump 28, EF-P-28. The breaker will not close due to malfunctions entered.

The crew may choose continue to monitor the lack of heat transfer symptom until they have come to the conclusion that NO FEEDWATER is available.

Step 3.1: Performs a symptom check. Based on incore ARO temperature rising, and no feedwater available, recognizes a lack of primary to secondary heat transfer is occurring.

OP-TM-EOP-004, Lack of Primary to Secondary Heat Transfer, Section 3.0 Step 3.1: Ensure no more than 1 RCP running per loop. No URO action taken as the LOOP caused all RCP's to turn off.

ARO Step 3.2: Initiate OP-TM-424-901, "Emergency Feedwater".

OP-TM-424-901, EMERGENCY FEEDWATER Step 4.2: If not Emergency Feedwater pumps are operating, and automatic HSPS/EFW actuation has occurred, the PLACE the EF-V-30 valves in Hand, with Zero Demand.

ARO Examinee presses the 'M' button on all four EF-V-30 controllers and lowers demand to zero. Examinee could pin each of the toaale switches in the close position.

OP-TM-EOP-004, Lack of Primary to Secondary Heat Transfer, Section 3.0 Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 61718 Page 25 of 32 Event

Description:

Loss of Offsite Power, Reactor Trip, Lack of Primary to Secondary Heat Transfer Time I Position I Aoolicant's Actions or Behavior ARO Step 3.3: Ensure reactor trip announcement.

Step 3.4: IAAT time step for after primary to secondary transfer Crew is established. This step will be used after the 1D 4160V ES bus is loaded onto the SBO diesel.

Step 3.5: IAAT step to go to OP-TM-EOP-009, HPI Cooling if Crew SCM approaches 25F. This step should be NA for this scenario.

Step 3.6: If RCS pressure approaches 2450 psig, and CRS/URO feedwater is available, the URO will ENSURE the PORV block valve is OPEN, then OPEN and deep seat the PORV.

Step 3.7: IAAT step for when FEEDWATER is available. This Crew step will be applicable after EF-P-2A is started.

Step 3.8: IAAT RCS pressure approaches 2450 psig and Crew FEEDWATER is not available, GO TO OP-TM-EOP-009, "HPI Cooling". This step is expected to be N/A for this scenario Step 3.9: Condensate booster pump cooling is not an option Crew for this scenario due to no condensate booster pumps or reactor coolant pumps running.

Step 3.10: When FEEDWATER is available, then continue.

Crew This is a hold point until the 1D 4160V ES bus is loaded onto the SBO diesel and EF-P-2A is started.

OP-TM-AOP-020, Loss of Station Power, Section 3.0 Follow up actions ARO Step 3.1: Initiate OP-TM-424-901, "Emergency Feedwater" Step 3.2: Initiate both OP-TM-861-901 and OP-TM-861-902 for ARO EG-Y-1A and EG-Y-1 B Operations.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 61718 Page 26 of 32 Event

Description:

Loss of Offsite Power, Reactor Trip, Lack of Primary to Secondary Heat Transfer Time I Position I Applicant's Actions or Behavior Step 3.3: Verify 1D 4160V and 1E 4160V busses are energized - RNO ARO

• Initiate OP-TM-864-901 "SBO Diesel Generator (EG-Y-

4) Operations

• If either ES 4160V bus is available, then Continue EXAMINER NOTE: The CRS should prioritize SBO diesel operations to power the 10 4160V ES bus. Once the 10 4160V ES bus is energized, EF-P-2A can be started and feedwater established.

OP-TM-864-901, SBO Diesel Generator (EG-Y-1A) Operations ARO Verifies precautions, limitations, and prerequisites ARO Step 4.1.1: Verify 1D 4160V bus is de-energized.

Step 4.1.2: The PPC is available, verify S2072, 4kV bus 1D ARO overcurrent, is NORM.

ARO Step 4.1.3: Ensure 1SA-D2 and 1SB-D2 are OPEN Step 4.1.4: Ensure the following control switches are in PTL:

A. BS-P-1A ARO B. The ES selected MU pump: MU-P-1A or MU-P-18-D C. DH-P-1A D. RR-P-1A E. EF-P-2A Step 4.1.5: PRESS and HOLD for approximately 8 seconds ARO the START PB for the SBO Diesel Generator Step 4.1.6: Generator voltage will be between 4.1 and 4.3 kV.

ARO No action taken.

Step 4.1.7: Generator frequency is between 59 and 61 Hz. No ARO action taken.

Appendix O Operator Action Form ES-0-2 Op Test No.: NRC Scenario # 1 Event# 61718 Page 27 of 32 Event

Description:

Loss of Offsite Power, Reactor Trip, Lack of Primary to Secondary Heat Transfer Time I Position I Aoolicant's Actions or Behavior ARO Step 4.1.8: ENSURE G1-02 is in PTL ARO Step 4.1.9: Place T1-C2 in PTL.

ARO Step 4.1.10: Close G2-12 (EG-Y-4 output breaker)

Step 4.1.11: Close T1-02 ( 1F 4160V bus cross tie to 1O ARO 4160V)

ARO Step 4.1.12: GO TO Section 4.4 EXAMINER NOTE: After the SBO is powering the 10 4160V ES bus, the CRS and ARO should prioritize starting EF-P-2A to restore feedwater.

EXAMINER NOTE: The crew could choose to restore seal injection via two methods. The crew could choose to restore SI while the 10 4kV bus is de-energized, which would drive them to starting MU-P-1 C. The crew could decide to wait until the 10 4kV bus is powered from the SBO diesel, and then start MU-P-1A.

Either method is acceptable to meet the critical task.

OP-TM-AOP-041, LOSS OF SEAL INJECTION {for starting either MU-P-1A or 1C)

URO Step 3.1: IAAT if SI and ICCW flow are lost. N/A for this event.

Step 3.2: IAAT for seal cooling lost for> 30 mins. N/A for this URO event.

Step 3.3: ENSURE MU-V-32 is in hand and closed. Examinee URO will use the toaale switch to close MU-V-32.

Step 3.4: When 10or1E 4160V bus is energized, then URO continue. Examinee determines that the 1O and/or 1E 4160 V bus is energized and continues.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # Event# 6/7/8 Page 28 of 32 Event

Description:

Loss of Offsite Power, Reactor Trip, Lack of Primary to Secondary Heat Transfer Time I Position I Applicant's Actions or Behavior Step 3.5: Verify a makeup pump is operating and aligned to URO seal injection. Examinee determines that no makeup pump is runninq and qoes to the RNO.

Step 3.5 RN01: ENSURE MU-V-3 is closed. Examinee URO presses green pushbutton on CC. Green pushbutton lights, the red push button extinguishes. Letdown is isolated.

Step 3.5 RN02: ENSURE MU-V-17 is closed. Examinee presses HAND button on MU-V-17. The white light becomes URO bright and red AUTO light extinguishes. Examinee closes the valves with the toggle switch.

URO Step 3.5 RN03: Examinee verifies MU tank level is >40".

Step 3.5 RN04: Examinee verifies MU tank level was never URO below 18" by looking at the trend on CC.

Step 3.5 RN05: If MU-V-77A& Bare open, then GO TO URO section 4.0. Examinee goes to section 4.0.

If the crew waits until the 1D 4160 kV bus is powered from the SBO diesel, they will perform Section 4.0. If they EXAMINER NOTE choose to start MU-P-1C, the crew will perform the applicable steps of section 4.0, then go to the RNO of step 4.4.

OP-TM-AOP-041, LOSS OF SEAL INJECTION, section 4.0 URO Step 4.0: MU-V-77A & Bare open. N/A for this event.

Step 4.1: Ensure MU-P-1A is ES selected. Examinee may URO determine from normal configuration control that MU-P-1A is ES selected, or dispatch an operator to verify.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # Event# 61718 Page 29 of 32 Event

Description:

Loss of Offsite Power, Reactor Trip, Lack of Primary to Secondary Heat Transfer Time I Position I Applicant's Actions or Behavior Step 4.2: Verify that MU-V-36 and MU-V-37 are open.

Examines determines from CC (red light lit, green light URO extinguished) or PCR (amber light lit, blue light extinguished) that MU-V-36 and MU-V-27 are open.

Step 4.3: ENSURE DR-P-1A and DC-P-1A are operating.

Examines starts both pumps on CC by taking the pistol grip to URO the start position and ensuring the red light becomes bright and the qreen liqht extinquishes.

Step 4.4: Start MU-P-1A. Examines starts MU-P-1A by taking CT-30 URO the pistol grip on CC to the start position. The red light becomes briqht, and the qreen liqht extinquishes.

If the crew chooses to start MU-P-1C, the will perform the following section. There are two paths available to start MU-P-1 C. If the examinee/crew decides that MU-P-1 B may be started from its current power supply, the crew will go to Section 5.0. In Step 5.1, the operator verifies that the 1E 4160V bus feeder from offsite power is closed, which it is not. The crew will then GO TO section 6.0.

EXAMINER NOTE:

The crew may choose to go right to section 6.0 based on the knowledge that while MU-P-1 B may technically be started on its current power supply, that the procedure will have the crew start MU-P-1 C instead, based on the feeder breaker from offsite power to the 1E 4160V bus. Either choice is acceptable. Only the section from starting MU-P-1C will be scripted here.

When dispatched, use the soft panels to open MU-V-BOOTH CUE:

76A&B, then report that they are open to the control room.

OP-TM-AOP-041, LOSS OF SEAL INJECTION, SECTION 6.0 Step 6.0: Examines will dispatch an operator to open MU-V-URO 76A&B.

Step 6.1: Examines ensures MU-P-1 C is ES selected by using URO normal configuration control and or dispatching an operator to the 1E 4160V bus.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 61718 Page 30 of 32 Event

Description:

Loss of Offsite Power, Reactor Trip, Lack of Primary to Secondary Heat Transfer Time I Position I Aoolicant's Actions or Behavior Step 6.2: Verify that MU-V-36 and MU-V-37 are open.

Examinee determines from CC (red light lit, green light URO extinguished) or PCR (amber light lit, blue light extinguished) that MU-V-36 and MU-V-27 are open.

Step 6.3: ENSURE DR-P-1 Band DC-P-1 Bare operating.

Examinee starts both pumps on CR by taking the pistol grip to URO the start position and ensuring the red light becomes bright and the green light extinguishes.

Step 6.4: Start MU-P-1 C. Examinee starts MU-P-1 C by taking CT-30 URO the pistol grip on CR to the start position. The red light becomes bright, and the green light extinguishes.

Step 6.5: Examinee waits until report of MU-V-76A & B being URO open, then qoes to step 3.5.

OP-TM-864-901, Section 4.4, While EG-Y-4 is loaded (UNIT Ops) on a 4160V bus Step 4.4.1: To start EF-P-2A:

1. Verify ESAS is defeated or not actuated ARO 2. Verify HSPS is defeated or not actuated

3. Start one large ES motor

4. Verify affected bus voltaqe is > 4100 volts EXAMINER NOTE: Once EF-P-2A is started, the CRS should continue in OP-TM-EOP-004 and Rule 4 of OP-TM-EOP-010 to establish feeding and steaming of both OTSG's.

OP-TM-EOP-004, Section 3.0 Step 3.11: IAAT OTSG pressure< 750 psig, then DEFEAT ARO HSPS Lo-Lo Pressure MFW Isolation.

Step 3.12: IAAT all RCPs are off then INITIATE Guide 7, "RCP URO Restart" Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 61718 Page 31of32 Event

Description:

Loss of Offsite Power, Reactor Trip, Lack of Primary to Secondary Heat Transfer Time I Position I Annlicant's Actions or Behavior Step 3.14: REDUCE OTSG Pressure so that secondary Tsat is ARO 40 to 60°F lower than incore thermocouple temperature.

EXAMINER NOTE: Step 3.14 is N/A. With EFW flow, RCS pressure should be lowering Step 3.15: REDUCE OTSG Pressure so that the secondary ARO Tsat is 90 to 100°F lower than incore thermocouple temperature.

Step 3.16: RAISE OTSG level to 75 to 85% operating range ARO with EFW.

Crew Step 3.17: ENSURE performance of an alarm review.

EXAMINER NOTE: If asked to evaluate EALs, acknowledge the order.

Step 3.18: REQUEST SM evaluate Emergency Action Levels CRS (EALs).

Step 3.19: When primary to secondary heat transfer has been Crew restored, then CONTINUE.

EXAMINER NOTE: Primary to secondary heat transfer will be present after natural circulation in verified. OP-TM-EOP-004 steps to reduce OTSG pressure, and raise OTSG level are performed to establish and strengthen natural circulation.

Natural Circulation may have been verified prior to this point.

OP-TM-EOP-010, Rule 4 Step 1: Examinee determines only one EFW pump is available and enters the RNO to maintain flow less than < 515 gpm.

ARO EFW flow can be totaled by using the EF-V-30 controller flow or using the PPC.

Step 2: Examinee verifies SCM is greater than 25F on the ARO PPC.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 61718 Page 32 of 32 Event

Description:

Loss of Offsite Power, Reactor Trip, Lack of Primary to Secondary Heat Transfer Time I Position I Aoolicant's Actions or Behavior ARO Step 3: Examinee verifies neither OTSG is dry.

Step 4: Examinee determines that no RCP is running and OTSG level is not > 50% in the operating range. Examinee ARO enters RNO to feed at maximum rate permitted (515 gpm in this case).

OP-TM-EOP-010, Guide 10 Guide 10: If all of the following conditions exist, then adequate natural circulation is present:

- RCS THOT minus TCOLD stabilizes at less than 50 °F.

- THOT < 600 °F.

- lncore temperature stabilizes and tracks THOT.

CT-12 URO - Cold leg temperatures approach saturation temperature for secondary side pressure.

- OTSG heat removal is indicated by feeding or steaming with stable OTSG pressure.

-SCM > 25F.

EXAMINER NOTE: Once natural circulation is verified, the scenario is can be terminated.

Appendix D Scenario Outline Form ES-D-1 Facility: Three Mile Island Scenario No.: 2 Op Test No.: TMl-2017-1 Examiners: Operators:

Initial Conditions:

• 85% power, MOL, load following

• EG-Y-1A is 2 days into a 6 day system outage

• Feedwater pump control is on the MSC Turnover: Maintain 85% power Critical Tasks:

• Trip All Reactor Coolant Pumps (CT-1)

• Reduce Steaming/Isolate Affected SGs (CT-22)

Event No. Malf. No. Event Type* Event Description 1 ES08A TSCRS Inadvertent 1600# ES actuation, "A" train, enter OP-TM-AOP-046 IURO IARO (URO: AOP-046 IMA's, ARO: Restores Letdown) 2 TH17A TSCRS 'A' OTSG Tube Leak, TS call, Reactivity manipulation RURO (URO: Lowers power) 3 TH13C CCRS RC-P-1 C High Vibrations CARO (ARO: Secures RCP) 4 IC63 I CRS Feedwater fails to re-ratio on loss of RCP IURO IARO 5 TH16A MCRS 'A' OTSG tube rupture, requiring HPI initiation, entry into OP-TM-MURO EOP-001 MARO 6 MU23A CCRS MU-P-1 A fails to start on ES CURO (URO: Starts MU-P-1A) 7 CCRS Loss of SCM, entry into OP-TM-EOP-002, then return to OP-TM-CURO EOP-005 CARO (URO: Rule 1, ARO: Steams 'A' OTSG)

• {N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Scenario Set-up NRC Scenario 2 Three Mile Island NRC Scenario #2 Event #1: The Lead Examiner will cue the Inadvertent 1600# ESAS Signal. The crew must quickly recognize the condition and perform the required Immediate Manual Actions of OP-TM-AOP-046, INADVERTENT ESAS ACTUATION, to minimize the RCS pressure transient and pressurizer in-surge due to HPI. Additionally, while at power, immediately reducing HPI also minimizes the possibility of a reactor trip on high RCS pressure.

The crew will diagnose the Inadvertent "A" 1600# ESAS Signal by multiple annunciators in alarm, "A" Train components in their ES actuated state, and/or "A" EOG running, while all primary indications appear steady or rising (RCS pressure not at 500#).

The URO will perform the Immediate Manual Actions of OP-TM-AOP-046, INADVERTANT ESAS. The ARO will restore letdown IAW OP-TM-211-950 (performing the appropriate portion of the procedure when restoring from isolation following an ESAS signal).

Once the plant is stabilized and Letdown is restored, the scenario can continue.

Event #2: The Lead Examiner will cue the 'A' OTSG Tube Leak. Any OTSG tube leak causes an abnormal increase in the release of radioactive materials to the environment.

The most fundamental objective is to minimize this release. The prioritized objectives of this procedure are:

• Maintain core cooling.

• Minimize the activity release to the atmosphere (minimize release duration, rate and concentration of radioisotopes, particularly iodine)

• Minimize the integrated tube leakage The crew will diagnose an OTSG tube leak based on RM-G-26, RM-A-5, and RM-A-15 indications (PR), Annunciator C-1-1 in alarm, and/or pressurizer level lowering (CC).

The CRS will announce entry into OP-TM-EOP-005, OTSG TUBE LEAKAGE. This is a reactivity manipulation event. The URO will perform reactor shutdown with ICS in Auto.

The ARO may lineup to feed to the RCS from the "B" RBCT for inventory control. The CRS will evaluate and declare Tech Spec 3.1.6.3 When sufficient reactivity manipulation has been observed, the scenario can continue.

Event #3/4: The lead examiner will cue the RC-P-1 C high vibrations. Vibrations will slowly worsen until they the motor exceeds 7 mils and pump exceeds 20 mils.

The CRS will enter OP-TM-PPC-L3124, and request the Shift Manager establish a duty team call within 30 minutes.

Time compression will be used, and the Shift Manager will report that the duty team directed the crew to shutdown RC-P-1 C in accordance with OP-TM-226.-153.

Scenario Set-up NRC Scenario 2 The crew will lower power to less than 75% and secure RC-P-1 C. Upon securing RC-P-1C, feedwater will fail to re-ratio requiring ICS to be placed in manual in accordance with OP-TM-621-471, down to the feedwater loop masters.

When the crew has completed the re-ratio of feedwater the scenario can continue.

Event #5: The Lead Examiner will cue the "A" OTSG Tube leakrate rising to approximately 500 gpm. The CRS will direct the initiation of High Pressure Injection and will continue with the shutdown. If the level in the Pressurizer goes below 150", then the CRS will enter OP-TM-EOP-001 to direct the Immediate Manual Actions, and then continue in OP-TM-EOP-005, OTSG Tube Leak.

Event #6/7: Makeup Pump, MU-P-1A will fail to start on the ES actuation. The URO must manually start MU-P-1A.

After the reactor trip, 25F subcooling margin will be lost and the crew will enter OP-TM-EOP-002, Loss of 25F subcooling margin. The crew will perform Rule 1 and initiate a cooldown in accordance with Guide 11.

When that is complete, the crew will return to OP-TM-EOP-005 for the OTSG 'A' tube leakage.

Termination: The scenario can be terminated when the crew has begun to preferentially steam the 'A' OTSG in OP-TM-EOP-005, OTSG TUBE LEAKAGE.

Scenario Set-up NRC Scenario 2 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Trip All RCPs - requires that the RCPs be tripped within 1 minute of Loss of Sub Cooling Margin, IAW OP-TM-102-106 reference FSAR 14.2.2.4.

Safety Significance: SBLOCA analyses were performed using conservative Appendix K assumptions with the objective of meeting 10 CFR50.46 criteria.

These analyses predicted that continued RCP operation, during certain SBLOCAs, could lead to RCS void fractions of 70% if RCPs continued to operate longer than [1 or 2] minutes following initiation of the SBLOCA. The analyses predicted that if RCPs were tripped after these high void fractions occurred, the core would not be adequately covered and fuel clad failure would occur.

Cues:

1. SCM meter reading less than 25F

2. P-T Display and associated alarms

3. Low RCS Pressure alarms Performance Indicators:

1. Operation of all console RCP trip devices Feedback:

1. Report by the URO to the crew that RULE 1 has been completed Scenario Set-up NRC Scenario 2 CT Reduce Steaming/Isolate Affected SGs (includes use of SG drains)-

Steam affected SGs to maintain level< [overfill setpoint]. If steaming alone cannot prevent SG fill, then use SG drains (if available) to maintain SG level below [overfill setpoint]. Isolate SG(s) if steaming and draining cannot prevent overfill and maintain RCS and isolated SG pressures < 1000 PSIG by use of [primary and secondary relief paths].

- Isolating Affected SGs outside of the following limits should be considered grounds for failure of the critical task:

- Do not allow isolation to occur with RCS pressure > 1000 psig.

- Do not allow the RCS to re-pressurize > 1000 psig with an isolated OTSG.

Safety Significance: The more probable tube rupture scenario is a tube leak in one SG with both SGs available. The preferred mitigation strategy is therefore isolation of the affected SG following the initial cooldown and depressurization to

<1000 PSIG. This limits the radiological consequences of the event, but does require cooldown to DHRS operation using one SG.

Both SGs are always used in the initial cooldown and depressurization to < 1000 PSIG. Prevention of MSSV lift on the affected SG(s) is integral to the goal of minimizing off-site release, and assurance requires RCS temperatures at or below 500°Fin order to maintain SCM when RCS pressure is< 1000 PSIG.

Once this initial cooldown and RCS depressurization to <1000 PSIG is completed, then SG isolation can be considered.

There are limitations on continued steaming of a SG with a SGTR. These limitations consider the overriding concerns of SGTR transients that dictate the isolation of the SG(s) and initiation of HPI cooling, if necessary. These limits are based on integrated radiation dose reaching predetermined values and SG filling due to tube leakage despite steaming to achieve maximum allowable cooldown rate.

SGs isolated due to SG fill criteria pose concerns related to liquid passing through MSSVs. MSSVs should be prevented from passing liquid, since their failure to reseat becomes more probable. For this reason, RCS and SG pressures are maintained <1000 PSIG by use of [primary and secondary relief paths]. These relief paths may include such things as letdown, PZR vents, HPVs, the PORV, TBVs and ADVs.

Cues:

1. Rising OTSG level

2. Rad Monitor Alarms

3. Lowering Pressurizer level

4. Lowering RCS Pressure

5. Automatic initiation of HPI Scenario Set-up NRC Scenario 2 Performance Indicators:

1. Operation of TBV/ADV controls Feedback:

1. SG(s) level and pressure

2. RCS pressure

3. MFW/EFW flow

4. MFW/EFW pump and valve status indication

5. TBV/ADV status indication

6. RCS pressure is maintained less than 1000 psig Industry Experience:

• Indian Point 2 (2/15/00) - Steam Generator Tube Failure (380 litres per minute)

• Palo Verde 2 (3/14/93) - Steam Generator Tube Leak ranged between 11 and 39 litres per day, suddenly turned to 900 litres per minute tube rupture.

PRA

• Steam Generator Tube Rupture (Initiating Event)

Scenario Set-up NRC Scenario 2 Event Description Procedure Support Initial Setup 85% Power, MOL Inadvertent 1600# ESAS OP-TM-AOP-046, Inadvertent ESAS Actuation 1

Tech Spec 3.5.1.1 OP-TM-EOP-005, OTSG Tube Leak OP-TM-EOP-010, Emergency Procedure Rules, 2 -30 gpm "B" OTSG Tube Leak Guides and Graphs 1102-4, Power Operations OP-TM-PPC-3124, RC-P-1C HIGH VIBRATION 3 RC-P-1 C High Vibrations 1102-4, Power Operations 4 Feedwater fails to re-ratio OP-TM-621-471, ICS MANUAL CONTROL OP-TM-EOP-001, Reactor Trip

-500 gpm "B" OTSG Tube Rupture OP-TM-EOP-010, Emergency Procedure Rules, 5

Guides and Graphs OP-TM-EOP-005, OTSG Tube Leak Loss of 25F Subcooling 6 OP-TM-EOP-002, Loss of 25F Subcooling Margin Margin Scenario Set-up NRC Scenario 2 ACTION COMMENTS/ INSTRUCTIONS DESCRIPTION Initialization IC-242 85% HFP ICS in AUTO Equilibrium XENON Tags and protected equipment for EG-Y-1A Malfunction EG01A Value: Insert EG-Y-1A will not start When: Immediately Malfunction EGR28 Value: Insert Trip EG-Y-1A fuel rack When: Immediately Malfunction ESQ? A Value: Insert Inadvertent 'A' side ESAS When: Event #1 actuation Trigger #10 Value: DMF ESO?A Removes Inadvertent 'A' When: dhndhp1 a > 0.9 ESAS actuation Malfunction TH1 ?A Value: 0.2 - 30 GPM tube leak 'A' OTSG When: Event #2 Malfunction TH 13C Value: 40% over 120 sec RC-P-1 C High Vibrations When: Event#3 Malfunction IC63 Value: Insert Feedwater fails to re-ratio When: Immediately Malfunction TH 16A Value: 4. 7 Ramp 180 secs "A" OTSG Tube Rupture When: EVENT 5 Remote MSR66 Value: Insert Initiate Aux Boilers When: EVENT 11 Remote FWR78 Value: MAN MS-V-13B Manual Control When: EVENT12 Remote FWR79 Value: 0 MS-V-13B Closed Position When: EVENT12 Trigger #20 When: ratpw < 20 Modifies TH16A to lose Command: mmf TH16A 15 60 subcooling margin after trip.

Malfunction MU23A Value: Event#5 MU-P-1A fails to start on ES.

When: Immediately Instructions:

1. Put G1-02 in PTL with info tag.

2. Place info tag on start PB for EG-Y-1A

3. Ensure LO-P-8A and 8B are running.

4. Ensure procedure copies of OP-TM-226-153 are available.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRG Scenario # 2 Event#

Page 9 of 27 Event

Description:

Inadvertent 'A' Train ES 1600# Actuation Time I Position I Aoolicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE EVENT 1.

Indications Available: Multiple Main Annunciator Panel Alarms illuminated, MU-P-1A running, ES positions indicated on PCR for "A" Train components.

When maintenance is requested to investigate, wait until EXAMINER NOTE: the appropriate time and report that loose coils in the actuation circuitry cause the ES actuation.

Crew Diagnoses an Inadvertent ES Actuation, "A Train 1600#.

Direct entry into OP-TM-AOP-046, Inadvertent ESAS CRS Actuation.

OP-TM-AOP-046, Inadvertent ESAS Actuation Step 2.1 (IMA): Defeats invalid ESAS signals by pressing "Defeat I Enable" pushbuttons for each of three channels, URO/ARO verifying that the amber "Defeat" light is lit for each channel and the blue Block load lights are not lit for each channel (PCR).

Step 2.2 (IMA): Determines that MU-P-1A is not required for seal injection and secures it by rotating the Control Switch in URO the counter-clockwise direction and verifying the green flag indicator is visible, and that the green Off light is lit and the red RunninQ liQht is not lit.

EXAMINERS NOTE: Once MU-P-1A is secured, MU-V-16A and MU-V-168 will have flow based on MU-P-18 operating.

Step 2.3 (IMA): Throttles MU-V-16A I 168 with HPI flow to URO maintain MU-P-1 B flow> 115 gpm.

Step 3.1: Announces entry into OP-TM-AOP-046, "Inadvertent ARO ESAS Actuation" over the plant page and radio.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event#

Page 10 of 27 Event

Description:

Inadvertent 'A' Train ES 1600# Actuation Time I Position I Aoolicant's Actions or Behavior CRS Step 3.2: IAAT for ICCW flow. NA for this scenario.

Step 3.3: Ensures MU-V-36 is Open by pressing the open pushbutton and verifying the red open light is lit and the green URO closed light is not lit (CC). MU-V-37 is already open, evidenced bv red open liqht lit and green closed light not lit (CC).

EXAMINERS NOTE: Steps 3.4 through 3.6 are N/A URO Step 3.7: Verifies MU-V-36 and MU-V-37 are Open.

Step 3.8: If MU-V-77A & 778 are OPEN, then perform the following:

URO

• ENSURE MU-V-16A is Closed

• ENSURE MU-V-168 is Closed EXAMINERS NOTE: Steps 3.9 and 3.10 are N/A Step 3.11: Ensures MU-V-14A is Closed by pressing the close pushbutton and verifying the green closed light is lit and the red URO open light is not lit (CC). MU-V-148 is already closed, evidenced by green closed light lit and red open light not lit (CC).

Step 3.12: IAAT step to ensure rods stay in desired bands. As CRS/URO scenario progresses, rods could pull and the URO could lower power and control rods with this step.

Step 3.13: If at power, then ENSURE two Secondary River ARO pumps are running.

ARO Step 3.14: INITIATE an alarm review.

Step 3.15: Initiates OP-TM-211-950, "Restoration of Letdown ARO Flow."

Appendix D Operator Action Form ES-D-2 Op Test No.: NRG Scenario # 2 Event#

Page 11of27 Event

Description:

Inadvertent 'A' Train ES 1600# Actuation Time I Position I Aoolicant's Actions or Behavior OP-TM-211-950, Restoration of Letdown Flow Section 3.0: Reviews Precautions, Limitations, and ARO Prerequisites.

BOOTH CUE: If contacted to verify integrity of Letdown Line, state "The integrity of the Letdown Line to MU-T-1 has been assessed and the Letdown line is intact".

EXAMINERS NOTE: Steps 4.1 through 4.4 are N/A.

Step 4.5: Ensures:

• MU-V-3 is closed by observing green closed light lit, red open light not lit.

ARO

• MU-V-4 is closed by pressing the green closed light, observing green closed light lit, red open light not lit.

• MU-V-5 is closed by pressing the Control Station toggle switch in the downward direction, observing the carrot position indicator is pointing to zero.

EXAMINERS NOTE: Step 4.6 is N/A Step 4.7: Verifies MU-V-1A and MU-V-1 Bare Open by the ARO indicatinQ liQhts for each beinQ red (not Qreen) (CC)

ARO Step 4.8: Opens MU-V-2A and MU-V-28 below:

Step 4.8.2: Verifies MU-V-2A and MU-V-28 are Open by the ARO indicating lights for each being red (not green) (CC)

Step 4.9.2: Throttles MU-V-5 to 10% open by operating the ARO dial on the MU-V-5 Control Station to the 10 position.

Step 4.10: Verifies MU-V-8 is aligned to the Thru position by ARO the indication Thru to filters lit and Bleed indication not lit (CC)

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event#

Page 12 of 27 Event

Description:

Inadvertent 'A' Train ES 1600# Actuation Time I Position I Aoolicant's Actions or Behavior Step 4.11: Opens MU-V-3 by pressing the open pushbutton ARO and observing the red open light lit and the green closed light not lit (CC)

EXAMINERS NOTE: Step 4.12 for OP-TM-541-901 is a procedure that is always open in the CR. Step 4.13 Letdown temperature is maintained< 125F.

Step 4.14: Raises letdown flow at < 2.5 gpm/min to desired ARO flow by operating the dial on the MU-V-5 Control Station in the clockwise direction to open MU-V-5 madually.

OP-TM-AOP-046, Section 3.0 EXAMINER NOTE: Step 3.16 is N/A Step 3.17: Declares a 3.5.1.1 (24 Hours) Tech Spec LCO time CRS clock.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event#

Page 13 of 27 Event

Description:

Inadvertent 'A' Train ES 1600# Actuation Time I Position I Aoolicant's Actions or Behavior EXAMINERS NOTE: Tech Spec 3.5.1.1 The reactor shall not be in a startup mode or in a critical state unless the requirements of Table 3.5-1, Column "A" and "B" are met, except as provided in Table 3.5-1, Column "C". Specification 3.0.1 applies.

TABLE 3.5-1 INSTRUMENTS OPERATING CONDITIONS C. Engineered Safety Features (C)

Operational (A) (B)

Action if Functional Minimum Minimum Conditions of Unit Operable Degree of Column A Channels Redundancy and B Cannot Be Met Engineered Safety Features:

1.a Reactor 2 1(b) (a)

Coolant Pressure Instrument Channels (a) Restore the conditions of Column (A) and Column (B) within an additional 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and COLD SHUTDOWN within the following 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.

I I Once the CRS has determined the Tech Spec, or as the EXAMINER NOTE: lead examiners discretion, inform the CRS that the cause of the Inadvertent ES has been fixed.

I I EXAMINERS NOTE: Once Letdown has been restored, Go to Event #2.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# 2 Page 14 of 27 Event

Description:

'A' OTSG Tube Leak Time I Position I Aoolicant's Actions or Behavior BOOTH CUE: When directed by the Lead Examiner INITIATE Event #2.

Indications Available: MAP Annunciator C-1-1 actuates, RM-A-5/15/RM-G-26 counts rise.

Crew Diagnoses the "A" OTSG Tube leak.

CRS Announces entry into OP-TM-EOP-005, OTSG Tube leakage OP-TM-EOP-005, OTSG Tube leakage Step 3.1: NOTIFY "Shift Dose Assessor" to begin offsite dose CRS assessment.

ARO Step 3.2: Announce OTSG TUBE LEAK.

INFO Step 3.3: INITIATE Guide 9, "RCS Inventory Control.

OP-TM-EOP-010, GUIDE 9, RCS Inventory Control URO Step C.1: Verify MU Pump is operating.

URO Step C.2: Verify MU-V-5 is closed.

Step C.3: Verify MU24-FI >20 gpm URO RNO: Ensure MU-V-18 is Open by pressing the Open Pushbutton (CC), verifying the valve open light is lit and the valve closed light is not lit.

URO Step C.4: Ensure MU-V-17 is open.

URO Step C.5: Verify Pressurizer level is being restored.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# 2 Page 15 of 27 Event

Description:

'A' OTSG Tube Leak Time I Position I Aoolicant's Actions or Behavior OP-TM-EOP-005, OTSG Tube leakage BOOTH CUE: When directed to fire both Auxiliary Boilers, request the control room to open CO-V-14A (if they have not) and insert Event #11.

Step 3.4: INITIATE the following procedures to start both Auxiliary Boilers:

ARO

- OP-TM-414-401, "Starting AS-B-1A".

- OP-TM-414-402, "Starting AS-B-18".

CRS Step 3.5: VERIFY the reactor is critical.

Step 3.6: IAAT pressurizer level < 150 inches and reactor power> 25%, then perform the following:

N/A

• INITIATE HPI.

• TRIP the reactor.

• GO TO EOP-001 Step 3.7: IAAT the turbine trips, and reactor power> 15%, then perform the following:

N/A

• TRIP the reactor

• GO TO EOP-001 Procedure Note: 1102-4, "Power Operation" actions to perform plant power reduction should be completed as resources permit. The rate of power reduction should be selected to maintain control and avoid lifting MSSVs.

Step 3.8: Verify SG/REACTOR DEMAND is in Auto, Ensures URO the ULD is HAND, sets the Load Rate of Change and then the ULD Target Load demand to 0%.

ARO Step 3.9: Place both FW-P-1A and FW-P-1 Bin Hand.

EXAMINERS NOTE: Acknowledge as the personnel listed in the next step, or acknowledge as Shift Manager to notify the personnel listed in the next step. Also acknowledge evaluating EAL's.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# 2 Page 16 of 27 Event

Description:

'A' OTSG Tube Leak Time I Position I Aoolicant's Actions or Behavior OP-TM-EOP-005, OTSG Tube leakage Step 3.10: REQUEST SM to:

- Evaluate Emergency Action Levels CRS - NOTIFY Power Team

- NOTIFY TSO

- NOTIFY NDO.

CRS Step 3.11: IDENTIFY the affected OTSG: ('A' OTSG)

BOOTH CUE: When directed to place the MS-V-13A handwheel in the closed position, insert Event #12 and then report the action complete.

Step 3.12: IAAT all of the following conditions exist:

- The affected OTSG is identified ARO

- EF-P-1 is not running

- Either Motor Driven EFW Pump is Operable then Place the Handwheel of the affected MS-V-13, in the CLOSED position.

CRS Declares a 3.1.6.2 and 3.1.6.3 (24 hours1 days <br />0.143 weeks <br />0.0329 months <br />) Tech Spec clock.

EXAMINERS NOTE: Technical Specification 3.1.6.3 - If the primary-to-secondary leakage through any one (1) steam generator exceeds 150 GPO, the reactor shall be placed in hot shutdown within 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br />, and in cold shutdown within 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br />.

EXAMINERS NOTE: After the Tech Spec call is made and sufficient reactivity manipulation has occurred, GO TO Event #3.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# 3/4 Page 17 of 27 Event

Description:

RC-P-1 C High Vibrations, Feedwater fails to re-ratio Time I Position I Aoolicant's Actions or Behavior BOOTH CUE: When directed by the Lead Examiner INITIATE Event #3.

Indications Available: PLF RCP Bentley Nevada Vibration Monitor, PPC Point L3124 RC-P-1C High Vibration Crew Diagnoses the RC-P-1 C has high pump and motor vibrations.

OP-TM-PPC-L3124, RC-P-1C High Vibrations ARO Attempts to reset the alarm, alarm will not reset.

EXAMINERS NOTE: The crew will evaluate the validity of the high vibration alarm.

The alarm will exceed the threshold to perform a duty team call regarding securing the RC pump. The CRS will request a duty team call to evaluate the status.

EXAMINERS NOTE: After the CRS requests the duty team call, use time compression and notify the CRS that the duty determined that the pump needs to be secured as soon as power is less than 75%.

EXAMINERS NOTE: Due to the 'A' OTSG tube leakage, power may be below the 75% threshold.

OP-TM-226-153, SHUTDOWN RC-P-1 C ARO Reviews/Verifies Precautions, Limitations, and Prerequisites Step 4.1: Evaluates the final RCP combination for effects of CRS vibrations and procedural requirements.

EXAMINERS NOTE: A 2/1 RCP combination with OTSG levels > LLL will require a re-ratio (-70% I 30%) of feedwater flow to A I B OTSG Step 4.2: Evaluates FW Flow requirements for new RCP ARO combination to minimize effects on Delta Tc Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# 3/4 Page 18 of 27 Event

Description:

RC-P-1 C High Vibrations, Feedwater fails to re-ratio Time I Position I Aoolicant's Actions or Behavior Step 4.3: Notifies Electrical Maintenance to monitor RC-P-1 C CRS vibrations.

Step 4.4: Places one of the following to Normal-After-Start:

ARO - RC-P-2C-2, Oil Lift Pump DC HP

- RC-P-2C-1, Oil Lift Pump AC HP ARO Step 4.5: Places RC-P-1 C in Pull to Lock EXAMINERS NOTE: At this point, the crew will diagnose that feedwater failed to re-ratio based on Delta Tc not recovering to -o and P-T plot indications.

Diagnoses feedwater re-ratio failure. Enters OP-TM-621-471, Crew ICS MANUAL CONTROL to take control of feedwater.

OP-TM-621-471, ICS MANUAL CONTROL CRS Reviews limits, precautions, and prerequisites URO Step 4.1: Ensures ULD is in HAND.

URO Step 4.2.1: Places SG/REACTOR DEMAND station in HAND.

URO Step 4.2.2: Ensures control rod position does not change.

ARO Step 4.2.3: Verifies alarm H-2-1 "ICS in Track" In.

Step 4.2.4: Description on how to change power with the URO SG/REACTOR DEMAND station. This will be used later to lower power due to the 'A' OTSG tube leak.

ARO Step 4.3: Manual feedwater control is needed.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# 3/4 Page 19 of 27 Event

Description:

RC-P-1C High Vibrations, Feedwater fails to re-ratio Time I Position I Applicant's Actions or Behavior ARO Step 4.4.1: Places the SG NB LOAD RATIO station in HAND.

ARO Step 4.4.2: Places SG A FW DEMAND station in HAND.

ARO Step 4.4.3: Places SG B FW DEMAND station in HAND.

Step 4.4.4: Adjusts SG A and/or B FW DEMAND to maintain ARO Tavg, deltaTc, and OTSG level within limits.

EXAMINERS NOTE: When feedwater is re-ratioed correctly, and the examiner has observed sufficient manual reactivity manipulation, the scenario can continue.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# 51617 Page 20 of 27 Event

Description:

OTSG Tube Rupture, Loss of Subcooling Margin, MU-P-1A fails to start on ES Time I Position I Aoolicant's Actions or Behavior BOOTH CUE: When directed by the Lead Examiner INITIATE Event 5.

Indications Available: Pressurizer level lowering rapidly, RCS Pressure lowering rapidly, "A" OTSG level rising rapidly URO Continues in Guide 9 OP-TM-EOP-010, Guide 9, RCS Inventory Control Step C.8: Verify PZR level is NOT being restored by observing rising level on Pressurizer level indicators (CC) and/or the PPC.

URO RNO: INITIATE HPI IAW OP-TM-211-901, "Emergency Injection HPl/LPI".

OP-TM-211-901, Emergency Injection (HPl/LPI)

Step 4.1.2: Verifies that ESAS Train A "Load Seq Block 4" lights (PCR) are not BLUE, and then presses the "A" Train 1600# ES Actuation Manual pushbutton (CC), verifying that block loadino is occurring for the "A" Train of ES (PCR).

Step 4.1.5: Verifies that ESAS Train B "Load Seq Block 4" lights (PCR) are not BLUE, and then presses the "B" Train 1600# ES Actuation Manual pushbutton (CR), verifying that block loading is occurring for the "B" Train of ES (PCR).

Step 4.3.1: Monitors HPI IAW RULE 2 and throttles HPI IAW Attachment 7.3.

Crew Diagnoses the Pressurizer has gone below 150".

URO Observes MU-P-1A did not start. URO starts MU-P-1A (in accordance with OS-24) and notifies the CRS.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# 51617 Page 21of27 Event

Description:

OTSG Tube Rupture, Loss of Subcooling Margin, MU-P-1A fails to start on ES Time I Position I Aoolicant's Actions or Behavior EXAMINERS NOTE: The CRS will direct the IMAs of OP-TM-EOP-001, Reactor Trip and following the Symptom Check he should re-enter OP-TM-EOP-005, OTSG Tube Leakage. Based on the reactor being tripped, previous actions have already been taken and the event picks up at step 3.24. The crew may or may not have made it through step 3.23, but those steps are not applicable once the reactor is tripped.

The URO will continue in Guide 9, RCS Inventory.

OP-TM-EOP-001, REACTOR TRIP URO Step 2.1 (IMA): Presses Both Reactor Trip and DSS pushbuttons (CC).

URO Step 2.2 (IMA): Verifies that the reactor is shutdown by one of the following:

1. Power Range Nuclear Instrumentation indicates less than 5% (CC)

2. All control rods are inserted (PC)

3. Source Range count rate is continuously lowering (CC)

URO Step 2.3 (IMA): Presses the Turbine Trip pushbutton (CL)

URO Step 2.4 (IMA): Verifies the Turbine Stop valves are closed by observing the indication on CL.

ARO Performs a Symptom Check, and identifies the "A" OTSG tube leak, and informs the CRS.

Diagnoses the "A" OTSG Tube leak rate increasing by lowering URO Pressurizer level and RCS pressure, and informs the CRS.

EXAMINERS NOTE: The CRS should continue in OP-TM-EOP-005. This event picks up at step 3.24. The crew may or may not have made it further.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# 51617 Page 22 of 27 Event

Description:

OTSG Tube Rupture, Loss of Subcooling Margin, MU-P-1A fails to start on ES Time I Position I Aoolicant's Actions or Behavior OP-TM-EOP-005, OTSG Tube Leakage.

Step 3.24: Verify control rod groups 1 through 7 are fully URO inserted.

ARO Step 3.26: Ensure announcement of reactor trip.

ARO Step 3.27: Dispatch an operator to check MSSV status.

ARO Step 3.28: Ensure performance of an alarm review.

EXAMINER NOTE: The step implementing CT-22 is below. Since the step is an IAAT, the isolation of 'A' OTSG will occur sometime later.

The script for the isolation of the 'A' OTSG will occur at the end of the scenario.

Step 3.29: IAAT OTSG A (B) pressure approaches, or is greater than 1000 psig, then perform the following:

CT-22 ARO - ENSURE MS-V-2A (MS-V-28) is Open.

- OPEN MS-V-30, E, F (MS-V-3A, B, C) to maintain OTSG pressure< 1000 psig.

EXAM IE EXAMINERS NOTE: Cooldown rate is 100°F/hr per Guide 11 until 10CFR 50.54x is invoked.

Step 3.30: IAAT OTSG level is rising due to tube leakage in an AVAILABLE OTSG, then preferentially STEAM to maintain CT-22 ARO OTSG level< 85% by adjusting the toggle switches for MS-V-30, E, F (MS-V-3A, B, C) upward/downward as necessary.

Procedure Note: If exceeding RCS or Pressurizer Tech Spec cooldown rate limits is needed to permit isolation of an OTSG, then 10CFR 50.54x entry should be evaluated.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# 51617 Page 23 of 27 Event

Description:

OTSG Tube Rupture, Loss of Subcooling Margin, MU-P-1A fails to start on ES Time I Position I Aoolicant's Actions or Behavior EXAMINERS NOTE: The OTSG tube rupture will continue to get worse until 25F Subcooling Margin is lost, and OP-TM-EOP-002 is entered.

OP-TM-EOP-002, LOSS OF 25F SUBCOOLING MARGIN URO Step 2.1 - PERFORM Rule 1, LSCM.

OP-TM-EOP-010, Rule 1, Loss Of Subcooling Margin Step 1 - VERIFY it has been more than two minutes since RCP URO start.

Step 2 - ENSURE fill RCPs are shutdown within one minute by CT-1 URO rotating the control switches (CC) counter-clockwise, observing red lights out, green lights lit, and no amps for each RCP.

Step 3 - INITIATE 4 # ESAS Actuation IAW OP-TM-642-902 4#

ESAS Actuation by pressing the A and B train 4# manual ESAS URO actuation buttons (CC and CR) and observing 4# ES actuation on PCR. This step was completed in guide 9, and may or may not be performed again. The 'B' side still will not work.

Step 4 - INITIATE OP-TM-424-901, "Emergency Feedwater" ARO and FEED IAW Rule 4, Feedwater Control.

OP-TM-EOP-002, Section 3.0 ARO Step 3.1 - ENSURE announcement of reactor trip.

Step 3.2 - IAAT LPI flow >1250 gpm in each line, then GO TO CRS EOP-006.

URO Step 3.3: Verifies both LPI pumps are both operating.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# 5/6/7 Page 24 of 27 Event

Description:

OTSG Tube Rupture, Loss of Subcooling Margin, MU-P-1A fails to start on ES Time I Position I Aoolicant's Actions or Behavior Step 3.4 - VERIFY PORV is closed. (Tailpipe ~P indicator, URO Alarm G-1-7, A0517).

Step 3.5 - INITIATE Attachment 1 "Isolation of possible sources CRS of leakaqe".

OP-TM-EOP-002, Attachment 1 Ensures the following valves are closed:

0 RC-V-1 (Spray) by taking the "Auto-Manual" switch (CC) to "Manual" and, if the spray valve is open, pressing the URO closed pushbutton (CC), verifying the closed light is lit and the open light is not lit.

0 RC-V-3 (Spray Block) by pressing the closed pushbutton URO (CC), verifying the closed light is lit and the open light is not lit.

0 MU-V-3 (Letdown Block) by pressing the closed URO pushbutton (CC), verifying the closed light is lit and the open light is not lit.

0 MU-V-1A (Letdown Cooler Isolation) by pressing the URO closed pushbutton (CC), verifying the closed light is lit and the open light is not lit.

0 MU-V-1 B (Letdown Cooler Isolation) by pressing the URO closed pushbutton (CC), verifying the closed light is lit and the open light is not lit.

OP-TM-EOP-002, LOSS OF 25F SUBCOOLING MARGIN URO Step 3.8 - VERIFY all RC pumps are shutdown.

Step 3.10 - IAAT RCS > 25 °F superheat, then GO TO EOP-CRS 008.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# 51617 Page 25 of 27 Event

Description:

OTSG Tube Rupture, Loss of Subcooling Margin, MU-P-1A fails to start on ES Time I Position I Aoolicant's Actions or Behavior Step 3.11 - If primary to secondary heat transfer is excessive CRS (XHT), then GO TO EOP-003.

Step 3.12 - VERIFY cooldown rate > 40 °F/hr, or primary to CRS secondary heat transfer (PSHT) exists.

Step 3.13 - If OTSG TUBE LEAKAGE exists, then GO TO EOP-CRS 005.

EXAMINERS NOTE: The scenario can be terminated when the crew re-enters OP-TM-EOP-005 isolates the 'A' OTSG.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# addendum Page 26 of 27 Event

Description:

Isolation of the 'A' OTSG Time I Position I Aoolicant's Actions or Behavior EXAMINER NOTE: When isolation criteria has been met, the crew will perform attachment 1A of OP-TM-EOP-005 to isolate the 'A' OTSG ARO Ensure closed the following valves :

MS-V-1A - CC - Examinee presses closed pushbutton. Green light becomes bright, white test light becomes bright, and red CT-22 ARO light stays bright. When the valve is fully is closed, only the Green liqht will remain briqht.

MS-V-1 B - CC - Examinee presses closed pushbutton. Green light becomes bright, white test light becomes bright, and red CT-22 ARO light stays bright. When the valve is fully is closed, only the Green light will remain bright.

FW-V-17A - CC - Examinee places the FW-V-17A ICS station in hand, and places the toggle switch in the closed position.

CT-22 ARO The examinee will verify the valve is closed by verifying the red position indicator beside the ICS station qoes to 0.

FW-V-5A - CC - Examinee verifies that the FW-V-5A RED CT-22 ARO closed pushbutton is bright. FW-V-5A should have closed when the reactor was tripped.

FW-V-16A- CC- Examinee places the FW-V-16A ICS station in hand, and places the toggle switch in the closed position.

CT-22 ARO The examinee will verify the valve is closed by verifying the red position indicator beside the ICS station qoes to 0.

FW-V-92A - CC - Examinee presses the GREEN closed CT-22 ARO pushbutton. The CLOSED light becomes bright, the RED pushbutton becomes DIM.

EF-V-30A- CL - Examinee presses the manual button on the CT-22 ARO EF-V-30A station and pins the toggle switch in the closed position.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# addendum Page 27 of 27 Event

Description:

Isolation of the 'A' OTSG Time I Position I Annlicant's Actions or Behavior EF-V-30D - CL - Examinee presses the manual button on the CT-22 ARO EF-V-30D station and pins the toggle switch in the closed position.

MS-V-3D, E, F - CC - Examinee places the MS-V-3D, E, F ICS station to HAND and presses the toggle switch in the CT-22 ARO closed direction. Examinee verifies that the MS-V-3D, E, F lights on CC are green.

MS-V-4A - CC - Examinee places MS-V-4A on the BU CT-22 ARO LOADER by pressing the BU LOADER button. Examinee ensures that the MS-V-4A demand wheel is in the 0 position.

MS-V-13A- CC- Examinee presses the MS-V-13A pushbutton. This step may have been done previously.

CT-22 ARO Examinee verifies the GREEN light becomes bright and the RED light becomes dim.

CA-V-4A or CA-V-5A- PCR- Examinee closes CA-V-4A or CT-22 ARO CA-V-5A on PCR (Below the ES status panel), by taking the barrel switch to the close to the close position.

Appendix D Scenario Outline Form ES-D-1 Facility: Three Mile Island Scenario No.: 3 Op Test No.: TMl-2017-1 Examiners: Operators:

Initial Conditions:

• 100% power, MOL

• Generator output meter GN-OM-1 is out of service for repair. Put computer points A0099 and A0098 on data trend to monitor MVAR and MW's.

Turnover: Remain at 100% power Critical Tasks:

• Natural Circulation RCS Flow (CT-12)

• Isolate Overcooling SG(s) (CT-17)

Event No. Malf. No. Event Type* Event Description 1 ZAOWDL TSCRS RB Flood Level Instrument Fails High (TS)

Ll806 2 MS04 CCRS MSIV inadvertent closure, entry into OP-TM-PPC-L2204 CURO (ATC: Lowers power< 90%), (BOP: Opens MS-V-1 D)

CARO 3 IC18 ICRS ULD fails @ 98% in auto RURO (URO: Lowers power with SG/RX Demand to less than 98%)

4 ED09C TSCRS Loss of Vital Bus "C" CARO (ARO: RM-A-BG interlock to defeat) 5 MS19A C CRS lsolable Steam Leak in Turbine Bldg, entry into OP-TM-AOP-051.

CARO 'B' OTSG (ARO: Isolate Steam Leak) 6 TC01 I CRS Turbine Trips, Reactor fails to automatically trip RD28 IURO (URO: IMA's) 7 ED01 MCRS Loss of Offsite Power with both Emergency Diesel Generators MURO available, entry into OP-TM-AOP-020.

MARO 8 MSO?B CCRS Stuck open MSSV's, entry into OP-TM-EOP-003.

CARO (ARO: Isolate "B" OTSG)

• (N)ormal, (R)eactivity, (l}nstrument, (C)omponent, (M)ajor Scenario Set-up NRC Scenario 3 Three Mile Island NRC Scenario #3 Event #1: The lead Examiner can cue the failure of LT-806 RB Flood Level Transmitter high. PRF1-4-6 alarm will be received. The CRS will declare a 30 day LCO Tech Spec (3.5.5.2).

IAW Tech Spec 3.5.5.2:

The channels identified for the instruments specified in Table 3.5-3 shall be OPERABLE. With the number of instrumentation channels less than required, restore the inoperable channel(s) to OPERABLE in accordance with the action specified in Table 3.5-3.

TABLE 3.5-3 POST ACCIDENT MONITORING INSTRUMENTATION Instrument or Control Parameter Required Number of Minimum Number of Channels Channels Containment Water Level 2 1 Containment Flood (LT-806/807)

Action Statement: B. 1. With the number of OPERABLE accident monitoring instrumentation channels less than the Required Channels OPERABLE requirements, restore the inoperable channel(s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br />.

Event #2/3: The lead examiner will cue the Closure of MS-V-1 D. The crew will identify this by the green closed light lit, white test light lit (during travel) and the red open light not lit (after travel is complete) (CC). The crew will enter OP-TM-PPC-L2204, which will direct lowering power less than 90% and reopening MS-V1A.

At 95% power, the ULD will fail, and the power reduction will stop. The crew will take ICS to manual in accordance with OP-TM-621-471, ICS MANUAL CONTROL procedure

.and lower power with the SG/RX demand station.

When MS-V-1 D has been opened, the scenario can continue.

Event #4: The lead examiner will cue the loss of Vital Bus 'C' (VBC).

The effects and compensatory actions of a loss of VBC which are significant for plant safety or operation are described in OP-TM-AOP-017.

This procedure stabilizes the plant and performs compensatory actions for equipment failures. The CRS will determine what tech specs we are in and brief the crew.

Once the brief is complete, the scenario can continue.

Event #5: The Lead Examiner will cue the lsolable Steam Leak in the Turbine Building.

Scenario Set-up NRC Scenario 3 The operators will diagnose a Secondary Side Steam Leak based on a lowered efficiency of the Secondary Plant (Megawatts, Header Pressure, OTSG pressures, etc.)

and a call-in report from the field.

The crew will diagnose the Steam Leak and the CRS will enter OP-TM-AOP-051, Secondary Side High Energy Leak. OP-TM-AOP-051 is entered for Steam Leaks that affect large portions of the plant and therefore it is not obvious to the operator what needs to be done initially to isolate the leak.

OP-TM-AOP-051 systematically attempts to isolate the leak remotely from the Control Room while taking steps to minimize the adverse effects of a steam environment on safety related equipment. The OP-TM-AOP-051 mitigation strategy for a Steam Leak in the Turbine Building is as follows:

• Attempt to isolate the leak from the Control Room.

• Shutdown and Cooldown the plant in a controlled manner to minimize pressure surges that could make the leak worse. Shutdown may have to be done quickly or the plant may have to be tripped depending on the circumstances.

The ARO will isolate Steam Leak by closing the appropriate valve, MS-V-5B. This can be performed because the steam supplies to the Main Feedwater Pumps are as follows:

• Below 25% power, Main Steam, only, supplies the Main Feedwater Pumps.

• Between 25% and 40% power, Main Steam supplements Extraction Steam as supplies to the Main Feedwater Pumps.

• Above 40% power, Extraction Steam, only, supplies the Main Feedwater Pumps.

Once the Steam Leak has been isolated, the scenario can continue Event #6: The lead examiner will cue the turbine trip. The reactor will not automatically trip, and the CRS/URO will enter OP-TM-EOP-001, REACTOR TRIP and perform the IMA's.

After the immediate manual actions and symptom check are complete, the scenario can continue.

Event #7/8: The lead examiner will cue the Loss of Offsite Power.

The crew will diagnose a loss of offsite power by multiple Annunciators in alarm, PPC points in alarm, RCP's secured (CC), loss of half of the Control Room lighting.

The CRS will enter OP-TM-AOP-020, LOSS OF STATION POWER. Both diesel generators will start, and power the 1D and 1E 4kV busses.

Scenario Set-up NRC Scenario 3 Two stuck open main steam safety valves on the "B" OTSG will cause conditions to be met for an Excessive Primary to Secondary Heat transfer. The CRS will announce

' transition into OP-TM-EOP-003, Excessive Primary to Secondary Heat Transfer. The ARO will perform Phase 1 and 2 isolation to secure emergency feedwater from the 'B' OTSG.

Termination: The scenario can be terminated when OTSG "B" has been isolated, Seal injection has been restored, and Natural Circulation has been established.

Scenario Set-up NRC Scenario 3 B&W Unit EOP Critical Task Description Document, 47-1229003-04:

CT Establish Natural Circulation RC Flow - Whenever forced RC flow is not available, NC flow should be established. Maintaining primary to secondary heat transfer via NC eliminates the need to add RC to the RB as would occur with the back up feed and bleed HPI core cooling mode.

o If primary to secondary heat transfer has been lost, then establish and maintain appropriate SG levels in accordance with Rule 4.0.

o Reduce SG pressure using the TBVs/ADVs to establish a positive primary to secondary side JT of - 50°F.

o RCS pressure should be maintained constant or slightly increasing using MU or HPI. RCS pressure should not be increased if PTS guidance is invoked.

o Trying to establish Natural Circulation RC flow outside of the following limits should be considered grounds for failure of the critical task:

• Establish Natural Circulation prior to transitioning into OP-TM-EOP-009, HPI Cooling.

Safety Significance: Enhances the transient mitigation capability of the plant by maintaining SGs operable and eliminates the need to add RC to the RB as with HPI Cooling.

Cues:

• Low RC flow alarm

• Verbal alert by plant staff that all RCPs have tripped

• SCM monitor and associated alarms

• P-T display and associated alarms Performance Indicators:

• Operation of EFW/FW pump and valve controls

• Operation of TBV/ADV controls

• Operation of MU/HPI pump and valve controls Feedback:

• Verbal verification that natural circulation has been established

• SG pressure

• RC temperature Scenario Set-up NRC Scenario 3 CT Isolate Overcooling SGs - This is a critical task in that continued feeding of an OTSG with a steam break will continue to overcool the RCS, which could result in emptying the Pressurizer and causing a loss of subcooling margin. This would significantly change the mitigation strategy of the event.

• Critical task (CT-17) is to isolate the affected OTSG prior to emptying the, pressurizer. Alternately if HPI held pressurizer level, cooldown below 329°F with HPI on would violate TS. Either condition should be considered grounds for failing critical task.

Safety Significance: If the overcooling SG has been identified then that SG should be isolated, otherwise both SGs should be isolated. Isolating a SG means to stop all FW flow (MFW and AFW) and steam flow (e.g., close TBVs, ADVs, steam supply to FW pumps, MSIVs etc.). FW flow should be maintained to the unaffected SG and cooling stabilized using the unaffected SG.

Isolation of a SG or both SGs should always follow a logical progression of increasingly more drastic attempts to isolate the SG. For example, if the overcooling is nor severe it may be possible to close both the TBVs and ADVs as well as the auxiliary steam valves thus isolating the SG. If this does not work, then for those plants which have main steam isolation valves, the main steam isolation valve should then be closed. For severe overcooling situations, [secondary plant protection system] will likely actuate.

Inappropriate mitigative actions can cause loss of both SGs even if only one SG is faulted; such a situation would cause degradation of the transient mitigation capability of the plant.

Cues:

1. SPDS displays and associated alarms

2. P-T display and associated alarms

3. Rising RB Pressure and Temperature

4. RB Fire/Heat alarms Performance Indicators:

1. Operation of HIPl/MU pump start switches

2. Operation of associated FW pump and valve controls (affected OTSG)

3. Operation of associated steam valve (included TBVs/ADVs) controls (affected OTSG)

4. Operation of MSIV's (affected OTSG)

Feedback:

1. RC temperature and pressure

2. SG level and pressure

3. MSIV status indication

4. MFW/AFW pump and valve status indications Scenario Set-up NRC Scenario 3 Event Description Procedure Support Initial Setup 100% power, MOL TS 3.5.5.2 LT-806, RB Flood Level 1 Instrument fails high TS Table 3.5-3 OP-TM-PRF1-0406, RB FLOOD LEVEL HI OP-TM-PPC-L2207, MAIN STEAM ISOL MS-V-1 D 2 MS-V-1 D closes 1102-4, POWER OPERATIONS ULD fails to lower power in 3 OP-TM-621-471, ICS MANUAL OPERATION AUTO OP-TM-AOP-017, LOSS OF VBC 4 Loss of Vital Bus 'C' (VBC)

TS 3.1.6 and 3.5.1.9 OP-TM-AOP-051, SECONDARY SIDE HIGH lsolable Steam Leak in the ENERGY LEAK 5

Turbine Building TS 3.4.1.2.3 Turbine trip, Reactor fails to 6 OP-TM-EOP-001, REACTOR TRIP trip automatically OP-TM-AOP-020, LOSS OF OFFSITE POWER 7 Loss of Offsite power OP-TM-EOP-010, EMERGENCY PROCEDURE RULES, GUIDES, AND GRAPHS Stuck open Main Steam OP-TM-EOP-003, EXCESSIVE PRIMARY TO 8 Safely Valves, Excessive SECONDARY HEAT TRANSFER Heat Transfer Scenario Set-up NRC Scenario 3 ACTION COMMENTS I INSTRUCTIONS DESCRIPTION IC-243 100% power, ICS in Auto Equilibrium Xenon 1/0 Override 02A3M27- Value: 100 LT-806 RB Flood Level ZAOWDLL1806 When: Event #1 Transmitter Fails High 1/0 Override PRF1-4-6 Value: ON PRF1-4-6 Alarms, RB Flood When: Event #1 Level High Event Trigger #1 Value: Sets PPC point A0449 to 90 Command: SET PPA0449 V = 90.0 inches to match Event #1 Monitor Point Value: SET PPA0449 0 =True Enables PPC Point A0449 to When: Immediately be set by event trigger #1 Malfunction MSR04 Value: 0.000 MS-V-1 D closes When: Event#2 Event #3 Trigger Value: ratpw < 98 ULD fails at -98%

Command: IMF IC18 84 Malfunction ED09C Value: Insert Loss of Vital Bus 'C' When: Event #4 Malfunction MS19B Value: 3 ramp of 2 mins Steam leak in the turbine When: Event#5 building Malfunction TC01 Value: Insert Turbine Trip When: Event#6 Malfunction RD28 Value: Insert Reactor auto trip block When: Immediately Malfunction ED01 Value: On Loss of Offsite Power When: Event#?

Malfunction MS05A Value: 100 MSSV on 'B' OTSG fails When: Event #7 100% open Malfunction MS05B Value: 100 MSSV on 'B' OTSG fails When: Event#? 100% open TRIGGER 10 Value: ORF MSR04 Deletes MSIV Inadvertent When: RATPW<92 Closure Alarm PRF1-3-3 Value: ON HSPS door opening when When: Event #12 swapping instruments REMOTE ICR32 Value: Def Clears SASS mismatch When: Event #13 w/ 30 sec TD alarms in step 3.8 REMOTE HSR09 Value: 1046 Sets HSPS channel to 1046 When: Event #14 w/ 10 sec TD REMOTE HSR10 Value: 1044 Sets HSPS channel to 1044 When: Event #14 w/ 20 sec TD REMOTE HSR11 Value: 1054 Sets HSPS channel to 1054 When: Event #14 w/ 30 sec TD Scenario Set-up NRC Scenario 3 REMOTE HSR12 Value: 1052 Sets HSPS channel to 1052 When: Event #14 w/ 40 sec TD REMOTE CHR04 Value: ON Starts AH-E-26 When: Event #15 Required procedures to have on hand:

1. 1104-15A, AUX AND FUEL HANDLING BUILDING SUPPLY AND EXHAUST SYSTEM, SECTION 4.3 Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event#

Page 10 of 31 Event

Description:

LT-806 RB Flood Level Instrument Fails High Time I Position I Aoolicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE Event #1.

Indications Available: PRF1-4-6 Alarm and Containment Flood Level Indicator CRS Direct entry into OP-TM-PRF1-0406, RB Flood Level Hi ARO should diagnose the failure of the RB Flood Level ARO instrument LT-806 based on other RB level instrumentation and RCS conditions.

Reviews TS 3.5.5.2 and TS Table 3.5-3 for RB Flood Level CRS Instrument requirements.

EXAMINER NOTE:

TS 3.5.5.2 The channels identified for the instruments specified in Table 3.5-3 shall be OPERABLE. With the number of instrumentation channels less than required, restore the inoperable channel(s) to OPERABLE in accordance with the action specified in Table 3.5-3.

TABLE 3.5-3 POST ACCIDENT MONITORING INSTRUMENTATION Required Minimum Actio Instrument or Control Parameter Number of Number of n

Channels Channels Containment Water Level 2 1 B Containment Flood (LT-806/807)

TS Table 3.5-3 ACTIONS - B.1: With the number of OPERABLE accident monitoring instrumentation channels less than the Required Channels OPERABLE requirements, restore the inoperable channel(s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br />.

EXAMINER NOTE: Once the TS call is made, Go To Event 2.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event# 2/3 Page 11of31 Event

Description:

MS-V-1 D closure, ULD fails to lower power Time I Position I Aoolicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE Event #2.

Indications Available: PPC-L2207 in alarm, MS-V-1 D indicates closed on CC, "B" OTSG Pressure/Level rise.

BOOTH CUE: If contacted as maintenance, inform the crew that "I see no damage to MS-V-1 D and the valve may be reopened when Ops is ready to open it" Direct entry into OP-TM-PPC-L2207, MAIN STEAM ISOL CRS MS-V1D.

EXAMINER NOTE: Step 4.1 is N/A.

PROCEDURE NOTE: The following steps are designed to prevent an overpressure condition that could challenge the RC-RV-2 (PORV) and to prevent operation in an unbalanced steam flow condition.

OP-TM-PPC-L2207, MAIN STEAM ISOL MS-V1D Step 4.2: VALIDATE actual valve movement by rising RCS CRS pressure and temperature or local valve position.

Step 4.3: REDUCE reactor power to less than 90% power IAW CRS 1102-4, "Power Operation".

EXAMINER NOTE: The CRS may perform either section 3.2 or 3.3 of 1102-4.

The steps are similar and therefore, only section 3.3 is scripted.

EXAMINER CUE: If directed as Shift Manager to perform or initiate Enclosure 2A, acknowledge the direction.

1102-4, POWER OPERATION Step 3.3.2.A.1: PERFORM Enclosure 2A (for an emergency CRS (forced) power reduction INITIATE Enclosure 2A).

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event# 2/3 Page 12 of 31 Event

Description:

MS-V-1 D closure, ULD fails to lower power Time I Position I Aoolicant's Actions or Behavior EXAMINER CUE: Acknowledge as the personnel listed in the next step, or acknowledge as Shift Manager to notify the personnel listed in the next step. Also acknowledge Logging the notifications.

Step 3.3.2.A.2: If power change is greater than 10 MWe, then perform the following:

a) NOTIFY the following:

- Power Team CRS

- TSO

- NDO b) LOG notifications to Power Team, TSO, and NDO in Control Room Log.

Step 3.3.2.A.3.a: MAINTAIN Generator Reactive Load IAW ARO OP-TM-301-472.

Step 3.3.2.A.3.b: If SG/REACTOR DEMAND is in AUTO, then REDUCE reactor power as follows:

URO

1. ENSURE ULD is in HAND by observing White HAND light lit, red AUTO light not lit (CC).

EXAMINER NOTE: The Load Rate of Change adjustment knob does not read in

"%". If the CRS directs a 1%/Min load rate of change, the URO will dial the adjustment knob to 10. If the CRS directs a 3%/Min load rate of change, the URO will dial the adjustment knob to 30.

Step 3.3.2.A.3.b: If SG/REACTOR DEMAND is in AUTO, then REDUCE reactor power as follows:

2. SET ULD LOAD RATE OF CHANGE to~ 1 %/minute for URO PLANNED reductions or at a rate determined by CRS for Forced power reductions by changing the Load Rate of Change adjustment knob in the clockwise direction until the correspondinQ value is achieved.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event# 2/3 Page 13 of 31 Event

Description:

MS-V-1 D closure, ULD fails to lower power Time I Position I Aoolicant's Actions or Behavior EXAMINER NOTE: The URO will decide MWe corresponding to the power level directed by the CRS by looking at the placard next to the ULD.

Step 3.3.2.A.3.b: If SG/REACTOR DEMAND is in AUTO, then REDUCE reactor power as follows:

3. SET ULD Target Load Demand to desired setpoint by URO placing the ULD Control Station toggle switch in the down direction until the target MWe is targeted by the indicator.

BOOTH NOTE: Ensure Event #3 is inserted at approximately 98% power.

At - 95% power, the ULD will stop responding. This will be URO identified by the generated MWe output on the PPC not lowering any longer.

Directs ICS to be put in manual in accordance with OP-TM-621-CRS 471, ICS MANUAL CONTROL to the SG/RX demand.

OP-TM-621-471, ICS MANUAL CONTROL URO Step 4.2.1 - Places the SG/Reactor Demand station in HAND URO Step 4.2.2 - Ensures control rod position does not change.

ARO Step 4.2.3 - Verifies alarm H-2-1 "ICS in Track" in 1102-4, POWER OPERATIONS Step 3.3.2.A.3.c - URO uses the SG/Reactor demand toggle URO switch to lower power.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event# 2/3 Page 14 of 31 Event

Description:

MS-V-1 D closure, ULD fails to lower power Time I Position I Aoolicant's Actions or Behavior BOOTH NOTE: Ensure Event #10 is automatically entered at 92% power to remove the MSIV fault. If not, then remove Remote MSR04 prior to the crew attempting to open the MSIV.

EXAMINER NOTE: Once Reactor Power is below 90%, the CRS will continue in OP-TM-PPC-L2207, MAIN STEAM ISOL MS-V1D.

OP-TM-PPC-L2207, MAIN STEAM ISOL MS-V1 D Step 4.4 RE-OPEN MSIV as soon as possible by pressing the red open pushbutton and observing all three lights lit during ARO travel, and only the red open light lit (green and white lights not lit) at the end of valve travel.

EXAMINER NOTE: Once MS-V-1 D is open, go to Event #4.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event# 4 Page 15 of 31 Event

Description:

Loss of Vital Bus 'C' (VBC)

Time I Position I Applicant's Actions or Behavior BOOTH CUE: When directed by the Lead Examiner INITIATE Event #4.

INDICATIONS AVAILABLE: Multiple Main Annunciator Panel Alarms illuminated, "C" RPS Cabinet deenergized, 1 of 2 Control Rod Positon Indication Panels deenergized, 1 Row of HSPS lights lit.

BOOTH CUE: If dispatched to investigate, report that the 'C' inverter AC and DC input supply breakers are open for not apparent cause.

Crew Diagnosis a loss of Vital Bus "C".

CRS Direct entry into OP-TM-AOP-017, Loss of VBC.

OP-TM-AOP-017, LOSS OF VBC Step 3.1 - Announces entry into OP-TM-AOP-017, "Loss of ARO VBC," over the plant paqe and radio.

Step 3.2 - Verifies PPC alarm L3461 "CRD AC Power Fault (B)"

CRS is clear EXAMINER NOTE: If asked, notify the CRS that there are no fuel moves in progess in the spent fuel pool.

CRS Step 3.3 - N/A no fuel move is in progress.

Step 3.4- Selects group 5-7 on CRD-FPM-B on the right side ARO of the Pl panel.

PROCEDURE NOTE: Loss of power to RM-A-8 trips AH-E-10, AH-E-11, and WDG-V-47.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event# 4 Page 16 of 31 Event

Description:

Loss of Vital Bus 'C' (VBC)

Time I Position I Applicant's Actions or Behavior Step 3.5 - Places RM-A-8G interlock switch in DEFEAT ARO position.

Step 3.6: Initiates 1104-15A to restore AUX and FHB ARO ventilation.

EXAMINER NOTE: The CRS/ARO may prioritize initiate 1104-15A to restore ventilation. If so, the highlights are below.

1104-15A, AUX AND FUEL HANDLING BUILDING SUPPLY AND EXHAUST SYSTEM, Section 4.3 Step 4.3.2.1 - Verify open I open AH-D-120, 121, 122, FH ARO BLDG Isolation Dampers ARO Step 4.3.2.2 - Starts AH-E-14 A/C or AH-E-14 BID ARO Step 4.3.2.3.A- Start AH-E-10 ARO Step 4.3.2.3.B- Start AH-E-11 BOOTH CUE: When directed to operate AH-E-26, use remote function on Event #15, CHR04 to ON and wait - 2 minutes and report status of AH-E-26.

AH-E-21, 90 & 91 are not modeled. When directed to operate these fans; wait 1 minutes and report the following status: AH-E-90 and 91 are running Step 4.3.2.34 - Restore control tower first floor ventilation by:

1. Press AH-D-28/617 Reset PB" and Start AH-E-20A or AH-E-20B ARO 2. Verify open AH-D-28/617 on ESAS indication on PCR or the white light on H&V panel

3. Dispatches an operator to start AH-E-21 (Not modeled)

4. Dispatches an operator to secure AH-E-90 and 91

5. Dispatches an operator to start AH-E-26 Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 3 Event# 4 Page 17 of 31 Event

Description:

Loss of Vital Bus 'C' (VBC)

Time I Position I Aoolicant's Actions or Behavior OP-TM-AOP-017, Loss of VBC ARO Step 3. 7 - Reviews Control room annunciators in alarm.

BOOTH CUE: When dispatched to perform OP-TM-621-452, "Defeating SASS Mismatch ALARM inputs", insert Event #13 and report back as complete after - 1 minute.

BOOTH CUE: To acknowledge the SASS alarm locally, use ICR15.

EXAMINER CUE: Swapping HSPS instruments is not necessary to move on in the scenario. Once the T.S. call is made, the scenario can continue.

Step 3.8 - Dispatches an operator to perform "OP-TM-621-452 ARO to defeat the SASS mismatch alarms for OTSG A & B SU LVL" BOOTH CUE: When directed to swap HSPS level inputs insert Event #12.

This will simulator opening the HSPS doors (PRF1-3-3) and swap the instruments. When all of the instruments are swapped, change event #12 to OFF, to close the HSPS door. Notify the control room when completed.

Step 3.9 - Dispatches an operator to swap to operable HSPS ARO instruments for EF-V-30A and EF-V-30C control.

EXAMINER NOTE: The CRS will initiate the following Tech Specs:

• 3.1.6.8 - When the reactor is critical above 2 percent, two reactor coolant leak detection systems of different operating principles shall be in operation for the Reactor Building with one of the two systems sensitive to radioactivity. The systems sensitive to radioactivity may be out-of-service for not more than 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> provided a sample is taken of the Reactor Building atmosphere every 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> and analyzed for radioactivity and two other means are available to detect leakage.

• Table 3.5-1, D - Channel Ill level signals - 2 min operable channels with 1 min degree of redundancy. Only 1 will be operable. Restore the channel within 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> or place the unit in HOT SHUTDOWN within the next 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br />.

• RM-A-8 and 15 timeclocks are not entered because RM-A-4, 5, and 6 are still operable.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event# 4 Page 18 of 31 Event

Description:

Loss of Vital Bus 'C' (VBC)

Time I Position I Applicant's Actions or Behavior CRS Step 3.10 - Initiates TS timeclock 3.1.6 and 3.5.1.9 Step 3.11 - Notifies Rad Pro to obtain RB air sample within 8 CRS hours.

EVALUATOR NOTE: When the Tech Specs are declared, go to Event #5.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event# 5 Page 19 of 31 Event

Description:

lsolable steam leak in the Turbine Building Time I Position I Aoolicant's Actions or Behavior BOOTH CUE: When directed by the lead examiner, insert Event #5 INDICATIONS AVAILABLE: Lowering Generated MWe, Lowering Tave, Reactor Power rising BOOTH CUE: Report, as Auxiliary Operator, "There is a large steam .leak on the North Side of the Turbine Building. Specific location is unknown" Crew Diagnoses the steam leak Announces entry into OP-TM-AOP-051, Secondary Side High CRS Enerav Leak.

OP-TM-AOP-051, SECONDARY SIDE HIGH ENERGY LEAK Step 3.1: ANNOUNCE entry into OP-TM-AOP-051, "Secondary ARO Side High Energy Leak" and to evacuate turbine building over the plant paQe and radio.

URO Step 3.2: MAINTAIN reactor power< 100%.

EXAMINER NOTE: Steps 3.3 through 3.6 are IAAT statements that are expected to remain N/A for the duration of the scenario.

BOOTH CUE: As Shift Manager, acknowledge the request to evaluate EAL's.

CRS Step 3.7: REQUEST SM to evaluate EALs.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRG Scenario # 3 Event# 5 Page 20 of 31 Event

Description:

lsolable steam leak in the Turbine Building Time I Position I Aoolicant's Actions or Behavior EXAMINER NOTE: Steps 3.8 through 3.9 are N/A.

Step 3.10: If leak is in Turbine Building, then GO TO Section CRS 6.0.

OP-TM-AOP-051, Section 6.0, TURBINE BUILDING Step 6.1: CONSIDER evacuating the following:

CRS - Operations Office Building using the back stairwell.

- Telephone Equipment Room in the Service BuildinQ.

EXAMINER NOTE: There is a procedure note that states that the crew can perform isolation of A and B side of the Turbine Bldg in any order. If the crew performs the "B" side first (Step 6.3), the steam leak will be isolated and step 6.2 will not be performed.

BOOTH CUE: When requested by the Control Room to report the status of the steam leak following closure of MS-V-5A, report "The steam leak IS NOT isolated.

When requested by the Control Room to close MS-V-5B, delete malfunction MS19B and report the status of the steam leak following closure of MS-V-5B, report "The steam leak IS isolated".

Step 6.2: If power >40% or FW-P-1 Bis tripped, then determine if leak is downstream of MS-V-5A by performing the following:

ARO - CLOSE MS-V-5A

- If steam leak is isolated, the GO TO Section 7.0 (The steam leak is NOT isolated)

- OPEN MS-V-5A Step 6.3: If power >40% or FW-P-1 Bis tripped, then determine if leak is downstream of MS-V-5B by performing the following:

ARO

- CLOSE MS-V-5B

- If steam leak is isolated, the GO TO Section 7.0 (The

• Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 3 Event# 5 Page 21of31 Event

Description:

lsolable steam leak in the Turbine Building Time I Position I Aoolicant's Actions or Behavior steam leak IS isolated)

EXAMINER NOTE: Once the leak is isolated and plant is stable, then GO TO Event #6.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event# 6 Page 22 of 31 Event

Description:

Turbine Trips, Reactor does not trip automatically, Entry into OP-TM-EOP-001, Reactor Trip Time I Position I Aoolicant's Actions or Behavior BOOTH CUE: When directed by the lead examiner, insert EVENT #6 INDICATIONS AVAILABLE: Turbine Trip alarm, generated megawatts go to zero, RCS pressure rises.

EXAMINER NOTE: The reactor will not automatically trip, the URO will have to trip the reactor from the console during the OP-TM-EOP-001 Immediate actions.

EXAMINER NOTE: Due to loss of Vital Bus 'C' the normal stop valve indication on console left is not available. The crew may use other redundant indications to verify the stop valves are closed.

Crew Recognizes the turbine trip, and that the reactor did not trip.

URO Performs OP-TM-EOP-001 Reactor Trip IMA's OP-TM-EOP-001, REACTOR TRIP Step 2.1: (IMA): Presses Both Reactor Trip and DSS URO pushbuttons (CC).

Step 2.2: (IMA): Verifies that the reactor is shutdown by one of the following:

URO

• Power Range nuclear instrumentation indicates less than 5% (CC)

• All control rods are inserted (PC)

• Source Range count rate is continuously lowering (CC)

URO Step 2.3: (IMA): Presses the Turbine Trip pushbutton (CL).

Step 2.4: (IMA): Verifies the Turbine Stop valves are closed by URO observing the indication on CL.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 3 Event# 6 Page 23 of 31 Event

Description:

Turbine Trips, Reactor does not trip automatically, Entry into OP-TM-EOP-001, Reactor Trip Time I Position I Aoolicant's Actions or Behavior OP-TM-EOP-001 Symptom check ARO Verifies power to 1D and 1E 4kV bus ARO Verifies SCM > 25F ARO Verifies no symptoms of XHT exist.

ARO Verifies no symptoms of LOHT exist.

ARO Verifies no symptoms of an OTSG tube leak exist.

EXAMINER'S NOTE: Once the Reactor Trip IMA's are complete, the ARO will perform a symptom check. At the end of the symptom check, go to the Event #7.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 718 Page 24 of 31 Event

Description:

Loss of Offsite Power, Stuck open MSSV's Time I Position I Applicant's Actions or Behavior BOOTH OPERATOR: When directed by the Lead Examiner INITIATE Event 7.

INDICATIONS AVAILABLE: Loss of all Control Room lighting, RCP's secured, loss of power to non-vital powered equipment.

EXAMINER NOTE: After the loss of offsite power, the crew will perform a symptom check, at which time they will identify an excessive heat transfer from the 'B' OTSG. This portion will be written that the URO restores SI, and the ARO isolates 'B' OTSG. After both are accomplished, the scenario can be terminated.

BOOTH CUE: Two minutes after the reactor trip announcement, inform the control room that 2 MSSV's are stuck open. The symptom check regarding the entry into XHT are presented below. The crew may enter XHT by using approaching criteria or wait until all of the conditions exist.

SYMPTOM CHECK The crew will be continuously performing a symptom check.

After the loss of power, 2 MSSV's will stay open. The crew must enter OP-TM-EOP-003 based on approaching or meeting the following criteria:

Crew

• RCS average temperature below 540F

• Uncontrolled lowering of RCS temperature

• Tsat for OTSG pressure is less than Tcold on affected OTSG(s)

This may be entered right after the event or shortly thereafter.

Crew Diagnoses Loss of Offsite Power.

CRS Announces entry into OP-TM-AOP-020, Loss of Station Power.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 718 Page 25 of 31 Event

Description:

Loss of Offsite Power, Stuck open MSSV's Time I Position I Aoolicant's Actions or Behavior OP-TM-AOP-020, LOSS OF STATION POWER ARO Step 3.1: Initiates Emergency Feedwater Step 3.2: Initiates OP-TM-861-901, "EG-Y-1A Emergency ARO Operations" and OP-TM-861-902, "EG-Y-1 B Emergency Operations".

Step 3.3: Verifies 1D 4160V and 1E 4160V busses are CRS eneraized CRS Steps 3.4: Verifies IC-P-1 B is running.

Step 3.5: Announces entry into AOP-020, breaking vacuum, ARO and venting generator hydrogen over the RED plant page and radio.

Step 3.6: SI is not > 22 gpm, RNO: Initiates OP-TM-AOP-041 URO for loss of Seal Injection.

Step 3.7 Initiate OP-TM-EOP-010 Guide 10, "Natural ARO Circulation".

OP-TM-EOP-010 Guide 10, "Natural Circulation" IAAT all RCPs are off, then A If all of the following conditions exist, then adequate natural circulation is present:

- RCS Thot minus Tcold stabilizes at less than 50 °F.

CT-12 ALL - THOT < 600 °F.

- lncore temperature stabilizes and tracks Thot.

- Cold leg temperatures approach saturation temperature for secondary side pressure.

- OTSG heat removal is indicated by feeding or steaming with stable OTSG pressure.

- SCM > 25°F.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 718 Page 26 of 31 Event

Description:

Loss of Offsite Power, Stuck open MSSV's Time I Position I Applicant's Actions or Behavior OP-TM-AOP-041, LOSS OF SEAL INJECTION (IF THERE IS AN ES ACTATION, THIS SECTION WILL NOT BE PERFORMED)

EXAMINER NOTE: Steps 3.1 and 3.2 are N/A for this scenario Step 3.3: Places MU-V-32 in HAND by pressing the White URO HAND pushbutton and verifying the White HAND light lit red AUTO light not lit.

CRS Step 3.4: 1D and 1E 4160V busses are both energized.

Step 3.5: Determines that a Makeup Pump is not running and IAW the RNO, performs the following:

1. Places MU-V-17 in HAND by pressing the White HAND URO pushbutton and verifying the White HAND light lit red AUTO light not lit (CC).

2. Dials MU-V-17 to full closed (CC).

CRS Step 3.5, RNO 4: Goes to Section 4.0.

OP-TM-AOP-041, LOSS OF SEAL INJECTION, SECTION 4.0 EXAMINERS NOTE: Step 4.0 is N/A for this scenario URO Step 4.1: Verifies MU-P-1A is ES selected.

URO Step 4.2: Verifies that MU-V-36 and 37 are open.

URO Step 4.3: Starts DR-P-1 A and DC-P-1 A URO Step 4.4: Starts MU-P-1A.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 718 Page 27 of 31 Event

Description:

Loss of Offsite Power, Stuck open MSSV's Time I Position I Aoolicant's Actions or Behavior URO Step 4.5: MU-V-77A & Bare Open, go to step 3.5 EXAMINER NOTE: The stuck open MSSV's on the "B" OTSG will cause conditions to be met for an Excessive Primary to Secondary Heat Transfer condition.

Diagnoses Excessive Heat Transfer and enters OP-TM-EOP-Crew 003, Excessive Primary To Secondary Heat Transfer.

OP-TM-EOP-003, EXCESSIVE PRIMARY TO SECONDARY HEAT TRANSFER ARO Step 3.1: Perform Rule 3, XHT OP-TM-EOP-010, RULE 3 EXCESSIVE HEAT TRANSFER ARO Step 1: Verifies OTSG level <97.5%.

Step 2: Verifies that primary to secondary heat transfer is ARO excessive.

Step 3: Performs Phase 1 isolation of "B" OSTG by:

CT-17 ARO - Closing MS-V-1C by pushing the Close pushbutton and observing the Close light lit and the Open and Test lights not lit (CC).

Step 3: Performs Phase 1 isolation of "B" OSTG by:

CT-17 ARO - Closing MS-V-1 D by pushing the Close pushbutton and observing the Close light lit and the Open and Test lights not lit (CC).

Step 3: Performs Phase 1 isolation of "B" OSTG by:

CT-17 ARO - Closing FW-V-178 by pushing the Close pushbutton and observing the Close light lit and the Open not lit (CC).

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 718 Page 28 of 31 Event

Description:

Loss of Offsite Power, Stuck open MSSV's Time I Position I Applicant's Actions or Behavior Step 3: Performs Phase 1 isolation of "B" OSTG by:

CT-17 ARO - Closing FW-V-16B by pushing the Close pushbutton and observing the Close light lit and the Open not lit (CC).

Step 3: Performs Phase 1 isolation of "B" OSTG by:

CT-17 ARO - Closing FW-V-5B by pushing the Close pushbutton and observing the Close light lit and the Open not lit (CC).

Step 3: Performs Phase 1 isolation of "B" OSTG by:

CT-17 ARO - Closing FW-V-92B by pushing the Close pushbutton and observing the Close light lit and the Open not lit (CC).

Step 3: Performs Phase 1 isolation of "B" OSTG by:

CT-17 ARO - Verifying MS-V-3A, MS-V-3B, and MS-V-C are closed by verifying green indicating light is present on CC.

Step 3: Performs Phase 1 isolation of "B" OSTG by:

CT-17 ARO

- Closes MS-V-4B by directing ensuring the indicating light on CC is green.

Step 4: Verifies the steam leak is not in the RB or Intermediate ARO Building.

ARO Step 5: Throttles EFW IAW Rule 4, "Feedwater Control".

Step 6: Verifies that OTSG level and pressure are NOT ARO stabilized, RNO: Performs Phase 2 isolation of the 'B' OTSG Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 7/8 Page 29 of 31 Event

Description:

Loss of Offsite Power, Stuck open MSSV's Time I Position I Applicant's Actions or Behavior Step 6: Performs Phase 2 isolation of the "8" OTSG by:

CT-17 ARO - Closes EF-V-308 by taking the EFW controller to manual and pinning the toggle switch to the left (CC)

Step 6: Performs Phase 2 isolation of the "8" OTSG by:

CT-17 ARO - Closes EF-V-30C by taking the EFW controller to manual and pinning the toggle switch to the left (CC)

Step 6: Performs Phase 2 isolation of the "8" OTSG by:

CT-17 ARO

- Closes MS-V-28 pressing the green closed pushbutton on console center.

OP-TM-EOP-010, RULE 4, FEEDWATER CONTROL Steps 1-3: Verifies two or more EFW pumps are running, SCM ARO is greater than 25°F, and that the "A" OTSG is not dry.

Step 4: Verifies that there is not a RCP running and that the "A" ARO OTSG level is at 50% or approaching 50%

EXAMINER NOTE: Scenario can be terminated when OTSG "B" has been isolated, and Natural Circulation has been established. If ES has actuated, the crew should terminate HPI prior to scenario termination.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# Attachment Page 30 of 31 Event

Description:

Terminate HPI steps Time I Position I Aoolicant's Actions or Behavior If the crew isolates the "B" OTSG prior to an ES actuation, this section will not be performed. These steps are EXAMINER NOTE:

attachment 7 .3 of OP-TM-211-901, and are found on the back of Rule 2 on the console.

Step 1 : Clears ESAS signals by pressing the 1600# BYPASS URO buttons for each train of ES that actuated.

Step 2 : N/A because only 2 MU pumps will be running due to URO the loss of offsite power.

Step 3: Throttling is permitted IAW Rule 2 based on SCM URO

>25F and HPI cooling not needed.

Step 4: Examinee will open MU-V-36 and MU-V-37 by pressing the RED open pushbuttons on CC. The GREEN URO closed lights will become dim, the RED lights will become bright.

URO Step 5: Emergency boration may or may not be required.

Step 6a: Examinee shutdown MU-P-1C by taking the pistol URO grip (CR) to the trip position. The RED light will become dim.

The GREEN light will become bright.

Step 6a: Examinee shutdown MU-P-1A by taking the pistol URO grip (CC) to the trip position. The RED light will become dim.

The GREEN light will become bright.

URO Step 6b: Examinee verifies MU-V-36 and 37 are open.

Step 6c: Examinee presses the MU-V-16A&B GREEN (CC) closed pushbuttons. The WHITE stop light and the GREEN URO closed light become bright. Only the GREEN closed light will remain bright when the valve is fully closed.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# Attachment Page 31of31 Event

Description:

Terminate HPI steps Time I Position I Aoolicant's Actions or Behavior Step 6d: Examinee presses the MU-V-16C&D GREEN (CR) closed pushbuttons. The WHITE stop light and the GREEN URO closed light become bright. Only the GREEN closed light will remain bright when the valve is fully closed.

HPI is terminated with the Makeup Pumps that started on EXAMINER NOTE: ES and the MU-V-16's are closed with the recirculation path (MU-V-36 and 37) is established.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Task No.: OF010009 Task

Title:

Given a set of conditions, determine JPM No.: ILT 16-01 NRC JPM the Emergency Action Level (EAL) SA4 and make a Protective Action Recommendation (PAR) IAW the facility Emergency Plan.

KIA

Reference:

2.4.44 (4.4) Modified Bank JPM To be conducted one on one.

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.

ILT 16-01 NRC JPM SA4 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initial Conditions:

• T= 0 minutes:

• Plant is at 100% Power.

• Weather: Breezy. Temp: 60°F. Wind: from 291° at 8 mph.

• AH-E-1 C is out of service.

• A loss of the '8' bus occurs and EG-Y-1 B fails to power on the 1E 4160V bus

• T= 10 minutes:

• Seismic motion is felt, PRF-1-3 Operating Basis Earthquake alarm is in

• RCS pressure starts dropping, the reactor operator trips the reactor and the crew performs the Immediate Manual Actions of OP-TM-EOP-001.

• UNISOLABLE RCS leakage exists at 500 gpm.

• T= 12 minutes:

• Reactor Building pressure peaks at 31 psig, then drops rapidly to O psig

• RM-G-23 reads 1.96 E+03 R/hr

• The Maintenance Supervisor has informed you that, EG-Y-1B is inoperable and will take 10 hours0.417 days <br />0.0595 weeks <br />0.0137 months <br /> to repair.

Task Standard: Correctly identifies EAL and PAR Required Materials: Perform in a location with:

o EAL Matrix o Shift Emergency Director Book General

References:

• EP-AA-111, EMERGENCY CLASSIFICATION AND PROTECTIVE ACTION RECOMMENDATIONS, Revision 19

• EP-AA-111-F-09, TMI PLANT BASED PAR FLOWCHART, Revision F

• EP-AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST, Revision W

• EP-AA-112-F-09, EMERGENCY PUBLIC ADDRESS ANNOUNCEMENTS, Revision E

• EP-MA-114-100-F-01, STATE/LOCAL EVENT NOTIFICATION FORM, Revision P

• EP-AA-1009 Addendum 3 EXELON NUCLEAR EMERGENCY ACTION LEVELS FOR THREE MILE ISLAND (TMI) STATION, Revision 2 ILT 16-01 NRC JPM SA4 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet

• EP-AA-112-100-F-06 ERO NOTIFICATION OR AUGMENTATION Revision V

• EP-AA-114-F-01 PWR RELEASE IN PROGRESS DETERMINATION GUIDANCE, Revision E

• EP-MA-114-100, MID-ATLANTIC STATE/LOCAL NOTIFICATIONS, Revision 23 Handouts:

• EP-AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST.

• Emergency Director Binder Initiating Cue:

• You are the Shift Manager and have the responsibilities of the Shift Emergency Director from the Control Room. I will act as your communicator. Declare the appropriate EAL and respond in accordance with the EP-AA-112-1 OO-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST.

Ensure all communications are marked as a DRILL.

Time Critical Task: Yes Validation Time: 23 minutes SIMULATOR SETUP N/A ILT 16-01 NRC JPM SA4 NU REG 1021, Revision 10

Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check)

EVALUATOR CUE: The Time Critical Start Time is when the Cue is acknowledged.

1. 1 Time Critical Start Time: ------

Performance Step: 1 Compares conditions to the EAL Table.

,/ Standard: Examines:

• Determines UNISOLABLE RCS leakage is present at 500 GPM and/or RM-G-22 I Rm-G-23 Readings.

• Reactor Building pressure peaks at 31 psig, then drops rapidly to 0 psig

• RM-G-23 reads 1.96 E+03 R/hr The examines should declare FG1 Comment:

EVALUATOR NOTE: The Examinee may announce his E-Plan Declaration to the Control Room, prior to implementing EP-AA-112-1 OO-F-01.

This would be the STOP Time #1.

EP-AA-112-1 OO-F-01 Performance Step: 2 Locate and Implement EP-AA-112-100-F-01 for GE.

Standard:

• Examines locates EP-AA-112-1 OO-F-01.

• Examines determines that Section 1.4 is to be implemented for General Emergency Initial Actions.

Comment:

ILT 16-01 NRC JPM SA4 NU REG 1021, Revision 10

Appendix C Page 5 of 12 _ Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR NOTE: The #1 Time Critical Stop Time is when the General Emergency is declared.

1. 1 Time Critical Stop Time: _ _ _ __

-~

1. 2 Time Critical Start Time: - - - - -

(This is the same time as #1 Stop Time)

EP-AA-112-100-F-01, Step 1.4.A Performance Step: 3 Announce the event classification, possible escalation paths, and declaration time to the Control Room staff.

-! Standard: Examinee announces FG1 based on RCS leakage> 150 gpm, reactor building pressure rapidly dropping, and RM-G-23 reading greater than 1.96 E+03 R/hr Comment:

EVALUATOR NOTE: Time Critical #1 must be equal to or less than 15 minutes.

Time Critical #1 = (Time of declaration)

(#1 Time start)

= - - - - mins ILT 16-01 NRC JPM SA4 NUREG 1021, Revision 10

Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-100-F-01, Step 1.4.B Performance Step: 4 Record the EAL, threshold(s) (as applicable) and declaration time.

Standard: Examinee records EAL FG1 on EP-AA-112-1 OO-F01.

Examinee records the time of declaration on EP-AA-112-1 OO-F01.

Comment:

EVALUATOR NOTE: Step 1.4C and 1.40 are N/A.

EVALUATOR CUE: Repeat Back any direction given to you with regards to EP-AA-112-F-09. {Tab#1)

EP-AA-112-100-F-01, Step 1.4.E Performance Step: 5 SELECT the Emergency Public Address Announcements from the form and DIRECT performance of the public address announcement within 15 minutes of event classification.

"./ Standard: Examinee fills out EP-AA-112-F-09 (found at tab 1), section 4.2.A, and hands to communicator (NRC examiner) to make the announcement.

Comment:

Description:

Loss of Fission Product Barriers I Words to that effect.

ILT 16-01 NRC JPM SA4 NU REG 1021, Revision 10

Appendix C Page 7 of 12 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR CUE: Repeat Back any direction given to you with regards to EP-AA-112-100-F-06. (Tab #2)

EP-AA-112-100-F-01, Step 1.4.F Performance Step: 6 If the ERO has not been activated, then DIRECT activation of the ERO Notification using Scenario 1, "Actual Event Respond to Facility," or Scenario 3, "Actual Event Alternate Reporting Location," as appropriate, per EP-AA-112-1 OO-F-06. (Tab #2)

Standard: Examinee hands out EP-AA-112-1 OO-F-06 and directs activation of the ERO notification using Scenario 1.

Comment:

ILT 16-01 NRC JPM SA4 NUREG 1021, Revision 10

Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR CUE: If requested to provide DAPAR information, then respond "Offsite dose projections are < 1 REM TEDE and < SREM COE thyroid".

EP-AA-112-100-F-01, Step 1.4.G Performance Step: 7 Determine the PAR per the Emergency Classification and Protective Action Recommendations procedure.

• Emergency Classification and PAR Procedure: EP-AA-111 (Tab 6)

• Plant Based PAR Flowchart: EP-AA-111-F-09 (Tab 7)

Examinee follows the flowchart of EP-AA-111-F-09, Page 1, as follows:

• Initial PAR after GE declared - Yes

• Any Loss of Containment? - Yes

• 1. Loss of Primary Containment: Yes AND EITHER:

2. Containment Rad Monitors ~4.40E+-3 R/Hr? NO OR EAL RG 1 been met? NO

• Is there a Hostile Action event in Progress?- No

• Is this PAR from the Control Room?- Yes

..J Standard: Examinee determines the following actions are required:

• Evacuate 2-mile radius, AND

• Evacuate 2-5 miles in the following downwind sectors per Table 2:

• NE I ENE I E I ESE I SE I SSE I S Comment:

ILT 16-01 NRC JPM SA4 NU REG 1021, Revision 10

Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR CUE: Repeat Back any direction given to you with regards to EP-MA-114-100-F-01.

EVALUATOR CUE: If asked, radioactive liquid is not expected to be transported beyond the protected area boundary, liquid effluent radiation monitors are reading normal, and no abnormal radioactivity has been detected beyond the protected area boundary.

EP-AA-112-100-F-01, Section 1.4.H Performance Step: 8 Direct performance of State/Local notifications within 15 minutes of the event classification as required per the Notifications procedure.

Notification Procedure EP-MA-114-100: (Tab 3)

Notification Form EP-MA-114-100-F-O 1): (Tab 4)

Release in Progress Determination Guidance EP-AA-114-F-01:

(Tab 21)

-I Standard: Examinee fills out EP-MA-114-100-F-01 (while using EP-MA-114-100 and EP-AA-114-F-01 for guidance) as follows:

- Block 1: This is a DRILL (This step NOT critical)

- Block 2: C- TMI

- Block 3: A- ONE

- Block 4: D- GENERAL EMERGENCY

- Block 5: Time and Date of declaration

- Block 6: A- INITIAL DECLARATION

- Block 7: FG1

- Block 8: B - Fission Product Barrier Degradation

- Block 9: B -AIRBORNE radiological release in progress

- Block 10: 291 (degrees) I 8 (miles per hour)

- Block 11: B-

@360 DEGREES FROM 0 MILES (SITE BOUNDRY) TO 2 MILES AND THE FOLLOWING SECTORS FROM 2 MILES TO 5 MILES:

@)NE/ENE/E/ESE/SE/SSE/S THIS PAR<l[HQDTHE RESULT OF A RAPIDLY PROGRESSING SEVERE ACCIDENT.

- Examinee hands the filled out form to the communicator.

Comment:

ILT 16-01 NRC JPM SA4 NU REG 1021, Revision 10

Appendix C Page 10 of 12 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR NOTE: Time Critical #2 must be equal to or less than 15 minutes.

Time Critical #2= (#2 Critical Stop Time)

(# 2Critical Start Time)

= - - - - mins Terminating Cue: When the candidate hands the completed Emergency Notification Form to the Communicator: Evaluation on this JPM is complete.

ILT 16-01 NRC JPM SA4 NU REG 1021, Revision 10

Appendix C Page 11 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM SA4 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT 16-01 NRC JPM SA4 NUREG 1021, Revision 10

Appendix C Page 12of12 Form ES-C-1 JPM CUE SHEET Initial Conditions:

• T= 0 minutes:

• Plant is at 100% Power.

• Weather: Breezy. Temp: 60°F. Wind: from 291° at 8 mph.

• AH-E-1 C is out of service.

• A loss of the '8' bus occurs and EG-Y-1 B fails to power on the 1E 4160V bus

• T= 10 minutes:

• Seismic motion is felt, PRF-1-3 alarm is in

• RCS pressure starts dropping, the reactor operator trips the reactor and the crew performs the Immediate Manual Actions of OP-TM-EOP-001.

• UNISOLABLE RCS leakage exists at 500 gpm.

• T= 12 minutes:

• Reactor Building pressure peaks at 31 psig, then drops rapidly to O psig

• RM-G-23 reads 1.96 E+03 R/hr

• The Maintenance Supervisor has informed you that, EG-Y-1B is inoperable and will take 10 hours0.417 days <br />0.0595 weeks <br />0.0137 months <br /> to repair.

Initiating Cue: You are the Shift Manager and have the responsibilities of the Shift Emergency Director from the Control Room. I will act as your communicator. Declare the appropriate EAL and respond in accordance with the EP-AA-112-100-F-01, SHIFT EMERGENCY DIRECTOR CHECKLIST.

Ensure all communications are marked as a DRILL.

Time Critical Yes ILT 16-01 NRC JPM SA4 NU REG 1021, Revision 10

Appendix C Page 1 of 7 Form ES-C-1 PERFORMANCE INFORMATION Facility: Three Mile Island Task No.: ADM08016 Task

Title:

REVIEW RB ENTRY SURVEY LOG JPM No.: ILT 16-01 NRC JPM SA3 KIA

Reference:

2.3.13 (3.8) Bank JPM: 2011 CERT SRO A3 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom X Simulator Plant Task Standard: Faults identified: Particulate and Oxygen are not within limits and the RWP does NOT identify any Respirator Requirements.

Required Materials:

• RP-TM-460-1007 Rev 8, Access to TMl-1 Reactor Building

• A current copy of a Radiation Work Permit for the Reactor Building that does NOT include respiratory protection requirements

• Attachment#1 of RP-TM-460-1007 Rev 8, filled out per the setup on the next page.

General

References:

• RP-TM-460-1007 Rev 8, Access to TMl-1 Reactor Building Handouts: RP-TM-460-1007 Access to TMl-1 Reactor Building, including a completed Attachment#1 of RP-TM-460-1007 and RWP #00305 Containment Work at Power.

Validation Time: 10 minutes.

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.

Initial Conditions:

• The plant has been steady at full power for 6 months.

• Neither the Kidney Filter System nor RB Purge System has been operated.

Initiating Cue: You are the Shift Manager on duty. Review a RB Entry Survey Log IAW RP-TM-460-1007, Access to TMl-1 Reactor Building, for a routine Reactor Building entry that is scheduled within the next 2 Hours.

Verify the lab results are within allowable range to allow RB entry using RWP#00305.

Appendix C Page 2 of 7 Form ES-C-1 PERFORMANCE INFORMATION Time Critical Task: N/A Validation Time: 15 Minutes SIMULATOR SETUP Attachment 1 Reactor Building Entry Survey Log Setup RM-A- Sample Lab Results Air Sample Log#

Particulate: 3E-8 µCi/cc 0.5 DAC Fraction A 161012-0001 Iodine: 0. 7E-8 µCi/cc 0.28 DAC Fraction A 161012-0001 Gas: 2.31 E-5 µCi/cc 0.62 DAC Fraction A161012-0002 Tritium (H3): 7.51 E-6 µCi/cc 0.38 DAC Fraction A161012-0003 Oxygen (02) 18.9 % on Gas Partitioner Explosive Gas <0.05 % on Gas Partitioner Carbon Monoxide 60 (ppm)

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check)

START TIME: _ _ _ _ _ __

Evaluator Cue: Provide a completed Attachment#1 of RP-TM-460-1007 and a copy of same procedure and RWP#00305 Containment Work at Power

'1 Performance Step: 1 Examinee reviews RM-A-2 sample lab results for Particulate.

Procedure Step: 3.2 Standard: Examinee verifies Particulate is NOT below 30% DAC as determined by analysis RM-A-2 air samples and identifies that respiratory protection is required for RB entry per section 3.2.

CUE: If Examinee calls Rad Con to verify RWP does NOT include any respiratory protection, confirm that it does not require respiratory protection.

If examinee wants to stop review, inform him/her to review all data on the Survey Log.

Comment:

Performance Step: 2 Examinee reviews RM-A-2 sample lab results for Iodine.

Procedure Step: 3.2 Standard: Examinee verifies Iodine is below 30% DAC as determined by RM-A-2 analysis of air samples.

Comment:

Performance Step: 3 Examinee reviews RM-A-2 sample lab results for Gas.

Procedure Step: 3.2 Standard: Examinee verifies Gas is below 1 DAC as determined by RM-A-2 analysis of air samples Comment:

CUE When examinee reviews the Tritium Value, inform the examinee the value is within required limits.

Performance Step: 4 Examinee reviews sample results for Tritium.

Standard: Examinee verifies Tritium is within required limits.

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION

"./ Performance Step: 5 Examinee reviews RM-A-2 sample results for Oxygen.

Procedure Step: 3.2 Standard: Examinee verifies Oxygen is below 19.5% as determined by analysis of air samples and notifies Occupational Safety and the Control Room of the result.

Comment:

Performance Step: 6 Examinee reviews RM-A-2 sample results for Explosive Gas.

Procedure Step: 3.2 Standard: Examinee verifies Explosive Gas is below 0.4% as determined by analysis of air samples.

Comment:

CUE: When examinee reviews Carbon Monoxide value inform the examinee the value is within required limits.

Performance Step: 7 Examinee reviews sample results for Carbon Monoxide.

Standard: Examinee verifies Carbon Monoxide is within required limits.

Comment:

"./ Performance Step: 8 Examinee may sign the RB Survey Log but Standard: Examinee does NOT approve RB entry due to:

• Respiratory protection is required per RP-TM-460-1007, but not specified on the RWP.

Comment:

Terminating Cue: When examinee has completed the paperwork and hand it in the JPM is terminated.

STOP TIME: _ _ _ __

Appendix C Page 5 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM SA3 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

Appendix C Page 6 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• The plant has been steady at full power for 6 months.

• Neither the Kidney Filter System nor RB Purge System has been operated.

INITIATING CUE: You are the Shift Manager on duty. Review a RB Entry Survey Log IAW RP-TM-460-1007, Access to TMl-1 Reactor Building, for a routine Reactor Building entry that is scheduled within the next 2 Hours.

Verify the lab results are within allowable range to allow RB entry using RWP # 00305.

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET ATTACHMENT 1 Page 1 of 1 (Example)

Reactor Building Entry Survey Log DATE: Today REACTOR POWER: _ _1~00~-

START TIME: 0700 TECHNICIAN: RP Tech I Re {;,e,h, I

Print/Sign

1. RM-A2 SAMPLE LAB RESULTS Air Sample Log#

PARTICULATE 3.0E-8 µCi/cc ~0~.5~-- DAC FRACTION A 161012-0001 IODINE 0.7E-8 µCi/cc 0.28 DAC FRACTION A161012-0001 GAS 2.31E-5 µCi/cc 0. 62 DAC FRACTION A161012-0002 TRITIUM (H3) 7.51E-6 µCi/cc 0.38 DAC FRACTION A161012-0003 OXYGEN (02) ~18=*~9_ _ _ % on Gas Partitioner EXPLOSIVE GAS <0.05  % on Gas Partitioner CARBON MONOXIDE 60 (ppm)

2. Readings from inside Reactor Building (If Required) NIA DAC Fraction Air Sample Log#

Particulate ________ µCi/cc (Gross ~y)

Gaseous ________ µCi/cc Iodine ________ µCi/cc Tritium (H 3 ) ________ µCi/cc Oxygen (02) ________  % CG/02 Meter

________ %on Gas Partitioner Explosive Gas (H 2 )  % CG/0 2 Meter

_ _ _ _ _ _ _ _ %on Gas Partitioner Carbon Monoxide _ _ _ _ _ _ _ (ppm)

See Attached HPGe Scan Results D Reactor Bldg. Purged Prior to Entry D Kidney Filter System Operated Prior to Entry D Iodines and Particulates < 30% DAC REVIEWED BY: - - - - - - - - - - - - - - - - Shift Manager Print/Sign

- - - - - - - - - - - - - - - - Radiation Protection Manager/Supervisor Print/Sign

Appendix C Job Performance Measure Form ES-C-1 Worksheet THREE MILE ISLAND UNIT 1 Task No.:

Facility:

Task

Title:

Use Station Drawing to Predict JPM No.: ILT 16-01 NRC JPM Impact of Component Failure and SA2 Evaluate Technical Specification Implications KIA

Reference:

G 2.2.41 (3.5/3.9) Bank JPM: TMI08 NRC JPM A2 SRO 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.

Initial Conditions: You are the CRS Plant is at 100% power Electricians have reported a broken cam connecting rod on G11-02 EG-Y-1 B output breaker.

Electricians have provided a copy of 208-164.

Only contacts associated with 52 MOC(2) are affected (Grid A-6)

Task Standard: Determine that 27/86 lockouts will not occur for condition of Diesel breaker closed and ESAS and declares a 7 day timeclock to return to service IAW Tech Spec 3.7.2.c and 3.7.2.f, Lockout inoperable.

Required Materials: Copies of site 208 and 209 electrical diagram books.

General

References:

208-314 1S 480 Volt Swgr, 208-316 1T 480 Volt Swgr., 208-169 Bus 1E UV and Potential Indicating Circuits, 208-300 Bus 1T UV Lock-out Relays, 208-318 Bus 1S UV Lock-out Relays Tech Spec 3.7.2.c and 3.7.2.f ILT 16-01 NRC JPM SA2 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Handout:

• 208-164, G11-02 Initiating Cue: You are directed to determine impact to operations based on this failure.

Time Critical Task: No Validation Time: 20 Minutes ILT 16-01 NRC JPM SA2 NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A ILT 16-01 NRC JPM SA2 NUREG 1021, Revision 10

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EXAMINER CUE: Direct the examinee to determine the impact of operations based on the failure. Hand the examinee the 208-164 drawing.

EXAMINER NOTE: A 208 and 209 will be used for the examinee to find the drawings.

Performance Step: 1 Obtains 208-164 G11-02 Elementary Electrical Diagram Standard: Drawing obtained.

Comment:

Performance Step: 2 52 MOC(2) located on drawing at grid A-6 (52 MOC(2))

Standard: Contacts located.

Comment:

Performance Step: 3 When Requested, Provide Electrical Prionts 314 and/or 316 to determine contact effect.

Standard: 208-314 and/or 208-316 referred to Evaluator Note: After student obtains appropriate diagram you may hand the candidate a copy they can mark up.

Comment:

ILT 16-01 NRC JPM SA2 NUREG 1021, Revision 10

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION

.,/ Performance Step: 4 Determines from 208-314 or 316 that 52/G11-02 contact remaining open will prevent 27/86 actuation for bus 1S or 1T, dependent on sheet 314 or 316 respectively.

Standard: Examinee verbalizes 27/86 for bus 18 or 1T will not work for the condition of diesel breaker closed with ESAS actuated.

Comment:

.,/ Performance Step: 5 Determines from 208-314 or 316 (which ever was not evaluated in previous step) that 52/G11-02 contact remaining open will prevent 27/86 actuation for bus 1S or 1T, dependent on sheet 314 or 316 respectively.

Standard: Examinee verbalizes 27/86 for bus 18 or 1T will not work for the condition of diesel breaker closed with ESAS actuated.

Comment:

.,/ Performance Step: 6 Reviews section 3.7.2.c and 3.7.2 .f of Technical Specifications and identifies that due to the failed load shedding ability Diesel is inoperable and declares a 7 day timeclock to repair.

Standard: Declares a 7 day time clock IAW Tech Specs due to the failed load shedding ability.

Comment:

Terminating Cue: When Tech Specs have been addressed this JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME: N/A ILT 16-01 NRC JPM SA2 NUREG 1021, Revision 10

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM SA2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT 16-01 NRC JPM SA2 NU REG 1021, Revision 10

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS: You are the CRS Plant is at 100% power Electricians have reported a broken cam connecting rod on G11-02 E G-Y-1 B output breaker.

Electricians have provided a copy of 208-164.

Only contacts associated with 52 MOC(2) are affected: (Grid A-6)

INITIATING CUE: You are directed to determine impact to operations based on this failure.

ILT 16-01 NRC JPM SA2 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: GOP002003 Task

Title:

PERFORM AN ESTIMATED JPM No.: ILT 16-01 NRC JPM CRITICAL ROD POSITION SA1-2 CALCULATION KIA

Reference:

2.1.43 (4.1/4.3) Bank JPM: TQ-TM-104-ADM-403-J100 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.

Initial Conditions: .* A sequential trip of both feedwater pumps and reactor trip 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> ago

• 100% power for 150 days prior to the trip

• Cycle Burnup is 300 EFPD from hourly log

• Tave= 532 °F

• Final critical boron concentration = 1469 ppm

• FINAL MIXED BORON DEPLETION CORRECTION FACTOR in the control room log is 0.95

• The Plant Process Computer is not available.

• No reactor engineering personnel are on site.

Task Standard: Identify all errors with the ECP. Calculate and approve an ECP.

Required Materials:

• OP-TM-300-000, REACTIVITY AND POWER DISTRIBUTION CALCULATIONS, Rev 8

• OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION, Rev 5

• Ruler

• Calculator ILT16-01 NRC JPM SA1-2 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet General

References:

• OP-TM-300-000, REACTIVITY AND POWER DISTRIBUTION CALCULATIONS, Rev 8

• OP-TM-300-403, ESTIMATED CRITICAL ROD POSITION, Rev 5 Initiating Cue: Perform a review and approval of an Estimated Critical Rod Position calculation. Make any corrections, if required.

Time Critical Task: No Validation Time: 25 mins ILT16-01 NRC JPM SA1-2 NUREG 1021, Revision 10

Appendix C Page 3of13 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATOR NOTE: This JPM may be administered without direct interaction between the examiner and examinee. Once the calculation has been completed, review the calculation for accuracy.

EVALUATORS CUE: Role play as SM and direct the Examinee to calculate, review, and approve an ECP for current plant conditions IAW OP-TM-300-403 Provide a copy of OP-TM-300-000 Reactivity and Power Distribution Calculations and OP-TM-300-403 Attachment 7 .1 and Attachment 7.2. (Last two pages of JPM)

OP-TM-300-403, Attachment 7.1 Performance Step: 1 Calculation is for an ECP at Date/Time Standard: Examinee verifies the current date and time on Attachment 7.1.

Comment:

OP-TM-300-403, Attachment 7.1, Step 1 Performance Step: 2 Enter the average reactor coolant temperature, TAVE, from the Initial Conditions Standard: Examinee verifies 532F on Line 1.

Comment:

OP-TM-300-403, Attachment 7.1, Step 2 Performance Step: 3 OBTAIN the cycle burn-up from the Initial Condition Sheet.

Standard: Examinee verifies 300 EFPD on Line 2 Comment:

ILT16-01 NRC JPM SA1-2 NUREG 1021, Revision 10

Appendix C Page 4 of 13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-403, Attachment 7.1, Step 3a Performance Step: 4 OBTAIN the Final Measured Boron Concentration, Initial Conditions.

Standard: Examinee verifies 1469 ppmB on Line 3a Comment:

EXAMINER NOTE: If the Examinee states that he/she is complete with the review, inform the examinee to perform the entire calculation.

OP-TM-300-403, Attachment 7.1, Step 3b

..J Performance Step: 5 Obtain the Boron Depletion Correction Factor from Initial Conditions.

Standard: Examinee finds 1.0 Examinee verifies 0.95 on line 3b.

Comment:

OP-TM-300-403, Attachment 7.1, Step 3c

..J Performance Step: 6 Calculate the Final Corrected Boron Correction .

Standard: Examinee finds 1469 Examinee verifies: 1469 X 0.95 =1396 ppmB on Line 3c (between 1395.5 - 1396)

Comment:

OP-TM-300-403, Attachment 7.1, Step 4 Performance Step: 7 DETERMINE the fuel excess reactivity per Figure 2.

Standard: Examinee verifies 11.4 on Line 4.

(Between 11.2 and 11.4%~k/k)

Comment:

ILT16-01 NRC JPM SA 1-2 NUREG 1021, Revision 10

Appendix C Page 5of13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-403, Attachment 7.1, Step 5a Performance Step: 8 DETERMINE the Inverse Boron Worth from Figure 8.

Standard: Examinee verifies 140.5 on Line 5a (between:140 and 141 ppmB /%l1k/k)

Comment:

OP-TM-300-403, Attachment 7.1, Step 5b

-I Performance Step: 9 DETERMINE the Boron reactivity Worth by dividing the current concentration (Step 3c) by the HZP Inverse Boron Worth (Step 5a)X(-1).

Standard: Examinee finds -10.46 on Line 5b.

Examinee calculates -9.94 (between -9.91 and -9.95 %l1k/k)

Comment:

OP-TM-300-403, Attachment 7.1, Step 6 Performance Step: 10 OBTAIN the xenon worth from Figure 13 Standard: Examinee verifies -0.1 on Line 6.

(between -0.05 and -0.15  %~k/k)

Comment:

ILT16-01 NRC JPM SA1-2 NUREG 1021, Revision 10

Appendix C Page 6of13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-403, Attachment 7.1, Step 7 Performance Step: 11 Obtain the Samarium and Plutonium Buildup after shutdown by using Figure 15.

Standard: Examinee verifies time since last SID on Line 7 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> Examinee verifies -0.1 O on Line 7 (between -0.09 and -0.11 o/ollk/k)

Comment:

OP-TM-300-403, Attachment 7.1, Step 8

'\/ Performance Step: 12 DETERMINE the inserted CRG 5-7 worth required for Criticality Standard: Examinee finds -0.74 on Line 8 Examinee calculates -1.26 (Between -1.20 and -1.30 o/ollk/k)

Comment:

EXAMINER NOTE: The Rod Tolerance and Rod Index bands are CRITICAL, NOT the value associated with the reactivity values.

OP-TM-300-403, Attachment 7.1, Step 9

'\/ Performance Step: 13 DETERMINE the Estimated Critical Rod Position from Figure 5a.

Standard: Examinee finds 236%

Examinee determines 175% on line 9.

(between 165 and 185% Rod Index)

Comment:

ILT16-01 NRC JPM SA1-2 NU REG 1021, Revision 10

Appendix C Page 7of13 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-403, Attachment 7.1, Step 10

-I Performance Step: 14 DETERMINE the Critical Rod Position Tolerance Band from Figure 5A.

Circle 0.5%  %~k/k Determine Minimum Rod Withdrawal Limit using Fig 5a Determine the Maximum Rod Withdrawal Limit Fig 5a Standard: Examinee verifies that the Steady State condition adjustments need to be made and 0.5% delta K/K is circled in Line 1Oa.

Examinee finds -1.24and183%

Examinee determines -1. 76+/-.02  %~k/k for a Rod Index of 118%

on Line 1Ob for Minimum Examinee finds -0.24 and 284%

Examinee determines -0.76+/-.02%~k/k for a Rod Index of 235%

on Line 1Oc for Maximum :

(Rod Positions: minimum between 110 and 130% and maximum between 225 and 245%)

Comment:

OP-TM-300-403, Attachment 7.1, Step 11 Performance Step: 15 If this is a Transient Xenon Startup, then record the interval that ECP is valid.

Standard: Examinee verifies Step 11 is N/A Comment:

OP-TM-300-403, Attachment 7.1, Approval Performance Step: 16 Note that an anomaly exists between the two calculations Standard: Examinee notifies the Shift Manager about the discrepancies.

Comment:

ILT16-01 NRC JPM SA1-2 NUREG 1021, Revision 10

Appendix C Page 8of13 Form ES-C-1 PERFORMANCE INFORMATION Terminating Cue: When examinee has notified the Shift Manager of an anomaly with the calculations, this JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME:

ILT16-01 NRC JPM SA1-2 NUREG 1021, Revision 10

Appendix C Page 9of13 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM SA1-2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT16-01 NRC JPM SA1-2 NU REG 1021, Revision 10

INITIAL CONDITIONS:

• A sequential trip of both feedwater pumps and reactor trip 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> ago

• 100% power for 150 days prior to the trip

• Cycle Burnup is 300 EFPD from hourly log

• Tave =532 °F

• Final critical boron concentration = 1469 ppm

• FINAL MIXED BORON DEPLETION CORRECTION FACTOR in the control room log is 0.95

• The Plant Process Computer is not available.

• No reactor engineering personnel are on site.

INITIATING CUE: Perform a review and approval of an Estimated Critical Rod Position calculation. Make any corrections, if required.

TIME CRITICAL: No

Appendix C Page 11 of 13 Form ES-C-1 JPM CUE SHEET ATTACHMENT 7.1 Estimated Critical Position Calculation Data Sheet Page 1 of 1 NOTE: Refer to Attachment 7.2 to complete this Data Sheet. Data may be entered in any sequence. Sign-off verifies all data entered as required. Approval signature indicates an "Independent Verification".

CALCULATION IS FOR AN ECP AT DATE/TIME Today/ Now

1. TAVE (Assume TAVE= 532 +/- 2°F) 532 °F

2. CYCLE BURNUP ~30=0'----_EFPD

3. 3a. FINAL MEASURED BORON CONCENTRATION 1469 ppmB 3b. BORON DEPLETION CORRECTION FACTOR ~1-~0_ _

(PPG, Control Room Log, Reactor Engineering, Reactivity Datasheet) 3c. FINAL CORRECTED BORON CONCENTRATION (3.a) X (3.b) = 1469 ppmB

4. FUEL EXCESS REACTIVITY (FIG 2) _,_1""-'1._,_4 _ _ _ _% L'ik/k

5. 5a. INVERSE BORON WORTH (FIG 8) 140.5 ppmB/% L'ik/k 5b. BORON REACTIVITY WORTH (3c I 5a) x (-1) = -10.46  % L'ik/k

6. XENON REACTIVITY WORTH (PPG, REACTOR ENGR., FIG 13) -0.1  % L'ik/k

7. SAMARIUM AND PLUTONIUM BUILDUP (FIG 15)

• TIME SINCE LAST SHUTDOWN 72 HRS

• REACTIVITY DUE TO BUILDUP -0.10  % L'ik/k

8. INSERTED CRG 5-7 WORTH REQUIRED FOR CRITICALITY (IRW)

(4+5b+6+7)x(-1)= -0.74  % L'ik/k

9. ESTIMATED CRITICAL ROD POSITION (FIG 5A) 236  % ROD INDEX

10. CRITICAL ROD POSITION TOLERANCE BAND (FIG 5A) 1Oa. Circle One: ~ 0.8%1'.'ik/k Use 0.5%1'.'ik/k for Steady State conditions if xenon (6) is 0.0 to -0.5%

Use 0.8%1'.'ik/k for Transient conditions if xenon (6) is more negative than -0.5%L'ik/k 10b. MINIMUM ROD WITHDRAWAL LIMIT (8- 1Oa) = -1.24 %L'ik/k => _,__18=3'----_ %ROD INDEX (FIG 5a) 10c. MAXIMUM ROD WITHDRAWAL LIMIT (8 + 1Oa) = -0.24 %L'ik/k => 284 %ROD INDEX (FIG 5a) 11 . If this is a transient Xenon startup, then record the interval that ECP is valid From: Date/Time NIA To: Date!Time ___N~Y,~'.A~-------

CALCULATED BY: --'R'-'-=0-"#'"-'-1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATE/TIME Today/ Now APPROVED BY (SRO): - - - - - - - - - - - - - - - - - DATE/TIME _ _ __

ILT16-01 NRC JPM SA1-2 NUREG 1021, Revision 10

Appendix C Page 12 of 13 Form ES-C-1 JPM CUE SHEET ATTACHMENT 7.2 Estimated Critical Position Calculation Instructions Page 1 of 1 NOTE: Figure numbers refer to attachments in OP-TM-300-000.

Data may also be obtained from approved references, e.g., current cycle Physics Data Manual or Reactivity Datasheet.

1. TAvE: The reactor coolant temperature is assumed to be 532 +/- 2°F

2. Cycle Burnup: From FIDMS Display 1 or the Hourly Log 3a. Measured Boron Concentration: Obtain the latest measured boron concentration from the RCS chemistry analysis, and check the Control Room log to verify that no major boron concentration changes have been made since the analysis. If major boron concentration changes have been made since the latest sample, request a new RCS boron concentration measurement. Until the new boron concentration is available, use OP-TM-300-409, Final RCS Boron Concentration Estimate Following RCS Feed and Bleed, to estimate the current boron concentration to calculate a preliminary ECB.

3b. Boron Depletion Correction Factor: From PPC, Control Room Log, or Reactor Engineering.

3c. Final Corrected Boron Concentration: Adjust the measured boron concentration to account for boron-1 O depletion by multiplying the Measured Boron Concentration by the Boron Depletion Correction Factor.

3. Fuel Excess Reactivity: From Figure 2.

5a. Inverse Boron Worth: From Figure 8 5b. Boron Reactivity Worth: Quotient of 3c and 5a.

6. Xenon Reactivity Worth: Obtain xenon worth using the PPC, FIDMS Display 22 or from program XENC# (where # is the current cycle number). Figure 13 may be used if the PPC and Reactor Engineering are unavailable, provided that power prior to shutdown was constant (+/- 2%FP) for at least 40 hours1.667 days <br />0.238 weeks <br />0.0548 months <br />.

7. Samarium and Plutonium Buildup Reactivity Worth: Record the number of hours since 0% FP and obtain Sm and Pu worth per Figure 15. If startup at any time during the cycle is within 5 days of a previous startup, contact Reactor Engineering for the appropriate reactivity worth.

8. Inserted CRG 5-7 Worth Required for Criticality: Add reactivity contributions from Lines 4 through 7.

9. Estimated Critical Rod Position: Rod position from Figure 5A corresponding to the reactivity value from Line 8.

10. Critical Rod Position Tolerance Band: As noted on the Calculation Data Sheet. Combine the reactivity value from Line 8 with the tolerance value from Line 1Oa and find the corresponding rod positions on Figure 5A.

11. For the purposes of this procedure, "Transient Xenon" conditions exist when the pre-critical Xe concentration is more negative than -0.5% i1k/k. Use the Xe value from Line 6 and a plot or table of Xe behavior with time. Estimate when Xe worth will be more or less negative than the value in Line § by 0.5% L1k/k.

NOTE: Refer to Attachment 7.2 to complete this Data Sheet. Data may be entered in any sequence. Sign-off verifies all data entered as required. Approval signature indicates an "Independent Verification".

ILT16-01 NRC JPM SA1-2 NU REG 1021, Revision 10

Appendix C Page 13of13 Form ES-C-1 JPM CUE SHEET SA1-2 ANSWER KEY DO NOT GIVE TO EXAMINEE CALCULATION IS FOR AN ECPAT DATE/TIME Today/ Now

1. TAVE (Assume TAVE= S32 +/- 2°F} S32 °F

2. CYCLE BURNUP =30:;..:0;.___EFPD

3. 3a. FINAL MEASURED BORON CONCENTRATION 1469 ppmB 3b. BORON DEPLETION CORRECTION FACTOR 0.95 (PPC, Control Room Log, Reactor Engineering, Reactivity Datasheet) 3c. FINAL CORRECTED BORON CONCENTRATION (3.a) X (3.b} = ~13~9~6_ _ ppmB

4. FUEL EXCESS REACTIVITY (FIG 2) 11.4  % L1k/k S. Sa. INVERSE BORON WORTH (FIG 8) 140.5 ppm B/% L1k/k Sb. BORON REACTIVITY WORTH (3c I Sa) x (-1) = -9.94  % L1k/k

6. XENON REACTIVITY WORTH (PPC, REACTOR ENGR., FIG 13) -0.1  % L1k/k

7. SAMARIUM AND PLUTONIUM BUILDUP (FIG 1S}

• TIME SINCE LAST SHUTDOWN 72 HRS

• REACTIVITY DUE TO BUILDUP -0.10  % L1k/k

8. INSERTED CRG S-7 WORTH REQUIRED FOR CRITICALITY (IRW)

(4 +Sb+ 6 + 7) x (-1) = -1.26  % L1k/k

9. ESTIMATED CRITICAL ROD POSITION (FIG SA) 175  % ROD INDEX

10. CRITICAL ROD POSITION TOLERANCE BAND (FIG SA) 1Oa. Circle One: O.S%L1k/k 0.8%L1k/k Use O.S%L1k/k for Steady State conditions if xenon (6) is 0.0 to -O.S%

Use 0.8%L1k/k for Transient conditions if xenon (6) is more negative than -O.S%L1k/k 10b. MINIMUM ROD WITHDRAWAL LIMIT (8- 10a) = -1.76 %L1k/k => _11~8_ _ %ROD INDEX (FIG Sa}

10c. MAXIMUM ROD WITHDRAWAL LIMIT (8 + 10a) = -0.76 %i1k/k => -..23~5____ %ROD INDEX (FIG Sa)

11. If this is a transient Xenon startup, then record the interval that ECP is valid From: Date/Time_ _;._N=/'A-'--------- To: Date/Time_ _-'N~'/,~J:\'----------

CALCULATED BY: _R~0~#~1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATE/TIME Todav!Now APPROVEDBY(SRO): ----------------~DATE/TIME _ _ _ _ __

ILT16-01 NRC JPM SA1-2 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Task No.: OF1000005 Task

Title:

Maintain Minimum Shift Staffing. JPM No.: ILT 16-01 NRC JPM Control Overtime SA1-1 KIA

Reference:

2.1.5 (3.9) Previous Exam: ILT 14-01 NRC 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.

Initial Conditions:

• You are the Control Room Supervisor.

• I will act as all other personnel.

• Plant is at 100% power.

• The time is 2300 on the Exam Date.

• The shift Scheduler is unavailable.

• The shift is staffed as follows:

• SRO 1 - Shift Manager

• You - CRS (not STA qualified)

• SRO 3-STA

• RO 1-URO

• R02-ARO

• RO 3-C&T RO

• The Shift Technical Advisor (STA), SRO 3, reports that his contact lenses have popped out and are lost. He reminds you that he has a license restriction that requires him to wear corrective lenses. His backup eyeglasses are missing and cannot be located, so he is going to get a pair of old prescription glasses from his locker.

• No other SRO's are currently at the station.

ILT 16-01 NRC JPM SA1-1 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Task Standard: Examinee identifies required actions to restore minimum staffing, and selects personnel in accordance with qualification and overtime requirements.

Required Materials:

• OP-TM-112-101-1002, Shift Staffing Requirements, Rev. 10

• Tech Spec 6.2.2 and Table 6.2-1, Amendment 219

• LS-AA-119, Overtime Controls, Rev. 12

• LMS Qual Matrix Report (Attachment #1)

• Prepared Overtime List (Attachment #2)

• LAPTOP for LMS Access

• A disconnected phone for simulation General

References:

• Technical Specifications Handout:

• OP-TM-112-101-1002, Shift Staffing Requirements, Rev. 10

• LS-AA-119, Ove.rtime Controls, Rev. 12

• LMS Qual Matrix Report (Attachment #1)

• Prepared Overtime List (Attachment #2)

Initiating Cue: You are to perform the steps necessary to ensure your shift is properly staffed. A phone is provided for any calls, if required.

Time Critical Task: N/A Validation Time: 7 minutes ILT 16-01 NRC JPM SA1-1 NU REG 1021, Revision 10

Appendix C Page 3of11 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATOR NOTE: Provide Examinee with OP-TM-112-101-1002, LS-AA-119, Shift Staffing Report .

.../ Performance Step: 1 Examinee references Technical Specifications and/or OP-TM-112-101-1002 to determine minimum shift staffing requirements for current conditions.

Standard: Examinee determines from OP-TM-112-101-1002, Section 4.1, that three SROs are required.

Examinee determines that due to the prescription being old, the STA cannot be considered one of the shift SRO's.

Examinee determines that a call out must be made to get shift staffing back to allowable numbers.

Comment:

EVALUATOR NOTE: Tech Specs allow for, except for Shift Manager, that shift crew composition may be one less than the minimum requirements for a period of time not to exceed 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

Performance Step: 2 Examinee initiates action to comply with Technical Specification requirements for three licensed SROs.

LOGS into LMS to verify qualifications.

CUE: After examinee demonstrates ability to log into LMS and locate qualifications, provide LMS Qual Matrix Report-Attachment 1, and Overtime list attachment 2.

Standard: Action initiated by referring to LMS Qual Matrix and Overtime list Comment:

ILT 16-01 NRC JPM SA1-1 NUREG 1021, Revision 10

Appendix C Page 4 of 11 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 3 Examinee seeks a replacement for the third licensed SRO position left vacant by the inability of the STA to meet requirements for the job.

Standard: Examinee references the Overtime Callout list to identify a replacement SRO to be called.

Comment:

EVALUATOR CUE: Once it is decided that someone must be called in, direct the examinee to use Attachment #2 in the order of personnel listed.

If examinee asks the status of a STA qualification with an "O" status, reply they have 20 days left on the qualification status.

The Shift Manager has directed NO waivers are to be used.

ILT 16-01 NRC JPM SA1-1 NU REG 1021, Revision 10

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR CUE: If examinee calls Miscavage to report to work, answer that you are on your way.

EVALUATOR NOTE: If examinee tells Miscavage to report to work, the JPM is completed UNSAT due to Miscavage not being qualified.

v Performance Step: 4 Examinee references the provided materials to evaluate the STA watch standing ability of Miscavage.

Standard: Examinee skips Miscavage as he is inactive per the LMS Qual Matrix Report.

Comment:

Evaluator's Cue: If examinee calls Johnson to report to work, answer "I just had three beers at a friend's house. If you need me though, I'll come in as soon as I can" EVALUATOR NOTE: If examinee tells Johnson to report to work, the JPM is completed UNSAT due to Johnson not being Fit for Duty.

v Performance Step: 5 Examinee references the provided materials to evaluate the STA watchstanding ability of Johnson.

Standard: Examinee initially informs Johnson to report to work immediately, then acknowledges alcohol consumption and informs Johnson NOT to report at this time due to Fit For Duty concerns.

Comment:

ILT 16-01 NRC JPM SA1-1 NUREG 1021, Revision 10

Appendix C Page 6of11 Form ES-C-1 PERFORMANCE INFORMATION Evaluator's Cue: If examinee calls Adams to report to work, answer "This is my one day off in the past seven days since I validated NRC exams in the simulator yesterday. If you need me though, I'll come in as soon as I can" EVALUATOR NOTE: If examinee tells Adams to report to work, the JPM is completed UNSAT due to Adams violating Work Hour Rule limitations .

../ Performance Step: 6 Examinee references the provided materials to evaluate the STA watchstanding ability of Adams.

Standard: Examinee initially informs Adams to report to work immediately, then informs Adams NOT to report at this time due to LS-AA-119 Section 5.1.1 requirement.

Comment:

Evaluator's Cue: If examinee calls Shuff to report to work, answer "I am making a self-declaration of fatigue and do not wish to report to work".

EVALUATOR NOTE: If examinee tells Shuff to report to work, the JPM is completed UNSAT due to Shuff being not Fit for Duty.

../ Performance Step: 7 Examinee references the provided materials to evaluate the STA watchstanding ability of Shuff.

Standard: Examinee initially informs Shuff to report to work immediately then acknowledges self-declaration of fatigue and informs Shuff NOT to report at this time IAW LS-AA-119 Section 5.6.

Comment:

ILT 16-01 NRC JPM SA1-1 NU REG 1021, Revision 10

Appendix C Page 7of11 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR CUE: If examinee calls Lewis to report to work, answer that you are on your way.

EVALUATOR NOTE: If examinee calls Lewis to report to work, the JPM is completed UNSAT due to Lewis not being qualified,

..,/ Performance Step: 8 Examinee references the provided materials to evaluate the STA watch standing ability of Lewis.

Standard: Examinee skips Lewis as he is inactive per the LMS Qual Matrix Report.

Comment:

Evaluator's Cue: If examinee calls Harris to report to work, answer "I am on vacation but I am home and if you need me though, I'll come in as soon as I can"

..,/ Performance Step: 9 Examinee references the provided materials to evaluate the STA watch standing ability of Harris.

Standard: Examinee informs Harris to report to work immediately.

Comment:

Terminating Cue: After examinee demonstrates ability to contact an SRO at home to have the appropriate one report to work, JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME: N/A ILT 16-01 NRC JPM SA1-1 NUREG 1021, Revision 10

Appendix C Page 8 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM SA1-1 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT 16-01 NRC JPM SA1-1 NUREG 1021, Revision 10

Appendix C Page 9of11 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• You are the Control Room Supervisor.

• I will act as all other personnel.

• Plant is at 100% power.

• The time is 2300 on the Exam Date.

• The shift Scheduler is unavailable.

• The shift is staffed as follows:

• SRO 1 - Shift Manager

• You - CRS (not STA qualified)

• SRO 3-STA

• RO 1 -URO

• R02-ARO

• RO 3-C&T RO

• The Shift Technical Advisor (STA), SRO 3, reports that his contact lenses have popped out and are lost. He reminds you that he has a license restriction that requires him to wear corrective lenses. His backup eyeglasses are missing and cannot be located, so he is going to get a pair of old prescription glasses from his locker.

• No other SRO's are currently at the station.

INITIATING CUE: You are to perform the steps necessary to ensure your shift is properly staffed. A phone is provided for any calls, if required.

ILT 16-01 NRC JPM SA1-1 NUREG 1021, Revision 10

Appendix G Page 10of11 Form ES-C-1 JPM CUE SHEET Attachment #1 LMS Qual Matrix Report Date: Exam Date 1: 15:00 AM Y =Currently Qualified (will not expire in the next 60 days) 0 =Currently Qualified (due to expire in 60 days or less) N =Not qualified (expired) (blank)= Qualification Never Assigned

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OJ Qualification ID Qualification Title Qualification Parent N-TM-OP-STA QUAL TMI STA: SHIFT QUALIFIED Root Qual 0 N y N N y 0 0 y y 0 N N 0 y y 0 N N N ILT 16-01 NRC JPM SA1-1 NU REG 1021, Revision 10

Appendix C Page 11 of 11 Form ES-C-1 JPM CUE SHEET Attachment #2 OVERTIME CALLOUT FOR Ops Shift Schedule STARTING AT (Exam Date) 17:30:00 AND ENDING AT (Exam Date +1) 06:00:00 SRO# 2 STA QUALIFICATION Shift Technical Advisor REPORT CREATION DATE exam date 23:00:00 NOTES:

Crew Currently Name Phone OT Accept Refuse Comments Working Shift Hours Day None Miscavage, B 0 Dav None Johnson, E 0 Dav None Adams, M 0 Day None Shuff, J 0 Dav None Lewis, D 0 Dav None Harris, R 0 Note: List created by PQS IAW LS-AA-119 ILT 16-01 NRC JPM SA1-1 NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Task No.: OF010009 Task

Title:

ERO Notification JPM No.: ILT 16-01 NRC JPM RA4 KIA

Reference:

2.4.39 (3.9) Previous NRC Exam: ILT 12-01 Examinee: NRC Examiner:

Facility Examiner: Date:

Method of testing:

Simulated Performance: x Actual Performance:

Classroom - - Simulator X Plant READ CUE SHEET ON LAST PAGE 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.

Initial Conditions:

• You are the Third Reactor Operator on shift.

• A General Emergency has been declared.

Task Standard: All notifications made satisfactorily.

Required Materials: None General

References:

EP-AA-112-100-F-06, ERO NOTIFICATION OR AUGMENTATION, Revision V.

Handouts: EP-AA-112-100-F-06, ERO NOTIFICATION OR AUGMENTATION, Revision V.

Initiating Cue: You are directed to call out the Three Mile Island Emergency Response Organization IAW EP-AA-112-100-F-06, ERO Notification or Augmentation.

Time Critical Task: No Validation Time: 15 minutes ILT 16-01 NRC JPM RA4 NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP Ensure the ERO Notification Phone is set up in the Simulator Observation area and is UNPLUGGED AND if using a phone in the simulator ENSURE it is ISOLATED.

Procedure: EP-AA-112-100-F-06 ERO Notification or Augmentation

1. Page 1:

a. Circle the Number "1.1"

b. Circle: "TMI", "threemileisland3" and "simulator10#"

2. Page 2:

a. Section 1.2: Circle "1.2" and "Block 01"

3. Log on the Simulator Computer and verify the shortcut for EVERBRIDGE icon is available.

ILT 16-01 NRC JPM RA4 NUREG 1021, Revision 10

Appendix C Page 3of13 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)

Start Time - - - - -

EXAMINER CUE: Direct the examinee to make the appropriate notifications per EP-AA-112-1 OO-F-06, ERO Notification or Augmentation.

Provide the Examinee a copy of EP-AA-112-100-F-06 PROCEDURE NOTE: The automated system will initiate the call out of management and bargaining unit personnel required to meet the ERO staffing requirements. Additional staffing of personnel shall be the responsibility of the individual Managers and Directors in the TSC I OSC I EOF I ENC /JIC following initial activation of those facilities.

Section 1 - Initiate Activation I Termination of Notification System using World Wide Web Section 2 - Initiate Activation I Termination of Notification System using live Everbridge Agent Section 3 - Initiate Activation I Termination of Notification System using a Standard Phone EP-AA-112-100-F-06, Step 1.3 Performance Step: 1 OPEN (double-click) the Everbridge Aware shortcut icon from your desktop computer. If shortcut Icon is not available or does not open, then ACCESS the World Wide Web and go to https://manager. everbridge. net/login Standard: Examines opens the Everbridge Aware shortcut from the desktop computer.

Comment:

ILT 16-01 NRC JPM RA4 NUREG 1021, Revision 10

Appendix C Page 4 of 13 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-100-F-06, Step 1.4 Performance Step: 2 ENTER the appropriate station specific User name and Password from Step 1.1 and SELECT (click) "Sign In.

Standard:

• Examinee enters TMI as Station

• Examinee enters threemileisland3 as User Name

• Examinee enters simulator10# as Password Comment:

EP-AA-112-100-F-06, Step 1.5 Performance Step: 3 VERIFY the appropriate Station Name is displayed, SELECT (click) "Proceed".

Standard: Examinee verifies TMI is displayed Comment:

EP-AA-112-100-F-06, Step 1.6 Performance Step: 4 SELECT (click) the +Launch Incident button.

Standard: Examinee clicks on+ Launch Incident button.

Comment:

EP-AA-112-100-F-06, Step 1.7 Performance Step: 5 SELECT (Click) on the appropriate Scenario from Step 1.2 ..

Standard: Examinee selects Scenario 1 Comment:

ILT 16-01 NRC JPM RA4 NUREG 1021, Revision 10

Appendix C Page 5of13 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-100-F-06, Step 1.8 Perform~nce Step: 6 VERIFY the appropriate scenario is displayed.

Standard: Examinee verifies Scenario 1 is displayed.

Comment:

EXAMINER NOTE: Step 1.09 is N/A.

EP-AA-112-100-F-06, Step 1.10 Performance Step: 7 If the scenario displayed is correct, then SELECT (click) "Send x template(s) Now".

Standard: Examinee determines that the scenario displayed is correct and selects "Send x template(s) Now"'.

Comment:

EP-AA-112-100-F-06, Step 1.11 Performance Step: 8 On the next screen, VALIDATE there is a date and time stamp for each notification listed.

RECORD Time Standard: Examinee validates "date and time stamp" for each notification and records time.

Comment:

EP-AA-112-100-F-06, Step 1.12 Performance Step: 9 SELECT "Log Out" to exit the Everbridge Aware Notification program.

Standard: Examinee selects "Log Out".

Comment:

ILT 16-01 NRC JPM RA4 NU REG 1021, Revision 10

Appendix C Page 6 of 13 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER CUE: State: "Two minutes has elapsed and no call to the Control Room has been received".

EP-AA-112-100-F-06, Step 1.13 Performance Step: 10 VERIFY that a call to the Control Room from the ERO notification system is received within 2 minutes after the system was initiated ..

Standard: Examinee recognizes that a confirmation call has not been received.

Comment:

EXAMINER NOTE: Step 1.14 is N/A EP-AA-112-100-F-06, Step 1.15 Performance Step: 11 If a confirmation call is not received in the Control Room within 2 minutes confirming scenario activation, then proceed to Section 2, Initiate Activation I Termination of Notification System Using Live Everbridge Agent.

Standard: Examinee recognizes that a confirmation call has not been received and goes to Section 2.

Comment:

EP-AA-112-100-F-06, Step 2.1 Performance Step: 12 CIRCLE the appropriate station specific Account Name, Organization Name, First Name, Last Name, and Response to Hint Question from the table below.

Standard: Examinee circles the following:

• Exelon - TMI under Organization Name

• TMI under first name

• ERONS Activator under last name

• Exelon under Response to Hint Question Comment:

ILT 16-01 NRC JPM RA4 NUREG 1021, Revision 10

Appendix C Page 7of13 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-100-F-06, Step 2.2 Performance Step: 13 CIRCLE the appropriate Activation Scenario Number for the event from the table below ..

Standard: Examines circles the following:

• Scenario 1 - Actual Event Respond to Facility - For Alert, Site Area, or General Emergency, or Security Events with On Site ERO reporting.

Comment:

EXAMINER CUE: State: "You hear a busy signal" when the examinee attempts to make a phone call in the next step and after the 2nd attempt.

EP-AA-112-100;.F-06, Step 2.3 Performance Step: 14 DIAL the ERO Notification System Activation phone number: 1-877-220- 4911.

Standard: Examines dials 1-877-220-4911, recognizes that there is a busy signal, and continues on.

Comment:

EP-AA-112-100-F-06, Step 2.4 Performance Step: 15 If the number is busy or does not answer after a 2nd attempt, then PROCEED to Section 3 Initiate Activation I Termination of Notification System Using Standard Phone.

Standard: Examines goes to Section 3.

Comment:

ILT 16-01 NRC JPM RA4 NUREG 1021, Revision 10

Appendix C Page 8of13 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-100-F-06, Step 3.1 Performance Step: 16 CIRCLE the appropriate station specific User ID, Station Password number and Organization ID from the table below.

Standard: Examinee circles the following:

• TMI under Station

• 730145# under User ID

• 143311# under Password

• 730145# under Organization ID Comment:

EP-AA-112-100-F-06, Step 3.2 Performance Step: 17 CIRCLE the appropriate Activation I Termination Scenario Number for the event from the table below.

Standard: Examinee circles the following:

• Scenario 1 - Actual Event Respond to Facility - For Alert, Site Area, or General Emergency, or Security Events with On Site ERO reporting.

Comment:

EXAMINER CUE: When the examinee attempts to make a phone call in the next step, state: "Welcome to EverBridge Aware. Please enter user ID followed by the pound SIGN".

EP-AA-112-100-F-06, Step 3.3 Performance Step: 18 DIAL the Everbridge AWARE system activation phone number -

1-85 7-444-0443

.../ Standard: Examinee dials 1-857-444-0443.

Comment:

ILT 16-01 NRC JPM RA4 NUREG 1021, Revision 10

Appendix C Page 9of13 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER NOTE: Steps 3.4 and 3.5 are N/A.

EXAMINER CUE: ENSURE the examiner hangs up the phone before entering any data.

If the examinee enters a number other than 730145#, then state: "Number not recognized".

EP-AA-112-100-F-06, Step 3.6 Performance Step: 19 When the System prompts "Enter your USER ID followed by the

1. sign", then ENTER the User ID provided in step 3.1 .

.../ Standard: Examinee enters 730145#

Comment:

ILT 16-01 NRG JPM RA4 NU REG 1021, Revision 10

Appendix C Page 10of13 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER CUE: State: "Please enter your password followed by the pound BUTTON".

EP-AA-112-100-F-06, Step 3.7 Performance Step: 20 When the system prompts "Enter your Password followed by the #sign" then ENTER the Password provided in step 3.1 ..

.../ Standard: Examinee enters 143311#

Comment:

EXAMINER CUE: State: "Please enter your organization ID followed by the Pound BUTTON".

EP-AA-112-100-F-06, Step 3.8 Performance Step: 21 When the system prompts "Enter your Organization ID followed by the# sign", then ENTER the Organization ID provided in step 3.1 .

.../ Standard: Examinee enters 730145#

Comment:

ILT 16-01 NRC JPM RA4 NUREG 1021, Revision 10

Appendix C Page 11 of 13 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER CUE: State: "Select a template or scenario".

EP-AA-112-100-F-06, Step 3.9 Performance Step: 22 When prompted, "To select a template or scenario, Enter the ID followed by the# sign", then ENTER the ID provided in step 3.2.

For "Actual Event with Respond to Facility" PRESS 1 Then #

..J Standard: Examinee presses 1then #

Comment:

EXAMINER CUE: State: "Actual Event Respond to Facility, Press 1 to send the message now, or press 2 to select a different scenario".

EP-AA-112-100-F-06, Step 3.10 Performance Step: 23 The System will state the name of the scenario. To select this scenario press 1 to send the message now or 2 to select a different scenario.

If the event name is correct, then PRESS 1.

Standard:

Examinee presses 1.

Comment:

EXAMINER CUE: State: "Your message has been sent" Terminating Cue: When the time of the scenario broadcast has been sent.

STOP TIME:

ILT 16-01 NRC JPM RA4 NU REG 1021, Revision 10

Appendix C Page 12of13 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM RA4 Examinee's Name:

Date Performed:

Facility Examiner:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT 16-01 NRC JPM RA4 NU REG 1021, Revision 10

Appendix C Page 13 of 13 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• You are the Third Reactor Operator on shift.

• A General Emergency has been declared.

INITIATING CUE: You are directed to call out the Three Mile Island Emergency Response Organization IAW EP-AA-112-1 OO-F-06, ERO Notification or Augmentation.

TIME CRITICAL: No ILT 16-01 NRC JPM RA4 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: Three Mile Island Task No.: C000028 Task

Title:

Perform the "SHIFTLY CHECKS" JPM No.: ILT 16-01 NRC JPM IAW 1301-1, DATA SHEET 1 RA2 KIA

Reference:

2.2.12 (3. 7) Bank JPM: TMI09 CERT JPM RO A2 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: X Classroom Simulator X Plant READ CUE SHEET ON LAST PAGE 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.

Initial Conditions:

• Operating at Full Power

• No evolutions in progress Task Standard: Shift and Daily logs completed with out of specification readings identified.

Required Materials: Frozen Simulator@ Normal Power Ops General

References:

1301-1, SHIFT AND DAILY CHECKS, Revision 176 Handout: 1301-1, Sections 1.0 thru 9.0 and DATA SHEET 1, Sections A.6 thru A.22 (only)

Initiating Cue: It is night shift you are the 3rd CRO. The Control Room Supervisor has directed you to perform 1301-1, SHIFT AND DAILY CHECKS, DATA SHEET 1, Sections A.6 thru A.22, to verify the current status. For the purpose of this JPM, the simulator is FROZEN.

Time Critical Task: No Validation Time: 20 minutes ILT 16-01 NRC JPM RA2 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP

• IC 016 (or Temporary IC 55)

• Malfunctions o MS02A set to 1% severity o NN-2-7 Annunciator window input fails set to off.

• Overrides o 02A3M08-ZAOMU17PIPRS MU-17PI set to 33 o 06A3A6-ZAOTl978 TMP Tl978 set to 12.2 o 06A3A5-ZAOTl977 TMP Tl977 set to 10.3

• Once RB building pressure is greater than 2.0 psig, Freeze the simulator.

• Freeze the simulator for the duration of this ADMIN JPM.

ILT 16-01 NRC JPM RA2 NU REG 1021, Revision 10

Appendix C Page 3 of 12 Form ES-C-1 VERIFICATION OF COMPLETION (Denote Critical Steps with a check mark)

START TIME:

Initiating Cue: It is night shift you are the 3rd CRO. The Control Room Supervisor has directed you to perform 1301-1, SHIFT AND DAILY CHECKS, DATA SHEET 1, Sections A.6 thru A.22, to verify the current status.

For the purpose of this JPM, the simulator is FROZEN.

EVALUATORS NOTE: The examinee may choose to print the logs from the PPC.

Performance Step: 1 Locate/review procedure.

Standard: Reviews Sections 1.0 through 9.0 Evaluator CUE: Provide JPM handout and state "the handout contains only those sections of 1301-1 that apply to the task".

Comment:

1301-1 DATA Sheet 1, A.6 Performance Step: 2 RPST HOT Compare: RC4A-TE2 (A0590) with RC4A-TE3 (A0592) and RC4B-TE2 (A0591) with RC4B-TE3 (A0593)

• Does each comparison agree within+/- 1.75°F?

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.7 Performance Step: 3 RPS IMBALANCE

• Do Nl-5 (A0626), Nl-6 (A0627), Nl-7 (A0628) and Nl-8 (A0629) values all agree within 2.5%?

Standard: Circles Y Comment:

ILT 16-01 NRC JPM RA2 NU REG 1021, Revision 10

Appendix C Page 4 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 1301-1 DATA Sheet 1, A.8 Performance Step: 4 RPS TOTAL RCS FLOW

• Do RC14-DPT1 (A0602), RC14-DPT2 (A0603), RC14-DPT3 (A0604), RC14-DPT4 (A0605) values all agree within 7.2 MLB/hr?

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.9 Performance Step: 5 INTERMEDIATE RANGE FLUX

• Do Nl-3 (A0576) and Nl-4 (A0577) values agree within one-half log amp?

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.9 Performance Step: 6 INTERMEDIATE RANGE FLUX

• Do Nl-3 (A0580) and Nl-4 (A0581) SUR values agree within one-half DPM?

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.10 Performance Step: 7 ES WIDE RANGE RCS PRESSURE

• Do RC3A-PT-3 (A0505), RC3A-PT4 (A0506), RC3B-PT3 (A0507) values agree within 50 psi?

Standar,d: Circles Y Comment:

1301-1 DATA Sheet 1, A.11 Performance Step: 8 ES RB PRESSURE

• Do BS-PT-282 (A0101), BS-PT-285 (A0102) & BS-PT-288 (A0103) values agree within 0.5 psi?

Standard: Circles Y Comment:

ILT 16-01 NRC JPM RA2 NUREG 1021, Revision 10

Appendix C Page 5 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 1301-1 DATA Sheet 1, A.12 If Performance Step: 9 REACTOR BUILDING

• Is Reactor Building pressure greater than 1.0 psi vacuum and less than 2.0 psig?

Standard: Circles N Comment:

1301-1 DATA Sheet 1, A.13 Performance Step: 1O REACTOR BUILDING 4# ESAS ACTUATION

• Are all blue lights for channels RB1, 2 & 3 A&B (groups 1, 2, & 3) de-energized?

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.13 Performance Step: 11 REACTOR BUILDING 4# ESAS ACTUATION

• Are ESAS actuation channels RB1, 2 & 3 A&B all enabled?

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.14 Performance Step: 12 REACTOR COOLANT SYSTEM 1600# ESAS ACTUATION

• Are all blue lights for channels RC1, 2 & 3 A&B (groups 1

& 2) de-energized?

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.14 Performance Step: 13 REACTOR COOLANT SYSTEM 1600# ESAS ACTUATION

• Are ESAS actuation channels RC1, 2 & 3 A&B all enabled?

Standard: Circles Y Comment:

ILT 16-01 NRC JPM RA2 NU REG 1021, Revision 10

Appendix C Page 6 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 1301-1 DATA Sheet 1, A.15 Performance Step: 14 REACTOR COOLANT SYSTEM 500# ESAS ACTUATION

• Are ESAS actuation channels RC4, 5 & 6 A&B all enabled?

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.16 Performance Step: 15 REACTOR BUILDING 30# ESAS ISOLATION

• Are all blue lights for channels ,RB4, 5 & 6 A&B de-energized?

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.16 Performance Step: 16 REACTOR BUILDING 30# ESAS ISOLATION

• Are ESAS actuation channels RB4, 5 & 6 A&B all reset?

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.17 Performance Step: 17 REACTOR TRIP CONTAINMENT ISOLATION

• Are RTI actuation channels RT1, 2 & 3 A&B all enabled?

Standard: Circles Y Comment:

ILT 16-01 NRC JPM RA2 NUREG 1021, Revision 10

Appendix C Page 7 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 1301-1 DATA Sheet 1, A.18 Performance Step: 18 CORE FLOODING SYSTEM/CORE FLOOD TANK LEVEL Using the operable instruments only: (Circle Y/N for each)

• Is CF2-Ll1 (A0480) and CF2-Ll2 (A0481);::: 11.29 and:::;; 11.87 ft?

• Is A04 76 and A04 77 ;::: 585 psig and :::;; 615 psig?

• Is CF-V-1A open?

• Is CF2-Ll3 (A0482) and CF2-Ll4 (A0483) ;::: 11.29 and :::;; 11.87 ft?

• Is A0478 and A0479;::: 585 psig and:::;; 615 psig?

• Is CF-V-1 B open?

Standard: Circles Y for all Comment:

1301-1 DATA Sheet 1, A.18 Performance Step: 19 CORE FLOODING SYSTEM/CORE FLOOD TANK LEVEL Is CF-T-1A boron concentration between 2317 and 2850 PPM?

Standard: Circles Y CUE: When requested, CF-T-1A boron Concentration is 2400 PPM Comment:

1301-1 DATA Sheet 1, A.18 Performance Step: 20 CORE FLOODING SYSTEM/CORE FLOOD TANK LEVEL Is CF-T-1 B boron concentration between 2317 and 2850 PPM?

Standard: Circles Y CUE: When requested, CF-T-1 B boron Concentration is 2450 PPM Comment:

ILT 16-01 NRC JPM RA2 NUREG 1021, Revision 10

Appendix C Page 8 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 1301-1 DATA Sheet 1, A.19 Performance Step: 21 MAKEUP TANK LEVEL & PRESSURE

• Do CPT #A0498 and A0426 agree within 2 inches and MU14/RC1-LR CH1 & MU-Ll-778A agree within 3 inches?

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.19

.../ Performance Step: 22 MAKEUP TANK LEVEL & PRESSURE

• Record local MU tank pressure indication, MU-Pl-1752.

Standard: Records MU tank pressure indication, MU-Pl-1752.

CUE: When requested, local MU tank pressure is 26.5 psig Comment:

.../ 1301-1 DATA Sheet 1, A.19 Performance Step: 23 MAKEUP TANK LEVEL & PRESSURE

• Do A1028 and MU17-PI agree with the local MU Tank pressure indication (MU-Pl-1752) within 3 psi?

Standard: Circles N Comment:

1301-1 DATA Sheet 1, A.20 Performance Step: 24 PRESSURIZER LEVEL

• Do RC-LT-777 (A1029), RC1-LT1 (C1720) and RC1-LT3 (C1722) values agree within 12 inches? (Circle Y/N)

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.20 Performance Step: 25 PRESSURIZER LEVEL

• Do MU14/RC1-LR CH2 (LT1 or LT3) and its corresponding XMTR on the PPC (C1720 or C1722) agree within 1O"?

Standard: Circles Y Comment:

ILT 16-01 NRC JPM RA2 NU REG 1021, Revision 10

Appendix C Page 9 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 1301-1 DATA Sheet 1, A.20 Performance Step: 26 PRESSURIZER LEVEL

• Do RC-Ll-777A and PPG point A1029 agree within 10"?

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.20 Performance Step: 27 PRESSURIZER LEVEL

• Is pressurizer level between 80 to 385 inches?

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.21 Performance Step: 28 PRESSURIZER TEMPERATURE

• Record Pressurizer temp RC2-TI (CC)

Standard: Records Pressurizer temp RC2-TI (CC)

Comment:

1301-1 DATA Sheet 1, A.21 Performance Step: 29 PRESSURIZER TEMPERATURE NOTE PPG A0504 is the non-selected pzr temperature instrument.

• Do RC2-TE1 & RC2-TE2 values agree within 20LiF?

Standard: Circles Y Comment:

1301-1 DATA Sheet 1, A.22 Performance Step: 30 SATURATION MARGIN MONITOR

• Record RCS Loop A sat margin RC-Tl-977 (PCL)

Standard: Records RCS Loop A sat margin RC-Tl-977 (PCL)

Comment:

ILT 16-01 NRC JPM RA2 NUREG 1021, Revision 10

Appendix C Page 10 of 12 Form ES-C-1 VERIFICATION OF COMPLETION 1301-1 DATA Sheet 1, A.22 Performance Step: 31 SATURATION MARGIN MONITOR

• Record RCS Loop B sat margin RC-Tl-978 (PCL)

Standard: Records RCS Loop B sat margin RC-Tl-978 (PCL)

Comment:

1301-1 DATA Sheet 1, A.22

.Y Performance Step: 32 SATURATION MARGIN MONITOR

• Do RC-Tl-978, CPT #A0406, RC-Tl-977, & CPT #A0938 all agree within 6.51 F?

Standard: Circles N Comment:

Terminating Cue: When DATA SHEET 1, A.6 THRU A.22 have been returned to the CRS: Evaluation on this JPM is complete.

Time: _ _ _ _ _ __

ILT 16-01 NRC JPM RA2 NU REG 1021, Revision 10

Appendix C Page 11 of 12 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM RA2 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT 16-01 NRC JPM RA2 NUREG 1021, Revision 10

Appendix C Page 12of12 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• Operating at Full Power

• No evolutions in progress INITIATING CUE: It is night shift you are the 3rd CRO. The Control Room Supervisor has directed you to perform 1301-1, SHIFT AND DAILY CHECKS, DATA SHEET 1, Sections A.6 thru A.22, to verify the current status. For the purpose of this JPM, the simulator is FROZEN.

TIME CRITICAL: No ILT 16-01 NRC JPM RA2 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: 22001027 Task

Title:

PERFORM A TRANSIENT JPM No.: ILT 16-01 NRC JPM LEAK RATE CALCULATION RA1-2 KIA

Reference:

2.1.23 4.3 I 4.4 Bank JPM: TQ-TM-104-ADM-OS24-J102 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom X Simulator Plant READ CUE SHEET ON LAST PAGE 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.

Initial Conditions:

• 100% power

• You have been assigned the duties of the Unit Reactor Operator (URO)

• The examiner will act as the Control Room Supervisor (CRS)

Task Standard: Calculate a leak rate of between 80 and 81 gpm.

Required Materials:

• OS-24, CONDUCT OF OPERATIONS DURING ABNORMAL AND EMERGENCY EVENTS, Rev. 28

• Calculator General

References:

• OS-24, CONDUCT OF OPERATIONS DURING ABNORMAL AND EMERGENCY EVENTS, Rev. 28 ILT16-01 NRC JPM RA1-2 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: The following data has been obtained from console indications and the plant computer:

DATA RECORDING TIME 0300 0303 0310 PRESSURIZER LEVEL 220inches 220inches 210inches (RC-Ll-777A I PPC C4017)

MAKEUP TANK LEVEL 86inches 84inches 80inches (MU-Ll-778A I PPC A0498)

RCS Tave 579.3'F 579.2'F 578.8'F (RC12-TIA I PPC A5066)

Total Water Added to the N/A 60 gal 420 gal Makeup Tank from 0300

• A step change in leakage is suspected at 0303 and the feed rate was raised on the batch controller as a result.

• The CRS has directed you to perform a Transient RCS Leakrate Calculation IAW OS-24, Attachment F, that will most accurately determine CURRENT leak rate.

Time Critical Task: No Validation Time: 10 minutes ILT16-01 NRC JPM RA 1-2 NUREG 1021, Revision 10

Appendix C Page 3 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATORS CUE: Role Play as CRS: When the examinee has requested a copy of the appropriate procedure, HAND a copy of OS-24, Attachment F to the examinee.

EVALUTORS NOTE: The longer the time interval between collecting data points, the more reliable the leakrate estimate will be. At a minimum leak rates should not be calculated for time intervals of< 5 minutes.

Performance Step: 1 Obtain copy of appropriate procedures.

Standard: Examinee will request a copy of OS-24, Attachment F.

Comment:

Performance Step: 2 Determine sets of data to use

'\/ Standard:

• Examinee determines that from 0300-0303 is less than 5 minutes and therefore not accurate.

• Examinee determines that a step rise in leak rate occurred at 0303, and therefore going from 0300-0310 will not be the most accurate leak rate calculated.

• Examinee determines that a larger leak rate is occurring in the 7 minute timeframe between 0303 and 0310, and uses those data points.

Comment:

ILT16-01 NRC JPM RA1-2 NUREG 1021, Revision 10

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION

"'./ Performance Step: 3 Determine Pressurizer level change.

(LiPL) * (12) =

(220-210) (12) = 120 Standard: Examinee calculates Pressurizer level change over the time period given by; Pressurizer level initial =220" Pressurizer level final =21 O" Examinee determines the level change in inches (10) and multiplies this number by 12.

120 Comment:

"'./ Performance Step: 4 Determine Makeup Tank level change (LiMTL) * (30) =

(84-80) (30) = 120 Standard: Examinee calculates Makeup Tank level change over the time period given by:

Makeup Tank level initial = 84" Makeup Tank level final= 80" Examinee then records this level change (4) in inches and multiplies this number by 30.

120 Comment:

ILT16-01 NRCJPM RA1-2 NU REG 1021, Revision 10

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION

.,,/ Performance Step: 5 Determine RCS Tave temperature change.

(~Tavg)*(COEFF) =

(579.2-578.8) (95) = 38 Standard: Examines calculates RCS Tave change over the time period given by:

RCS Tave initial - RCS Tave final Examines then records this temperature change in (0.4)°F and multiply this number by a coefficient from the Table on the bottom of Attachment F. (94 Gal/'F) 38 Comment:

Performance Step: 6 Determine the number of gallons added to the MU/RCS systems.

Total Gallons added - gallons added during 1st 3 minutes=

360 Gallons Standard: Examines during the period of time the calculation is in progress observes and records ALL inventory added to the RCS.

Then records this makeup to the RCS in gallons 360 Comment:

Performance Step: 7 Determine the total time period between the start and finish of the Leak Rate determination.

TIME final - TIME initial.

0310 - 0303 = 7 minutes Standard: Examines calculates the time period for the Leak Rate determination by; Then records this time change in minutes r

Comment:

ILT16-01 NRC JPM RA1-2 NU REG 1021, Revision 10

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION "1 Performance Step: 8 Determine the transient RCS Leak Rate.

Standard: Examinee calculates TOTAL RCS Leak Rate using Attachment F formula; 80.3 gpm. (80-81 gpm)

Comment:

EVALUATOR NOTE: When the examinee has finished the calculation and is reporting the Total Leak Rate to the CRS, respond with "I understand you have calculated Total RCS Leak Rate at (whatever number the examinee uses) gpm."

Terminating Cue: When the Total RCS Leak Rate number is delivered to the CRS, this JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME: N EVALUATION NOTE:

• If the student incorrectly uses the data for 0300 and 0303, they will come up with 36.3 GPM

• If the student incorrectly uses the data for 0300 and 0310, they will come up with 67 .2 GPM

• Calculated Leak Rate is 80.3 gpm. (0303 to 0310)

Leak Rate== [(flPL)*(12) + (flMTL)*(30) - (flTavg)*(COEFF) +GAL ADD] I flTIME Leak Rate= ((10x12) + (4x30) - (0.4x95) + 360)/7 Leak Rate= (120+120-38+360)/7 Leak Rate = 562/7 Leak Rate = 80.28 gpm ILT16-01 NRC JPM RA1-2 NUREG 1021, Revision 10

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 Cert JPM Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT16-01 NRC JPM RA1-2 NU REG 1021, Revision 10

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• 100% power

• You have been assigned the duties of the Unit Reactor Operator (URO)

• The examiner will act as the Control Room Supervisor (CRS)

INITIATING CUE: The following data has been obtained from console indications and the plant computer:

DATA RECORDING TIME 0300 0303 0310 PRESSURIZER LEVEL 220inches 220inches 210inches (RC-Ll-777A/ PPC C4017)

MAKEUP TANK LEVEL 86inches 84inches BO inches (MU-Ll-778A I PPC A0498)

RCS Tave 579.3°F 579.2"F 578.8°F (RC12-TIA I PPC A5066)

Total Water Added to the N/A 60 gal 420 gal Makeup Tank from 0300

• A step change in leakage is suspected at 0303 and the feed rate was raised on the batch controller as a result.

• The CRS has directed you to perform a Transient RCS Leakrate Calculation IAW OS-24, Attachment F, that will most accurately determine CURRENT leak rate.

TIME CRITICAL: No ILT16-01 NRC JPM RA1-2 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: 62201020 Task

Title:

Shutdown Margin for Low JPM No.: ILT 16-01 NRC JPM Temperature Conditions RA1-1 KIA

Reference:

2.1.43 (4.1/4.3) NewJPM Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom X Simulator Plant READ CUE SHEET ON LAST PAGE 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.

Initial Conditions:

• RCS temperature 350°F at 1300 on 6/30/17, which coincides with 20 hours0.833 days <br />0.119 weeks <br />0.0274 months <br /> after shutdown from 100%.

• Previous power change was refueling outage 16 months ago.

• 600 EFPD

• Boron Concentration is 220 ppm

• Boron Depletion factor from the PPC is .8006

• Xenon Reactivity Worth from the PPC is -2.638 %~k/k

• The Control Rod in location 5-9 is stuck, fully withdrawn Task Standard: Calculate a Quantitative shutdown margin for this low temperature situation, and determine that the SOM will not be more negative than -1

%~k/k ILT16-01 NRC JPM RA1-1 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Required Materials:

• OP-TM-300-000, REACTIVITY AND POWER DISTRIBUTION CALCULATIONS, Rev 8

• OP-TM-300-206, SHUTDOWN MARGIN FOR LOW TEMPERATURE CONDITIONS, Rev 3

• OP-TM-300-401, INOPERABLE ROD WORTH, Rev 1

• Calculator

• Ruler General

References:

• OP-TM-300-000, REACTIVITY AND POWER DISTRIBUTION CALCULATIONS, Rev 8

• OP-TM-300-206, SHUTDOWN MARGIN FOR LOW TEMPERATURE CONDITIONS, Rev 3

• OP-TM-300-401, INOPERABLE ROD WORTH, Rev 1 Initiating Cue: The Shift Manager has directed you to calculate a QUANTITATIVE (Determine a Numerical Value) assessment of Shutdown Margin (SOM),

IAW OP-TM-300-206 for a temperature of 350°F, and the parameters provided in the cue sheet.

Time Critical Task: No Validation Time: 25 mins ILT16-01 NRC JPM RA1-1 NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet PAPERWORK SETUP

1. Print copies of:

A. OP-TM-300-000, REACTIVITY AND POWER DISTRIBUTION CALCULATIONS B. OP-TM-300-206, SHUTDOWN MARGIN FOR LOW TEMPERATURE CONDITIONS

i. Sign off Prerequisites C. OP-TM-300-401, INOPERABLE ROD WORTH ILT16-01 NRC JPM RA1-1 NU REG 1021, Revision 10

Appendix C Page 4of11 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATORS CUE: The Shift Manage direct you to calculate a QUANTITATIVE (Determine a Numerical Value) assessment of Shutdown Margin (SOM}, IAW OP-TM-300-206 for a temperature of 350

°F, and the parameters provided in the cue sheet.

OP-TM-300-206, Precautions, Limitations, and Prerequisites Performance Step: 1 Examines reviews precautions, limitations, and prerequisites Standard: Examines reviews section 3.0 of OP-TM-300-206 Comment:

OP-TM-300-206, Step 4. 1 Performance Step: 2 DETERMINE whether a qualitative or quantitative assessment of Shutdown Margin is desired.

Standard: Per SM Direction is to perform a Quantitative assessment of SDM Comment:

OP-TM-300-206, Step 4. 1.1 Performance Step: 3 If a qualitative assessment of Shutdown Margin is desired, the DETERMINE Shutdown margin IAW section 4.2.

Standard: Examines determines a qualitative assessment of Shutdown Margin is not desired, and N/A's the step.

Comment:

ILT16-01 NRCJPM RA1-1 NUREG 1021, Revision 10

Appendix C Page 5of11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-206, Step 4.1.2 Performance Step: 4 If a quantitative assessment of Shutdown Margin is desired, the DETERMINE Shutdown margin IAW section 4.3.

Standard: Examinee determines a quantitative assessment of Shutdown Margin is desired, signs off the step. The examinee will go to section 4.3 Comment:

EXAMINER NOTE: If the examinee asks, there is no Reactor Engineer or DTSQA-approved software available.

OP-TM-300-206, Step 4.3.1 Performance Step: 5 PERFORM calculation per Attachment 7.3 and instructions in Attachment 7.4 or DTSQA-approved software.

Standard:

Comment:

OP-TM-300-206, Attachment 7.3 Performance Step: 6 CALCUATION FOR A SOM AT: DATE TIME Standard: Examinee fills in 06/30/17 and 1300 from the cue sheet.

Comment:

OP-TM-300-206, Attachment 7.3, Step 1 Performance Step: 7 Tave (<530°F)

Standard: Examinee fills in 350 °F from the cue sheet.

Comment:

ILT16-01 NRC JPM RA1-1 NUREG 1021, Revision 10

Appendix C Page 6 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-206, Attachment 7.3, Step 2 Performance Step: 8 Cycle burnup Standard: Examinee fills in 600 EFPD from the cue sheet.

Comment:

OP-TM-300-206, Attachment 7.3, Step 3a Performance Step: 9 Measured Boron Concentration Standard: Examinee fills in 220 ppm from the cue sheet.

Comment:

OP-TM-300-206, Attachment 7.3, Step 3b Performance Step: 1O Boron Depletion Correction Factor Standard: Examinee fills in .8006 from the cue sheet Comment:

.../ OP-TM-300-206, Attachment 7.3, Step 3c Performance Step: 11 Corrected Boron Concentration (3a X 3b) =

Standard: Examinee divides 220 ppm X .8006 = 176.13 ppm (BAND: 176.1 to 176.132)

Comment:

OP-TM-300-206, Attachment 7.3, Step 4 Performance Step: 12 Excess Reactivity (Fig 1.)

.../ Standard: Examinee uses figure 1 of OP-TM-300-000 and gets a value of

-.6 %L'.lk/k (Band: .5 to .7%L'.lk/k)

Comment:

ILT16-01 NRC JPM RA1-1 NUREG 1021, Revision 10

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-206, Attachment 7.3, Step 5 Performance Step: 13 Xenon Reactivity Worth (PPC, Reactor Engr.)

Standard: Examinee fills in -2.638%~k/k from the cue sheet.

Comment:

OP-TM-300-206, Attachment 7.3, Step 6a Performance Step: 14 Samarium and Plutonium Buildup Reactivity Worth (Fig 15):

Time since shutdown hrs Standard: Examinee fills in 20 hours0.833 days <br />0.119 weeks <br />0.0274 months <br /> from the cue sheet.

Comment:

OP-TM-300-206, Attachment 7.3, Step 6b Performance Step: 15 Samarium and Plutonium Buildup Reactivity Worth (Fig 15):

Reactivity due to samarium and plutonium buildup.

"./ Standard: Examinee uses OP-TM-300-000, Figure 15 and fills in

-0.055%~k/k. (Band: -0.05 to -0.06%~k/k)

Comment:

OP-TM-300-206, Attachment 7.3, Step 7a Performance Step: 16 Inoperable Control Rods:

No. of known inoperable rods (>0%WD)

Standard: Examinee fills in 1 from the cue sheet.

Comment:

ILT16-01 NRC JPM RA1-1 NUREG 1021, Revision 10

Appendix C Page 8of11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-206, Attachment 7.3, Step 7b Performance Step: 17 Inoperable Control Rods:

Total inoperable rod worth (OP-TM-300-401)

I/ Standard: Examinee performs OP-TM-300-401 section 1. Examinee identifies that the rod in location 5-9 is fully withdrawn and uses attachment 7.3 of OP-TM-300-000 to determine the worth of the control rod in that position is 0.851 %~k/k. Examinee fills in line 7b with 0.851%~k/k and attaches Attachment 7.1 of OP-TM-300-401 to OP-TM-300-206.

Comment:

OP-TM-300-206, Attachment 7.3, Step 8 Performance Step: 18 Reactivity Addition Due to Reduced Tave (Fig. 17)

If Standard: Examinee uses OP-TM-300-000, Figure 17 and fills in 3.8%~k/k.

(BAND: 3. 7 to 3.9%~k/k)

Comment:

I/ OP-TM-300-206, Attachment 7.3, Step 9a Performance Step: 19 Boron Reactivity Worth at Reduced Tave:

Reduced temperature Inverse Boron Worth (Fig. 7)

Standard: Examinee uses OP-TM-300-000, Figure 7 and fills in a value of 104 ppmB/%~k/~ (BAND: 102 to 106 ppmB/%~k/k)

Comment:

OP-TM-300-206, Attachment 7.3, Step 9b Performance Step: 20 Total Worth (3c/9a) x (-1) =

I/ Standard: Total Worth (176.13I104) x (-1) =-1.69%~k/k (BAND: -1.73 to -1.66)

Comment:

ILT16-01 NRC JPM RA1-1 NU REG 1021, Revision 10

Appendix C Page 9 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-206, Attachment 7.3, Step 10 Performance Step: 21 Shutdown Margin (4 + 5 + 6b + ?b + 8 + 9b) =

-I Standard: Shutdown Margin (0.6 + (-2.638) + (-0.055) + 0.851 + 3.8 +

(-1.69) =0.868%~k/k (BAND: 0.62 to 1.1)

Comment:

OP-TM-300-206, Attachment 7.3, Acceptance Criteria Performance Step: 22 Examinee determines that the calculated SOM does not meet the acceptance criteria, and notifies the examiner.

Standard: Examinee determines that the calculated SOM does not meet the acceptance criteria, and notifies the examiner.

Comment:

Terminating Cue: This JPM can be terminated after the examinee completes the calculation and determines that SOM is NOT satisfied.

STOP TIME: TIME CRITICAL STOP TIME:

ILT16-01 NRC JPM RA1-1 NUREG 1021, Revision 10

Appendix C Page 10of11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM RA1-1 Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT16-01 NRC JPM RA1-1 NUREG 1021, Revision 10

Appendix C Page 11 of 11 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• RCS temperature 350°F at 1300 on 6/30/17, which coincides with 20 hours0.833 days <br />0.119 weeks <br />0.0274 months <br /> after shutdown from 100%.

• Previous power change was refueling outage 16 months ago.

• 600 EFPD

• Boron Concentration is 220 ppm

• Boron Depletion factor from the PPC is .8006

• Xenon Reactivity Worth from the PPC is -2.638 o/oilk/k

• The Control Rod in location 5-9 is stuck, fully withdrawn INITIATING CUE: The Shift Manager has directed you to calculate a QUANTITATIVE (Determine a Numerical Value) assessment of Shutdown Margin (SOM), IAW OP-TM-300-206 for a temperature of 350 °F, and the parameters provided in the cue sheet.

TIME CRITICAL: No ILT16-01 NRC JPM RA1-1 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: 21101013 Task

Title:

Emergency Borate Using the BAMT JPM No.: ILT 16-01 NRC JPM A as the Source - Alternate Path KIA

Reference:

004 A2.14 3.8/3.9 Bank JPM: TQ-TM-104-211-J110 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom - - - Simulator X Plant READ CUE SHEET ON LAST PAGE 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.

Initial Conditions:

• The plant is stable post trip, with one control rod stuck out.

• You are the URO

• The examiner will act as the CRS and ARO

• The booth operator will be the Auxiliary Operator Task Standard: Initiate an alternate method of emergency boration.

Required Materials:

• OP-TM-EOP-010, 'Emergency Procedure Rules, Guides and Graphs', Rev 19.

General

References:

• OP-TM-EOP-010, 'Emergency Procedure Rules, Guides and Graphs', Rev 19.

Initiating Cue: As the URO, Initiate Emergency Boration IAW Rule 5, Emergency Boration Time Critical Task: No Validation Time: 4 minutes ILT16-01 NRC JPM A NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP

1. Reset the simulator to IC 246 or similar 100% IC.

2. Run the setup:

~ Initialize the simulator and go to run.

~ INSERT malfunction RD0202 IMMEDIATELY, stuck rod Group 4.

~ OVERRIDE MU-V-148 Open Pushbutton to OFF o 02A5S77-ZDIPBOMUV14B

~ TRIP the Rx and carry out immediate manual actions.

~ Stabilize the plant post trip

~ INSERT malfunction MUR69, MU-V-14A Breaker Open

~ MONITOR:

o MUMMT - Make Up Tank Mass o MUBMUT1 - Make Up Tank Boron Concentration

3. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.

4. This completes the setup for this JPM.

ILT16-01 NRC JPM A NUREG 1021, Revision 10

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATORS CUE: As the CRS, direct the examinee to initiate Emergency Boration IAW Rule 5.

OP-TM-EOP-010, Rule 5, Step 1 Performance Step: 1 WAA T one of the following conditions exist:

• 1% dk/k SHUTDOWN has been achieved for the expected plant condition IAW Figure 10 of OP-TM-300-000, "Reactivity and Power Distribution Calculations", or OP-TM-300-205, "Shutdown Margin for Hot Shutdown Conditions", or OP-TM-300-206, "Shutdown Margin for Low Temperature Conditions."

• LPI > 1250 gpm per line

• Tavg > 525 'F and stable or rising and all Control Rods are inserted, and Neutron flux is lowering as expected.

then emergency boration may be terminated.

Standard: The examinee will read the step, and leave it open. It will be not applicable for this JPM.

Comment:

OP-TM-EOP-010, Rule 5, Step 2 Performance Step: 2 VERIFY a MU pump is operating.

Standard: Examinee verifies that MU-P-1 B is operating.

Comment:

BOOTH CUE: If the examinee contacts the Primary AO to Manually open MU-V-14A/B, wait 10 seconds and report that MU-V-14A/8 will not manually operate.

ILT16-01 NRC JPM A NUREG 1021, Revision 10

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-EOP-010, Rule 5, Step 3 Performance Step: 3 Perform one of the following:

• OPEN MU-V-14A, Standard: Examinee recognizes MU-V-14A does not have power.

Comment:

OP-TM-EOP-010, Rule 5, Step 3 Performance Step: 4 Perform one of the following:

• OPEN MU-V-14B, Standard: Examinee presses the MU-V-14B Open PB. Examinee diagnoses that MU-V-14B is not opening and informs the CRS.

Comment:

OP-TM-EOP-010, Rule 5, Step 3 Performance Step: 5 Perform one of the following:

• PERFORM Guide 1 "Emergency Boration Backup Methods."

Standard: Examinee goes to GUIDE 1 to perform Emergency Boration Comment:

ILT16-01 NRC JPM A NU REG 1021, Revision 10

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION Alternate Path Begins EXAMINER NOTE: There are two possible backup sources for boration, the BAMT and the RBAT.

EXAMINER CUE: If the examinee asks the backup Emergency Boration source, inform them that the BAMT is the source.

OP-TM-EOP-010, Guide 1, Step A.1 v Performance Step: 6 If the backup Emergency Boration source is the BAMT, then perform the following:

OPEN MU-V-51 Standard: Examinee pushes the open pushbutton for MU-V-51 and observes the red "open" light comes on and the green "close" light goes out.

Comment:

OP-TM-EOP-010, Guide 1, Step A.2 v Performance Step: 7 START boric acid pumps CA-P-1A and CA-P-18 Standard: Examinee starts CA-P-1A by turning the control switch to the start position and observes the red light comes on and the green light goes out pump.

Examinee starts CA-P-1 B by turning the control switch to the start position and observes the red light comes on and the green light goes out pump Comment:

Terminating Cue: Once MU-V-51 is open and CA-P-1A and 1B are running, the JPM can be terminated.

STOP TIME:

ILT16-01 NRC JPM A NU REG 1021, Revision 10

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM A Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT16-01 NRC JPM A NU REG 1021, Revision 10

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• The plant is stable post trip, with one control rod stuck out.

• You are the URO

• The examiner will act as the CRS and ARO

• The booth operator will be the Auxiliary Operator INITIATING CUE: As the URO, Initiate Emergency Boration IAW Rule 5, Emergency Bo ration TIME CRITICAL: No ILT16-01 NRC JPM A NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: EOPG21001 Task

Title:

REMOVING MU-P-1 B FROM JPM No.: ILT 16-01 NRC JPM B SERVICE KIA

Reference:

004 A4.11 3.4/3.3 Bank JPM: TQ-TM-104-211-J108 Examines: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom - - - Simulator X Plant READ CUE SHEET ON LAST PAGE 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.

Initial Conditions:

• You are assigned the duties of the Unit Reactor Operator (URO).

• The Plant is at 100% power, with ICS in full automatic.

• MU-P-1 B has developed a leak on the inboard seal, which has increased in severity over the past 3 days.

• The necessary repair parts have now been assembled, and it is necessary to remove MU-P-1 B from service using MU-P-1A to affect the repairs.

• MU-P-1A cooling water is being supplied from NSCCW.

Task Standard: MU-P-1A is supplying seal injection, and MU-P-1B is secured. IC-P-1B is running.

Required Materials:

• OP-TM-211-433, Removing MU-P-1B From Service with procedure completed up to Section 4.0, Main Body

• OP-TM-211-437, Supplying Seal Injection From MU-P-1A

• OP-TM-541-438, Removing IC-P-1A From Service ILT16-01 NRC JPM B NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet General

References:

• OP-TM-211-433, Removing MU-P-1 B From Service

• OP-TM-211-437, Supplying Seal Injection From MU-P-1A

• OP-TM-211-000, Makeup And Purification System

• OP-TM-543-439, Swapping MU-P-1A Cooling to NS

• OP-TM-543-401, Operating DC-P-1A For Other Than Decay Heat Removal Operations

• OP-TM-541-438, Removing IC-P-1A From Service

• OP-TM-211-440, Supplying Seal Injection From MU-P-1C Initiating Cue: The Control Room Supervisor has directed you to remove MU-P-1 B from service IAW OP-TM-211-433 Time Critical Task: No Validation Time: 25 minutes SIMULATOR SETUP

1. Reset the simulator to IC 16 or equivalent 100% power IC

2. Place simulator in FREEZE.

A No malfunctions required to complete the task.

3. This completes the setup for this JPM.

ILT16-01 NRC JPM B NUREG 1021, Revision 10

Appendix C Page 3 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Steps with a check mark Denote Critical Steps)

START TIME:

EVALUATORS CUE: Provide examinee copy of OP-TM-211-433. Prerequisites have been completed and signed off (Step 3.3.1).

OP-TM-211-433 Performance Step 1: Examinee reviews procedure (purpose, material and special equipment, precautions, limitations, and prerequisites) and proceeds to Section 4.0, Main Body Standard: Procedure is reviewed and proceeds to Section 4.0, Main Body Comment:

EXAMINER CUE: Once determined that MU-P-1A is available for supplying seal injection, provide a blank copy OP-TM-211-437, Supplying Seal Injection from MU-P-1A OP-TM-211-433, Step 4.1 Performance Step 2: If MU-P-1A is available, then INITIATE OP-TM-211-437 Supplying Seal Injection from MU-P-1A.

Standard: Examinee determines MU-P-1A is available and enters OP-TM-211-437, Supplying Seal Injection from MU-P-1 A and obtains a copy of OP-TM-211-437.

Comment:

OP-TM-211-437 Performance Step 3: Examinee reviews procedure (purpose, material and special equipment, precautions, limitations, and prerequisites) and proceeds to Section 4.0, Main Body Standard: Procedure is reviewed and proceeds to Section 4.0, Main Body Comment:

ILT16-01 NRC JPM B NUREG 1021, Revision 10

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-437 Performance Step 4: Examines reviews procedure (purpose, material and special equipment, precautions, limitations, and prerequisites) and proceeds to Section 4.0, Main Body Standard: Procedure is reviewed and proceeds to Section 4.0, Main Body Comment:

OP-TM-211-437 Step 4.1 Performance Step 5: If MU-P-1A may be in service> 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br />, then INITIATE OP-TM-543-439, Swapping MU-P-1A Cooling To NS.

Standard: OP-TM-543-439, Swapping MU-P-1A Cooling To NS will be initiated.

Comment:

OP-TM-211-437 Step 4.2 EXAMINER NOTE: Steps 4.2.1through4.2.7 will be verified. Use of OP-TM-543-401 to start Decay Closed Cooling is NOT required OP-TM-211-437 Step 4.2.8 v Performance Step 6: START MU-P-1A (CC).

Standard: MU-P-1A is Placed in start position and left in Normal After Start.

Verify Red light ON, Green light is NOT LIT Comment:

OP-TM-211-437 Step 4.2.9 Performance Step 7: VERIFY the following:

• D-1-4, MU P 1A/B/C GEAR LUBE OIL PRESS LO is Clear.

• MU-P-1A/B ES Indication (PCR) is Blue I On.

• Makeup Flow (MU24AFI) (CC) is stable.

• Seal Injection Flow (MU42 Fl)(CC) is stable (36 - 40 gpm).

• MU Pump Discharge Pressure (MU2Pl){CC) is stable Standard: Examines verifies indications.

Comment:

ILT16-01 NRC JPM B NU REG 1021, Revision 10

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-437 Step 4.3 "I/ Performance Step 8: PLACE MU-P-1 Bin Normal After Stop Standard: MU-P-1 Bis placed in Normal After Stop Verify Green light is ON, Red light NOT LIT Comment:

OP-TM-211-437 Step 4.3.1 Performance Step 9: VERIFY the following:

• D-1-4, MU P 1A/B/C GEAR LUBE OIL PRESS LO is Clear.

• Makeup Flow (MU24AFI) (CC) is stable.

• Seal Injection Flow (MU42 Fl)(CC) is stable (36 - 40 gpm).

• MU Pump Discharge Pressure (MU2Pl)(CC) is stable Standard: Above indications are verified Comment:

OP-TM-211-437 Step 4.4 Performance Step: INITIATE OP-TM-541-438, Remove IC-P-1A from Service (to start IC-P1 B and place IC-P-1 A in standby).

Standard: OP-TM-541-438, Remove IC-P-1A from Service is entered.

Comment:

OP-TM-541-438 Performance Step: Examines reviews procedure (purpose, material and special equipment, precautions, limitations, and prerequisites) and proceeds to Section 4.0, Main Body Standard: Procedure is reviewed and proceeds to Section 4.0, Main Body Comment:

EXAMINER NOTE: When examinee requests OP-TM-541-438, REMOVE IC-P-1A from service, hand them the provided copy.

OP-TM-541-438 Step 4.1.1 "I/ Performance Step: PLACE IC-P-1 B-EX1 in Normal-After-Start Standard: IC-P-1 Bis started by placing IC-P-1 B-EX1 in Normal-After-Start Verify Red light ON, Green light is NOT LIT Comment:

ILT16-01 NRC JPM B NUREG 1021, Revision 10

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-541-438 Step 4.1.2 and 4.1.3

../ Performance Step: VERIFY system flow is stable on IC-5FI (CR) and PLACE IC-P-1A-EX1 in Normal-After-Stop Standard: System flow is verified to be stable and IC-P-1A is places in Normal-After-Stop and returns to OP-TM-211-437 Verifies IC-P-1A Green Light LIT, Red Light OFF Comment:

OP-TM-211-437 Step 4.4.1 Performance Step: VERIFY IC-P-1 Bis operating Standard: IC-P-1 Bis verified to be operating by verifying Red light is ON and Green light NOT LIT and returns to OP-TM-211-433 Comment:

OP-TM-211-433 Step 4.2 Performance Step: If MU-P-1A is not available, then INITIATE OP-TM-211-440 Supplying Seal Injection from MU-P-1 C.

Standard: Step 4.2 is N/A Comment:

OP-TM-211-433 Step 4.3 Performance Step: VERIFY MU-P-1 Bis shutdown Standard: Examines verifies MU-P-1 B Green Light LIT, Red Light OFF Comment:

Examiner CUE: When asked, inform examinee you will make appropriate logs OP-TM-211-433 Step 4.4 Performance Step: NOTIFY Control Room Supervisor and LOG MU-P-1 B removed from service Standard: Examines Notifies CRS and Logs MU-P-1 B removed from service Comment:

Terminating Cue: JPM may be terminated when examinee has reported Seal Injection is being supplied from MU-P-1A, IC-P-18 is running, and MU-P-1 B is shutdown STOP TIME:

ILT16-01 NRC JPM B NUREG 1021, Revision 10

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM B Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT16-01 NRC JPM B NUREG 1021, Revision 10

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• You are assigned the duties of the Unit Reactor Operator (URO).

• The Plant is at 100% power, with ICS in full automatic.

• MU-P-1 B has developed a leak on the inboard seal, which has increased in severity over the past 3 days.

• The necessary repair parts have now been assembled, and it is necessary to remove MU-P-1 B from service using MU-P-1A to affect the repairs.

• MU-P-1A cooling water is being supplied from NSCCW INITIATING CUE: The Control Room Supervisor has directed you to remove M U-P-1 B from service IAW OP-TM-211-433.

TIME CRITICAL: No ILT16-01 NRC JPM B NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: 64201006 Task

Title:

Respond to an Inadvertent ESAS JPM No.: ILT 16-01 NRC JPM C Actuation-Alternate Path KIA

Reference:

006A2.13 3.7/4.2 Modified JPM: TQ-TM-104-A46-J100 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom - - - Simulator X Plant READ CUE SHEET ON LAST PAGE 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.

Initial Conditions:

• 100% power

• You are the URO

• The examiner will act as the ARO and CRS

• The ICO will act as the Auxiliary Operators in the plant.

Task Standard: Makeup Pump 1C is secured, MU-V-168 is throttled open to establish MU PUMP FLOW of> 115 gpm.

Required Materials:

• OP-TM-AOP-046, 'Inadvertent ESAS Actuation', Rev 6 General

References:

• OP-TM-AOP-046, 'Inadvertent ESAS Actuation', Rev 6 Initiating Cue: Respond to the cues or indications provided by the examiner or the simulator.

Time Critical Task: No Validation Time: 10 minutes ILT16-01 NRC JPM C NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP

1. Reset the simulator to IC 16 or temporary IC 239.

2. ENSURE SI Flow is less than 40 gpm.

3. Insert:

a. MALFUNCTION ESOSB on EVENT #1

b. MALFUNCTION MU07 immediately to 45% (ensure this setting does not let SI flow go greater than 40 gpm)

c. REMOTE RSR09 to EMERG on Event #2 with a 20 second time delay

d. Override ZDIMU42FIC(2) 02A5A03-ZDIMU42FIC(2) to OFF to ensure MU-V-32 will not transfer to hand.

4. Place the simulator in RUN.

5. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.

6. This completes the setup for this JPM.

ILT16-01 NRCJPMC NUREG 1021, Revision 10

Appendix C Page 3 of 8 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATORS CUE: When the examinee is in role, direct the ICO to insert Event

1. 1.

EVALUATORS NOTE: The examinee may perform immediate actions from memory, or pull the IMA book from below the console.

Either method is acceptable.

BOOTH CUE: When directed by the examiner, insert EVENT #1.

Performance Step: 1 Diagnoses an inadvertent 500# ES signal on the 'B' train of ES.

Standard: Examinee recognizes the failure and makes an update on the 'B' train 500# signal failure.

Comment:

OP-TM-AOP-046, Immediate Actions, Step 2.1 Performance Step: 2 Defeat the invalid ESAS signals.

Standard: Examinee will attempt to defeat the invalid 'B' ES signals by pressing the 500# bypass and/or channel reset pushbuttons on console right. The signal will not be able to be cleared, and the RNO of Step 2.1 is entered.

Comment:

EXAMINER CUE: When the examinee GOES TO section 5.0, hand the examinee a copy of the procedure and direct the examinee to perform OP-TM-AOP-046.

ILT16-01 NRC JPM C NUREG 1021, Revision 10

Appendix C Page 4 of 8 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-AOP-046, Immediate Actions, Step 2.1 RNO Performance Step: 3 2. If "B" train can not be defeated then GO TO section 5.0.

Standard: The examinee recommends going to Section 5.0 of OP-TM-AOP-046.

Comment:

OP-TM-AOP-046, Section 5.0, Step 5.1

../ Performance Step: 4 Shutdown the "B" train Makeup Pump NOT required for seal injection.

Standard: The examinee should recognize that MU-P-1C (on Console Right) and rotate the pistol grip counterclockwise to shutdown the pump. The green and amber lamps should light.

Comment:

OP-TM-AOP-046, step 5.2 is not applicable BOOTH CUE: When the examinee directs an Auxiliary Operator to OPEN RSTSP "B" using key #98, and PLACE "Makeup &

Purification" transfer switch in EMERG position, insert EVENT#2.

OP-TM-AOP-046, Step 5.3 Performance Step: 5 If B side RSD system available, then perform the following:

1. OPEN RSTSP "B" using key #98 ( 1S 480V Bus Room)

2. PLACE "Makeup & Purif' transfer switch in EMERG position.

Standard: Examinee will dispatch an operator to perform this step. When the step is completed, the examinee will move to the next step.

Comment:

ILT16-01 NRC JPM C NUREG 1021, Revision 10

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER CUE: If the examinee requests the positions of MU-V-77A & Band MU-V-76A & B, reply that they are in their normal position.

The examinee can verify the position of the above valves by using the configuration control placard on console center, below the makeup pump control switches.

EXAMINER CUE: In addition to raising the setpoint on the MU-V-32 controller (SI controller) the examinee may attempt to take the controller to hand, and demand MU-V-32 open to raise SI flow > 40 gpm. Either or both methods are acceptable, but neither method will work, as the valve is failed in the current position.

OP-TM-AOP-046, Step 5.4 Performance Step: 6 If all of the following conditions exist:

- MU-V-77A & Bare Open

- MU-V-76A & Bare Closed

- "A" train ESAS did not actuate, then perform the following:

1. RAISE SI flow to > 40 gpm using setpoint controller.

Standard: The examinee will rotate the SI setpoint clockwise to raise SI demand. This will not get SI flow greater than 40 gpm, and the RNO should be entered.

Comment:

Alternate Path Begins ILT16-01 NRCJPMC NUREG 1021, Revision 10

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION BOOTH CUE: If dispatched as an Auxiliary Operator to investigate MU-V-32, wait 30 seconds and report that MU-V-32 appears normal.

EXAMINER NOTE: In OS-24, MU Pump Flow includes normal makeup (MU24-FI), seal injection (MU42-FI), HPI Flow and pump recirculation flow of 95 GPM per pump. In this JPM, there is no recirculation flow due to MU-V-37 closing on the inadvertent ES, therefore to get to >115 gpm, the operator will sum seal injection (- 35 gpm) and the flow through MU-V-168. The flows can easily be seen from the PPC on the makeup system overview screen.

OP-TM-AOP-046, Step 5.4 RNO

...J Performance Step: 7 THROTTLE MU-V-168 to establish a MU PUMP FLOW of> 115 gpm.

Standard: The applicant should throttle open MU-V-168 by pressing the red OPEN pushbutton. The operator will have to press the white STOP pushbutton when MU-V-168 is in the desired position.

The operator may choose to throttle open or closed MU-V-168 to establish 115 gpm flow rate.

Comment:

Terminating Cue: When MU-V-168 is throttle open to a MU PUMP Flow >115 gpm, the JPM can be terminated.

STOP TIME:

ILT16-01 NRCJPMC NU REG 1021, Revision 10

Appendix C Page 7 of 8 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM C Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT16-01 NRCJPMC NU REG 1021, Revision 10

Appendix C Page 8 of 8 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• 100% power

• You are the URO

• The examiner will act as the ARO and CRS

• The ICO will act as the Auxiliary Operators in the plant.

INITIATING CUE: Respond to the cues or indications provided by the examiner or the simulator.

TIME CRITICAL: No ILT16-01 NRC JPM C NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: EOPG21001 Task

Title:

Transfer to Reactor Building Sump JPM No.: ILT 16-01 NRC JPM D Recirculation - Alt Path KIA

Reference:

005 A2.04 2.9/2.9 Bank JPM: TQ-TM-104-212-J100 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom Simulator X Plant READ CUE SHEET ON LAST PAGE 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.

Initial Conditions:

• You are assigned the duties of the extra RO.

• The examiner will act as the URO, ARO, and CRS.

• The ICO will act as the Auxiliary Operators in the plant.

• Reactor is shutdown with a LOCA in progress.

• OP-TM-EOP-001 and OP-TM-EOP-006 are in progress.

• OP-TM-EOP-010, Guide 20 has been completed.

• BWST level is at 13 feet and lowering.

• LPI throttling is in progress per Rule 2.

• DH-V-38A/B are closed Task Standard: LPI flow balanced ,::: 2800 gpm, but >1250 gpm per loop. If BWST level lowered to less than 6.33 feet, DH-V-5A and 5B must be closed.

Required Materials:

• OP-TM-EOP-010, 'Emergency Procedure Rules, Guides and Graphs', Rev 19

• OP-TM-211-901, 'Emergency Injection (HPl/LPI)', Rev 7 General

References:

• OP-TM-EOP-010, 'Emergency Procedure Rules, Guides and Graphs', Rev 19

• OP-TM-211-901, 'Emergency Injection (HPl/LPI)', Rev 7 ILT16-01 NRC JPM D NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: The CRS has directed you to transfer the reactor building sump to recirculation mode IAW OP-TM-EOP-010, Guide 21 Time Critical Task: No Validation Time: 20 minutes ILT16-01 NRC JPM D NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP

1. Reset the simulator to IC 16 or equivalent 100% power IC (Temporary IC 236)

2. Place simulator in FREEZE.

o Insert Malfunction TH04 at 10% severity.

o Insert remote DHR05 IN to energize CF-V-1A Breaker o Insert remote DHR06 IN to energize CF-V-1 B Breaker o Insert remote DHR17 IN to energize DH-V-1 Breaker o Insert remote DHR18 IN to energize DH-V-2 Breaker o Insert remote DHR19 IN to energize DH-V-3 Breaker o Insert remote DHR11 at 100% to open DH-V-64 o Insert EVENT TRIGGER:

o dhvdhv6b > 0.01 on EVENT 2 "Command" irf dhr25 out. This will cause the breaker for DH-V-6B to trip when the examinee attempts to open DH-V-6B.

3. Place the simulator in RUN.

A. Using OP-TM-EOP-001 and OP-TM-EOP-006, control and monitor plant conditions.

B. Bypass/Reset all ESAS signals.

C. Complete all steps of Guide 20.

D. When BWST level is approximately 13 feet or, terminate HPI and place the Simulator in FREEZE.

4. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.

5. This completes the setup for this JPM.

ILT16-01 NRC JPM D NUREG 1021, Revision 10

Appendix C Page 4 of 11 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATORS CUE: Provide a copy of OP-TM-EOP-010, Guide 21.

OP-TM-EOP-010, Guide 21, Step 1 Performance Step: 1 ANNOUNCE initiation of RB sump recirculation over the page and radio.

Standard: Examinee announces initiation of RB sump recirculation over plant page and radio Comment:

OP-TM-EOP-010, Guide 21, Step 2 Performance Step: 2 VERIFY RB Flood Level> 29 in.

Standard: Examinee will read Reactor Building Flood level indication on Panels CC and/or CR to verify that levels are greater than 29 inches.

Comment:

BOOTH CUE: When contacted to verify DH-V-38A or DH-V-388 is closed, wait one minute and report back that both DH-V-38A and DH-V-398 is closed.

ILT16-01 NRC JPM D NUREG 1021, Revision 10

Appendix C Page 5 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-EOP-010, Guide 21, Step 3 Performance Step: 3 VERIFY either DH-V-38A or DH-V-38B is Closed Standard: Contacts AO via radio to verify either DH-V-38A or DH-V-38B is Closed Comment:

OP-TM-EOP-010, Guide 21, Step 4

..,/ Performance Step: 4 THROTTLE both DH-V-4A and DH-V-4B to the maximum controllable flow s 3000 gpm in each line Standard: Examinee throttles DH-V-4A and DH-V-4B using the OPEN and STOP pushbuttons on Panels CC and CR to achieve max controllable flows of s 3000 gpm in each line Comment:

EXAMINER CUE: As CRS acknowledge report of breaker trip for DH-V-68 and entry into RNO section.

BOOTH CUE: If asked, role-play as AO and respond to request to investigate tripped breaker.

OP-TM-EOP-010, Guide 21, Step 5

..,/ Performance Step: 5 When BWST level reaches 9.5 ft., or RB Flood Level> 56 inches, then

- OPEN DH-V-6A

- OPEN DH-V-6B Standard: Examinee observes BWST level and Reactor Building Flood level on Panels CC and CR When BWST level drops below 9.5 feet or flood level > 56 inches examinee will attempt to OPEN DH-V-6A and DH-V-6B by depressing the OPEN pushbutton for each on Panels CC and CR respectively.

WHEN the pushbutton for DH-V-6B is depressed the breaker for this valve will trip, leaving the valve in the CLOSED position.

The examinee should announce that the breaker for DH-V-6B has tripped, and may request an AO to investigate the tripped breaker.

Examinee enters RNO section, announces same to CRS Comment:

ILT16-01 NRG JPM D NU REG 1021, Revision 10

Appendix C Page 6of11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-EOP-010, Guide 21, Step 6

.../ Performance Step: 6 When BWST level reaches 6.33 ft., or RB Flood Level> 56 inches, then

- CLOSE DH-V-5A

- CLOSE DH-V-5B Standard: Examinee observes BWST level and Reactor Building Flood level on Panels CC and CR. When BWST level drops below 6.33 feet or flood level > 56 inches examinee will CLOSE DH-V-5A and DH-V-5B by depressing the CLOSE pushbutton for each on Panels CC and CR respectively.

Examinee observes RED lights extinguish and GREEN Lights become bright for DH-V-5A and 5B.

Comment:

EXAMINER NOTE: Examinee could wait until BWST LEVEL is below 6.33 feet to initiate alternate path, or initiate alternate path and then perform steps for when BWST level is less than 6.33 feet. Either order is acceptable.

Alternate Path Begins EXAMINER CUE: Acknowledge entry into OP-TM-211-901 if/when announced.

Provide copy of OP-TM-211-901 OP-TM-EOP-010, Guide 21, Step 5 RNO

..,/ Performance Step: 7 1. PLACE affected DH pump in PTL

2. PLACE affected BS pump in PTL

3. INITIATE contingency actions for one DH pump IAW OP-TM-211-901, "Emergency Injection HPl/LPI" Standard: 1. Examinee places extension control for DH-P-1 Bin PTL

2. Examinee places extension control for BS-P-1 B in PTL

3. Examinee obtains copy of OP-TM-211-901 and announces entry into procedure Comment:

ILT16-01 NRC JPM D NU REG 1021, Revision 10

Appendix C Page 7 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-901, Precautions, Prerequisites, and Limitations Performance Step: 8 Review precautions, limitations, & prerequisites.

Continue at step 4.2. 7 under Contingency Actions Standard: Examinee reviews precautions, limitations, & prerequisites.

Examinee determines, upon procedure review, that he/she needs to initiate contingency step 4.2. 7.

Comment:

OP-TM-211-901, Step 4.2.7.1, 4.2.7.2, and 4.2.7.3.A are not applicable. Examinee should proceed to step 4.2.7.3B.

BOOTH CUE: Role-play as AO and when requested, report back that it has been determined that both DH-V-38A and B are accessible in step 4.2. 7.3.A.

OP-TM-211-901, Step 4.2.7.3.B

...J Performance Step: 9 IAAT DH-P-1A or DH-P-1 Bis not operating, then perform the following:

B. If DH-V-38A and Bare accessible, then perform the following:

1) CLOSE DH-V-4 on the train with the inoperable DH pump Standard: Examinee closes DH-V-48 on Panel CR Comment:

BOOTH CUE: Role-play as AO, respond when requested to open DH-V-38A and DH-V-38B and report back that both valves are open.

Remote function DHR14 opens both valves.

ILT16-01 NRC JPM D NUREG 1021, Revision 10

Appendix C Page 8of11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-901, Step 4.2.7.3.B

.../ Performance Step: 10 2) OPEN DH-V-38A and DH-V-388 (Aux Bldg 281' el.)

Standard: Requests AO to open DH-V-38A and DH-V-388 Comment:

EXAMINER CUE: Acknowledge performance of Rule 2 for LPI throttling in the next step.

OP-TM-211-901, Step 4.2.7.3.B Performance Step: 11 3) THROTTLE DH-V-4A and DH-V-48 to balance LPI flow IAW Rule 2 Standard: Examinee obtains laminated copy of Rule 2, LPI Throttling.

Announces performance of Rule 2 Comment:

EXAMINER NOTE: In ill! cases, throttle using DH-V-4A and DH-V-48 and flow indications on DH-Fl-802A and DH-Fl-803A OP-TM-EOP-010, Rule 28, Step 1

.../ Performance Step: 12 VERIFY both DH-V-6A and DH-V-68 Closed Standard: Examinee determines that DH-V-6A is OPEN and DH-V-68 is CLOSED.

Examinee performs RNO section of Rule 2 for LPI throttling.

Comment:

ILT16-01 NRC JPM D NUREG 1021, Revision 10

Appendix C Page 9of11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-EOP-010, Rule 28, Step 1 RNO Step 1 is not applicable OP-TM-EOP-010, Rule 28, Step 1 RNO

...J Performance Step: 13 2. If both DH-V-38A and DH-V-388 are Open, then THROTTLE both trains for balanced total flow s 2800 gpm Standard: Examinee throttles DH-V-4A and DH-V-48 using the OPEN and STOP pushbuttons on Panels CC and CR, respectively, to achieve a balanced total LPI flow of s 2800 gpm, but >1250 gpm per loop, as indicated on DH-Fl-802A and DH-Fl-803A Comment:

Terminating Cue: JPM may be terminated when examinee reports balanced LPI total flow S 2800 gpm, but >1250 GPM per loop. In addition the examinee must close DH-V-5A and DH-V-58 if 8WST level lowers to less than 6.33 feet.

STOP TIME:

ILT16-01 NRC JPM D NUREG 1021, Revision 10

Appendix C Page 10of11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM D Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT16-01 NRC JPM D NU REG 1021, Revision 10

Appendix C Page 11 of 11 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• You are assigned the duties of the extra RO.

• The examiner will act as the URO, ARO, and CRS.

• The ICO will act as the Auxiliary Operators in the plant.

• Reactor is shutdown with a LOCA in progress.

• OP-TM-EOP-001 and OP-TM-EOP-006 are in progress.

• OP-TM-EOP-010, Guide 20 has been completed.

• BWST level is at 13 feet and lowering.

• LPI throttling is in progress per Rule 2.

• DH-V-38A/B are closed INITIATING CUE: The CRS has directed you to transfer the reactor building sump to recirculation mode IAW OP-TM-EOP-010, Guide 21 TIME CRITICAL: No ILT16-01 NRC JPM D NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: 53401007 Task

Title:

Perform Emergency Operations of JPM No.: ILT 16-01 NRC JPM E Reactor Building Emergency Cooling Water - Alternate Path KIA

Reference:

022 A4.04 3.1 I 3.2 Modified JPM: TQ-TM-104-534-J100 Examines: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom Simulator X Plant READ CUE SHEET ON LAT PAGE 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.

Initial Conditions:

• You are the ARO.

• The examiner will act as the URO and CRS.

• The Plant is at 100% power.

• There is a small steam leak inside Containment.

• The Director of Operations is informed of the situation.

Task Standard: "A" Reactor Building Emergency cooling is initiated, and RR-P-1 Bis in PTL.

Required Materials:

• OP-TM-534-901, RB EMERGENCY COOLING OPERATIONS, Rev 14 General

References:

• OP-TM-534-901, RB EMERGENCY COOLING OPERATIONS, Rev.

14 Initiating Cue: The Control Room Supervisor has directed you to initiate Reactor Building Emergency Cooling using OP-TM-534-901, RB Emergency Cooling Operations.

ILT16-01 NRC JPM E NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Time Critical Task: No Validation Time: 8 minutes ILT16-01 NRC JPM E NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP

1) Reset the simulator to IC16.

2) Insert override 03A6S05-ZDIRRV1 B(2)CLS CR RR-V-1 B CLOSE/OPEN to ON

3) Insert override 03A6S1O-ZDIRR18(1 )OPN CR RR-V-1 B CLOSE/OPEN to OFF

4) Insert Malfunction MS02B at 0.1 % severity

5) Place the simulator in freeze.

ILT16-01 NRC JPM E NUREG 1021, Revision 10

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATORS CUE: Direct the examinee to:

"Initiate RB Emergency Cooling in accordance with OP-TM-534-901 ".

EVALUATORS CUE: When the procedure is located, hand the examinee a copy of the procedure.

OP-TM-534-901, Precautions, Limitations and Prerequisites Performance Step: 1 Examines reviews Precautions, Limitations, and Prerequisities.

Standard:

Comment:

BOOTH CUE: When directed, respond as the AO and use Remote Function CCR 32 to close NS-V-85. lmmediatley report that NS-V-85 is closed.

OP-TM-534-901, Step 4.1.1 Performance Step: 2 DISPATCH an operator to CLOSE NS-V-85 (IB 295: S of RR Valve Room Standard: An AO is dispatched via radio to close NS-V-85.

Comment:

EXAMINER NOTE: The NOTE in the procedure allows the examinee to perform either train first or both trains in parallel.

ILT16-01 NRC JPM E NUREG 1021, Revision 10

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-534-901, Step 4. 1.2 Performance Step: 3 IAAT expected equipment response is not obtained when initiating the desired train(s) of R8EC, then INITIATE Section 4.2, Contingency Actions Standard: Step is left open.

Comment:

OP-TM-534-901, Step 4.1.3

.../ Performance Step: 4 START or VERIFY running:

- RR-P-1A

- RR-P-18 Standard: RR-P-1A and RR-P-18 are started on CC (CR) by turning the extension control to the Normal After Start position and verifying the RED/RUNNING light(s) lit and GREEN/OFF lights off.

Comment:

OP-TM-534-901, Step 4.1.4

.../ Performance Step: 5 ENSURE OPEN:

- RR-V-3A (Train A)

- RR-V-38 (Train 8)

- RR-V-3C (Train A or 8)

Standard: The valves are verified open (RED/OPEN lights lit and GREEN/CLOSED lights off).

Comment:

EXAMINER NOTE: RR-V-1 B not opening is the beginning of the alternate path.

The student may identify RR-V-1 B not opening after they check the pressure indicators. The alternate path script begins after they check the pressure indicators.

ILT16-01 NRC JPM E NUREG 1021, Revision 10

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-534-901, Step 4.1.5

.../ Performance Step: 6 ENSURE OPEN:

- Train A - Train 8

- RR-V-4A - RR-V-48

- RR-V-4C - RR-V-4D

- RR-V-1A - RR-V-18 Standard: Examinee presses the RED/OPEN pushbutton and verifies the RED/OPEN lights are lit and the GREEN/CLOSED LIGHTS are off for each valve listed.

Examinee notes that RR-V-18 open light does not become bright and the close light stays lit.

Comment:

OP-TM-534-901, Step 4.1.6 Performance Step: 7 VERIFY the coolers in service are controlled at 50 - 75 psig:

- RR-Pl-224

- RR-Pl-225

- RR-Pl-226 Standard: Examinee checks in-service coolers controlled at 50 - 75 psig.

Comment:

ILT16-01 NRC JPM E NU REG 1021, Revision 10

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION Alternate Path Begins BOOTH Cue: If directed to open RR-V-1 B, wait 30 seconds and report that the operator for RR-V1 B is broken OP-TM-534-901, Steps 4.2.1 through 4.2.9 are not applicable.

OP-TM-534-901, Step 4.2.10

..,/ Performance Step: 8 If RR-V-1 B is closed, then perform the following:

1. Open RR-V-1 B

2. If RR-V-1 Bis NOT open, the place RR-P-1 Bin PTL.

Standard: Examinee attempts to open RR-V-1 B. When the valve does not open, the examinee will place RR-P-1 Bin PTL.

Comment:

Terminating Cue: When RR-P-1 B is in PTL, the JPM can be terminated.

STOP TIME:

ILT16-01 NRC JPM E NUREG 1021, Revision 10

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM E Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT16-01 NRC JPM E NU REG 1021, Revision 10

Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• You are the ARO.

• The examiner will act as the URO and CRS.

• The Plant is at 100% power.

• There is a small steam leak inside Containment.

• The Director of Operations is informed of the situation.

INITIATING CUE: The Control Room Supervisor has directed you to initiate Reactor Building Emergency Cooling using OP-TM-534-901, RB Emergency Cooling Operations.

TIME CRITICAL: No ILT16-01 NRC JPM E NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: 73101008 Task

Title:

Transfer BOP Susses from 1Bto1A JPM No.: ILT 16-01 NRC JPM F Aux Transformer KJA

Reference:

062 A4.01 3.3/3.1 Modified JPM: TQ-TM-104-731-J100 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom Simulator X Plant READ CUE SHEET ON LAST PAGE 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.

Initial Conditions:

• 100% power

• No major equipment out of service

• No surveillances in progress

• You are the ARO

• The examiner will act as the CRS

• The booth operator will be the Auxiliary Operator Task Standard: The 1C 4160V bus successfully transferred to the 1A Auxiliary Transformer.

Required Materials:

• 1107-1, 'Normal Electrical System', Rev 98, Section 5.3 Section 5.3.1 are signed complete, 5.3.2.A is N/A. Examinee will start on 5.3.2.B

• 2 copies of 1107-11, 'TMI Grid Operations', Rev 40, Section 3.5.3 o Indicate Step 3.5.3.1.1 Prerequisites are complete, and sign off steps 3.5.3.1.2 1-4 as complete ILT16-01 NRC JPM F NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet General

References:

• 1107-1, 'Normal Electrical System', Rev 98

• 1107-11, 'TMI Grid Operations', Rev 40 Initiating Cue: Place the 1C 4kV bus on the 'A' Auxiliary Transformer IAW 1107-1, Section 5.3, Manual Hot Bus Transfers of 4kV or 7kV busses.

Time Critical Task: No Validation Time: 11 minutes ILT16-01 NRC JPM F NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP

1. Reset the simulator to IC 16 NOTE: It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.

3. This completes the setup for this JPM.

4. Pull up Area 16 Group 13 trend on PPC ILT16-01 NRC JPM F NU REG 1021, Revision 10

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATORS CUE: Direct the examinee to place the 1C 4kV busses on the 1A Auxiliary Transformer, IAW Section 5.3, Manual Hot Bus Transfers of 4kV or 7kV busses.

Provide the examinee with a copy of the procedure.

1107-1, Prerequisites, Step 5.3.1 Performance Step 1: Examines reviews the notes, caution, and prerequisites Standard: Examines reviews the notes, caution, and prerequisites Comment:

Examiner's Note: 1107-1, Procedure, 5.3.2.A will be marked NIA and examinee will continue to Step 5.3.2.B EXAMINER CUE: Notify the examinee that the URO will be logging all events in the log book.

EXAMINER NOTE: The next section is for the 1C 4kV bus.

1107-1, Procedure, 5.3.2.B Performance Step 2: At PR Panel, note tap changer positions:

1A 18- - -

Standard: Examines notes tap changer positions for 1A and 1B at Panel PR Comment:

ILT16-01 NRC JPM F NU REG 1021, Revision 10

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER NOTE: When requested by the examinee, provide a copy of 1107-11 TMI Grid Operations, Section 3.5.3. Indicate Steps 3.5.3.1.1 Prerequisites as completed. In addition sign off 3.5.3.1.2 Procedure Steps 1, 2 , 3, and 4 as completed.

1107-1, Procedure, 5.3.2.B Performance Step 3:

• Verify or place Aux Xfmr 1A load tap changer switch in manual IAW 1107-11, TMI Grid Operations.

• Verify or place Aux Xfmr 1B load tap changer switch in manual IAW 1107-11, TMI Grid Operations.

Standard: Examinee will request 1107-11 to place the 1A and 1B load tap changers in manual.

Comment:

EXAMINER NOTE: NEXT STEP IS IN 1107-11 1107-11, Procedure, 3.5.3.1.2 for both Load Tap Changers

...J Performance Step 4:

• On panel PR SELECT "Manual" on the "Auto-Man" select switch for the Aux. Transformer LTC to be manipulated

• While monitoring voltage on CR, RAISE or LOWER the tap changer, as required, to maintain voltage between 4162 and 4218 volts using the "Raise - Lower" switch on panel PR.

Standard: The examinee will select manual on each load tap changer, and ensure voltage is between 4162-4218 volts on CR.

Comment:

EXAMINER NOTE: NEXT STEP IS IN 1107-1 ILT16-01 NRC JPM F NUREG 1021, Revision 10

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION 1107-1, Procedure, 5.3.2.B Performance Step 5: Verify that the 230 kV busses are cross tied.

- At least one cross-tie is required Standard: Examinee should verify on panel SS-1 that at least one cross tie is energized.

Comment:

EXAMINER NOTE: A momentary low voltage alarm is acceptable. Use the below band until loads are transferred over to the other Aux Transformer.

1107-1, Procedure, 5.3.2.B Performance Step 6: Verify the transformer that is to lose load is between 4150V and 4176V (4150V is the Low Voltage Alarm and 4176V is one tap above this) or adjust the LTC as needed.

Standard: If voltage is not with the band, the examinee will adjust voltage to the band using the LTC on the 1B Auxiliary Transformer.

Comment:

EXAMINER NOTE: A momentary high voltage alarm is acceptable.

1107-1, Procedure, 5.3.2.B Performance Step 7: Adjust the voltage on the transformer that is picking up load so that the voltage is 4218V to 4244V (4218V is top of the Tap Changer Control Band and 4244V is 1 tap above this. The High Voltage Alarm is 4250V.

Standard: If the voltage is not in bank, the examinee will adjust voltage to the band using the LTC on the 1A Auxiliary Transformer.

Comment:

ILT16-01 NRC JPM F NU REG 1021, Revision 10

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION 1107-1, Procedure 5.3.2.B Step 7 is not applicable.

EXAMINER NOTE: Closing the feeder breaker to the 1C 4kV bus to the 1A Auxiliary Transformer, and opening the breaker for the 1C 4kV bus to the 18 Auxiliary Transformer should be done in rapid succession.

1107-1, Procedure, 5.3.2.B

...J Performance Step 8: Close the feeder breaker from the transformer being loaded.

Standard: Examinee turns (FROM THE 1A AUXILIARY TRAN FORMER) 1SA-C2 breaker control to the CLOSE position and holds until the RED CLOSED light comes on.

Comment:

...J Performance Step 9: Open the feeder breaker from the transformer being unloaded.

Standard: Examinee turns (FROM THE 1B AUXILIARY TRANFORMER) 1SB-C2 breaker control to the TRIP position and holds until the GREEN TRIPPED light comes on.

Comment:

Terminating Cue: Once the 1C 4kV bus being supplied by the 1A Auxiliary Transformer only, the JPM can be terminated.

STOP TIME:

ILT16-01 NRC JPM F NUREG 1021, Revision 10

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM F Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT16-01 NRC JPM F NUREG 1021, Revision 10

Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• 100% power

• No major equipment out of service

• No surveillances in progress

• You are the ARO

• The examiner will act as the CRS

• The booth operator will be the Auxiliary Operator INITIATING CUE: Place the 1C 4kV bus on the 'A' Auxiliary Transformer IAW 1107-1, Section 5.3, Manual Hot Bus Transfers of 4kV or ?kV busses.

TIME CRITICAL: No ILT16-01 NRC JPM F NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND UNIT 1 Task No.: 53101011 Task

Title:

Cross Connect the Secondary River JPM No.: ILT 16-01 NRC JPM G Water System to the Nuclear River Water System KIA

Reference:

026 AA2.02 (2.9/3.6) Modified Bank TQ-TM-104-531-J001 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom Simulator X Plant READ CUE SHEET ON LAST PAGE 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.

Initial Conditions:

• For this event you are assigned the duties of the Unit RO.

• NR-P-1 B is tagged out for maintenance, 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> in to a 36-hour outage.

• NR-P-1 C tripped 6 minutes ago.

• OP-TM-AOP-031, LOSS OF NUCLEAR SERVICES COMPONENT COOLING, was entered due to NS cooler outlet temperature approaching 100°F. Progression through step 3.8 has just been completed.

Task Standard: Secondary River Water is cross connected with Nuclear River Water and temperatures are being controlled.

Required Materials: None General

References:

OP-TM-EOP-001, REACTOR TRIP, Rev. 16 OP-TM-AOP-031, LOSS OF NUCLEAR SERVICES COMPONENT COOLING, Rev. 6 OP-TM-541-901, CROSS-TIE SECONDARY RIVER TO SUPPLY NUCLEAR RIVER, Rev. 3 ILT 16-01 NRC JPM G NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Handout: OP-TM-541-901, CROSS-TIE SECONDARY RIVER TO SUPPLY NUCLEAR RIVER, Rev. 3 Initiating Cue: The CRS has directed you to Cross-Tie Secondary River to supply Nuclear River IAW OP-TM-541-901.

Time Critical Task: NO Validation Time: 25 minutes ILT 16-01 NRC JPM G NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP

• IC16 or Temporary IC 184

1. Ensure NR-P-1A/C are running.

2. Place NR-P-18 extension controls in PTL on CC and CR. Hang information tags on both switches.

3. Insert remote function RWR10 to OUT, to rack out breaker for NR-P-18

4. Open NR-V-4A and NR-V-48 on PL. (note, NR-V-4A is a jog control valve therefore opening requires the switch to be held down until only the open light is on.)

5. Insert malfunction RW02C to trip NR-P-1 C.

6. Perform OP-TM-EOP-001 IMA's and execute OP-TM-AOP-031 up through Step 3.9

7. Raise River Water temperature high enough to result in NS cooler outlet temperature>

100°F

• Insert Remote Function RWR14 at 100°F (It takes - 6 minutes in run for NS Cooler Outlet Temperatures to exceed 100°F)

8. Adjust MUT level for current plant conditions (MUMMT to 27500)

9. Set Event 1 to close the following breakers:

• RWR47 1A ES SHMCC Unit 2A (NR-V-1) Value - CLOSE

• RWR19 1A ES SHMCC Unit 28 (NR-V-3) Value - CLOSE

• RWR20 1A ESV MCC Unit 80 (NR-V-5) Value - CLOSE

• RWR21 18 ESV MCC Unit 1OD (NR-V-6) Value - CLOSE

• RWR48 18 ES SHMCC Unit 2A (NR-V-7) Value - CLOSE

10. Place the simulator in FREEZE

11. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.

12. This completes the setup for this JPM.

ILT 16-01 NRC JPM G NU REG 1021, Revision 10

Appendix C Page 4of10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATOR CUE: When OP-TM-541-901 has been located, provide a copy of OP-TM-541-901.

OP-TM-541-901, PRECAUTIONS, LIMITATIONS, AND PREREQUISITES Performance Step: 1 Precautions - None Limitations - To prevent SR pump motor overload, maintain secondary river header pressure (as read on SR-Pl-134) greater than 21 psig.

Prerequisites - VERIFY one of the following conditions:

• Reactor is shutdown

• TS 3.0.1 action statement has been entered Standard: Examinee verifies the reactor is shutdown.

Comment:

EVALUATOR NOTE: Step 4.1 is N/A OP-TM-541-901, Step 4.2 Performance Step: 2 ENSURE NR-V-4A or NR-V-48 is Closed.

Standard: Close NR-V-4A or NR-V-48 are Closed as indicated by Green lights on PL or Blue lights on (PCR).

Comment:

ILT 16-01 NRC JPM G NUREG 1021, Revision 10

Appendix C Page 5 of 10 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-541-901, Step 4.3 Performance Step: 3 ENSURE discharge valves are Closed on all NR or SR pumps which are shutdown.

Standard: Examines closes the discharge valves on all non-running NR and SR pumps, by depressing close PB NR-V-1C on (CR) and close PB SR-V-1A (CL).

Comment:

OP-TM-541-901, Step 4.4 Performance Step: 4 DISPATCH an Operator to Close the following breakers:

• NR-V-2-BK (1A ES Screen House MCC Unit 2A)

• NR-V-3-BK (1A ES Screen House MCC Unit 28)

• NR-V-7-BK (1 BES Screen house MCC Unit 2A)

• NR-V-5-BK (1A ES Valves MCC Unit 80)

• NR-V-6-BK (18 ES Valves MCC Unit 100)

Standard: Examines contacts an AO and directs closing of the breakers for NR-V-2, NR-V-3, NR-V-5, NR-V-6 and NR-V-7.

BOOTH OPERATOR When requested to close the breakers for NR-V-2, NR-V-3, CUE: NR-V-5, NR-V-6, and NR-V-7:

• Acknowledge the request.

• Insert Event 1. Ensure RWR19, RWR20, RWR21, RWR47 and RWR48 inserted.

• Report that the breakers for NR-V-2, NR-V-3, NR-V-5, NR-V-6, NR-V-7 are closed Comment:

ILT 16-01 NRC JPM G NU REG 1021, Revision 10

Appendix C Page 6of10 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-541-901, Step 4.5 Performance Step: 5 IAAT NR piping between NR-V-3 and NR-V-5 is ruptured or blocked, then CLOSE the following valves:

• NR-V-3

• NR-V-5 Standard: Determines no rupture in piping, leaves the step open (IAAT).

Comment:

OP-TM-541-901, Step 4.6

~ Performance Step: 6 ENSURE the third Secondary River pump is operating.

Standard: Starts the third SR pump SR-P-1A by rotating extension control clockwise (CL) observes RED light on GREEN light off.

Comment:

OP-TM-541-901, Step 4.7

~ Performance Step: 7 ENSURE SR pump discharge valves are OPEN.

Standard: Opens the discharge valve for SR-P-1A, SR-V-1A by depressing Open PB. Notes GREEN light out, RED light lit.

Comment:

OP-TM-541-901, Step 4.8

~ Performance Step: 8 WAAT OPEN NR-V-2-BK is CLOSED, then OPEN NR-V-2.

Standard: Presses the OPEN pushbutton for NR-V-2 (CC). Notes green light out, red light lit.

Comment:

ILT 16-01 NRC JPM G NU REG 1021, Revision 10

Appendix C Page 7of10 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-541-901, Step 4.9

" Performance Step: 9 WAAT NR-V-7-BK is closed, then OPEN NR-V-7.

Standard: Presses the OPEN pushbutton for NR-V-7 (CC). Notes green light out, red light lit.

Comment:

" OP-TM-541-901, Step 4.10 Performance Step: 10 WAJfr NR-V-6-BK is CLOSED, then OPEN NR-V-6 ..

Standard: Presses the OPEN pushbutton for NR-V-6. Notes green light out, red light lit.

Comment:

OP-TM-541-901, Step 4.11 Performance Step: 11 THROTTLE SR-V-2 to maintain Secondary River discharge pressure (SR-Pl-134) above 21 psig.

Standard: If necessary, Examinee throttles SR-V-2 to maintain Secondary River discharge pressure (SR-Pl-134) above 21 psig.

Comment:

EVALUATOR NOTE: NR-V-16A is an Appendix R valve, power is removed and the valve is full open.

EVALUATOR NOTE: NR-V-168/C are full open already.

EVALUATOR NOTE: NR-V-160 should not need to be manipulated (per validation results). NS cooler outlet temperature should be less than 95°F and slowly lowering.

OP-TM-541-901, Step 4.12 Performance Step: 12 THROTTLE OPEN NR-V-16 A, B, C, D to maintains NS cooler outlet temperature less than 95 °F.

Standard: If needed, Examinee directs an NLO to throttle open NR-V-160 to maintains NS cooler outlet temperature less than 95 °F.

Comment:

ILT 16-01 NRC JPM G NUREG 1021, Revision 10

Appendix C Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-541-901, Step 4.13 Performance Step: 13 THROTTLE OPEN NR-V-15A, B to maintain IC cooler outlet temperature less than 100 °F.

Standard: Examinee throttles NR-V-15A/ Bon (CR) by pressing open PB for short periods of time, to maintain IC cooler outlet temperature less than 100 °F.

Comment:

Terminating Cue: When candidate has control (giving the direction to throttle NR-V-160 and/or throttling an NR-V-15) of outlet temperatures JPM may be terminated.

STOP TIME: TIME CRITICAL STOP TIME: N/A ILT 16-01 NRC JPM G NU REG 1021, Revision 10

Appendix C Page 9of10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM G Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT 16-01 NRC JPM G NUREG 1021, Revision 10

Appendix C Page 10of10 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• For this event you are assigned the duties of the Unit RO.

• NR-P-1 B is tagged out for maintenance, 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> in to a 36-hour outage.

• NR-P-1 C tripped 6 minutes ago.

• OP-TM-AOP-031, LOSS OF NUCLEAR SERVICES COMPONENT COOLING, was entered due to NS cooler outlet temperature approaching 100°F. Progression through step 3.8 has just been completed.

INITIATING CUE: The CRS has directed you to Cross-Tie Secondary River to supply Nuclear River IAW OP-TM-541-901.

TIME CRITICAL: No ILT 16-01 NRC JPM G NUREG 1021, Revision 10

Appendix C Page 1 of 10 Form ES-C-1 PERFORMANCE INFORMATION Facility: THREE MILE ISLAND Task No.: 66101004 Task

Title:

Respond IAW OP-TM-MAP-C0101 JPM No.: ILT 16-01 NRC JPM H Alarm Response with Failure -

Alternate Path KIA

Reference:

072 A3.01 (2.9 I 3.1) Previous JPM: 12-01 NRC Exam Examines: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: Actual Performance: x Classroom Simulator X Plant READ CUE SHEET ON LAST PAGE 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.

Initial Conditions:

• 100% power

• You are the ARO.

• The examiner will act as the URO and CRS.

• The booth operator will be the Auxiliary Operators.

• No Maintenance or surveillances are scheduled for this shift.

Task Standard: Control Building is on Recirc with AH-E-18A running IAW OP-TM-826-901, CONTROL BUILDING VENTILATION SYSTEM RADIOLOGICAL RESPONSE OPERATIONS Required Materials:

• OP-TM-MAP-C0101, Radiation Level HI, Rev 3

• OP-TM-826-901, CONTROL BUILDING VENTILATION SYSTEM RADIOLOGICAL RESPONSE OPERATIONS, Rev 3 General

References:

• OP-TM-MAP-C0101, Radiation Level HI, Rev 3

• OP-TM-826-901, CONTROL BUILDING VENTILATION SYSTEM RADIOLOGICAL RESPONSE OPERATIONS, Rev 3 Initiating Cue: Respond to the cues and indications given by the simulator as well as any input from the CRS.

Time Critical Task: No Validation Time: 15 mins ILT 16-01 NRCJPM H NUREG 1021, Revision 10

Appendix C Page 2of10 Form ES-C-1 PERFORMANCE INFORMATION SIMULATOR SETUP

1. Reset the simulator to IC 16

2. Insert the following Malfunctions:

RM01 G, AH-E-17 A fails to trip on interlock, insert immediately Set RM24 =3000 on EVENT #1 Set RM27 =4020 on EVENT #1 ZDICSAHE18B(2) to ON for EVENT #2 ZDICSAHE18B(4) to OFF for EVENT #2 HVB-6-11 to ON for EVENT #2

3. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.

4. This completes the setup for this JPM.

ILT 16-01 NRC JPM H NUREG 1021, Revision 10

Appendix C Page 3of10 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATORS CUE: The examinee may recognize that the Automatic actions of C-1-1 did not occur and may perform the actions IAW OS-24.

BOOTH CUE: When directed, insert EVENT #1 EVALUATORS CUE: Acknowledge condition and entry into OP-TM-MAP-C0101.

OP-TM-MAP-C0101, Step 4.1 Performance Step: 1 ANNOUNCE alarm over plant page and radio.

Standard:

• Announces RM-A-1 Hi Alarm over the plant page and radio.

Comment:

BOOTH CUE: Acknowledge, as RadPro to verify the alarm and determine the source.

OP-TM-MAP-C0101, Step 4.2 Performance Step: 2 Notify Radiation Protection to verify the alarm and determine the source.

Standard:

• Notifies Radiation Protection to verify the alarm and determine the source.

Comment:

Evaluator Cue: If addressed, state that SCBA's are not required.

ILT 16-01 NRC JPM H NUREG 1021, Revision 10

Appendix C Page 4 of 10 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-MAP-C0101, Step 4.3.1 Performance Step: 3 IAAT High alarm is Lit, then PERFORM OP-TM-826-901,"

Control Building Ventilation System Radiological Response Operations":

Standard:

• Verifies RM-A-1 High alarm is Lit (PRF), and PEFORMS OP-TM-826-901.

Comment:

OP-TM-826-901, Precautions, Limitations, and Prerequistes Performance Step: 4 Examinee retrieves procedure and verifies prerequisites.

Standard: Examinee marks off steps.

Comment:

OP-TM-826-901, Step 4. 1.1 is not applicable EVALUATORS CUE: TIME AH-E-17A is secured:

OP-TM-826-901, Step 4.1.2

.../ Performance Step: 5 ENSURE the following fans are shutdown:

- AH-E-17A and AH-E-178

- AH-E-95A and AH-E-958

- AH-E-20A and AH-E-208 Standard:

• Ensures AH-E-178, AH-E-95A/B, AH-E-20A/B are shutdown.

• Recognizes that AH-E-17A is running and secures AH-E-17A, by rotating extension control in the counter-clockwise direction (H&V A).

• Recognizes that AH-E-20A is running and secures AH-E-20A, by rotating extension control in the counter-clockwise direction (H&V A).

Comment:

ILT 16-01 NRC JPM H NU REG 1021, Revision 10

Appendix C Page 5of10 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-826-901, Step 4.1.3 Performance Step: 6 SHUTDOWN AH-E-19A and AH-E-198.

Standard:

• Verifies AH-E-198 secure and secures AH-E-19A by rotating extension control in the counter-clockwise direction (H&V A).

Comment:

OP-TM-826-901, Step 4.1.4 Performance Step: 7 ENSURE AH-D-28 or AH-D-617 are CLOSED.

Standard:

• Ensures AH-D-28 or AH-D-617 is CLOSED by observation of indication on H&V Center and/or PCR.

Comment:

OP-TM-826-901, Step 4.1.5 Performance Step: 8 PLACE ext. control for AH-E-93/94A and AH-E-93/948 to the OFF position.

Standard:

• Places ext. controls for AH-E-93/94A and AH-E-93/948 to the OFF position on H&V Center.

Comment:

EXAMINER NOTE: After AH-E-188 is started direct EVENT #2 inserted to trip AH-E-188 and start the alternate path.

OP-TM-826-901, Step 4.1.6 Performance Step: 9 START AH-E-188 (A) if AH-E-17A (8) was previously operating.

ILT 16-01 NRC JPM H NUREG 1021, Revision 10

Appendix C Page 6 of 10 Form ES-C-1 PERFORMANCE INFORMATION Standard:

• STARTS AH-E-188 (H&V B), by rotating extension control to start and waiting for discharge damper to drive to the open position, recognizes it does not start.

Comment:

BOOTH CUE: When directed, insert Event #2 and verify AH-E-18B trips and alarm HVB-6-11 comes in.

Alternate Path Begins EXAMINER NOTE: The 'B' train, which is the standby train, trips. The 'A' train must be used. Student must recognize and identify the need to allow a two minute time delay and then proceed with

'A' train vice expected 'B' train.

EXAMINER CUE: When the candidate states that there is a 2 minute wait, announce "time compression is in effect and 2 minutes has elapsed" .

.../ EVALUATORS CUE: TIME AH-E-18A is started:

(must be greater than 2 mins from when AH-E-17 A is secured.)

OP-TM-826-901, Step 4.1. 7

.../ Performance Step: 10 If the opposite train of ventilation is unavailable, then WAIT 2 minutes after AH-E-17 A (B) was shutdown and START AH-E-18A (B).

Standard:

• Waits 2 minutes ILT 16-01 NRC JPM H NU REG 1021, Revision 10

Appendix C Page 7of10 Form ES-C-1 PERFORMANCE INFORMATION

• Starts AH-E-18A by rotating extension control on H&V A clockwise and holding until the discharge damper travels and the RED light comes on indicating AH-E-18 contactor picked up.

Comment:

OP-TM-826-901, Step 4.1.8 Performance Step: 11 ENSURE AH-E-19A or Bis operating.

Standard:

• Ensures AH-E-19A is operating, by observing RED light (H&V A).

Comment:

ILT 16-01 NRC JPM H NUREG 1021, Revision 10

Appendix C Page 8 of 10 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-826-901, Step 4.1.9 Performance Step: 12 ENSURE AH-E-95A or Bis operating.

Standard:

• Ensures AH-E-95A is operating by observing RED light H&V Center.

Comment:

OP-TM-826-901, Step 4. 1.10 Performance Step: 13 START AH-E-90 and AH-E-91.

Standard:

• Orders an NLO to START AH-E-90 and AH-E-91.

ICO Cue: Acknowledge, as an NLO, to start AH-E-90 and AH-E-91.

Comment:

Terminating Cue: When AH-E-1 SA has been started and the order has gone out to an NLO to start AH-E-90/91, the JPM may be terminated.

STOP TIME:

ILT 16-01 NRC JPM H NU REG 1021, Revision 10

Appendix C Page 9of10 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM H Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT 16-01 NRC JPM H NU REG 1021, Revision 10

Appendix C Page 10 of 10 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• 100% power

• You are the ARO.

• The examiner will act as the URO and CRS.

• The booth operator will be the Auxiliary Operators.

• No Maintenance or surveillances are scheduled for this shift.

INITIATING CUE: Respond to the cues and indications given by the simulator as well as any input from the CRS.

TIME CRITICAL No ILT 16-01 NRC JPM H NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: 44104015 Task

Title:

Manually/Locally operate the turbine JPM No.: ILT 16-01 NRC JPM I bypass valves (MS-V-3A-F)

KIA

Reference:

041 A4.08 3.0/3.1 Bank JPM: TQ-TM-105-411-J100 Examines: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: x Actual Performance:

Classroom - - - Simulator - - - Plant x READ CUE SHEET ON LAST PAGE 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.

Initial Conditions:

• Reactor trip and plant cooldown has commenced

• You are an Auxiliary Operator

• The examiner will be all control room operators Task Standard: Take local manual control of MS-V-3C.

Required Materials:

• OP-TM-411-451, MANUAL CONTROL OF TBVs/ADVs, Rev 7 General

References:

• OP-TM-411-451, MANUAL CONTROL OF TBVs/ADVs, Rev 7 Initiating Cue: The Control Room Supervisor has directed you to establish communication with the control room and take local manual control of MS-V-3C, IAW OP-TM-411-451, MANUAL CONTROL OF TBVs/ADVs ,

Attachment 7.1.

Time Critical Task: No Validation Time: 6 minutes ILT16-01 NRC JPM I NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A ILT16-01 NRC JPM I NU REG 1021, Revision 10

Appendix C Page 3 of 7 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATORS CUE: Direct the examinee to:

"Establish communications with the CRO and take local manual control of MS-V-3C, in accordance with OP-TM-411-451, Attachment 7.1 and await further direction from the control room".

EVALUATORS CUE A copy of the procedure should be located at the valve, or if requested by the examinee, the examiner may hand Attachment 7.1.

EXAMINER CUE: If asked the status of the MS-V-3A/B/C ICS hand station, inform the student that "MS-V-3/4 station for MS-V-3C is in HAND".

OP-TM-411-451, Attachment 7.1, Step 1 Performance Step: 1 Establish communications with the control room.

Standard: Examinee LOCATES MS-V-3C on the west side of the Main Condenser, 322' elevation of the Turbine Building and ESTABLISHES communications with the CRO with a Radio or headset, which is located north west of MS-V-3C.

Comment:

EXAMINER CUE: If examinee describes rotating handwheel to align the holes in the sleeve and stem, inform him/her that holes are aligned.

OP-TM-411-451, Attachment 7.1, Step 2

..J Performance Step: 2 TURN handwheel to align holes in sleeve with hole in stem (either set of holes in sleeve will work).

Standard: Examinee DESCRIBES rotating handwheel to align the holes in the sleeve and the stem using either set of holes.

Comment:

ILT16-01 NRC JPM I NU REG 1021, Revision 10

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER CUE: If examinee describes inserting the pin, inform him/her that the pin is inserted OP-TM-411-451, Attachment 7.1, Step 3

...J Performance Step: 3 INSERT pin into sleeve/stem .

Standard: INSERT pin into the holes of the sleeve and stem for the manual operator.

Comment:

EXAMINER NOTE: Auto/Manual switch for MS-V-3s is located on side of positioner box.

EXAMINER CUE: If examinee describes how to position switch correctly, inform him/her the switch is in MANUAL.

OP-TM-411-451, Attachment 7.1, Step 4

...J Performance Step: 4 PRESS and ROTATE Auto/Manual switch, 90 degrees counterclockwise to Manual position Standard: Examinee DESCRIBES Pressing and Rotating the AUTO I MANUAL Switch 90 degrees counter clockwise to the MANUAL position.

Comment:

EXAMINER CUE: If examinee describes how to open the actuator equalizing valve correctly, inform him/her the valve is open.

OP-TM-411-451, Attachment 7.1, Step 5

...J Performance Step: 5 OPEN Actuator Equalizer valve MS-V-1162 for MS-V-3C.

Standard: Examinee OPENS the actuator Equalizing Valve by turning it counterclockwise to the fully OPEN position.

Comment:

ILT16-01 NRC JPM I NU REG 1021, Revision 10

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-411-451, Attachment 7.1, Step 6 Performance Step: 6 MAINTAIN Turbine Header Pressure within limits by adjusting TBV I ADV handwheel.

Standard: Examinee INFORMS CRO that MS-V-3C is in MANUAL control and awaiting instructions to position valve.

Comment:

Terminating Cue: When examinee reports to CRO that MS-V-3C is in LOCAL I MANUAL control, JPM may be terminated STOP TIME:

ILT16-01 NRC JPM I NU REG 1021, Revision 10

Appendix C Page 6 of 7 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM I Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT16-01 NRC JPM I NU REG 1021, Revision 10

Appendix C Page 7 of 7 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• Reactor trip and plant cooldown has commenced

• You are an Auxiliary Operator

• The examiner will be all control room operators INITIATING CUE: The Control Room Supervisor has directed you to establish communication with the control room and take local manual control of MS-V-3C, IAW OP-TM-411-451 MANUAL CONTROL OF TBVs/ADVs, Rev 7, Attachment 7.1.

TIME CRITICAL: No ILT16-01 NRC JPM I NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: 54104005 Task

Title:

Emergency Makeup to Nuclear JPM No.: ILT 16-01 NRC JPM J Service Closed Cooling Surge Tank (NS-T-1)

KIA

Reference:

008 A4.07 2.9/2.9 Bank JPM: TQ-TM-105-541-J100 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: x Actual Performance:

Classroom - - - Simulator ---

Plant x READ CUE SHEET ON LAST PAGE 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.

Initial Conditions:

• Reactor power is 67%, after a loss of 1C 4160V bus

• NS-T-1 level is slowly lowering due to a small leak

• You are an Auxiliary Operator

• The examiner will be all control room operators Task Standard: Fill NS-T-1 with the condensate system in accordance with OP-TM-541-921.

Required Materials:

• OP-TM-541-921, EMERGENCY MAKEUP TO NS-T-1, Rev 2 with prerequisites signed off. N/A section 4.1.

General

References:

• OP-TM-541-921, EMERGENCY MAKEUP TO NS-T-1, Rev 2 Initiating Cue: The lnplant Supervisor has directed you to establish communications with the control room and lineup the condensate system for Emergency Makeup to NS-T-1, IAW OP-TM-541-921, EMERGENCY MAKEUP TO NS-T-1, Section 4.2.

Time Critical Task: No ILT16-01 NRC JPM J NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 8 minutes SIMULATOR SETUP N/A ILT16-01 NRCJPMJ NU REG 1021, Revision 10

Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATORS CUE: Direct the examinee to:

"Lineup the condensate system for emergency makeup of NS-T-1, IAW OP-TM-541-921, Section 4.2" OP-TM-541-921, Section 4.2, Step 1 Performance Step: 1 VERIFY CLOSED SC-V-115 (355' TB NW side SC surge tank 4' above floor).

Standard: Examinee VERIFIES CLOSED SC-V-115.

Comment:

EVALUATOR NOTE: Examinee should locate a ladder but may simulate using it to Open CO-V-170.

OP-TM-541-921, Section 4.2, Step 2

.../ Performance Step: 2 OPEN CO-V-170. (305' TB 10' SE of CO-P-2C 12' above floor).

Standard: Examinee OPENS CO-V-170.

Comment:

OP-TM-541-921, Section 4.2, Step 3

.../ Performance Step: 3 Throttle OPEN NS-V-104 as needed to maintain NS-T-1 level between 3 and 6 feet. (322' TB on wall just S of elevator 2' W of DW-P-1)

Standard: Examinee Throttles OPEN NS-V-104 as needed to maintain NS-T-1 level between 3 and 6 feet.

Comment:

Terminating Cue: When Secondary AO demonstrates control of NS-V-104 the JPM may be terminated.

STOP TIME:

ILT16-01 NRC JPM J NU REG 1021, Revision 10

Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM J Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT16-01 NRCJPMJ NUREG 1021, Revision 10

Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• Reactor power is 67%, after a loss of 1C 4160V bus

• NS-T-1 level is slowly lowering due to a small leak

• *You are an Auxiliary Operator

• The examiner will be all control room operators INITIATING CUE: The lnplant Supervisor has directed you to establish communications with the control room and lineup the condensate system for Emergency Makeup to NS-T-1, IAW OP-TM-541-921, EMERGENCY MAKEUP TO NS-T-1, Section 4.2.

TIME CRITICAL: No ILT16-01 NRC JPM J NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: 23104001 Task

Title:

Take Corrective Action for an JPM No.: ILT 16-01 NRC JPM K Unauthorized Waste Gas release -

In plant KIA

Reference:

071 G2.1.30 4.4/4.0 Bank JPM: TQ-TM-105-231-J100 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance: x Actual Performance:

Classroom ---

Simulator - - - Plant x READ CUE SHEET ON LAST PAGE 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.

Initial Conditions:

• 100% power

• An authorized release is in progress from Waste Gas Decay Tank "A"

• Three sets of readings have been completed on 1104-27, Waste Disposal-Gaseous, ENCLOSURE 2 Task Standard: Identify that Waste Gas Tank 'B' pressure is lowering and secure the release in accordance with 1104-27, section 3.17.

Required Materials:

• 1104-27, Rev 87 and three sets of readings on Enclosure 2.

• A 4th set of evaluator readings of Enclosure 2 General

References:

• 1104-27 Initiating Cue: Perform the fourth set of 1104-27, ENCLOSURE 2 readings at the local panel Time Critical Task: No ILT16-01 NRC JPM K NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 11 minutes ILT16-01 NRC JPM K NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A Procedure Preparation

1. 1104-27, Enclosure 2, with three sets of prior readings

2. 1104-27, Rev 87, with section 3. 7 filled out through and including 3. 7.2.26 (N/A Method 2 in step 3.7.2.8)

3. 1104-27, section 3.17, not given to the examinee until requested.

ILT16-01 NRC JPM K NU REG 1021, Revision 10

Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark)

START TIME:

EVALUATORS CUE: Perform the fourth set of 1104-27, ENCLOSURE 2 readings at the local panel Provide Examine 1104-27 Section 3. 7 and Enclosure 2 EVALUATORS CUE: As each instrument is located or the control room is contacted, provide the instrument reading cues as listed for the 4th set of readings on the attached EVALUATOR ENCLOSURE 2.

1104-27 Enclosure 2 Performance Step: 1 Using Enclosure 2, the examine takes the 4th set of readings Standard: Examinee identifies each instrument used to take the appropriate reading.

Contacts the Control Room for RM-A-8 readings.

Examinee logs readings on Enclosure 2 Comment:

EVALUATORS CUE: When the examinee notifies Shift management and ask if the release should be terminated, respond: "Terminate the release IAW the procedure".

1104-27, Step 3.7.2.27

..,/ Performance Step: 2 If at any time any gas tank has a pressure decrease other than the tank being released then perform the following:

(N/A this step if no pressure drop occurs)

• Inform Shift Management of the problem.

Go to section 3.17 to terminate the gas release.

Standard: Examinee recognizes WDG Tank '8' pressure has lowered and

• Notifies Shift Management

• Goes to Section 3.17 to terminate Gas release ILT16-01 NRC JPM K NU REG 1021, Revision 10

Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION Comment:

EXAMINER CUE: Provide the examinee with Section 3.17 1104-27, Section 3.17 Performance Step: 3 Prerequisites:

• A Waste Gas Decay Tank is being released to the atmosphere.

• Per Enclosure 2, a Waste Gas Decay Tank has lowering pressure and it is not being released to the atmosphere.

Standard: Examinee verifies prerequisites Comment:

EXAMINER CUE: The WDG-V-47 bleed control valve is open and pressure is lowering to ZERO 1104-27, Step 3.17.2.1

..,/ Performance Step: 4 Bleed off air from WDG-V-47 by adjusting the hand loader for WDG-V-47 to 0 psig.

Standard: Examinee simulates bleeding off air from WDG-V-47 by turning the control valve (knob) on the panel in the counter-clockwise direction.

Comment:

ILT16-01 NRC JPM K NU REG 1021, Revision 10

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER CUE: Indication for WDG-V-47 will go from red to green to indicate closed.

1104-27, Step 3.17.2.2

...J Performance Step: 5 Close WDG-V-47 by depressing the Close PB.

Standard: Simulates depressing WDG-V-47 CLOSE PB and verifies closed indication Comment:

EXAMINER CUE: WDG-FR-123 is located in the LWDS panel. When the examinee goes to the door, show the examinee the attached picture of WDG-FR-123 to perform the next step. Indicate WDG-FR-123 is set at "ZERO" after the examinee performs the next step.

1104-27, Step 3.17.2.3

...J Performance Step: 6 Reset WDG-FR-123 setpoint to "O" .

Standard: Examinee Adjusts WDG-FR-123 setpoint to "ZERO".

Comment:

ILT16-01 NRC JPM K NU REG 1021, Revision 10

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER CUE: Provide valve closed and locking device status cues for any valve operated. Closing WDG-V-30 is the critical task.

1104-27, Step 3.17.2.4

...J Performance Step: 7 Close and lock closed the applicable manual outlet valve on the tank being released. (N/A the valves not open)

• Close and lock closed WDG-V-30 for WDG-T-1A.

• Close and lock closed WDG-V-31 for WDG-T-1 B.

• Close and lock closed WDG-V-32 forWDG-T-1C.

Standard: Examinee Locates and simulates closing WDG-V-30 by turning it in the clockwise direction.

WD-G-V-31 & 32 are N/A Comment:

Terminating Cue: After WDG-V-30 is simulated closed, this JPM is complete STOP TIME:

ILT16-01 NRC JPM K NUREG 1021, Revision 10

Appendix C Page 8 of 9 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRC JPM K Examinee's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: SAT UNSAT Examiner's Signature: Date:

ILT16-01 NRC JPM K NU REG 1021, Revision 10

Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• 100% power

• An authorized release is in progress from Waste Gas Decay Tank "A"

• Three sets of readings have been completed on 1104-27, Waste Disposal-Gaseous, ENCLOSURE 2 INITIATING CUE: Perform the fourth set of 1104-27, ENCLOSURE 2 readings at the local panel TIME CRITICAL: No ILT16-01 NRC JPM K NU REG 1021, Revision 10