ML17230A327

Draft Operating Exam (Sections a, B, and C) (Folder 2)

ML17230A327
Person / Time
Site:	Three Mile Island
Issue date:	07/03/2017
From:	Exelon Generation Co
To:	D'Antonio J Operations Branch I
Shared Package
ML16210A446	List: IR 05000289/2017301 ML17230A294 ML17230A316 ML17230A327 ML17233A133 ML17233A134 ML17233A135 ML18081A807 ML18081A808 ML18081A811
References
CAC U01944
Download: ML17230A327 (435)

Text

{{#Wiki_filter:Appendix D Scenario Outline Form ES-0-1 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 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:
• Electrical Power Alignment (CT-8)
• Natural Circulation RCS Flow (CT-12)

I 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-1 A 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) I 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 I CRS 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-1 A, 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 scenario. 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 hours or be in COLD SHUTDOWN within the next 12 hours. 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 erttergency feedwater pump) breaker not closing, and the loss of 1D4160V 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 Electrical Power Alignment - If station auxiliary power is not available, then perform the following: o In the event that no emergency AC supply (or alternate AC source) is available, then perform [SBO procedure] and continue attempts to restore AC power. Performing electrical alignment control outside of the following limits should be considered grounds for failure of the critical task:

• In a condition where no emergency AC supply is available, place the Station Blackout Diesel (SBO) on a 4160 volt ES bus within 10 minutes.

Time Duration Source: FSAR Section 8.5: An alternate AC {AAC) power source is utilized at TMl-1, provided by the SBO diesel generator. The AAC power source has been designed so that it will be available within ten minutes of the onset of the station blackout event, and it has sufficient capability and capacity to operate systems necessary for coping with a station blackout for the required station blackout duration of four hours to bring the plant to and maintain it in safe shutdown. Safety Significance: Plant electrical power is necessary for the operation of normal and emergency plant equipment. Therefore, it is important that the plant operator provide normal AC power, usually supplied through the station auxiliary transformer(s). If normal AC power cannot be supplied, then actions are necessary to initiate operation of the emergency AC source(s) including alternate AC supplies, if applicable. If both normal and emergency AC power are lost, then a station blackout has occurred. For such events, station blackout procedures provide plant specific actions which are to be taken while efforts are being made to restore AC power. Providing normal AC power greatly enhances the transient mitigation capability of the plant, e.g. normal RCS make up systems remain operational. Cues:

             - Auxiliary and emergency bus voltage low alarms
             - Verbal indication by plant staff that auxiliary and emergency AC bus voltage is low
             - Overhead lights turn off Performance Indicators:
             - Operation of auxiliary/emergency AC power source controls (SBO)

Feedback:

             - Auxiliary/emergency bus voltage normal Scenario Set-up NRC Scenario 1
           -  Verbal indication by plant staff of auxiliary/emergency AC power equipment status 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 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 O 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 (EG-Y-4) OPERATIONS 4160V ES bus Restore heat transfer, start 8 OP-TM-424-901, EMERGENCY FEEDWATER Emergency Feed Pump 2A Scenario Set-up NRC Scenario 1 ACTION COMMENTS I INSTRUCTIONS DESCRIPTION IC-241 Initial setup for shutdown EG-Y-1 A protected equipment Malfunction EG01 A 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-1 B fails to autostart ZDINRP1 BT(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-1NB HI TEMP When: Event# 13 INTERLOCK LIFTED LEAD Remote MUR60 Value: Lifted MU-V-3 HI TEMP When: Event# 14 INTERLOCK LIFTED LEAD Remote RWR 12 Value: NR-P-1 B NR-P-1 B ES selected When: Event# 15 Instructions:

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

2. Place info tag on start PB for EG-Y-1 Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event#

Page 10 of 26 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 Conducts 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 2A 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 11of26 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. 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 hours or be in COLD SHUTDOWN within the next 12 hours.

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. 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 12 of 26 Event

Description:

NR-P-1A Trips, NR-P-1 B Fails to Auto-Start Time I Position I Aoolicant'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-1C 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-1 B 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-B0105, 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 13 of 26 Event

Description:

NR-P-1A Trips, NR-P-1 B Fails to Auto-Start Time I Position I Applicant'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.: NRC Scenario # Event# 3 Page 14 of 26 Event

Description:

NR-P-1A Trips, NR-P-18 Fails to Auto-Start Time I Position I Aoolicant'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 hours, 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-1B and ES select NR-P-1B on the 1R 480V ES bus and also to close NR-V-1A. EXAMINER NOTE: Once the 72 hour 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 15 of 26 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 Tavg 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 16 of 26 Event

Description:

Generated Megawatts fail to 0 volts, Entry into OP-TM-AOP-070 Time I Position I Applicant'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 A/B Load Ratio
• ULD Step 3.8: Verifies Main Feedwater Pump dP is greater than 30 ARO osid.

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 17 of 26 Event

Description:

Loss of ICS AUTO Power Makeup subfeed Time I Position I Aoolicant'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, D-3-3, and F-1-4 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. 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-ARO 472 "Manual Pressurizer Level Control". OP-TM-211-472, Manual Pressurizer Level Control Step 4.2: If MU Hand Power is available, then manually control Pzr level as follows:

1. PLACE MU-V-17 in HAND by pressing White HAND PB ARO

2. VERIFY White HAND light is Lit on (CC).

3. ADJUST Pressurizer level as required using toggle switch.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 5 Page 18 of 26 Event

Description:

Loss of ICS AUTO Power Makeup subfeed Time I Position I Aoolicant's Actions or Behavior OP-TM-AOP-027, Loss of ATA or ICS AUTO Power Step 3.11: Initiates OP-TM-211-950, "Restoration Of Letdown ARO Flow". 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 ManaQer 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. Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 5 Page 19 of 26 Event

Description:

Loss of ICS AUTO Power Makeup subfeed Time I Position I Aoolicant's Actions or Behavior 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. 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

                          #11 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-1 A and MU-V-1 B are Open by the ARO indicatinQ liQhts for each beinQ red (not Qreen) (CC) Step 4.8.2: Ensures MU-V-2A and MU-V-2B are open by rotating the control switch for each valve (PCR) to Open, and ARO verifying that the green light goes out and the red light is lit for each valve (CC and PCR). BOOTH CUE: If directed as an Auxiliary Operator to throttle MU-V-98 one-quarter turn open, PLACE MUR54 to a value of 10 and then report back that MU-V-98 is one-quarter turn open (MU-V-98 is not modeled in the simulator). I I Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 5 Page 20 of 26 Event

Description:

Loss of ICS AUTO Power Makeup subfeed Time I Position I Aoolicant's Actions or Behavior 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). 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 is not Lit on URO 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# 1 Event# 61718 Page 21of26 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. 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, the crew will recognize that the 1D 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 # 1 Event# 61718 Page 22 of 26 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 10 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. 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 occurrinq. 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". 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. Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 61718 Page 23 of 26 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 3.7: 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 Coolin~:i". 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. 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 S80 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, S80 Diesel Generator (EG-Y-1A) Operations ARO Verifies precautions, limitations, and prerequisites ARO Step 4.1.1: Verify 1D 4160V bus is de-energized. Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 61718 Page 24 of 26 Event

Description:

Loss of Offsite Power, Reactor Trip, Lack of Primary to Secondary Heat Transfer Time I Position I Aoolicant's Actions or Behavior CT-8 Step 4.1.2: The PPC is available, verify S2072, 4kV bus 1D ARO overcurrent, is NORM. CT-8 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 CT-8 ARO B. The ES selected MU pump: MU-P-1A or MU-P-1 B-D C. DH-P-1A D. RR-P-1A E. EF-P-2A CT-8 Step 4.1.5: PRESS and HOLD for approximately 8 seconds ARO the START PB for the SBO Diesel Generator CT-8 Step 4.1.6: Generator voltage will be between 4.1 and 4.3 kV. ARO No action taken. CT-8 Step 4.1.7: Generator frequency is between 59 and 61 Hz. No ARO action taken. CT-8 ARO Step 4.1.8: ENSURE G1-02 is in PTL CT-8 ARO Step 4.1.9: Place T1-C2 in PTL. CT-8 ARO Step 4.1.10: Close G2-12 (EG-Y-4 output breaker) CT-8 Step 4.1.11: Close T1 -D2 ( 1F 4160V bus cross tie to 1D 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. Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 61718 Page 25 of 26 Event

Description:

Loss of Offsite Power, Reactor Trip, Lack of Primary to Secondary Heat Transfer Time I Position I Aoolicant's Actions or Behavior 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 voltage 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" 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. Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 61718 Page 26 of 26 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 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, 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 Turnover: Maintain 85% power I

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 I CARO (ARO: Secures RCP) I I 4 IC63 ICRS 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-1A fails to start on ES i CURO (URO: Starts MU-P-1A) I 7 CCRS Loss of SCM, entry into OP-TM-EOP-002, then return to OP-TM-EOP-005 I CURO 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 #5/6/7: 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. Makeup Pump, MU-P-1A will fail to start on the ES actuation. The URO must manually start MU-P-1 A. 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.

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°F in 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 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-1C 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 I

           -500 gpm "B" OTSG Tube I

Rupture OP-TM-EOP-010, Emergency Procedure Rules, 5 I 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 I 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 ES07 A Value: Insert Inadvertent 'A' side ESAS When: Event #1 actuation Trigger #10 Value: DMF ES07A Removes Inadvertent 'A' When: dhndhp1 a > 0.9 ESAS actuation Malfunction TH17A Value: 0.2 - 30 GPM tube leak 'A' OTSG When: Event #2 Malfunction TH13C 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: Insert 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.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# Page 9 of 25 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. 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 Running light 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-1 B operating. Step 2.3 (IMA): Throttles MU-V-16A I 168 with HPI flow to URO maintain MU-P-1 B flow > 115 qpm. Step 3.1: Announces entry into OP-TM-AOP-046, "Inadvertent ARO ESAS Actuation" over the plant page and radio. CRS Step 3.2: IAAT for ICCW flow. NA for this scenario. Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# Page 10 of 25 Event

Description:

Inadvertent 'A' Train ES 1600# Actuation Time I Position I Applicant's Actions or Behavior 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 by red open light 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." OP-TM-211-950, Restoration of Letdown Flow Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# Page 11of25 Event

Description:

Inadvertent 'A' Train ES 1600# Actuation Time I Position I Applicant's Actions or Behavior 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 pointinQ 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 1O 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) 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) Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# Page 12 of 25 Event

Description:

Inadvertent 'A' Train ES 1600# Actuation Time I Position I Aoolicant's Actions or Behavior 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 gradually. OP-TM-AOP-046, Section 3.0 EXAMINER NOTE: Step 3.16 is N/A Step 3.17: Declares a 3.5.1.1 (72 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 25 Event

Description:

Inadvertent 'A' Train ES 1600# Actuation Time I Position 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: 2 N/A (g) 1.c: Manual Pushbutton (g) The Operability requirement is for the manual actuation switch for the specified feature on each train to be OPERABLE.

1. If the manual actuation switch on one train is inoperable, restore the switch to OPERABLE status within 72 hours or be in HOT SHUTDOWN within the next 6 hours.

2 If both manual actuation switches for that feature are inoperable, then place the reactor in HOT SHUTDOWN in 6 hours and COLD SHUTDOWN within the followina 24 hours. 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 25 Event

Description:

       'A' OTSG Tube Leak Time      I   Position   I                       Applicant'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-27 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 25 Event

Description:

       'A' OTSG Tube Leak Time      I   Position   I                         APPiicant'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, "Startinq 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 Tarqet 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 25 Event

Description:

       'A' OTSG Tube Leak Time      I   Position   I                      Applicant'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
                                     - EF-P-1 is not running ARO
                                     - 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 hours) 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 hours, and in cold shutdown within 36 hours. 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 25 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-1C 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 ReviewsNerifies 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% / 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 25 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 25 Event

Description:

RC-P-1 C High Vibrations, Feedwater fails to re-ratio Time I Position I Aoolicant's Actions or Behavior ARO Step 4.4.1: Places the SG A/B 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, the scenario can continue. Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# 5/6/7 Page 20 of 25 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 loading 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 21of25 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 "B" OTSG tube leak, and informs the CRS. Diagnoses the "B" 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 25 Event

Description:

OTSG Tube Rupture, Loss of Subcooling Margin, MU-P-1A fails to start on ES Time I Position I Applicant'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. Step 3.29: IAAT OTSG A (8) pressure approaches, or is greater than 1000 psig, then perform the following: 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.

EXAMINERS NOTE: Cooldown rate is 100°F/hr per Guide 11until10CFR 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. 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. Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 2 Event# 51617 Page 23 of 25 Event

Description:

OTSG Tube Rupture, Loss of Subcooling Margin, MU-P-1A fails to start on ES Time I Position I Applicant's Actions or Behavior 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. Step 3.4 - VERIFY PORV is closed. (Tailpipe LlP indicator, URO Alarm G-1-7, A0517). Step 3.5 - INITIATE Attachment 1 "Isolation of possible sources CRS of leakage". OP-TM-EOP-002, Attachment 1 Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 2 Event# 5/6/7 Page 24 of 25 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 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. 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. Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 2 Event# 5/6/7 Page 25 of 25 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 I I EXAMINERS NOTE: The scenario can be terminated when the crew re-enters OP-TM-EOP-005 and is preferentially steaming the 'A' OTSG. If isolation criteria has been met, the scenario can be ended when the 'A' OTSG isolated. 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 Turnover: Remain at 100% power Critical Tasks:
• Natural Circulation RCS Flow (CT-12) I i
• Isolate Overcooling SG(s) (CT-17) I I

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-8G 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 ICRS Turbine Trips, Reactor fails to automatically trip RD28 IURO (URO: IMA's) I 7 ED01 MCRS Loss of Offsite Power with both Emergency Diesel Generators MURO available, entry into OP-TM-AOP-020. MARO i 8 I MSO?B CCRS Stuck open MSSV's, entry into OP-TM-EOP-003. I 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 hours. 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-17 *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 not 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-1D 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 I trip automatically I 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 ZAOWDLLl806 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 #2 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: 1 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 #7 Malfunction MS05A Value: 100 MSSV on 'B' OTSG fails When: Event#? 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 Appendix D Operator Action Form ES-D-2 Op Test No.: NRG Scenario # 3 Event# Page 10 of 29 Event

Description:

LT-806 RB Flood Level Instrument Fails High Time I Position I Annlicant'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 (L T-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 hours. 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 11of29 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 29 Event

Description:

MS-V-1 D closure, ULD fails to lower power Time I Position I Applicant'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 Loq.

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 corresponding value is achieved.

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event# 2/3 Page 13 of 29 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 AUTO 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.: NRG Scenario # 3 Event# 2/3 Page 14 of 29 Event

Description:

MS-V-10 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-V10. 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 29 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 29 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 B/D 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 29 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 hours provided a sample is taken of the Reactor Building atmosphere every 8 hours 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.

CRS Step 3.10 - Initiates TS timeclock 3.1.6 and 3.5.1.9 Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event# 4 Page 18 of 29 Event

Description:

Loss of Vital Bus 'C' (VBC) Time I Position I Applicant's Actions or Behavior 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 29 Event

Description:

lsolable steam leak in the Turbine Building Time I Position I APPiicant'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 Enerqy 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 29 Event

Description:

lsolable steam leak in the Turbine Building Time I Position I Applicant'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 delete malfunction MS198 and report the status of the steam leak following closure of MS-V-58, 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-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 isolated)

Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 3 Event# 5 Page 21of29 Event

Description:

lsolable steam leak in the Turbine Building Time I Position I Applicant's Actions or Behavior I I 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 29 Event

Description:

Turbine Trips, Reactor does not trip automatically, Entry into OP-TM-EOP-001, Reactor Trip Time I Position I Applicant'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 29 Event

Description:

Turbine Trips, Reactor does not trip automatically, Entry into OP-TM-EOP-001, Reactor Trip Time I Position I Applicant's Actions or Behavior 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 29 Event

Description:

Loss of Offsite Power, Stuck open MSSV's Time I Position I Aoolicant'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. Crew Diagnoses Loss of Offsite Power. CRS Announces entry into OP-TM-AOP-020, Loss of Station Power. 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-18 Emergency Operations". Step 3.3: Verifies 1D 4160V and 1E 4160V busses are CRS enerqized CRS Steps 3.4: Verifies IC-P-1 Bis running. Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 718 Page 25 of 29 Event

Description:

Loss of Offsite Power, Stuck open MSSV's Time I Position I Applicant's Actions or Behavior 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.

OP-TM-AOP-041, LOSS OF SEAL INJECTION 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. Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 718 Page 26 of 29 Event

Description:

Loss of Offsite Power, Stuck open MSSV's Time I Position I Applicant's Actions or Behavior 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. 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 Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario # 1 Event# 7/8 Page 27 of 29 Event

Description:

Loss of Offsite Power, Stuck open MSSV's Time I Position I Aoolicant's Actions or Behavior 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 "8" 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 liqhts not lit (CC). Step 3: Performs Phase 1 isolation of "8" OSTG by: CT-17 ARO - Closing MS-V-10 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 "8" 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). Step 3: Performs Phase 1 isolation of "8" OSTG by: CT-17 ARO - Closing FW-V-168 by pushing the Close pushbutton and observing the Close light lit and the Open not lit (CC). Step 3: Performs Phase 1 isolation of "8" OSTG by: CT-17 ARO - Closing FW-V-58 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 29 Event

Description:

Loss of Offsite Power, Stuck open MSSV's Time I Position I Aoolicant's Actions or Behavior 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 Step 6: Performs Phase 2 isolation of the "B" OTSG by: ARO - Closes EF-V-30B by taking the EFW controller to manual and pinning the toggle switch to the left (CC) Step 6: Performs Phase 2 isolation of the "B" OTSG by: ARO - Closes EF-V-30C by taking the EFW controller to manual and pinning the toggle switch to the left (CC) Appendix D Operator Action Form ES-D-2 Op Test No.: NRC Scenario# 1 Event# 718 Page 29 of 29 Event

Description:

Loss of Offsite Power, Stuck open MSSV's Time I Position I Aoolicant's Actions or Behavior Step 6: Performs Phase 2 isolation of the "B" OTSG by: 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, Seal Injection has been restored, and Natural Circulation has been established. 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) New JPM 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:

• RCS temperature 350°F at 1300 on 6/30/17, which coincides with 20 hours 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 %"1k/k
• The Control Rod in location 5-9 is stuck, fully withdrawn Task Standard: Calculate shutdown margin for this low temperature situation, and determine that the SOM will not be more negative than -1 %"1k/k 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 ILT16-01 NRC JPM RA1-1 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-300-206, SHUTDOWN MARGIN FOR LOW TEMPERATURE CONDITIONS, Rev 3
• OP-TM-300-401, INOPERABLE ROD WORTH, Rev 1 Initiating Cue: The CRS has directed you to perform OP-TM-300-206, SHUTDOWN MARGIN FOR LOW TEMPERATURE CONDITIONS for an RCS temperature of 350°F Time Critical Task: No Validation Time:

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-300-205, SHUTDOWN MARGIN FOR LOW TEMPERATURE

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 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark) START TIME: EVALUATORS CUE: Direct the examinee to calculate shutdown margin, 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 Examinee reviews precautions, limitations, and prerequisites Standard: Examinee reviews section 3.0 of OP-TM-300-206 Comment: OP-TM-300-206, Section 4.0 NOTE Performance Step: 2 Examinee reviews the note. Standard: Examinee determines that they will have to use flowchart 2 in OP-TM-300-000 to determine if a quantitative or qualitative assessment is required. Comment: OP-TM-300-206, Step 4. 1 Performance Step: 3 DETERMINE whether a qualitative or quantitative assessment of Shutdown Margin is desired. Standard: Comment: ILT16-01 NRC JPM RA1-1 NUREG 1021, Revision 10

Appendix C Page 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-000, Flowchart 2 f/owpath Performance Step: 4 l<!!<f~ru OP*TM-AOP-CH Standard: Examinee follows the above flowpath and determines that OP-TM-300-206 is the correct procedure, and since the CRS wants a value for Shutdown Margin, the quantitative assessment is complete. Comment: OP-TM-300-206, Step 4. 1. 1 Performance Step: 5 If a qualitative assessment of Shutdown Margin is desired, the DETERMINE Shutdown margin IAW section 4.2. Standard: Examinee determines a qualitative assessment of Shutdown Margin is not desired, and N/A's the step. Comment: ILT16-01 NRC JPM RA1-1 NUREG 1021, Revision 10

Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-206, Step 4.1.2 Performance Step: 6 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: 7 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: 8 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: 9 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 7of12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-206, Attachment 7.3, Step 2 Performance Step: 10 Cycle burnup Standard: Examinee fills in 600 EFPD from the cue sheet. Comment: OP-TM-300-206, Attachment 7.3, Step 3a Performance Step: 11 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: 12 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: 13 Corrected Boron Concentration (3a X 3b) = Standard: Examinee divides 220 ppm X .8006 = 176.13 ppm Comment: OP-TM-300-206, Attachment 7.3, Step 4 Performance Step: 14 Excess Reactivity (Fig 1.) "./ Standard: Examinee uses figure 1 of OP-TM-300-000 and gets a value of

                         -.6 o/o~k/k (Band: .5 to .7%~k/k)

Comment: ILT16-01 NRC JPM RA1-1 NU REG 1021, Revision 10

Appendix C Page 8 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-206, Attachment 7.3, Step 5 Performance Step: 15 Xenon Reactivity Worth (PPC, Reactor Engr.) Standard: Examinee fills in -2.638%Lik/k from the cue sheet. Comment: OP-TM-300-206, Attachment 7.3, Step 6a Performance Step: 16 Samarium and Plutonium Buildup Reactivity Worth (Fig 15): Time since shutdown hrs Standard: Examinee fills in 20 hours from the cue sheet. Comment: OP-TM-300-206, Attachment 7.3, Step 6b Performance Step: 17 Samarium and Plutonium Buildup Reactivity Worth (Fig 15): Reactivity due to samarium and plutonium buildup. '1 Standard: Examinee uses OP-TM-300-000, Figure 15 and fills in

                         -0.055%Lik/k. (Band: -0.05 to -0.06%L'lk/k)

Comment: OP-TM-300-206, Attachment 7.3, Step 7a Performance Step: 18 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 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-206, Attachment 7.3, Step 7b Performance Step: 19 Inoperable Control Rods: Total inoperable rod worth (OP-TM-300-401)

"\/ 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 o/o~k/k. Examinee fills in line 7b with 0.851 o/o~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: 20 Reactivity Addition Due to Reduced Tave (Fig. 17)

"\/ 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: "\/ OP-TM-300-206, Attachment 7.3, Step 9a Performance Step: 21 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/o/o~k/k (BAND: 102 to 106 ppmB/o/o~k/k) Comment: OP-TM-300-206, Attachment 7.3, Step 9b Performance Step: 22 Total Worth (3c/9a) x (-1) = "\/ Standard: Total Worth (176.13I104) x (-1) = -1.69%~k/k Examinee may have different numbers based on bands. Comment: ILT16-01 NRC JPM RA1-1 NU REG 1021, Revision 10

Appendix C Page 10 of 12 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-300-206, Attachment 7.3, Step 10 Performance Step: 23 Shutdown Margin (4 + 5 + 6b + 7b + 8 + 9b) = ~ Standard: Shutdown Margin (0.6 + (-2.638) + (-0.055) + 0.851 + 3.8 +

                                =

(-1.69) 0.868%~k/k Comment: OP-TM-300-206, Attachment 7.3, Acceptance Criteria Performance Step: 24 Examines determines that the calculated SOM does not meet the acceptance criteria, and notifies the examiner. Standard: Examines 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: N ILT16-01 NRC JPM RA1-1 NUREG 1021, Revision 10

OP-TM-300-000 Revision 8 Page 39 of 42 ATTACHMENT 7.27 Figure 15 Cycle 21 Samarium and Plutonium Buildup Following Reactor Shutdown Page 1of1 NOTE: Linearly interpolate between EFPD. If startup at any time during the cycle is within 5 days of a previous startup, contact Reactor Engineering for the appropriate reactivity worth. For use with OP-TM-300-205, OP-TM-300-206, OP-TM-300-402, and OP-TM-300-403 .

i: 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 360 380 400

-a <f. 0.00 0.00 C> 0 II ~ -0.05 -0.05

 ~

w

                                                                                                                                                    ---4EFPD
 .c -0.10                                   ------ -----                                                                                     -0.10
  ~                                          --          - ------ ------ ------ ------ ----- ------ ------ ------ ------ ----- ------ ------        ------- 100 EFPD
  ~ -0. 15                                           - -      -                                                                              -0. 15 - -   -300EFPD
 ~>

0 ctl

                                                                   --    --      -~--
                                                                                               -~--~-~--~-~--~--                                    -500EFPD

(!) ll:: -0.20 -0.20 --e-- 680 EFPD

      -0.25                                                                                                                                  -0.25
      -0~                                                                                                                                    -0~

0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 360 380 400 Hours After Shutdown Each Div. = 5 Hour Cycle Physics Manual Table A-8

OP-TM-300-000 Revision 8 Page 41 of 42 ATTACHMENT 7.29 Figure 17 Cycle 21 Reactivity Addition for Tave < 530°F Page 1of1 NOTE: Linearly interpolate between EFPD curves. For use with OP-TM-300-206. 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 360 380 400 420 440 460 480 500 520 540

          ""'32  7.0                                                                                                                                                          7.0
          '#                                                                                           I    I   I       I    I   I        I    I    I   I    I ci     6.5                                                                                           4          125     300          500     680                    6.5 II         ..__ "'-..                                                                  Temp.      EFPD        EFPD    EFPD         EFPD    EFPD
           >                .......... "'-..                                                       70         5.647       5.597    5.940       6.242   6.494 i:5    6.0                                                                                                                                                          6.0
          .<::          '              "'-.. "-..-. "'-..                                          350        3.221       3.208    3.454       3.685   3.865
           ""'          ~
                                 '           ['-....

w 5.5 **~

                                        ' ' ' ..........                                                                                                                      5.5
                                       ~ ' ' .... "'-..           "'-..

5.0 ~

                                                                                 ~
                                                                                     ~

5.0 4.5 4.0

                                                           '      ~      ',
                                                                        """"" ~

['-...._ r--, ............

                                                                                     ~

t-, ~ ~ r--- 4.5 4.0

                                                                                                                                                                                  ~680EFPD
                                                                                                                                                                                  -SOOEFPD
           ~                                                                                ..,.,_,             ['-....
                                                                                                                        ~~
           ~
            >                                                                                          i'-. ' ' ' '                                                               ---300 EFPD 0

(ti Q) 3.5

                                                                                                            '   I'        ' ~

3.5

           ~
                                                                                                                                 ~                                                ------- 125 EFPD 3.0                                                                                                           '                                              3.0
                                                                                                                                  ~

2.5 ~ --r----*- ~-- 2.5

                                                                                                                                                                                  --4EFPD
                                                                                                                                     ..... \

2.0

                                                                                                                                          ~~                                  2.0
                                                                                                                                                ~~

1.5 1.5

                                                                                                                                                      ~

1.0

                                                                                                                                                        ~                     1.0
                                                                                                                                                               ~~fl..

0.5 0.5 0.0 I I 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 360 380 400 420 440 460 480 500 520 540

                                                                                                                                                                            0.0 Temperature                                               Each Div. = 4 DEGF Cycle Physics Manual Table A-6

OP-TM-300-000 Revision 8 Page 30 of 42 ATTACHMENT 7.18 Figure 7 Cycle 21 Inverse Boron Worth vs. RCS TAVE Page 1of1 NOTE: Linearly interpolate between EFPD curves. For use with OP-TM-300-206.

 ~
 -a         60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 360 380 400 420 440 460 480 500 520 540
 ~      160                                                                                                                                                                                                                          160 03 E

a. I I I I I I I I I I I I a.

0 125 300 500 680 150 -

                                                                                                                                                                                                                               /     150 Temp.                                EFPD                  EFPD
 '5                     70 EFPD 109.77             107.48                101.82 EFPD 93.95 EFPD 86.24                                                                                             v         .-*

w

  ~     140  -

350 124.46 122.42 116.26 107.50 98.65 /

                                                                                                                                                                                                              ~ .. -** ....          140 532
                                                                                                                                                                                       ~

149.70 147.66 140.52 130.29 120.10 v..

                                                                                                                                                                                                                             /
  .r:.                                                                                                                                                                          _

t:: /---:-:: ,.,.,.,.  ;

                                                                                                                                                                                                                                         --OEFPD 130                                                                                                                                                                              ,,..                                        130 0

s:c:

                                                                                                                                        ~

v  :-:--- "',,..;

                                                                                                                                                                                                              /
                                                                                                                                                                                                                       /                 ------- l 25 EFPD
                                                                                                                                                               ...      /
                                                                                                                                                                    /
                                                                                                                                                                                                  /

0 _..... i--- m 0 120 i--- ~ .. --- .. --

                                                                                                                            --  --      ""'/
                                                                                                                                                           /

v L.--,..../ - 120 ---300EFPD Q.) rJ) Q.) - --- ....- --- -- -- -- -- i--- i---

                                                                                      -~
                                                                                                                 --                                 ,... /
                                                                                                                                                                    /
                                                                                                                                                                                            ...... /
                                                                                                                                                                                                              /
                                                                                                                                                                                                                                         ----- 500 EFPD
   > 110       --* .... ---

110

   =                        ,..- -- --
                                                    --                                                                                          v

_..,..,... v 1..-a-" i--- i---

                                                                                                                                                                                                                                         -B-680 EFPD
               - --                                                                                I--                                                   _..,..,...

_../ 100 i--- i - - ---- ~ 100 i---

               -- ----                                                              i---

I - - i--- 90 80 G-

                  -         I--

I-- 90 80 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 360 380 400 420 440 460 480 500 520 540 Temperature Each Div. = 4 DEGF Cycle Physics Manual Tables 15 and 16

OP-TM-300-206 Revision 3 xe Gen ti Page 1 of 8 Level 2 - Reference Use SHUTDOWN MARGIN FOR LOW TEMPERATURE CONDITIONS 1.0 PURPOSE 1.1 This procedure is used to determine the amount of reactivity by which the reactor could be subcritical. A Shutdown Margin of> 1% ~k/k must be maintained at all times (T.S. 3.5.2.1 ). This procedure assumes that RCS TAVE is

      < 530°F. Shutdown Margin for temperatures ~ 530°F is determined in OP-TM-300-205.

2.0 MATERIAL AND SPECIAL EQUIPMENT None 3.0 PRECAUTIONS, LIMITATIONS, AND PREREQUISITES 3.1 Precautions None 3.2 Limitations None 3.3 Prerequisites 3.3.1 VERIFY all data sources (OP-TM-300-000 attachments, Reactivity Data.sheet, AREVA Physics Data Manual) are for the current fuel cycle. 3.3.2 VERIFY RCS TAVE is < 530°F

OP-TM-300-206 Revision 3 Page 2 of 8 4.0 MAIN BODY NOTE: OP-TM-300-000, Flowchart 2 may be consulted for additional insight into Shutdown Margin determination and suggested actions. A Shutdown Margin of >1 % ~k/k must be maintained at all times (T.S. 3.5.2.1 ). Verification that Shutdown Margin is >1 % ~k/k does not imply that the reactor is subcritical by 1% ~k/k. The qualitative assessment verifies that the Shutdown Margin is

                >1 % ~k/k, but does not provide a numerical value for Shutdown Margin. The quantitative assessment determines a numerical value for Shutdown Margin.

4.1 DETERMINE whether a qualitative or quantitative assessment of Shutdown Margin is desired. 4.1.1 If a qualitative assessment of Shutdown Margin is desired, then DETERMINE Shutdown margin IAW Section 4.2. 4.1.2 If a quantitative assessment of Shutdown Margin is desired, then DETERMINE Shutdown margin IAW Section 4.3. 4.2 Qualitative Assessment of Shutdown Margin 4.2.1 PERFORM assessment per Attachment 7.1 and instructions in Attachment 7.2. 4.2.2 If Shutdown Margin cannot be qualitatively assessed, then DETERMINE Shutdown Margin IAW Section 4.3. 4.2.3 If Shutdown Margin can be qualitatively assessed per Step 4.2.1, then COMPLETE Section 2.0 of Attachment 7.1, Acceptance Criteria. 4.2.4 ENSURE SRO review of Acceptance Criteria. 4.2.5 SEND a copy of the completed Attachment 7.1 to Reactor Engineering.

OP-TM-300-206 Revision 3 Page 3 of 8 4.3 Quantitative Assessment of Shutdown Margin 4.3.1 PERFORM calculation per Attachment 7.3 and instructions in Attachment 7.4 or DTSQA-approved software. 4.3.2 If Shutdown Margin is not more negative than -1 % tik/k, then 1, RE-VERIFY the calculation.

2. INFORM the Shift Manager.

3. NOTIFY Reactor Engineering.

4. TAKE action to satisfy T.S. 3.5.2.1 and 3.5.2.5.

REFER to the following procedures for guidance: OP-TM-AOP-062, Inoperable Rod, to address inoperable control rods OP-TM-EOP-010, Emergency Procedure Rules, Guides, and Graphs, for Emergency Boration guidance 4.3.3 ENSURE an SRO reviews calculations and Acceptance Criteria. 4.3.4 SEND a copy of the completed calculation to Reactor Engineering

OP-TM-300-206 Revision 3 Page 4 of 8 5.0 RETURN TO NORMAL None

6.0 REFERENCES

6.1 Developmental References 6.1.1 BWFC Operating Guidelines 64-1234740-00 6.1.2 TMl-1 Technical Specifications 6.1.3 1103-15A, Shutdown Margin and Reactivity Balance (superseded) 6.2 Implementing References 6.2.1 OP-TM-300-000, Reactivity Management and Power Distribution Calculations 6.2.2 OP-TM-300-401, Inoperable Rod Worth 6.2.3 Physics Data Manual (current cycle) 7.0 ATTACHMENTS 7.1 Shutdown Margin at Low Temperature - Qualitative Assessment 7.2 Shutdown Margin at Low Temperature - Qualitative Assessment Instruction Sheet 7.3 Shutdown Margin at Low Temperature Calculation Data Sheet 7.4 Shutdown Margin at Low Temperature Calculation Instruction Sheet

OP-TM-300-206 Revision 3 Page 5 of 8 ATTACHMENT 7.1 Shutdown Margin at Low Temperature - Qualitative Assessment 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". 1.0 ASSESSMENT IS FOR A SOM AT: D A T E - - - - - - T I M E - - - - - -

1. TAVE - - - - OF

2. Cycle burnup _ _ _ EFPD 3 Plant condition D ~ 350°F Shutdown, CRG 1-7 at 0% WO, :5 1 Control Rod Stuck Out D ~ 70°F Flooded Nozzle, CRG 1-7 at 0% WO, :5 1 Control Rod Stuck Out D ~ 70°F Cold Shutdown, CRG 1-4 at 100% WO, CRG 5-7 at 0%WD D Other ( s p e c i f y ) - - - - - - - - - - - - - - - - - - -

NOTE: For 350°F assessments, no Xenon credit per OP-TM-300-411 may be taken. Reactivity Datasheet values INCLUDE adjustment for actual B-10 depletion.

4. Shutdown concentration corresponding to the condition checked above per Table 6 or Figure 10 or Reactivity Data sheet, including any adjustment for actual B-10 depletion (OP-TM-300-410) and/or Xenon (OP-TM-300-411 ).

_ _ _ _ ppmB

5. Current RCS Boron concentration (CHEMISTRY) _ _ _ _ ppmB

6. VERIFY the current RCS boron concentration (1.5) is greater than or equal to the required shutdown concentration. (Circle one) Yes I No

7. If the answer is "No, then RETURN to Step 4.2.2 in the main body.

2.0 ACCEPTANCE CRITERIA

1. Shutdown margin is verified to be more negative than -1 % ~k/k. (Circle one) Yes I No

2. If Shutdown Margin is not more negative than -1 % ~k/k, then TAKE action to satisfy T.S. 3.5.2.1 and 3.5.2.5 ASSESSED BY _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATEnlME _ _ _ _ _ __

APPROVED BY (SRO) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATE/TIME _ _ _ _ _ __

OP-TM-300-206 Revision 3 Page 6 of 8 ATTACHMENT 7.2 Shutdown Margin at Low Temperature - Qualitative Assessment Instruction Sheet Page 1 of 1 NOTE: Figure numbers refer to attachments in OP-TM-300-000. 1.3 The 350°F shutdown concentration includes a credit for Xenon equivalent to the 80%FP equilibrium Xenon reactivity worth. 1.4 Value for Reactivity Datas.heet is already adjusted for B-10 depletion. The values in Table 6 and Figure 10 were developed assuming maximum B-10 depletion of RCS boron, combined with a boron source at nominal B-10 abundance.

1. 7 If Shutdown Margin cannot be assessed qualitatively, the procedure directs the user to determine it quantitatively.

OP-TM-300-206 Revision 3 Page 7 of 8 ATTACHMENT 7.3 Shutdown Margin at Low Temperature Calculation Data Sheet Page 1 of 1 NOTE: Refer to Attachment 7.4 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". 1.0 CALCULATION IS FOR A SOM AT: D A T E - - - - - - T I M E - - - - - -

1. TAVE ( < 530°F) _ _ _ _ oF

2. Cycle burnup _ _ _ _ EFPD 3 a. Measured Boron Concentration _ _ _ _ ppmB

b. Boron Depletion Correction Factor (PPC, Control Room Log, Reactor Engineering, Reactivity Datasheet)

c. Corrected Boron Concentration (3a x 3b) = ppmB

4. Excess Reactivity (FIG. 1) _ _ _ _ %,A.k/k

5. Xenon Reactivity Worth (PPC, Reactor Engr.) _ _ _ _ %,A.k/k

6. Samarium and Plutonium Buildup Reactivity Worth (FIG. 15) 6a. Time since last shutdown HRS 6b. Reactivity due to samarium and plutonium buildup _ _ _ _ %,A.k/k

7. Inoperable Control Rods 7a. No. of known inoperable rods (>0%WD) 7b. Total inoperable rod worth (OP-TM-300-401) = _ _ _ _%,A.k/k (In addition to the stuck rod required by T.S. included in Line 5)

8. Reactivity Addition Due to Reduced TAVE (FIG. 17) _ _ _ _ %,A.k/k

9. Boron Reactivity Worth at Reduced TAVE 9a. Reduced temperature Inverse Boron Worth (FIG. 7) _ _ _ _ ppmB/%,A.k/k 9b. Total worth (3c / 9a) x (-1) = _ _ _ _ %,A.k/k

10. Shutdown Margin (4 + 5 + 6b + 7b + 8 + 9b) = _ _ _ _ %,A.k/k CAUTION Verification of Shutdown Margin more negative that -1 % L'>k/k does not imply 1% L'>k/k subcriticality.

2.0 ACCEPTANCE CRITERIA

1. Shutdown margin is verified to be more negative than -1 % t,k/k. (Circle one) Yes I No

2. If Shutdown Margin is not more negative than -1 % ,A.k/k, then TAKE action to satisfy T.S. 3.5.2.1 and 3.5.2.5.

CALCULATED BY _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ DATE/TIME------- APPROVEDBY(SRO) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ DATE/TIME _ _ _ _ _ __

OP-TM-300-206 Revision 3 Page 8 of 8 ATTACHMENT 7.4 Shutdown Margin at Low Temperature Calculation Instructions Page 1 of 1 NOTE: Figure numbers refer to attachments in OP-TM-300-000 Data also may be obtained from approved references, e.g., current cycle Physics Data Manual or Reactivity Datasheet.

1. Average RCS Temperature:

With RCP's running or verified natural circulation, if~ 525°F, use RC-12-TA 1 (Center Console TAVE); if< 525°F, use average of Thot and T cold*

2. Cycle Burnup: From FIDMS Display 1 or the Hourly Log.

3a. Measured Boron Concentration: Obtain the latest measured boron concentration from 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, request a new RCS boron measurement. Until the new measurement is available, use OP-TM-300-407 or 409 to estimate the current boron concentration to calculate a preliminary shutdown margin. 3b. Boron Depletion Correction Factor: From PPC, Control Room Log, or Reactor Engineering or Reactivity Data sheet. 3c. Corrected Boron Concentration: Adjust the measured boron concentration to account for boron-10 depletion by multiplying the measured Boron Concentration by the Boron Depletion Correction Factor.

4. Excess Reactivity: From Figure 1.

5. Xenon Reactivity Worth: Obtain xenon worth using the PPC, FIDMS Display 22, or program XENC#

(where# equals the current cycle number). Figure 12 may be used if the PPC and Reactor Engineering are unavailable, provided that power has been constant (+/- 2%FP) for at least 40 hours. For steady state operations, use the current xenon value from FIDMS. For power reductions, xenon reactivity worth will peak (become more negative) and then become less negative over time. Therefore, the xenon contribution to SOM will decrease. To provide a conservative xenon value, use the minimum expected xenon worth value between the time of the current calculation and the time of the next planned SOM calculation. A new SOM calculation should be performed prior to xenon worth becoming less negative than the value assumed in the calculation. For power increases, use the current xenon value from the FIDMS.

6. Samarium and Plutonium Buildup Reactivity Worth: If at power, use 0 Sm and Pu worth. If shutdown, 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.

7. Inoperable Control Rods that are not Fully Inserted: If a control rod is known to be inoperable, a penalty is applied. This is in addition to the stuck rod penalty included in Excess Reactivity (Line 5). If the known inoperable rod is fully inserted, no inoperable rod penalty should be applied. If an inoperable rod is partially inserted, contact Reactor Engineering for possible credit for rod worth. If one or more rods are inoperable, OP-TM-300-401 should be used to determine the inoperable rod worth.

8. Reactivity Addition due to reduced T AvE: From Figure 17.

9. Boron Reactivity worth at reduced T AvE: Divide the Corrected Boron Concentration by the reduced temperature Inverse Boron Worth (Figure 7) and multiply by -1.

OP-TM-300-401 Revision 1 ti Page 1 of 3 Level 2 - Reference Use INOPERABLE ROD WORTH 1.0 PURPOSE 1.1 This procedure is used to determine the penalty associated with known inoperable rods. This supports Shutdown Margin calculations in OP-TM-300-205 and OP-TM-300-206. 2.0 MATERIAL AND SPECIAL EQUIPMENT None 3.0 PRECAUTIONS, LIMITATIONS, AND PREREQUISITES 3.1 Precautions None 3.2 Limitations None 3.3 Prerequisites 3.3.1 VERIFY a known inoperable rod exists in a safety or regulating group. 4.0 MAIN BODY 4.1 PERFORM calculation of inoperable rod worth per Attachment 7 .1. 4.2 ATTACH the calculation to the Shutdown Margin determination.

OP-TM-300-401 Revision 1 Page 2 of 3 5.0 RETURN TO NORMAL None

6.0 REFERENCES

6.1 Developmental References 6.1.1 1103-15A, Shutdown Margin and Reactivity Balance (superseded) 6.2 Implementing References 6.2.1 OP-TM-300-000, Reactivity Management and Power Distribution Calculations 6.2.2 OP-TM-300-205, Shutdown Margin for Hot Shutdown Conditions 6.2.3 OP-TM-300-206, Shutdown Margin for Low Temperature Conditions 7.0 ATTACHMENTS 7.1 Determination of Inoperable Rod Worth

OP-TM-300-401 Revision 1 Page 3 of 3 ATTACHMENT 7.1 Determination of Inoperable Rod Worth Page 1 of 1 NOTE: Data may be entered in any sequence. Sign-off verifies all data entered as required. Approval signature indicates an "Independent Verification". Use the Date, Time, and EFPD from the Shutdown Margin determination. CALCULATION IS FOR: DATE TIME _ _ _ __ EFPD - - - - To be used with Attachment 7.1 of (circle one): OP-TM-300-205 OP-TM-300-206

1. IDENTIFIED INOPERABLE RODS:

If the identity of an inoperable rod is known, use the inoperable rod worth provided in OP-TM-300-000 Attachment 7.3 for each inoperable rod. 1a. Identified Inoperable Rod Location(s) 1b. Summation of Identified Inoperable Rod Worth(s) - - - %~k/k

2. UNIDENTIFIED INOPERABLE RODS: If one or more control rods are known to be inoperable, but the identity of the rod(s) is not known, complete the following:

2a. Unidentified Inoperable Rod Worth (Figure 4)

                                                                           - - - %~k/k 2b.      No. of Inoperable Rods (>0% WD) 2c. Total Unidentified Inoperable Rod Worth (2a x 2b)   =         - - - %~k/k

3. TOTAL INOPERABLE ROD WORTH (1b + 2c) = - - - %~k/k

4. RECORD total inoperable rod worth on OP-TM-300-205 Attachment 7 .1 or on OP-TM-300-206 Attachment 7.1, at the requested step as applicable. Attach to the applicable attachment.

RECORDED BY _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATE/TIME _ _ _ __ APPROVED BY (SRO) _ _ _ _ _ _ _ _ _ _ _ _ DATE/TIME _ _ _ __

OP-TM-300-000 Revision 8 Page 14 of 42 ATTACHMENT 7.3 Table 1 Cycle 21 Known Inoperable Rod Worth Page 1 of 1 NOTE: For use with OP-TM-300-401. Cycle 21 Group# - Rod # 4 - <125 EfPD 125 - <500 EFPD 500 - 680 Ef PO (1/8th Core Symm. Loe.)  %~/k  %~k 3ak/k 6-1, 6-3, 6-5, 6-7 (H-14} 0.262 0.422 0.308 7-1, 7-3, 7-5, 7-7 {H-12) 0.271 0.316 0.302 2-1, 2-3, 2-5, 2-7 (H-10) 0.100 0.100 0.100 7-9 ~H-8} 0.100 0.100 0.100 5-1, 5-3, 5-4, 5-6, 5-7,, 5-9, 0.893 0.964 0.851 5-10, 5-12 OC-13) 4-1, 4-2, 4-3.t 4-4, 4-5, 4-6, 0.334 0.339 0.339 4-7, 4-8 (K-11) 2-2, 2-4, 2-6, 2-8 (<-9} 0.100 0.100 0.100 1-1.. 1-2, 1-3, 1-4, 1-5, 1-6, 1364 1A51 l.495 1-7, 1-8 (L-14) 6-2, 6-4, 6-6, 6-8 (L-10} 0.331 0.249 0.222 3-1, 3-2, 3-3, 3-4, 3-5, 3-6, 1.618 1.618 1.724 3-7, 3-8 irv1-13} 5-2, 5-5, 5-8, 5-11 (M-11) 1.144 0.929 0.682 7-2, 7-4, 7-6, 7-8 (N-12) 1.618 1.618 1.724 Cycle Physics Manual Table A-4

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 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 NRCJPM 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 210 inches (RC-Ll-777 A 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 RA1-2 NU REG 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 . (APL}*(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 (AMTL}*(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 NRC JPM RA1-2 NUREG 1021, Revision 10

Appendix C Page 5 of 8 Form ES-C-1 PERFORMANCE INFORMATION "\/ Performance Step: 5 Determine RCS Tave temperature change. (A Tavg)*(COEFF) = (579.2-578.8)(95) =38 Standard: Examinee calculates RCS Tave change over the time period given by: RCS Tave initial - RCS Tave final Examinee 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 151 3 minutes= 360 Gallons Standard: Examinee 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: Examinee calculates the time period for the Leak Rate determination by; Then records this time change in minutes 1 Comment: ILT16-01 NRC JPM RA1-2 NUREG 1021, Revision 10

Appendix C Page 6 of 8 Form ES-C-1 PERFORMANCE INFORMATION -I 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== [(APL)*(12) + (AMTL)*(30) - (ATavg)*(COEFF) +GAL ADD] I ATIME 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 NRCJPM 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-777 A 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 I

• 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

Number TMI - Unit 1 Operations Department Administrative Procedure OS-24 Title Revision No. Conduct of 0 erations Durin Abnormal and Emergenc Events 28 ATTACHMENT F Page 2 of 3 PPC Tools for estimating RCS leakrate and the limitations of these tools

1. "FLOBAL" (C4054) AND "MASBAL" (C4053)

• Calculation is updated each minute based on data from last 5 or 6 minutes.
• Feed or bleed operations are not accounted for in either the MASBAL or FLOBAL calculation.
• Flow inputs for each HPI line flow will be zero GPM if flow is < 65 GPM.

Reference:

PPC Guide Section 27.0. C4053 and C4054 are set to BAD (no value displayed) if any of the following conditions exist:

• Cooldown rate (5 min avg)> 100°F /HR
• SCM < 25°F
• RCS pressure < 350 psig
• Reactor power !!.. > 25% in 5 minutes ECCS Reactor Building Sump In-Leakage Rate (C4038)
• Calculated every 60 seconds, using the average of the two ECCS RB Sump Level indications (A0447 and A0448). Point is only valid if level is 3" - 90".
• Calculated using the following:

3* - 10": 102.85 gal/inch 10" - 24": 143.97 gal/inch 24"-68": 102.85 gal/inch 68" - 90": 112.20 gal/inch

3. Normal RB Sump lnleakage (C4232)

Calculated every 15 minutes using C4235 Average Normal RB Sump Level. The calculation uses 9.35 Gal/Inch It will indicate invalid if <3.5 inches in the sump or if sump level is lowering.

4. Primarv Secondary Leakrate (C4042)

• 10 minute average of calculation based on current RM-A-5 c:;ounts and previous chemistry analysis of RCS and OFF-Gas activity.

Reference:

PPC Guide Section 16.2.15 37

Number TMI - Unit 1 Operations Department Administrative Procedure OS-24 Title Revision No. Conduct of 0 erations Durin Abnormal and Emergenc Events 28 ATTACHMENT F Page 3 of 3 PPC Tools for estimating RCS leakrate and the limitations of these tools C4042 will not be calculated if:

• RM-L-1 Lo (C4022) changes by 100% from value when last correction factor was entered
• RM-A-5 < 200 CPM
• Correction factor is older than 7 days
• Condenser vacuum < 23 "Hg Vac 38

Number TMI - Unit 1 Oper~tions Department Administrative Procedure OS-24 Title Revision No. Conduct of 0 erations Durin Abnormal and Emergenc Events 28 ATTACHMENT F Page 1of3 Transient RCS Leakrate Calculation Methodology

a. This method should not be relied upon for leakrate determinations at < 5 GPM. The uncertainty in the result will vary greatly based on the stability of RCS conditions.

b. 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.

c. In order to collect data points at the same time, the required plant parameters should be put on the same computer group so they can be printed out and then used in the calculation.

RCS leakrate (GPM) = [(APL)*(12) + (AMTL)*(30) - (ATavg)*(COEFF) +GAL ADD] I ATIME APL = change in Pressurizer Level (Computer Point C4017) (initial - final inches) AMTL = change in Makeup Tank Level (Computer Point A0498) (initial - final inches) ATavg =change in RCS Average Temperature (Computer Point A5066) (initial - final °F) GAL ADD = gallons added to the MU/RCS systems during the observation period ATIME =change in time (final - initial minutes) COEFF = 95 gall°F if Tavg is 579 °F otherwise use the table below Average RCS temperature COEFF over period of evaluation (GAL/OF) 579 95 555 90 532 84 510 78 485 72 450 66 385 54 350 48 305 42 270 38 36

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 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: 15 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 NUREG 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 4of12 Form ES-C-1 VERIFICATION OF COMPLETION 1301-1 DATA Sheet 1, A.8 Performance Step: 4 RPS TOT AL 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?

Standard: 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: 10 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 NUREG 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 A0476 and A0477;::: 585 psig and :5 615 psig?
• Is CF-V-1A open?
• Is CF2-Ll3 (A0482) and CF2-Ll4 (A0483) ;::: 11.29 and :5 11.87 ft?
• Is A0478 and A0479;::: 585 psig and :5 615 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 -I 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 MAKEUPTANKLEVEL&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 MU 14/RC1 -LR CH2 (L T1 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 NUREG 1021, Revision 10

Appendix C Page 9of12 Form ES-C-1 VERIFICATION OF COMPLETION 1301-1 DATA Sheet 1, A.20 Performance Step: 26 PRESSURIZER LEVEL

• Do RC-Ll-777A and PPC 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 PPC A0504 is the non-selected pzr temperature instrument.

• Do RC2-TE1 & RC2-TE2 values agree within 20 1 F?

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 NU REG 1021, Revision 10

Appendix C Page 10of12 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 '\/ 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 NUREG 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 NU REG 1021, Revision 10

Appendix C Page 12 of 12 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

1301-1 Revision 176 DATA SHEET 1 Page 3 of 7 "Checks Applicable at >Hot Shutdown Through Power Operations" SECTION A Shiftly Checks to Be Made At 2100 and 0900 +/- 1 Hour (Frequency per T.S. Table 1.2) 2100 +/- 1 0900 +/- 1 A.6 RPS T HOT Tech. Spec. 4.1-1.7 and 3.5-1A.5 Compare: RC4A-TE2 (A0590) with RC4A-TE3 (A0592) and RC4B-TE2 (A0591) with RC4B-TE3 (A0593) Does each comparison agree within+/- 1.75°F? (Circle Y/N) YI N YI N A.7 RPS IMBALANCE Tech. Spec. 4.1-1.4 and 3.5-1A.7 when >15% power. Do Nl-5 (A0626), Nl-6 (A0627), Nl-7 (A0628) and Nl-8 (A0629) .M> values all agree within 2.5%? (Circle Y/N/NA) YIN I NA Y/N/NA A.8 RPS TOT AL RCS FLOW Tech. Spec. 4.1-1.10 and 3.5-1A.7 Do RC14-DPT1 (A0602), RC14-DPT2 (A0603), RC14-DPT3 (A0604), RC14-DPT4 (A0605) values all agree within 7.2 MLB/hr? (Circle Y/N) YI N YI N A.9 INTERMEDIATE RANGE FLUX Tech. Spec. 4.1-1.5 and 3.5-1A.3 Do Nl-3 (A0576) and Nl-4 (A0577) values agree within one-half log amp? (Circle Y/N) YI N YI N Do Nl-3 (A0580) and Nl-4 (A0581) SUR values agree within one-half DPM? (Circle Y/N) Y I N Y I N A.10 ES WIDE RANGE RCS PRESSURE Tech. Spec. 4.1-1.15/17, 3.5-1C.1.a/2.a/2.c, and 3.5-1C.3.e Do RC3A-PT-3 (A0505), RC3A-PT4 (A0506), RC3B-PT3 (A0507) values agree within 50 psi? (Circle Y/N) YI N YI N A.11 ES RB PRESSURE Tech. Spec. 4.1-1.19a, 3.5-1C.1b/2.b, and 3.5-1C.3.a Do BS-PT-282 (A0101 ), BS-PT-285 (A0102) & BS-PT-288 (A0103) values agree within 0.5 psi? (Circle Y/N) YI N YI N A.12 REACTOR BUILDING Tech. Spec. 3.6.4 Is Reactor Building pressure greater than 1.0 psi vacuum and less than 2.0 psig? (Preferred instruments: BS-Pl-982B, BS-Pl-1186) YI N YI N A.13 REACTOR BUILDING 4# ESAS ACTUATION Tech. Spec. 3.5-1C.1.b/2.b/3.a, 4.1-1.19a Are all blue lights for channels RB1, 2 & 3 A&B (groups 1, 2, & 3) de-energized? (Circle Y/N) Y I N YI N Are ESAS actuation channels RB1, 2 & 3 A&B all enabled? (Circle Y/N) YI N Y I N 11

1301-1 Revision 176 DATA SHEET 1 Page 4 of 7 "Checks Applicable at >Hot Shutdown Through Power Operations" SECTION A Shiftly Checks to Be Made At 2100 and 0900 +/- 1 Hour (Frequency per T.S. Table 1.2) 2100 +/- 1 0900 +/- 1 A.14 REACTOR COOLANT SYSTEM 1600# ESAS ACTUATION Tech. Spec. 3.5-1C.1.a/3e, 4.1-1.19b Are all blue lights for channels RC1, 2 & 3 A&B (groups 1 & 2) de-energized? (Circle Y/N) YI N YI N Are ESAS actuation channels RC1, 2 & 3 A&B all enabled? (Circle Y/N) Y I N Y I N A.15 REACTOR COOLANT SYSTEM 500# ESAS ACTUATION Tech. Spec. 3.5-1C.2.a Are ESAS actuation channels RC4, 5 & 6 A&B all enabled? (Circle Y/N) Y I N YI N A.16 REACTOR BUILDING 30# ESAS ISOLATION Tech. Spec. 3.5-1C.3.d, 4.1-1.19d Are all blue lights for channels RB4, 5 & 6 A&B de-energized? (Circle Y/N) YI N YI N Are ESAS actuation channels RB4, 5 & 6 A&B all reset? (Circle Y/N) Y I N YI N A.17 REACTOR TRIP CONTAINMENT ISOLATION Are RTI actuation channels RT1, 2 & 3 A&B all enabled? (Circle YIN) Y I N YI N A.18 CORE FLOODING SYSTEM/CORE FLOOD TANK LEVEL Tech. Spec. 3.3.1.2.a, 4.1-5 Using the operable instruments only: (Circle Y/N for each) Is CF2-Ll1 (A0480) and CF2-Ll2 (A0481) ~ 11.29 and~ 11.87 ft? YI N YI N

            *is A0476 and A0477 ~ 585 psig and~ 615 psig?                      Y I N         Y I N Is CF-V-1A open?                                                  Y I N         YI N Is CF2-Ll3 (A0482) and CF2-Ll4 (A0483) ~ 11.29 and ~ 11.87 ft?    YI N          Y I N Is A0478 and A0479    ~ 585 psig and~ 615 psig?                   Y I N         YI N Is CF-V-1 B open?                                                 YI N          Y I N Is CF-T-1A boron concentration between 2317 (Tech. Spec. 3.3.1.2.b) and 2850 PPM?                                                              Y I N         Y I N Is CF-T-18 boron concentration between 2317 (Tech. Spec. 3.3.1.2.b) and 2850 PPM?                                                              Y I N         YI N 12

1301-1 Revision 176 DATA SHEET 1 Page 5 of 7 "Checks Applicable at >Hot Shutdown Through Power Operations" SECTION A Shiftly Checks to Be Made At 2100 and 0900 +/- 1 Hour (Frequency per T.S. Table 1.2) 2100 +/- 1 0900 +/- 1 A.19 MAKEUP TANK LEVEL & PRESSURE Tech. Spec. 4.1--1.27 Do CPT #A0498 and A0426 agree within 2 inches and MU14/RC1-LR CH1 & MU-Ll-778A agree within 3 inches? (Circle Y/N) Y I N YI N Record local MU tank pressure indication, MU-Pl-1752. Do A1028 and MU17-PI agree with the local MU Tank pressure indication (MU-Pl-1752) within 3 psi? (Circle Y/N) YI N YI N A.20 PRESSURIZER LEVEL Tech. Spec. 4.1-1.26, 3.1.3 and Table 3.5-2 Do RC-LT-777 (A1029), RC1-LT1 (C1720) and RC1-L T3 (C1722) values agree within 12 inches? (Circle Y/N) YI N YI N Do MU 14/RC1-LR CH2 (L T1 or LT3) and its corresponding XMTR on the PPC (C1720 or C1722) agree within 1O"? (Circle Y/N) YI N YI N Do RC-Ll-777A and PPC point A1029 agree within 10"? (Circle Y/N) YI N YI N Is pressurizer level between 80 to 385 inches? (Circle Y/N) YI N YI N A.21 PRESSURIZER TEMPERATURE Tech. Spec. 4.1-1.22 Record Pressurizer temp RC2-TI (CC) NOTE PPC A0504 is the non-selected pzr temperature instrument. Do RC2°TE1 & RC2-TE2 values agree within 20°F? (Circle Y/N) YI N YI N A.22 SATURATION MARGIN MONITOR Tech. Spec. 4.1-1.49 and Table 3.5-2 Record RCS Loop A sat margin RC-Tl-977 (PCL) Record RCS Loop B sat margin RC-Tl-978 (PCL) Do RC-Tl-978, CPT #A0406, RC-Tl-977, & CPT #A0938 all agree within 6.5°F? (Circle Y/N) YI N YI N 13

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 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 NUREG 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. Procedure: EP-AA-112-1 OO-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" ILT 16-01 NRC JPM RA4 NUREG 1021, Revision 10

Appendix C Page 3of12 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~os 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: Examinee 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 12 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 5 of 12 Form ES-C-1 PERFORMANCE INFORMATION EP-AA-112-100-F-06, Step 1.8 Performance 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 NUREG 1021, Revision 10

Appendix C Page 6of12 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: 1O 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 7 of 12 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: 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: 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: Examinee 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: Examinee goes to Section 3. Comment: ILT 16-01 NRC JPM RA4 NUREG 1021, Revision 10

Appendix C Page 8of12 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 uses 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 - 1-857-444-0443 "\/ Standard: Examinee dials 1-857-444-0443. Comment: ILT 16-01 NRC JPM RA4 NUREG 1021, Revision 10

Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER NOTE: Steps 3.4 and 3.5 are N/A. EXAMINER CUE: 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

                                # sign, then ENTER the User ID provided in step 3.1 .
..,/ Standard:                 Examinee enters 730145#

Comment: 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 NU REG 1021, Revision 10

Appendix C Page 10of12 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 # ..,/ 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 11 of 12 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 12 of 12 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 NU REG 1021, Revision 10

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 n Revision V Training Page 1 of 16 ERO NOTIFICATION OR AUGMENTATION 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 Section 4- Initiate Activation of Alternate Notification System using World Wide Web Section 5- Initiate Activation of Alternate Notification System using a Standard Phone Section 6- Initiate Activation I Termination of Notification System using Station-applicable Call Trees

1. INITIATE A~TIVATION l IERMINATIQN OF NOTIFICATION SYSTEM USIN~ THE WORLD WIDI; WEB

~ CIRCLE the appropriate station specific User Name and Station Password D number from the table below. Station User Name Password Braidwood braidwood3 simulator01# Byron blackhawk.3 simulator02# Clinton clinton3 simulator03# Dresden dresden3 simulator04# LaSalle lasalle3 simulator05# Limerick limerick3 simulator06# Oyster Creek oystercreek3 simulator07# Peach Bottom peachbottom3 simulator08# Quad Cities quadcities3 simulator09# 'TM!) Cthreemileislan~ (§iulator1 o#J Document Retention SRRS ID - 5B.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 2of16 ERO NOTIFICATION OR AUGMENTATION lrg; CIRCLE the appropriate Activation I Termination Scenario event from the table below . D

                   ./"\.._
    "-""\...->

1 - Actual Event 02-Unusual 03 - Actual Event 04- Event 05 - Activation Respond to Event Alternative Facility Termination Cancellation Facility Response Unusual Notification to all Notification to all For Alert, Site Events For Events with Off ERO Members, ERO Members, Area, or General excluding Site ERO reporting Station Station Emergency, or Security location requirements Management and Management Security Events Events as determined by the EOF Responders and EOF with On Site ERO (HU1) Emergency Director that event has Responders that reporting CM-1 been terminated. activation has

  *Optional for all                                                               been cancelled.

other unusual Events Document Retention SRRS ID - 5B.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 3of16 ERO NOTIFICATION OR AUGMENTATION 1.3. OPEN (double-click) the Everbidge shortcut icon from your desktop D computer. If shortcut Icon is D.Q1.available or is !lQifunctioning, then OPEN a web browser, then TYPE https://manager.everbridge.net/login. A. If internet is D.Q1.available, then GO TO Step 2. NOTE: User Name and Passwords are case sensitive and will lock out after four (4) failed attempts. 1.4. ENTER the appropriate station specific User name and Password from Step 1.1 and SELECT (click) "Sign In". D 1.5. VERIFY the appropriate Station Name is displayed, SELECT (click) D "Proceed". 1.6. SELECT (click) the +Launch Incident button. D 1.7. SELECT (Click) on the appropriate Scenario from Step 1.2. 1.8. VERIFY the appropriate Scenario is displayed. D 1.9. If the scenario displayed is !lQicorrect, then SELECT (click) correct D scenario from list and RETURN to Step 1.8. 1.10. If the scenario displayed is correct, then SELECT (click) "Send x D template(s) Now". 1.11. On the next screen, VALIDATE there is a date and time stamp for each D notification listed. RECORD Time 1.12. SELECT "Log Out" to exit the Everbridge Notification program. D 1.13. VERIFY that a call to the Control Room from the ERO notification system is D received within 2 minutes after the system was initiated. 1.14. RECORD time of the confirmation call to the Control Room D 1.15. If a confirmation call is not received in the Control Room within 2 minutes D confirming scenario activation, then PROCEED to Section 2, Initiate Activation I Termination of Notification System Using Live Everbridge Agent. 1.16. INFORM the Shift Emergency Director of the status of the ERO Notification D System Initiation and EXIT this procedure. Document Retention SRRS ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 4of16 ERO NOTIFICATION OR AUGMENTATION

2. INITIATE AC!IVATIQ~ l TERMINA!ION QF ~QTIFl~ATIQN SYSTEM USING LIVE EVERBRIDGE AGENT 2.1. CIRCLE the appropriate station specific Account Name, Organization Name, D First name, Last name and response to Hint Question from the table below.

Account Name Organization First Name Last name Response to Name (Station) Hint Question Braidwood Braidwood ERO NS Exelon Activator Exelon Generation Byron Byron ERONS Exelon Company LLC Activator Clinton Clinton ERO NS Exelon Activator NOTE: Dresden Dresden ERONS Exelon Everbridge will Activator then ask for your LaSalle LaSalle ERONS Exelon organization. Activator Provide your station name Limerick Limerick ERO NS Exelon for your Activator response. Oyster Creek Oyster Creek ERO NS Exelon Activator Peach Bottom Peach Bottom ERONS Exelon Activator Quad Cities Quad Cities ERO NS Exelon Activator TMI TMI ERO NS Exelon Activator Document Retention SRRS ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 5of16 ERO NOTIFICATION OR AUGMENTATION 2.2. CIRCLE the appropriate Activation Scenario Number for the event from the D table below. 01 -Actual 02- Unusual 03 - Actual Event 04- Event 05 - Activation Event Respond Event Alternative Facility Termination Cancellation to Facility Response Unusual Events Notification to all Notification to all For Alert, Site excluding For Events with Off ERO Members, ERO Members, Area, or General Security Events Site ERO reporting Station Station Emergency, or (HU1) location Management and Management Security Events requirements as EOF Responders and EOF with On Site CM-1 determined by the that event has been Responders that ERO reporting Emergency Director terminated. activation has

 *Optional for all                                                                 been cancelled.

other unusual Events Document Retention SRRS ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 6of16 ERO NOTIFICATION OR AUGMENTATION 2.3. DIAL the ERO Notification System Activation phone number: 1-877-220- D 4911. 2.4. If the number is busy or does !!Qianswer after a 2nd attempt, then D PROCEED to Section 3 Initiate Activation I Termination of Notification System Using Standard Phone. 2.5. When asked for your Everbridge Account Name, Organization Name, First D name, Last Name and Hint question, then PROVIDE the appropriate information from step 2.1. 2.6. ASK the Live Everbridge Agent if there is a current "Incident" Broadcast D running for your station. 2.7. If the Live Everbridge Agent confirms the appropriate scenario has been D activated, then STOP here and do not proceed with steps 2.8 to 2.16 below. 2.8. If the Live Everbridge Agent confirms that the appropriate scenario has llQ1 D been activated, then PROCEED to step 2.9. 2.9. INFORM the Everbridge Agent that you would like to Launch a Scenario. D 2.10. When asked for the Scenario number, then STATE the appropriate D Scenario number followed by the corresponding name of the Scenario you wish to launch. PROVIDE the appropriate information from step 2.2. 2.11. When asked by the Everbridge Agent "Would you like me to send this D scenario (message) now?", then REPLY Yes. 2.12. VERIFY with the Everbridge Agent that the ERO Activation scenario has D been successfully initiated. A. If Everbridge Agent indicates that ERO Activation scenario was D unsuccessful or that there is a problem with the Everbridge system and cannot successfully activate the scenario, then PROCEED to Section 4*, Initiate Activation of Alternate Notification System using the World Wide Web. Document Retention SRRS ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 7of16 ERO NOTIFICATION OR AUGMENTATION 2.13. RECORD the Broadcast ID number time 0 2.14. VERIFY that a call to the Control Room from the ERO notification system is 0 received within 2 minutes after the system was initiated. 2.15. RECORD time of the confirmation call to the Control Room 0 2.16. If a confirmation call is .ll.Qireceived in the Control Room within 2 minutes 0 confirming scenario activation, then PROCEED to Section 3, Initiate Activation I Termination of Notification System Using Standard Phone. 2.17. INFORM the Shift Emergency Director of the status of the ERO Notification 0 System Initiation and EXIT this procedure. Document Retention SRRS ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 8of16 ERO NOTIFICATION OR AUGMENTATION

3. INITIATE A~TIVATIQN l TEBMINATIQN OF NQTIFICATIQN SYSTEM USING STANDARD PHQNE 3.1. CIRCLE the appropriate station specific User ID, Station Password number D and Organization ID from the table below.

Station User ID Password Organization ID Braidwood 728993# 993661# 728993# Byron 828536# 536611# 828536# Clinton 728994# 993691# 728994# Dresden 729007# 007971# 729007# LaSalle 729008# 008001# 729008# Limerick 730135# 135761# 730135# Oyster Creek 730189# 189741# 730189# Peach Bottom 730144# 143281# 730144# Quad Cities 729009# 008031# 729009# TMI 730145# 143311# 730145# 3.2. CIRCLE the appropriate Activation I Termination Scenario Number for the D event from the table below. 1 - Actual Event 2- Unusual 3 - Actual Event 4- Event 5 - Activation Respond to Event Alternative Termination Cancellation Facility Facility Response Unusual Events Notification to all Notification to all For Alert, Site Area, excluding For Events with Off ERO Members, ERO Members, or General Security Events Site ERO reporting Station Station Emergency, or (HU1) location Management and Management Security Events with CM-1 requirements as EOF Responders and EOF On Site ERO determined by the that event has Responders that reporting Emergency been terminated. activation has Director been cancelled. 3.3. DIAL the Everbridge system activation phone number 857-444-0443. D 3.4. If the number is busy or does filll_answer after a 2nd attempt, then DIAL the D Document Retention SRRS ID - 5B.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 9of16 ERO NOTIFICATION OR AUGMENTATION ERO Notification System Activation Alternate phone number 800-971-5015. 3.5. If the alternate phone number is busy or does not answer after a 2nd attempt, D then PROCEED to Section 4, Initiate Activation of Alternate Notification System using the World Wide Web. 3.6. When the System prompts "Enter your USER ID followed by the# sign", D then ENTER the User ID provided in step 3.1. 3.7. When the system prompts "Enter your Password followed by the # sign" D then ENTER the Password provided in step 3.1. 3.8. When the system prompts "Enter your Organization ID followed by the# D sign", then ENTER the Organization ID provided in step 3.1. 3.9. When prompted, "To select a template or scenario, Enter the ID followed by D the# sign", then ENTER the ID provided in step 3.2. A. For "Actual Event with Respond to Facility" PRESS 1 Then# D B. For "Unusual Event" PRESS 2 Then # D C. For "Actual Event Alternative Facility Response" PRESS 3 Then# D D. For "Event Termination" PRESS 4 Then# D E. For "Activation Cancellation" PRESS 5 Then# D 3.10. The System will state the name of the scenario. To select this scenario press D 1 to send the message now or 2 to select a different scenario. A. If the event name is correct, then PRESS 1. D B. If event name is !!21..correct, then PRESS 2 and RETURN to step 3.9. D Document Retention SRRS ID- 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 10of16 ERO NOTIFICATION OR AUGMENTATION 3.11. When the activation is complete and the System states "Your message has D been sent", then HANG UP the phone. 3.12. RECORD the time of the scenario broadcast D 3.13. VERIFY that a call to the Control Room from the ERO notification system is D received within 2 minutes after the system was initiated. 3.14. RECORD time of the confirmation call to the Control Room D 3.15. If a confirmation call is llQ1.received in the Control Room within 2 minutes D confirming scenario activation, then PROCEED to Section 4, Initiate Activation of Alternate Notification System using the World Wide Web. 3.16. INFORM the Shift Emergency Director of the status of the ERO Notification D System Initiation and EXIT this procedure. Document Retention SRRS ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 11 of 16 ERO NOTIFICATION OR AUGMENTATION

4. INITIATE ACTIVATION QF ALTERNATE NOTIFICATIO~ SYSTEM USING TH~

WQRLD WIDE W~B 4.1. CIRCLE the appropriate station from the table below. D Station User ID Password Braidwood 010101 010101 Byron 020202 020202 Clinton 050505 050505 Dresden 070707 070707 LaSalle 090909 090909 Limerick 101010 101010 Oyster Creek 121212 121212 Peach Bottom 131313 131313 Quad Cities 141414 141414 TMI 151515 151515 4.2. CIRCLE the appropriate Activation for the event from the table below. D 01 - Actual Event 03 - Actual Event Respond to Facility Alternative Facility

Response

For Alert, Site Area, or General Emergency. For Security events or other events as

      *Optional for Unusual        determined by the Event.              Emergency Director.

Document Retention SRRS ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 12of16 ERO NOTIFICATION OR AUGMENTATION 4.3. OPEN a web browser and TYPE: https://myportal.opentext.com/ in the address D bar. A. IF the internet is not available, then GO to Section 5. 4.4. ENTER the appropriate station specific Username and Password from Step 4.1 D and SELECT "Sign In". 4.5. CLICK on the arrow in the Create/Send Job bar, then CLICK on Mixed Media. D 4.6. SELECT the appropriate template from the drop down from step 4.2. D 4.7. VERIFY the appropriate template is displayed. D 4.8. If template displayed is .ll.Qlcorrect, then PROCEED to Section 5, Initiate D Activation of Alternate Notification System using telephone activation. 4.9. IF the template displayed is correct, then CLICK Review & Send. D A. VERIFY the appropriate information is displayed. B. CLICK on "Submit". 4.10. On the next screen, VALIDATE that the message sent by receiving a green box D with the message job number. Record Job No Record Time 4.11. If a green confirmation box is .Il.21.displayed, then PROCEED to Section 5, D Initiate Activation of Alternate Notification System using telephone activation. 4.12. CLICK the 'x' in the green box. D 4.13. SELECT 'Sign Out' to Exit the Easylink Notification program. D 4.14. INFORM the. Shift Emergency Director of the status of the Alternate ERO D Notification System Initiation and EXIT this procedure. Document Retention SRRS ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 13of16 ERO NOTIFICATION OR AUGMENTATION

5. INITIATE A~TIVATIQN QF ALTERNATE NOTIFICATION SYSTEM USING A STANDARD PHQ~E 5.1. CIRCLE the appropriate station from the table below. D Station User ID Password Distribution List Number Braidwood 010101 010101 010101 Byron 020202 020202 020202 Clinton 050505 050505 050505 Dresden 070707 070707 070707 LaSalle 090909 090909 090909 Limerick 101010 101010 101010 Oyster Creek 121212 121212 121212 Peach Bottom 131313 131313 131313 Quad Cities 141414 141414 141414 TMI 151515 151515 151515 Document Retention SRRS ID - 5B.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 14of16 ERO NOTIFICATION OR AUGMENTATION 5.2. CIRCLE the appropriate Activation Script for the event from the table below. D 01 - Actual Event 03 - Actual Event Respond to Facility Alternative Facility

Response

For Alert, Site Area, or General Emergency. For Security events or other events as

    *Optional for Unusual        determined by the Event.             Emergency Director.

5.3. DIAL the Easylink toll free number 1-866-515-0663. D 5.4. When the System prompts "Enter your USER ID,# sign, then your Password,# D sign", then ENTER the User ID and Password provided in step 5.1. NOTE: You will be prompted to "Wait while we verify your ID and password" 5.5. When the System prompts "To create a message, Press 1", then ENTER 1. D 5.6. When the System prompts "To enter a distribution list, Press 1", then ENTER 1. D 5.7. When the System prompts "Enter your distribution list followed by the # key, D then ENTER the list number provided in step 5.1. 5.8. When the System prompts "To confirm Press 1, to reenter your list number D Press#", then ENTER 1 to confirm or# to reenter the number. Document Retention SRRS ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 15of16 ERO NOTIFICATION OR AUGMENTATION NOTE: Step 5.1 O through 5.12 applies to stations that are supported by the Emergency D Operations Facilities at Cantera or Coatesville. All other stations can move to step 5.13. 5.9. When the system prompts "Press 1 to enter a second distribution list number then PRESS 1 . 5.10. When the system prompts "Enter the distribution list number followed by the # D sign", then ENTER the appropriate distribution number provided below: Stations Emergency Operations Facility Distribution List Number Braidwood 040404 Byron Clinton Cantera Dresden LaSalle Quad Cities Limerick 060606 Peach Bottom Coatesville Three Mile Island 5.11. When the System prompts "To confirm Press 1, to reenter your list number D Press#", then ENTER 1 to confirm or# to reenter the number. 5.12. When the system prompts "Press 2 to Record Your Message" then PRESS 2. D 5.13. When the system prompts, "Press# to play the same message for both live and D answering machine recipients", then PRESS #. 5.14. When the system prompts, "Press 2 to Select a Script", then PRESS 2. D 5.15. When the system prompts, "Press 1 to Enter a Script Number, then PRESS 1. D 5.16. When the system prompts, "Enter Script Number", the ENTER the script D number provided in step 5.2. 5.17. When the system prompts, "Press 1 to Confirm Script Number", then PRESS 1. D 5.18. When the system prompts, "For Immediately Delivery Press 1" then PRESS 1. D Document Retention SRRS ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 16of16 ERO NOTIFICATION OR AUGMENTATION 5.19. RECORD the job number provided by the system. D Record Job No Record Time 5.20. When the system prompts, "Press 9 to end the call" then PRESS 9. D 5.21. IF you do D..Q!_receive a job number, then PROCEED to Section 6, Initiate D Activation/Termination of Notification System Using Station-Applicable Call Trees. 5.22. INFORM the Shift Emergency Director of the station of the ERO Notification D System Initiation and EXIT this procedure.

6. INITIATE A~TIVATIQNlTERMINATIQN QF NQTIEl~ATIQN SYSTEM USIN~

STATIQN-APPLl~AaLI; ~ALL TREES 6.1. NOTIFY or AUGMENT ERO by using station-applicable call tree located on D the station EP website.

7. REFERENCES 7 .1 . Commitment CM-1: Regulatory Commitment Number 5 identified in Attachment 11 of Letter to NRC dated Aug 1_7, 2005, (RS-05-101 ). (Steps 1.2, 2.2, 3.2)

Document Retention SRRS ID - 58.100

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 Examines: 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)
• SR03-STA
• RO 1 -URO
• RO 2-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.

Task Standard: Examinee identifies required actions to restore minimum staffing, and selects personnel in accordance with requirements to control overtime. ILT 16-01 NRC JPM SA1-1 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet 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 Qua I Matrix Report (Attachment #1)
• Prepared Overtime List (Attachment #2)
• A disconnected phone for simulation General

References:

• Technical Specifications Handout:
• OP-TM-112-101-1002, Shift Staffing Requirements, Rev. 10
• LS-AA-119, Overtime Controls, Rev. 12
• LMS Qua I 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, LMS Qual Matrix Report, and Overtime list. ...J 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 hours 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. Standard: Action initiated by referring to Overtime list Comment: ILT 16-01 NRC JPM SA1-1 NUREG 1021, Revision 10

Appendix C Page 4of11 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. ILT 16-01 NRC JPM SA1-1 NUREG 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 . ..,/ Performance Step: 4 Examinee references the provided materials to evaluate the STA watchstanding 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 . ..,/ 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 NUREG 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, ...J Performance Step: 8 Examinee references the provided materials to evaluate the STA watchstanding 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 due to my wife having surgery tomorrow afternoon. If you need me though, I'll come in as soon as I can" ...J Performance Step: 9 Examinee references the provided materials to evaluate the STA watchstanding 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 NU REG 1021, Revision 10

Appendix C Page 8 of 11 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.: ILT 16-01 NRCJPM 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
• RO 2-ARO
• R03-C&TRO
• 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 C 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 c.... s:: r en en ..,, < en -<

                                                                                                                ~

Ill Ill Ill 0 )>  ?\ I I "'U )> 0 Cl>  :::J c Cl> w  :::r w ...., 0.. w w 3 0

r iil 0 iil en 0..

(ii" iii" :E: ~ c ....,

                                                                                                                                                                    ....,  ff    w   3  <     ro         ()

E:

                                                                                                                                                                                              ?- -~

J 0.. iii" ()

w Cl> () w (ii" _=ll -Cl> 3 §: 0 s* - -s::

                                                                                                                                                          '<        (ii"
                                                                                                                      ;><""                    (/)

(/) '< 0

                                                                                             -:::J

0

J 3

(/) Cl>

                                                                                                                     -)>    :::J (ii" -iil 0

w (Q (/) 0 c.... -

0  :?:'.

(/) s:: 0 s

                                                                                                                                                                                        -     c.... Ill -

Cl> G) rn 0 z _Cl> '::< z Ill c.... Qualification ID Qualification Title Qualification Parent N-TM-OP-STA QUAL TMI STA: SHIFT QUALIFIED Root Qual y N N N y y N N 0 N y y 0 0 0 0 0 N y 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 Day None Johnson, E 0 Day None Adams, M 0 Day None Shuff,J 0 Day None Lewis, D 0 Day 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

OP-TM-112-101-1002 Revision 10 n tio Page 1 of 9 TMI Training and Reference Material SHIFT STAFFING REQUIREMENTS 1.0 PURPOSE This purpose of this procedure is to: Provide required information for shift staffing to meet Technical Specification requirements, Emergency Plan requirements and Fire Brigade requirements. Provide reference material for proper LMS qualification codes for the required positions (Attachment 2). Provide instructions on how to verify LMS qualifications. NOTE: This document does not specify new requirements, but references the base documentation for the requirements. 2.0 TERMS AND DEFINITIONS 2.1 SRO - Senior Reactor Operator holding an "Active" NRC license as defined in 10 CFR 55. 2.2 CRO - Reactor Operator holding an "Active" NRC license as defined in 10 CFR 55. 2.3 URO - Unit Reactor Operator, the CRO required to be present in the Control Room. 2.4 ARO - Assistant Reactor Operator, the second on shift CRO. 2.5 R0 Third Reactor Operator, the third on shift CRO. 3.0 RESPONSIBILITIES 3.1 It is the responsibility of the Shift Manager on duty to ensure these manning requirements are met at all times.

OP-TM-112-101-1002 Revision 10 Page 2 of 9 4.0 MAIN BODY NOTE: Specific permission must be granted by the Plant Manager and the Site Vice President to deviate from the below listed requirements. 4.1 Per TMI Tech Specs Section 6, Table 6.2-1, the minimum shift operations manning requirements must consist of the following: Plant> 200°F ij,CS Temperature Plant< 200°F RCS Temperature 1 Shift Manager (SM) 1 Shift Manager (SM) 1 Control Room Supervisor (SRO) 1 Control Room Supervisor* 3 Control Room Operators*** 2 Control Room Operators (at least 2 RO) (at least 1 RO) 4 Auxiliary Operators** 4 Auxiliary Operators 1 Shift Technical Advisor (STA)

• May be waived by the Senior Manager, Operations. Either a qualified SRO, Shift Manager, or Control Room Supervisor must be on shift at all times when below 200°F.

     **      The minimum shift crew composition of 4 Auxiliary Operators assumes 4 qualified operators.

a. Two of the Auxiliary Operators must meet the requirements to be designated as Fire Brigade members.

b. Two of the Auxiliary Operators must meet the requirements to be assigned as personnel designated to facilitate the safe shutdown of the Unit.

     ***     Except for the Shift Manager, shift crew composition may be one less than the minimum requirements for a period of time not to exceed 2 hours 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 of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an incoming shift crewman being late or absent.

4.1.1 A minimum of 1 SRO and 1 RO must be in the Control Room at all times when RCS temperature is >200°F. 4.1.2 At least 1 SRO or 1 RO must be in the Control Room at all times when RCS temperature is <200°F.

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 hours 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: 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 4of13 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 -I 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 -I Performance Step: 6 Calculate the Final Corrected Boron Correction. Standard: Examinee finds 1469 Examinee verifies: 1469 X 0.95 =1396 ppmB on Line 3c 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%tik/k) Comment: ILT16-01 NRC JPM SA1-2 NU REG 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 /%iik/k) Comment: OP-TM-300-403, Attachment 7.1, Step 5b

,/ 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 %iik/k) Comment: OP-TM-300-403, Attachment 7.1, Step 6 Performance Step: 1O OBTAIN the xenon worth from Figure 13 Standard: Examinee verifies -0.1 on Line 6. (between -0.05 and -0.15 %!1k/k) Comment: ILT16-01 NRC JPM SA1-2 NUREG 1021, Revision 10

Appendix C Page 6 of 13 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 hours Examinee verifies -0.10 on Line 7 (between -0.09 and -0.11 %L'.lk/k) Comment: OP-TM-300-403, Attachment 7.1, Step 8 .Y 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 -1.5 and-1.6 %L'.lk/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

.Y  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

-'1 Performance Step: 14  DETERMINE the Critical Rod Position Tolerance Band from Figure 5A.

Circle 0.5% %L1k/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 -1.24 and 183% Examinee determines -1.76 %Lik/k for a Rod Index of 118% on Line 1Ob for Minimum Examinee finds -0.24 and 284% Examinee determines -0.76%Lik/k for a Rod Index of 235% on Line 1Oc for Maximum : (minimum between 11 O 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 NU REG 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 SA 1-2 NU REG 1021, Revision 10

INITIAL CONDITIONS:

• A sequential trip of both feedwater pumps and reactor trip 72 hours 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 _ _

(PPC, 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 _ _ _ _% i'lk/k

5. 5a. INVERSE BORON WORTH (FIG 8) 140.5 ppmB/% i'lk/k 5b. BORON REACTIVITY WORTH (3c I 5a) x (-1) = -10.46  % i'lk/k

6. XENON REACTIVITY WORTH (PPC, REACTOR ENGR., FIG 13) -0.1  % i'lk/k

7. SAMARIUM AND PLUTONIUM BUILDUP (FIG 15)

• TIME SINCE LAST SHUTDOWN 72 HRS
• REACTIVITY DUE TO BUILDUP -0.10  % i'lk/k

8. INSERTED CRG 5-7 WORTH REQUIRED FOR CRITICALITY (IRW)

(4 + 5b + 6 + 7) x (-1) = -0.74  % i'lk/k

9. ESTIMATED CRITICAL ROD POSITION (FIG 5A) 236  % ROD INDEX

10. CRITICAL ROD POSITION TOLERANCE BAND (FIG 5A) 10a. Circle One: 0.5%i'lk/k 0.8%i'lk/k Use 0.5%i'lk/k for Steady State conditions if xenon (6) is 0.0 to -0.5%

Use 0.8%i'lk/k for Transient conditions if xenon (6) is more negative than -0.5%~k/k 10b. MINIMUM ROD WITHDRAWAL LIMIT (8- 10a) = -1.24 %i'lk/k => _18~3_ _ %ROD INDEX (FIG 5a) 10c. MAXIMUM ROD WITHDRAWAL LIMIT (8 + 10a) = -0.24 %i'lk/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"""'!._,_f\'-----------

CALCULATED BY: _R~0~#~1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATE/TIME Today/Now APPROVED BY (SRO): - - - - - - - - - - - - - - - - - DATE/TIME _ _ __ ILT16-01 NRC JPM SA1-2 NU REG 1021, Revision 10

Appendix C Page 12of13 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 S32 +/- 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 PPG, Control Room Log, or Reactor Engineering. 3c. Final Corrected Boron Concentration: Adjust the measured boron concentration to account for boron-10 depletion by multiplying the Measured Boron Concentration by the Boron Depletion Correction Factor.

3. Fuel Excess Reactivity: From Figure 2.

Sa. Inverse Boron Worth: From Figure 8 Sb. Boron Reactivity Worth: Quotient of 3c and Sa.

6. Xenon Reactivity Worth: Obtain xenon worth using the PPG, FIDMS Display 22 or from program XENC# (where# is the current cycle number). Figure 13 may be used if the PPG and Reactor Engineering are unavailable, provided that power prior to shutdown was constant (+/- 2%FP) for at least 40 hours.

7. Samarium and Plutonium Buildup Reactivity Worth: Record the number of hours since 0% FP and obtain Sm and Pu worth per Figure 1S. If startup at any time during the cycle is within S days of a previous startup, contact Reactor Engineering for the appropriate reactivity worth.

8. Inserted CRG S-7 Worth Required for Criticality: Add reactivity contributions from Lines 4 through 7.

9. Estimated Critical Rod Position: Rod position from Figure SA 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 SA.

11. For the purposes of this procedure, "Transient Xenon" conditions exist when the pre-critical Xe concentration is more negative than -O.S% L'.lk/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 O.S% L'.lk/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 SA 1-2 NU REG 1021, Revision 10

Appendix C Page 13 of 13 Form ES-C-1 JPM CUE SHEET SA1-2 ANSWER KEY DO NOT GIVE TO EXAMINEE CALCULATION IS FOR AN ECP AT DATE/TIME Todavl Now

1. TAVE (Assume TAVE= 532 +/- 2°F) 532 °F

2. CYCLE BURNUP -300- -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) = 1396 ppmB

4. FUEL EXCESS REACTIVITY (FIG 2) -'--11~.-'--4 _ _ _ _% ~k/k

5. 5a. INVERSE BORON WORTH (FIG 8) 140.5 ppmB/% ~k/k 5b. BORON REACTIVITY WORTH (3c I 5a) x (-1) = -9.94  % ~k/k

6. XENON REACTIVITY WORTH (PPC, REACTOR ENGR., FIG 13) -0.1  % ~k/k

7. SAMARIUM AND PLUTONIUM BUILDUP (FIG 15)

• TIME SINCE LAST SHUTDOWN 72 HRS
• REACTIVITY DUE TO BUILDUP -0.10  % ~k/k

8. INSERTED CRG 5-7 WORTH REQUIRED FOR CRITICALITY (IRW)

(4+5b+6+7)x(-1)= -1.26  % ~k/k

9. ESTIMATED CRITICAL ROD POSITION (FIG 5A) 175  % ROD INDEX

10. CRITICAL ROD POSITION TOLERANCE BAND (FIG 5A) 1Oa. Circle One: ~ 0.8%~k/k Use 0.5%~k/k for Steady State conditions if xenon (6) is 0.0 to -0.5%

Use 0.8%~k/k for Transient conditions if xenon (6) is more negative than -0.5%~k/k 10b. MINIMUM ROD WITHDRAWAL LIMIT (8- 10a) = -1.76  %~k/k => -'--11~8_ _ %ROD INDEX (FIG 5a) 10c. MAXIMUM ROD WITHDRAWAL LIMIT (8 + 10a) = -0.76  %~k/k => ~23~5_ _ %ROD INDEX (FIG 5a)

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~'/,""--F\'---------

CALCULATED BY: _R~0~#~1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ DATE/TIME Todav!Now APPROVED BY (SRO): - - - - - - - - - - - - - - - - - DATE/TIME _ _ _ _ __ ILT16-01 NRCJPMSA1-2 NUREG 1021, Revision 10

OP-TM-300-000 Revision 8 Page 25 of 42 ATTACHMENT 7.13 Figure SA Cycle 21 Integral Rod Worth - HZP, No Xenon Page 1 of 1 NOTE: Linearly interpolate between EFPD curves. For use with OP-TM-300-402, OP-TM-300-403, and OP-TM-300-404.

2 -3.5 -3.5

   ~

0 II

                           ~
                                     -       -,~
   .2'    -3.0   -- - -- '
                           ~       '                r--..                                                                                                                                                                             -3.0 0
   .I::
                            "r::,;   "'                    '    ~?..

lJ.J 1'- I"

• f"... \.

          -2.5                                                                                                                                                                                                                        -2.5

• 1"- ' 1',

                                                '                                   [\,

r--..'~ \ --t"-- 6.80 Ef PD

    .r::

t:: , I" h I\ 0

    ='=   -2.0
                                                                 --    )'.,'
                                                                        ~ .........      "

I I<,,.,. --~ ~~ -2.0 - - 500 EFPD u 0

                                                                                  *- -  i.....~~
                                                                                           '*                  r-,~                                                                                                                        -  -  -3CDEFPD ct::
                                                                                                - ._1-..              ....,        r-..
     ~                                                                                                   --                             1"-

Cl 2c:

          -1.5                                                                                                  '
                                                                                                             -.r.;.  !-.         '      "'~
                                                                                                                                                                                                                                      -1.5 ------- 12< EFPD 1,

r-.._ " ' I"\ 'ii

                                                                                                                                                                                                                                           --OEFPD
          -1.0                                                                                                                              r-;; ....' x"'
                                                                                                                                                       ~,                                                                             -1.0
                                                                                                                                                                  ...._'-*      ~,...
                                                                                                                                                          ~,...__          ..,..._         '
                                                                                                                                                                *-~'                    ....
                                                                                                                                                                      ~

I' ' !l.

          -0.5                                                                                                                                                                                                                        -0.5
                                                                                                                                                                               ~                              \
                                                                                                                                                                                        ....                 \\.
                                             - - - ~-
                                                                                                                                                                                                           '\
                                                                                                                                                                                                        ~
                                                                                                                                                                                                                 ...... .__...... ~

0.0 0.0 0 10 20 30 40 50 60 70 80 90 100 0 10 20 0 CRG' CRG 0 10 20 30 40 50 60 70 80 90 100 Each Div.= 1% WO CRG6 Control Rod Group Position (%WO) Cycle Physics Manual Table 27

OP-TM-300-000 Revision 8 Page 22 of 42 ATTACHMENT 7.10 Figure 2 Cycle 21 Fuel Excess Reactivity (HZP) Page 1of1 NOTE: For use with OP-TM-300-402 and OP-TM-300-403. 0 50 100 150 200 250 300 350 400 450 500 550 600 650 700

           ""'   15                                              I 15

i' I

           ""O N

0 14 I HZP, No Xenon, HFP Sm I 14

~

II I a> i------ I

           -EC1l 13                                                                                                       13 w

12

                                       ----- ~                                                                            12
                                                  ~
            .z. 11                                       ~        -                                                      11
            *:;:                                              ~               !

e ~

              ~ 10                                                                                                        10 0::

rn ~~! rn Q)

              ~   9  -                   *-         -                                                                     9 w

Qi i~ it 8 I t'-. 8 7 i

                                                                                        ~~                                7
                                                                                             ~

6

                                                                                                   "" ~                   6 5                                                             -                           !'-..         5 4                                                                                                       4 0  50     100  150      200 250     300     350    400   450  500    550     600      650         700 Cycle 21 Burnup (EFPD)              Each Div.= 10 EFPD Cycle Physics Manual Table 7

OP-TM-300-000 Revision 8 Page 31 of 42 ATTACHMENT 7.19 Figure 8 Cycle 21 HZP Inverse Boron Worth Page 1of1 NOTE: For use with OP-TM-300-205, OP-TM-300-402, and OP-TM-300-403. 0 50 100 150 200 250 300 350 400 450 500 550 600 650 700 151 151

         ,,~    149                                                                                                149
          ~

co E a. 147

                          ---- ~                         --                                                        147
                                  ~

a.

         "'6    145                                                                                                145 0
          .~
          .I:::

143 ~ 143 WJ le 141 ~ 141

                                                  "~

139 139 0

137 c

                                                          "  ~                                                     137 0

0 135 ""!'... 135

                                                                        ~

co

             ~  133                                                                                                133 I~

Q) E 131 - 131 129 127

                                                                                 "' """ ~                          129 127 125                                                                                                125 123                                                                            ~                   123
                                                                                                          ~

121

                                                                                                      """    ~

121 119 119 0 50 100 150 200 250 300 350 400 450 500 550 600 650 700 Cycle 21 Burnup (EFPD) Each Div. = 10 EFPD Cycle Physics Manual Table 15

OP-TM-300-000 Revision 8 Page 37 of 42 ATTACHMENT 7.25 Figure 13 Cycle 21 Transient Xenon Reactivity Worth Page 1of1 NOTE: For use with OP-TM-300-402, OP-TM-300-403, and OP-TM-300-411.

                                                     .I .. l""I" *1 .... 1... 1*

0 10 20 30 40 50 60 70 80 90 100 40

               - . f    R . .. I . .. I                                                             j -4.0
         ~

I I "O

         ?J.

0

               -3 . 5  ~ II      I \\    7 100
                                              %FP                                                         -3.5 II
         .i 0

R\1 J ~~ I r30 0

I I I I I -2.5

         ~

i:!' t; -2.0 -2.0 ra Q) ct:: c: 0

ij -1.5 -1.5

               -1. 0  t-----1                                                                              -1.0
               -0.5   +------+--l         r---+--------.-~~__,----r----r-----+----+------+                 -0.5 oo    t 0

I.

                              . 10    20
                                             .I ..

30 40

                                                               . I~

50 60 70 I 80 90 i oo 100 Each Div. = 2 Hour Hours After Shutdown Cycle Physics Manual Table A-5 and Program XENCXX

OP-TM-300-000 Revision 8 Page 39 of 42 ATTACHMENT 7.27 Figure 15 Cycle 21 Samarium and Plutonium Buildup Following Reactor Shutdown Page 1of1 NOTE: Linearly interpolate between EFPD. If startup at any time during the cycle is within 5 days of a previous startup, contact Reactor Engineering for the appropriate reactivity worth. For use with OP-TM-300-205, OP-TM-300-206, OP-TM-300-402, and OP-TM-300-403 . ~ 0 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 320 340 360 380 400

'cf-
~

0.00 0.00 0 c:i 6.;:: -0.05 -0.05

  ~

w

                                                                                                                            ---4EFPD
  ..c: -0.10                                                                                                          -0.10 t:

0 ------- 100 EFPD

  ~
  ~ -0.15                                                                                                             -0.15 - - - _;oo EFPD t;                                                                                                                        -5COEFPD C'tl (1) 0::   -0.20                                                                                                         -0.20 --e-- 680 EFPD
        -0.25                                                                                                         -0.25
        -0.30                                                                                                         -0.30 0    20   40   60   80  100 120 140 160 180 200 220 240 260 280 300 320 340 360 380 400 Hours After Shutdown Each Div.= 5 Hour Cycle Physics Manual Table A-8

OP-TM-300-403 Revision 5 ti Page 1 of 4 Level 2 - Reference Use ESTIMATED CRITICAL ROD POSITION 1.0 PURPOSE 1.1 This procedure is used to calculate the Estimated Critical Position (ECP) and associated positions in which the reactor is expected to go critical. This calculation will typically be performed after the final RCS boron concentration has been established. 2.0 MATERIAL AND SPECIAL EQUIPMENT None 3.0 PRECAUTIONS, LIMITATIONS, AND PREREQUISITES 3.1 Precautions None 3.2 Limitations 3.2.1 For transient Xenon conditions (Xe worth more negative than -0.5% L1k/k), the ECP is only valid while Xe worth is within 0.5% L1k/k of the value used in the calculation. 3.3 Prerequisites 3.3.1 VERIFY all data sources (OP-TM-300-000 attachments, Areva Physics Data Manual, Reactivity Datasheet, etc.) are for the current cycle.

                                                                                           \

OP-TM-300-403 Revision 5 Page 2 of 4 4.0 MAIN BODY 4.1 PERFORM calculations per Attachment 7.1 or DTSQA-approved software. 4.2 SEND a copy of the completed calculation data sheet to Reactor Engineering. 5.0 RETURN TO NORMAL None

6.0 REFERENCES

6.1 Developmental References 6.1.1 OP-TM-300-000, Reactivity and Power Distribution Calculations 6.1.2 BWFC Operating Guidelines 64-1234 740-00 Reactivity Balance 6.1.3 1103-158, Estimated Critical Conditions (superseded) 6.2 Implementing References 6.2.1 Physics Data Manual (current cycle) 7.0 ATTACHMENTS 7.1 Estimated Critical Position Calculation Data Sheet 7.2 Estimated Critical Position Calculation Instructions

OP-TM-300-403 Revision 5 Page 3 of 4 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--------

1. TAVE (Assume TAVE= S32 +/- 2°F) S32 °F

2. CYCLE BURNUP _ _ _ EFPD

3. 3a. FINAL MEASURED BORON CONCENTRATION _ _ _ ppmB 3b. BORON DEPLETION CORRECTION FACTOR (PPC, Control Room Log, Reactor Engineering, Reactivity Datasheet) 3c. FINAL CORRECTED BORON CONCENTRATION (3.a) X (3.b) = _ _ _ ppmB

4. FUEL EXCESS REACTIVITY (FIG 2) _ _ _ _%Lik/k S. Sa. INVERSE BORON WORTH (FIG 8) _ _ _ _ _ppmB/% llk/k Sb. BORON REACTIVITY WORTH (3c I Sa) x (-1) = _ _ _ _%Lik/k

6. XENON REACTIVITY WORTH (PPC, REACTOR ENGR., FIG 13) _ _ _ _%Lik/k

7. SAMARIUM AND PLUTONIUM BUILDUP (FIG 1S)

• TIME SINCE LAST SHUTDOWN _ _ _ HRS REACTIVITY DUE TO BUILDUP

                                                                                                - - - -% Lik/k

8. INSERTED CRG S-7 WORTH REQUIRED FOR CRITICALITY (IRW)

(4 + Sb + 6 + 7) x (-1) = _ _ _ _ %Lik/k

9. ESTIMATED CRITICAL ROD POSITION (FIG SA)  % ROD INDEX

10. CRITICAL ROD POSITION TOLERANCE BAND (FIG SA) 1Oa. Circle One: 0. S%llk/k 0.8%Lik/k Use O.S%Lik/k for Steady State conditions if xenon (6) is 0.0 to -O.S%

Use 0.8%Lik/k for Transient conditions if xenon (6) is more negative than -O.S%llk/k 10b. MINIMUM ROD WITHDRAWAL LIMIT (8-10a) = _ _ _ %llk/k => _ _ _ %ROD INDEX (FIG Sa) 10c. MAXIMUM ROD WITHDRAWAL LIMIT (8 + 10a) = _ _ _ %Lik/k => _ _ _ %ROD INDEX (FIG Sa)

11. If this is a transient Xenon startup, then record the interval that ECP is valid From: Date/Time_ _ _ _ _ _ _ __ To: Date/Time_ _ _ _ _ _ _ _ _ __

CALCULATED B Y : - - - - - - - - - - - - - - - - - - - DATE/TIME _ _ _ _ __ APPROVEDBY(SRO): - - - - - - - - - - - - - - - - - - D A T E / T I M E _ _ _ _ __

OP-TM-300-403 Revision 5 Page 4 of 4 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-10 depletion by multiplying the Measured Boron Concentration by the Boron Depletion Correction Factor.

4. 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 hours.

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% '1k/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 6 by 0.5% '1k/k.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND UNIT 1 Task No.: 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-7) Task Standard: Determination 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. Required Materials: Copies of site 208 and 209 electrical diagram books. General

References:

208-3141S 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 Handout:

• 208-164, G11-02 ILT 16-01 NRC JPM SA2 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1

                              ~*          Worksheet 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 NIA 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-7 (52 MOC(2)) Standard: Contacts located. Comment: Performance Step: 3 Refers to sheet 314 or 316 to determine contact effect. Standard: 208-314 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 NU REG 1021, Revision 10

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION

..j 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 1S 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 1S or 1T will not work for the condition of diesel breaker closed with ESAS actuated. Comment: ../ Performance Step: 6 Determines 3.7.2.f and 3.7.2.c of Technical Specifications apply due to the failed load shedding ability and declares a 7 day timeclock to repair. Standard: Declares a 7 day timeclock IAW 3.7.2.c 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 NUREG 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 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-7) INITIATING CUE: You are directed to determine impact to operations based on this failure. ILT 16-01 NRC JPM SA2 NU REG 1021, Revision 10

3.7 UNIT ELECTRIC POWER SYSTEM Applicability Applies to the availability of electrical power for operation of the unit auxiliaries. Objective To define those conditions of electrical power availability necessary to ensure:

a. Safe unit operation

b. Continuous availability of engineered safeguards Specification

3. 7 .1 The reactor shall not be made critical unless all of the following requirements are satisfied:

a. All engineered safeguards buses, engineered safeguards switchgear, and engineered safeguards load shedding systems are operable.

b. One 7200 volt bus is energized.

c. Two 230 kV lines are in service.

d. One 230 kV bus is in service.

e. Engineered safeguards diesel generators are operable and at least 25,000 gallons of fuel oil are available in the storage tank.

f. Station batteries are charged and in service. Two battery chargers per battery are in service.

3. 7 .2 The reactor shall not remain critical unless all of the following requirements are satisfied:

a. Offsite Sources:

(i.) Two 230 kV lines are in service to provide auxiliary power to Unit 1, except as specified in Specification 3.7.2e below. (ii.) The voltage on the 230 kV grid is sufficient to power the safety related ES loads, except as specified in Specification 3.7.2.h below.

b. Both 230/4.16 kV unit auxiliary transformers shall be in operation except that within a period not to exceed eight hours in duration from and after the time one Unit 1 auxiliary transformer is made or found inoperable, two diesel generators shall be operable, and one of the operable diesel generator will be started and run continuously until both unit auxiliary transformers are in operation. This mode of operation may continue for a period not exceeding 30 days.

3-42 Amendment No. 188, 212, 224

c. Both diesel generators shall be operable except that from the date that one of the diesel generators is made or found to be inoperable for any reason, reactor operation is permissible for the succeeding seven days provided that the redundant diesel generator is:

1. verified to be operable immediately;

2. within 24 hours, either:

a. determine the redundant diesel generator is not inoperable due to a common mode failure; or,

b. test redundant diesel generator in accordance with surveillance requirement 4.6.1.a.

In the event two diesel generators are inoperable, the unit shall be placed in HOT SHUTDOWN in 12 hours. If one diesel is not operable within an additional 24 hour period the plant shall be placed in COLD SHUTDOWN within an additional 24 hours thereafter. With oo_e diesel generatpr inoperable, in addition to the above, verify that: All required systems, subsystems, trains, components and devices that depend on the remaining OPERABLE diesel generator as a source of emergency power are also OPERABLE or follow specifications 3.0.1.

d. If one Unit Auxiliary Transformer is inoperable and a diesel generator becomes inoperable, the unit will be placed in HOT SHUTDOWN within 12 hours. If one of the above sources of power is not made operable within an additional 24 hours the unit shall be placed in COLD SHUTDOWN within an additional 24 hours thereafter.

e. If Unit 1 is separated from the system while carrying its own auxiliaries, or if only one 230 kV line is in service, continued reactor operation is permissible provided one emergency diesel generator shall be started and run continuously until two transmission lines are restored.

f. The engineered safeguards electrical bus, switchgear, load shedding, and automatic diesel start systems shall be operable except as provided in Specification 3.7.2c above and as required for testing.

g. One station battery may be removed from service for not more than eight hours.

h. If it is determined that a trip of the Unit 1 generator, in conjunction with LOCA loading, will result in a loss of offsite power to Engineered Safeguards buses, the plant shall begin a power reduction within 24 hours and be in HOT SHUTDOWN in'WI additional 6 hours, except as provided in Specification 3.7.2.e above.

3-43 Amendment No. 98, 188, 212, 224, 268 278

The Unit Electric Power System is designed to provide a reliable source of power for balance of plant auxiliaries and a continuously available power supply for the engineered safeguards equipment. The availability of the various components of the Unit Electric Power System dictates the operating mode for the station. Verification of emergency diesel generator and station battery operability normally consists of verifying that the surveillance is current, and that other available information does not indicate inoperability. It is recognized that while testing the redundant emergency diesel generator (EDG) in accordance with surveillance requirement 4.6.1.a, the EDG will not respond to an automatic initiation signal. In this situation, the 12 hour time clock will not be entered per the provisions of section 3. 7 .2.f. due to the low probability of an event occurring while the EDG is being tested. Trip of TMl-1 could result in a change in the 230 kV system (Grid) voltage at the TMI substation. The predicted voltage following a loss of the unit is referred to as the Post-Contingency voltage for trip of TMl-1. The transmission system operator monitors 230 kV system conditions for Post Contingency voltages. If the Post-Contingency voltage is less than the value required to support safety related ES loads, the transmission system operator will notify the TMI Unit 1 control room. The required voltage setpoint values for dual or single auxiliary transformer operation are specified by degraded grid calculations. The appropriate setpoint for the current plant condition(s) is provided to the Grid operator. The required voltage setpoint is based on the Large Break LOCA loading which results in the greatest ES loads. L Upon receipt of a valid Post-Contingency voltage Alarm for Loss of TMl-1, TMI will implement the Low System (Grid) Voltage Procedure. An allowed action time of 24 hours provides the transmission system operator time to take actions to reconfigure the 230 kV system for improved voltage support. The time allowed has been evaluated for the level of risk associated with the increased reliance on use of the onsite sources. 3-43a Amendment No. ~ 224

8 0 a J 208-164 IOM REVISIONS REV I ZONE DESCRIPTION E

            ~H-" 11 c                                                                                                                                                      -3 28       I        IREVlSED    TO .NC:ORPORATE ECR *s-00319, Rev O l
            ~                                                                                                                       1
                                                                                                                                                                         ..,jf
 -r-          JOA       II5                      _                                                                                  I       I        .l." ".L       6

_g_ LEGEND: -

            ~~J12                                                                                                                                        ~

33 - TRUCK OPERATED CELL SW!TCH

i1 I T32-~ 0 T82-11 SRC -

Mi - SPRING RELEASE COIL MOTOR CUT-OrF S\./ITCH D

                                   '.:j G2-12                                  !_!)_

s" 4-0C, M2 LS P0~-1 TEST LS5 - MECHNICAL TRIP MONITOR S'Wl'TH d _CLOSE 1{ R)O s<_o ,CQ_o 3*PT

                                                                                                       *r JN*3                                                              SPRINll CHARGlNG MOTOR SC:!!~

c' 3 cj_ 6S 3T-PCI 17 11lJJl7

                                                                         '9C 19 cSS
                                                                                 ~b-2 css
                                                                                                             *_Jt..1-B TRIP L4-0X
                                                                                                                                                            ~ TESl -~
                                                                                                                                                                                                                 >8 Kl r:-       TDC:r*tx                      Slot 17Z  t I OIE-I T~

IOCI lESf SWIT(r\ 8&>B/JE *.). css

                                                                                                                                                                                                                                                                                                     .crcr-                     7CI "TB*-*

7J.~

                                                                                                                                                                                                                                                                                                                                             '"I
                                                                                                                                                                                                                                                                                                                                      ~ I~! c65 0

JN*4 0 V

                                                                                                                                                                                                                                                                                                                                                                                            'X -

EJEVl!;ES MOUNTED ON CONTROL ROON [;ONSOLE CR OEV\CES MDl\ttTEIJ ON COIHROL ROOM VERT ICU nNEI. DIESEL GEN ELECT EOUIPMENT CABINET(COLT, DWG NO. (117

                                                                                                                                                                                                                                                                                                                                                                                             - TERlllNAlS .D.T DIESEL GENERATOR ELECTRICAL CABINET TP - TEST POINTS LOCATED IN SWlTC'-lGEAR l

Ql 27 Pll CS - CONTACTOR SWITCH 9 LSS 2 I c .. loT_o2!>B__ rar,~,,, 1 3Z &4G, I n;.-.4 1ZJ - MALE BANANA TEST JACK l'l'J - FEMALE BANANA TEST JACK 20;-osi 1E14 RES. I ,T * ' £! I I 10 SC SJP 10 S\-\.\50 S2.(/SA-E2) JN*IQ I__ NOTES. -

                                                                                        !El4                                                                                                                                                                                                                                                        TBl-7 1[14                                                                                                                                                         "TPI                                                                                                                                                 l   WYLE 5-3AH-DPR-.350-1200-78 BREAKER, TP-3                                                                                                                                                                                                                       SHOWN IN CONNECTED, DISCHARGED & OPENED POSIT*ON 1B21-2(1E13) 5 TDC                               U2l 2-7XHTP                                                                                                                                                                                                                                                         k.            k.                   Z.. All OEV!C£S WITHOUT LOCATIONS ARE MOUNTED IN SWITCHGEAR.

Sl-il(o.,-2.: E.1_2_ _ I JN-'2. TB5-11 [] T85-12 TB21-1(1E13) 1[1 5+ TBl-2. £ 54 .* C3 98 ~ Tl(9) TBG*S T RE FERENGE.S:

                                                                $1-USI            52(1,&EL)                  ¢Tl%*7                                                                                                                                                                                 BC                                                                                    SS-206-127          SS OEVE.LOPMENT (TAG:    SS/G1 J-02)       CR #415

_l_E_I- ll:J:M c 1EI TR1fi-11 llC TBH3 S-2:03-G04

                                                                                                                                                                                                                                                                                                                                                                                                 ]02166 4/4 LOG.IC w'YLE BREAKER SCHEMATIC C4~------'                                       Ull s~ 141         SZ(Tl-EZ)                                                                                                                                                *LATERU CClllHCU                           l\CITHlllf>  ~OllTM'rlS IEZ                                                                                                                                                          MDJlljJ.LLYIN. LOO:El>

KANDLE WHEN OOT. HAINTAIJll~G TBNI { ~~U. ~~~Kl"* C7 T85-9 WHOI PULl.E~ OUT: T~-IZ Ml ~ ~~m~ l ~g ~ &Jp~E 7 l 59x2 :1 s9x3'..L s9x2 CONTROL SIVlTCH GS5 (TAG: CS/S11-V2) CR #414 §! SELECTOR SWITCH OEVHOPMENT(TA~: C..'Jt/Gll~02.) J l",:L~,, I~ 59XI IJt"' '1" ..a

                                                                                                                                                     ~-'.

1 . .~ PULL

                                                                                                                                                                                    . +  <"""J'<""

"""v":T

_ l2_ !OLOC! 1 o--f 1-01c aco-1 1--o e ~ x x 7~1--01C aco-4 ~a l\C.7~ 9 o--{ l--09C lOCQ-i J-olG ~ ~ ~ 9 o-f l-0 9C lDCo--lf--010 "t f-'° 1JIQ-.11-ol!C r-o11-.~ ~ l-0 5"~:1 ~1~181X3z.1~ 12CO-j K llQ-4 llC 5 o-f CQ-l f--0 11** "r "0-l 1-<l'" mo-; k>" .#,~ ' ' 1.Jo--t f-013C 1°1~ 1~~ 1-0uc 16CQ-I j--016. ~ .,., Ho-I ~15C \ no-t I-one nco-; J-oia* 17o--ll--OHC 1aco-i t-o1e 1 ~ J 7 5 5 12 ~ ~ ~-~ G.E. COMPANY SB10 SWITCH t~l-Ot9C 2oc0-l 1-0,-¥o-I 14 Sl-U7Z. -1;:;- ~ I ~~~ 6 ~~2-: 2 t>ISTOL GRIP HANDLE no--t 1-o21c l-0 2 "'lr B 22Co-f TS-10 ' RED ANO GREEN FLAGS MAINTAINED IN PULL TO LOCK 1*1 G.E. COMPANY 16SB1 ,CORB1N LOCI(., LOCKABLE. IN ALL P0$1TION5 I KE:Y REMOVABLE IN ALL POSlTION':I, COHTAcrs MAINfAINEO IN ANY POSITION ~>----<>r-<L.l~+---~---~------------...i-_J lP..f) ~ 30A 30A 12 .f!2_ . ALARM 208-755 ~)l§.j,1sc rl;--1;--~o---r-1~1_]uv~!~J,g__ l 1

,[Lr1:1~1~r1~JJ~

1 I MOC{3) (-)HVli 52 I __T SP~CBB"7~- - -- - SJ~VEZ~ - ---- j ~~~1ss \~[Jrs 1->ESHV 8 css +tci IO CS5 Cod File Nome 208164_R28 MOU2) Y,,,,_ SPARE 110 ~[Rs 1 1~[c~S 1 *10 "Io ~SS- 20~*58 9 SUS IE U/V SH. \lo-, G'2 L B32.A. 51 en - - - -r-- Cl CO - - -- BUS 1T U/V BLIS IS U/V r SPARE. SHEEi 31<<. SHEET 314 I C4-l4-*C"7r 17*:*tI s2 ~ Sl Sl ~g ~]£ THIS IS A COMPUTER GENERATED 'JRAWING DO Exelon. A MOC .ar i (1) ~ NOT REVISE IT MANUALLY siK - --C7~ - J_ -- J Nuclear t---J (-)1-lVI +cc~ ~  ;,i' AB03t CB0~"2.** 1~ :lc~s I 4cJ f~ !cfcs> CBCB SPN<E Cl CS 17 30 D*l! IAN) DIESEL (DL) ~H-OZ ELECT 4160V SWJTC (DL-) '5PA.RE SH.ISi i 4 *t4 .IS 51-1.,147 SH.lSO SH.IS~ TEST E~E.~1. qEN. D1E5EL ACS.LOA.~ CLo~+.---J cs 1 ~a-=z. fs~-~'2. Tl*E.2.. ISA-El ISB*E.?.. PA.\C.r\ A.I-JN BR.KR GEN. G11-02 DIESEL GENEF CLO$t'D/OPEN f'jl..,_N'f.L ""';R\f' BR"K.R (AN) (DL) DWG NO OlE.'SE.L Gill-02. SS-205*~1 1RIP GENERATOR B l-.OCKE.D OllT (#2075) '.:iS-20~-641 TMl-1 208-1 BLOCK.SD ss-20~-ec:iS SCALE. NONE SS- 2.0'7-84~ NO OWG NO 71TLE REFERENCES 8 7 6 5 4 3 2 Z7/ 59 A l THREE W MG-6 --~ ELECTRICAL ELEMENTARY DIAGRAMS -1, 5-2 J - ~ - G E CO HGA17A52F ( TDDO) 480V. SWITCHGEAR (E.S.) (1S-1R) ~ -W ~K'2.41 "~ - G.t:: Co. ~\80 T~Ga 4-SOVM-\S(CR ~4G:.'2.~) 480V ENG'D. SAFEGUARDS BUS ExeJBIJ. ucear CAD FILE: THIS IS A 1S P.T. AND SWITCHGEAR REVISED TO INCORPORATE DO NOT RE 480V BUS IS 125V DC AT 480V SWGR. 13 ECR 16-00060 REV.O RJW v-ri ~ .~ I I . 5-1 p~...,..~~-...~~~- REV I DRAFT I CHECK IAPPROVEDI IJATF I I ~*P' JOA I ct: I .. TO SH. 366 s CJ z *II ' 'I' , 'I' , ""' RESET 3 SH, ~ 52/611-02 E.S. BUS IE 16~' IES I ~~, UNDERVOLTAGE SPAR£ SH.169 L SH ~ DC z 0 *II '
• LL
• LL I 5-1 2
0 (/) L&J 3 111 UYSS T3 j:: en g a.0 LL. 0 7/59 _r--r 27/59 lJYS11 a:: LaJ ;Ho£R_LH.,. 5 T O'VERvoLTAGE + TH '"SS-209-592 -¥ Ac!:~ION tn !5 (/) 4( V9LTAGE I CA81NET z a.. _, L&J 27/59 l.. 27/59 0 0 0 UJ z a:: e1 < SI 5-1 UVS3 Tl i5 0 CD SH RC.S SET NS UVS2A--...:t 11s n n It 31.25W I + "" TI-I 27 /5~A { +:*ll:!I ~*w liJ  !;r. ALARM RES SET a1on 31 .25W ffl <J\-2 27/ 86A c - 3UVS e'Ds~ £S52 ~SI ~ TO SH. 366 UVN ,. 2"' PRES. l-ITfl:. { C~Pq COIJT. CJ!..&.. 2*** -~- - - - -- - FROM SH. 318 ~H-~ I i l l l l N lC. I

I ~ I~ I I

r YOl..TMETE~ ~E.\.E.C.T~ iaw. (1:.-1~) I T C ~ z LLI ~ 27/59 27/59 0 C> Si SI 0 z a:: Q IQ I. - c m UVT2 SI RFS SET 27/868 SI 17S 0 UVT2A 31.25W , ,--1:.SBX/\T I.LI ~ c 1 5UVT -R\.\V 27 /59A +- 27/59A ALARM RES SET 310!1 31.2~W 2 ~ 211 +~w E'.~BX B / ~ '  : !Iyi I PRESS.1-lTR. { e.m* E$1'2* ~i1 30A UVN l + I L_ GROUP<\
• 5-2 FROM SH. 300
~~:~~* ---11---1 1 - ------------------ NR-P1B-l I l "! r SH. 357 l:-UV2. '2. 4 2C lie.. -'-~ c\.C 3C. N \I VO\..TMETE.R $E\..'CC.'TOt:l (\\*\~) s,w. I I +1 l ~5~X/1~ PT21g UV/OV 4L.JVT (DP\..) 480VBUS I ~R:Pic-c~ D~* s""ii:"s11 +rf NR-PI~ - L t T* J,o L ;J _I I l\LY.1.-';_u *u ~,,,,_.._.,,, ~*- 30A D 27 1 27X- 27X-2 I o_r_ 27X-4 I l_j_ 27X-4 43/S I A 1:1-4 IE 4 43/SIB 1[14 I 43/SIC IE 4  ! 43/SIO I IE13 43/SIE J;3/SIF IE 4 'AT 1E14 9yT IEl31 I I L" t,,, ,, ,  ! 1[13 1[13 12 iEi3 18'~ 17 '8~~ 18~ 18 18 _17 ul? luVU IUYV I "<lJ" "[11" I 16 ,., 12 O'. (_) 3 IJi 15U" A12, 1"2,-1 ' .1:: 14 '?7-2 11 IE14 "r::'I 15 I L_.:;o" ~ 27-3 1 E!4 Y 15 . :n-4/ IE13 15 27-5 IE13 16r 15 27-6 IE13 868/IE 27X-2 ~ 27X-3 IE14 IEl4 ,- IE13 ,- IEl3 I 11 I 11  : 11 11 90 10 "' UVEIA tuvE1c I +uvE o UVEIE .UVE IF f- <( 52/G I I -0 2 i52/G I I -02 I _i l u ', E3 .,4-- E3 06 9 06 IUVT.-----..---- ""r" D ID ~~7X- 27X-2 27X-3 27X I 27X-5 IUVH '83~5 0J 1E 4 T 1Ei4  ? ifi3 5 ~-J 5  ? 70 7 7 27X-I 27X-2 27X-3 <27X-4 [ 27X-5 <"27X-6 ~ IE14 Ei4 c IE14 Q 80 IE 13 8 IEl3 8 . 1El3 LI 27XETO 5000 5oon 5000 --l f B I $: TDOE. L2 !El4 (LONG DELAY) (SHORT DELAY) TD l@§P'J_, J_, i"tl3

t-4 :ti l\JOTES:

~l~¢'1f* ¢'°¢" '~ I. FO~ GENERAL NOTES A~C LEGEND. SEE SHEET  ! . o

2. U/V RELAYS 27-1 .2,3 AND 27-4,5,6 CONTACTS

[TERMINALS 1 ~ 12) ARE SHOWN FOR BUS VOLTAGES *+ ~ - BELJW RESPEC-IVE JRCPOUT SETTINGS ANO WITH NORMAL 5 SP I~ COCITRCL POWER VOLTAGE. EF AUX ~ RELAYS SH. J

3. ALL RELAY CONTACTS ARE SHOWN ON 208-169 SHTS ~ 2 EXCEPT AS NO-ED ON CONTAC- DEVELCPMENTS. SEE DWG SS-209-756 HIS OWG IUV Bl

,1 J me ~84 ~ 1 6 43/SIA Y5 IE14 ly /,6 43/S:B IE 14 6 43/S C IE14 6 43/SIO IE13 6 43/SIE ~3 l !6 43/SIF IEl3 6 43/SIG 1E13 ~ 27XETO ,A 27XF-D nc 5 5 15 95 5 CAD FILE, VIC,732. 17, 014.002-,0501 THIS IS A CO~PUTER GENERATED DWG. DO NOT REVISE IT MANUALLY 5 IEl4 5, IE13 II w ,--"l§ - , IEl3"'"') 0 a'.l <( +07 ~f

>: +07 +07 +07 ~07 +07 +07 D

O'. LL I 5 27X-4 27- I 27-? 27-3 27-4 27-5 27-6 59- I NUCLEAR SAFETY RELAT \ 0 w ' 4 1El4 IE14 IE14 IEi3 Ei3 '.E13 IEi3 lf~ D z \UV3 - 18 -ne -n8 -08 -08 -n8 IEl3 I~u H f-z I 27X-5 I~,,tl I 0 u I ~~ 5 I I s.G. MILLER NUCLEAR I GAI 5- I I me I I I 1E14 I!:: 14 IE 13 I I I I I I ELECTRICAL ELEMENT1 ;J 7~ Al t . 2UV I ti5-2 IE:4 tS 27Z , IE I 4 sf 43/SIA IE 14 8 143/S'.3 E 14 7.l v 8Y 1 43/SIC IE 4 8 143/S C 'E13 'tvrn 8' IE13 16 8 1~ IE13 7 8  ! 43/SIG IE13 ENGINEER DATE 4160V SWITCHGEAR E.S. BUS IE UNDERVOLTAGE TMI DWG. NO. ~POTE~ MANAGER APPROVAL CATE UNIT I 208-169 f< P Exelon~ SHEET 001 - LE~ENO METROPOLITAN EDISON CO~PANY MACIE GILBERT ASSOCIATI 27 :SBA & B - G E CO. 12 HEA 63G - SHOWN RESET. CHK'CI, FB Nuclear THREE MILE ISLAND NUCLEAR STATION UNIT #l ENGINEERS AND CONSI (REF GEK
• 1277 J. READING, PENNA.
27 /86AX & BX ..: G.E. CO. HGA33B - 0.25 SEC TDOD ELECTRICAL ELEMENTARY DIAGRAMS 4192 SS-208-3 6 n/(~ U80V. SWITCHGEAR ( E. s.) ( IT- IR} WORK CIRCI~~. BIZE DRA'/ REV BUS IT UV LOCK-OUT RELAYS CAD FILE: 208300_R6 THIS IS A COMPUTER GENERA TED DO NOT REVISE IT MANUALLY. UVTa I 17 17 ~1 . + 12SV DC SUPPLY & RESET P.B* z I 'f' 27/86A SS-209-5811 4 LI.I 1 I r 1 +.. l 1 .1 L-T ..... + .J.. 27/ ~I I I 1 ..,... 86A 27/869  ?::; z 0 0 z C/) LI.I en t::> 00.. 0:: 0:: .... ::> <C ~ en .G,,,. . 0 18 19 RESET COil + ;f, .!J! I I 27/86AX RCBI RCB75 27/86BX ........i TH RESET COIL 18 19 Cl) Cl. LI.I ~crHH z ..J LI.I oci PCR E.S. PANEL EQUIPMENT UZ 0:: i5 i J. UVN c as 27/BGA I 27/86B LI.I ~ "1 Cl 1 ~ ~1 ~ B6MO i I l 1 1 1 1 Q 2T 1<> 3T u 4T 12 sT [ sJ is 2T 10 3T 11 4T T ~ c s I sn. P78 T+ c $4 ~ LS. PANEL I RCB62 + s E.S. PANEL I s s Is s Is I T-12 SH.2911 3119 SW-PIB SH.3~5 SS-209-589 SS-2Q9-589 27/868 1" " "1 . . '"1 "' ' 27~86A ~1 61 01 13 9T 16 8T 15 1I. Ill' 11 m . 1 1 1 1 ' i ' 1 16 T+ c T+ c T+ ca +T s s s s s s s s SR-PIB SH.3q7 SR-Pl C SH. 3~8 NR-PIB SH.357 NR-PIC SH.359 SHEET 001 - LEGEND 27/86A & El, - G.E. CO. 12HEA63G - SHOWN RESET Exelon =~'-==-"~~e METROPOLITAN rn1soN co1.1PANY THREE MILE ISLAND NUCLEAR STHION UNIT #1 MADE cHK'c. RP FB a1LBERTAssoc1A* ENGINEERS AND CON 1---.---.!..:!!:!~~--------1-------------------1 SQ. CF. GC READING, PENN 01a~ ~ ~~ ~!:: ~~: ~~~~s:-:~;~~ :~0, ~,§) 6 ELECTRICAL ELEMENTARY DIAGRAMS 480 V. SWITCHGEAR ( E. s. ) ( I S-1 R) 4192 ISS-208- ~ WORK ORDER SIZE DRA ,~i;* ?M* ~.J..~~!i 2-MP*Fll*'*+-'/. 3;/"- HG REV REVISION BUS IS UV LOCKOUT RELAYS CAD FILE: 208318_R6 THIS IS A COMPUTER GENERATED DO NOT REVISE IT MANUALLY. UVS3 17 + 125V DC SUPPLY & RESET P.B. 17 0:: SS-209-581! 2~A 4 "z I.I.I L-T 1201 * ..... _+ 01 ,,,. I I i::: 27/ 86A TH  ;;; 18 RCH7l! u

-;f~~27/86A ~RESET'*'!!!.

~ a:: 0 TH I.I... ~ .... COIL I I ~ 27/86BX RESET ' 0 COIL I.I.I RCBJ 191 ~I I H -t:__ot-12~AX ,- t---o-t-~~~~~~~-.~~~~~~~~~~~--1----1~ 27/86BX I.I.I 0::: PCR E.S. PANEL EQUIPMENT I
• UVN 27/86A \ 27/868 I.I.I
 !;t "1 °' 1 C* 1 Cl S6A5' 1 : l Cl 1 1 RCP~ 1 c 2T 10 3T 11 4T 12 51  : 51 15 13 2T 31 11 4T T + c I s Cl IC-PIB s I CIA IA-Pis 54 + r.s. PANEL I I RCB6 l + c c Is I s c RC-PZB I s SH 528 SH 572 SS-209-58 9 E.S. PANEL. LO P7 G/H SH 530 IS-12 '
• SS-209-SS& -
• SH.-292 $14.'2. I LO-P7 I/ J 27/86A SH.S~5 27/866
'~ l '" "1 .C> 1 1 Cl I

1 Cl 1 l 1 --------

1 ROMS ' 7 T I ij 6 r 13 er 15 gr 15  : 6 T 12 7T IOT ar I ij 9 T 16 T+ c 9. T~. Is s Is c I I s c s I s s I c SF-Pl B DH-Tl HlR.B s s RC*P'2D HS-PIB SH.353 HS-P1C SH.35ij SH.575 SH.529 SH* 530 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 KlA

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, survey not approved. 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. Time Critical Task: N/A Validation Time: 15 Minutes

Appendix C Page 2 of 7 Form ES-C-1 PERFORMANCE INFORMATION 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: O.?E-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) 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 'If Performance Step: 1 Examinee reviews RM-A-2 sample results for Particulate. Standard: Examinee verifies Particulate is NOT below 30% DAC as determined by RM-A-2 reading and identifies that respiratory protection is required for RB entry per section 3.2. Comment: 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. Performance Step: 2 Examinee reviews RM-A-2 sample results for Iodine. Standard: Examinee verifies Iodine is below 30% DAC as determined by RM-A-2 reading. Comment: Performance Step: 3 Examinee reviews RM-A-2 sample results for Gas. Standard: Examinee verifies Gas is below 1 DAC as determined by RM-A-2 reading. Comment: Performance Step: 4 Examinee reviews RM-A-2 sample results for Tritium. Standard: Examinee verifies Tritium is below 1 DAC as determined by RM-A-2 reading. Comment: Performance Step: 5 Examinee reviews RM-A-2 sample results for Explosive Gas. Standard: Examinee verifies Explosive Gas is below 0.4% as determined by RM-A-2 reading. Comment:

Appendix C Page 4 of 7 Form ES-C-1 PERFORMANCE INFORMATION '\/ Performance Step: 6 Examines reviews RM-A-2 sample results for Oxygen. Standard: Examines verifies Oxygen is below 19.5% as determined by RM-A-2 reading and notifies Occupational Safety and the Control Room of the result. Comment: '\/ Performance Step: 7 Examines may sign the RB Survey Log but Standard: Examines 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.

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 IR;; Te-eh-Print/Sign

1. RM-A2 SAMPLE LAB RES ULTS Air Sample Log #

PARTICULATE 3.0E-8 µCi/cc ___,0::..:..;.5=---- DAG FRACTION A161012-0001 IODINE 0.7E-8 µCi/cc 0.28 DAG FRACTION A 161012-0001 GAS 2.31E-5 µCi/cc 0.62 DAG FRACTION A 161012-0002 TRITIUM (H3) 7.51E-6 µCi/cc 0.38 DAG FRACTION A 161012-0003 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 DAG Fraction Air Sample Log#

Particulate _______ µCi/cc (Gross ~y) Gaseous _______ µCi/cc Iodine _______ µCi/cc 3 _______ µCi/cc Tritium (H ) Oxygen (02) _______  % CG/0 2 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% DAG COMMENTS:---'N~O=N~E=---------------------------- REVIEWED BY: - - - - - - - - - - - - - - - - Shift Manager Print/Sign

                         - - - - - - - - - - - - - - - - Radiation Protection Manager/Supervisor Print/Sign

RADIATION WORK PERMIT FACILITY: TM 1 YEAR: -1..§_ RWP NUMBER: 00305 REVISION: QQ_ TYPE: AST LO,...'\.TION: 1RB308100 ELEVATION: ROOM: AREA: T:... .E: CONTAINMENT WORK AT POWER

              **NO ENTRY INSIDE       (0-RING,    IMB, BIO- SHIELD) ON THIS RWP**

INITIATED: 11/30 / 15 SCHEDULED START : 01/01 / 16 EXPECTED COMPLETE : 01/01/17 ALARA CATEGORY : 0 PROTECTIVE CLOTHING AND RESPIRATORY PROTECTION REQUIREMENTS ALL PC'S PER RP X DOSIMETRY REQUIREMENTS EXTREMITY - HANDS MULTIPLE DOSIMETRY: EXTREMITY - FEET RELOCATE DOSIMETRY: ION CHAMBER . ALARMING DOSIMETER: Y SET TO ALARM AT: 25 MREM OR AT: 1000 MREM/HR ADMINISTRATIVE / EXPOSURE CONTROL REQUIREMENTS MINIMUM TEDE BALANCE OF 325 MREM REQUIRED FOR ENTRY pr - JOB MEETING REQUIRED N AUTO ENTRY/EXIT PERMITTED X W~-~ ORDER NUMBER REQUIRED: _N_ SIGNATURE CHECK AT SIGN-IN: X HEALTH PHYSICS COVERAGE AND MONITORING PERIOD SURVEY FREQ: 1 ROUTINE SURVE HP COVERAGE: INTERMITTENT SPECIAL INSTRUCTIONS / REMARKS

1) THIS RWP ALLOWS HIGH RADIATION AREA AND LOCKED HIGH RADIATION AREA ACCESS:

A SPECIFIC HRA BRIEFING IS REQUIRED TO ENTER AREAS POSTED AS HRA OR LHRA.

2) EACH WORKER SIGNING ON THIS RWP MUST REVIEW THE ALARA PLAN OR MICRO ALARA PLAN (MAP) FOR INSTRUCTIONS PERTAINING TO HIS/HER JOB OR SPECIFIC EVOLUTION, AS APPLICABLE.

3) NO ENTRY INSIDE D-RINGS ON THIS RWP.

4) HAND HELD RADIO IS REQUIRED TO BE TAKEN INTO THE RB TO COMMUNICATE WITH THE LHRA ACCESS CONTROL RCT.

5) PREREQUISITES AND PRECAUTIONS AS OUTLINED IN RAD PRO PROCEDURE RP-TM-460-1007 AS TO BE FOLLOWED.

6) FACE SHIELD REQUIRED WHEN GAS CONCENTRATIONS EXCEED ONE DAC.

7) NO ENTRY ONTO 346' ELEVATION WITHOUT RP SUPERVISION APPROVAL.

~~~~~~~~~~~~~~~~(_SPECIAL INSTRUCTIONS ARE CONTINUED ON NEXT PAGE) APPROVALS / TERMINATION

 ...                            Name                     Date            Signatures PREPARED BY                JAMES HOGAN                  11/30/15 WORK SUPERVISOR:           JAMES D SHRUM                12/21/15 HP SUPERVISOR              JAMES D SHRUM                12/21/15 TERMINATED BY POST JOB REVIEW:

RADIATION WORK PERMIT FACILITY: TM 1 YEAR: -1.§_ RWP NUMBER: 00305 REVISION: _QQ_ TYPE: AST LOCATION: 1RB308100 ELEVATION: ROOM: AREA: TITLE: CONTAINMENT WORK AT POWER ~~~-

         **NO ENTRY INSIDE       0-RING,   IMB, BIO- SHIELD) ON THIS RWP**

SPECIAL INSTRUCTIONS / REMARKS

8) COMPLY WITH RP-AA-302 FOR ALPHA MONITORING

9) COMPLY WITH RP-AA- 300-1002 FOR AREAS POSTED FOR ELECTRON CAPTURE (EC).

10 CHANGES TO PC REQUIREMENTS ARE TO BE IN ACCORDANCE WITH RP-AA-410,SECT.4.1 ~-11) RWP DOSE SET POINTS LIMITS BASED ON 1:1 RATIO NEUTRON TO GAMMA WHICH EQUATES TO 50 MR TOTAL DOSE

12) NEUTRON DOSE ESTIMATION TO BE COMPLETED PER RP-AA-210.

                     ****       ** NO YEARLY INFORMATION FOUND **

RP-TM-460-1007 E lonG ti Revision 8 Page 1 of 19 TMI Training and Reference Material ACCESS TO TMl-1 REACTOR BUILDING

1. PURPOSE This Training and Reference Material describes sampling, equipment and conditional requirements needed prior to entry into the TMl-1 Reactor Building.

2. TERMS AND DEFINITIONS 2.1. Hazards - Possible hazards which may exist in Reactor Building include gamma and neutron radiation (reactor critical), airborne radioactive contamination, and explosive or oxygen-deficient atmosphere.

2.2. Containment Integrity 2.2.1. Established when the equipment hatch is bolted in place and both doors of the personnel airlock and emergency airlock are closed and sealed. 2.2.2. As established by 1101-3, Containment Integrity and Access Limits. 2.2.3. One door of the personnel airlock or emergency airlock may be open for refueling, or personnel passage, or up to 24 hours for maintenance, provided the other door is closed. 2.2.4. Containment integrity must be in effect when the following conditions exist:

1. Reactor coolant pressure 300 psig or greater, and

2. Reactor coolant temperature 200°F or greater, and

3. Nuclear fuel in the core.

3. MAIN BODY jNOTE:I This T&RM is written to establish the requirements to support completion of discrete activities. The use of individual applicable sections to complete a discrete activity is allowable. However, completion of all steps within the section(s) used is required unless otherwise specified in the step.

3.1. Equipment (not all of which may be required for each entry)

• Combustible Gas and Oxygen Meter (CG/0 2 meter)
• Establish FME Log in accordance with MA-AA-716-008 (FME Program)

RP-TM-460-1007 Revision 8 Page 2of19

• Beta-Gamma or Gamma dose rate meter
• Neutron dose rate meter (ASP-1/NRD or equivalent).
• Appropriate Air Sampler
• Tritium Sampler
• Personnel dosimetry as specified on RWP
• Gas Sampling Apparatus
• Protective clothing and respiratory protection as specified on RWP
• Gas partitioner
• RM-A2
• Door Keys
• HpGe System 3.2. Prerequisites
• Reactor Building purged per Procedure OP-TM-823-406, OP-TM-823-408 and CY-TM-170-2012 or
• Kidney Filter System operated for at least four (4) hours per OP-TM-823-404 or
• Ensure that particulate/radioiodine airborne activity inside containment is below 30% DAC as determined by analysis of air samples or RM-A2 reading (See Attachment 4 for using RM-A2 readings) or
• Make entry with respiratory protection or per TEDE ALARA Evaluation as specified on RWP. Guidance for airborne iodine activity actions are provided in Attachment 7.
• If noble gas in excess of 1 DAC and has increased by X3 over previous sample, contact Rad. Engineering.

JNOTE:J When particulate/iodine airborne activity exceeds 0.1 DAC the Kidney Filter System will be operated (if operating conditions permit) until particulate/iodine airborne activity falls below 0.1 DAC. Appropriate respiratory protection will apply for all entries.

• A meter capable of monitoring for CO (Carbon Monoxide) is required for entering into the Reactor Building unless an alternate means of sampling has been performed.

RP-TM-460-1007 Revision 8 Page 3of19

• Ensure non-radiological samples are taken or will be taken as stated below and any time explosive gas buildup or oxygen deficiency is probable. Contact Occupational Safety and the Control Room if the sample results are either of the following:

a. More than 0.4 percent hydrogen (RM-A2 samples) or combustible gas meter alarms (by CG/02 meter inside RB)

b. Oxygen levels are less than 19.5%.

• If containment integrity exists and the RB hasn't been purging for 12 hours or more, non-radiological samples should be:

a. Performed weekly,

b. Taken within 24 hours before RB entries or taken by portable combustible CG/02 meter during initial entry, and

c. Required every 24 (+/- 12) hours during RB entries.

JNOTE:J Normal or emergency entry monitoring inside the reactor building may be performed by any personnel trained in the use of the CG/0 2 meter. There is a CG/0 2 meter located in the Unit 1 RP Field Operations office.

• Ensure applicable Section of Attachment 1 has been completed and reviewed whenever non-radiological samples are taken.

3.3. Precautions

• All Reactor Building initial entries will be made in accordance with the TMI Two-Man Rule unless otherwise approved by RPM or designee.
• All Reactor Building initial entries will be made in accordance with a valid RWP except Emergency Entries. (See para. 3.5)
• All entries into the Reactor Building while the reactor is critical are to be reviewed with RP Field Ops prior to entry. Items to be discussed in this review include, but are not limited to: work to be performed, area work is to be performed in, routes taken to access area, anticipated time in the area, expected radiological conditions and applicable ALARA Review requirements.

Based on the above, RP will determine whether RP Technician coverage is necessary.

a. The following areas may be entered without a technician escort provided Rad Protection Supervisor (RPS) concurrence has been obtained:

279' elevation, all areas outside the secondary shield and specified boundary inside the Letdown Cooler Room.

RP-TM-460-1007 Revision 8 Page 4of19 308' elevation, all areas outside the secondary shield. 346' elevation, all areas outside posted neutron high radiation areas.

b. RP Technician coverage is required for entry into areas on top of D-Rings, on the operating floor, and inside the secondary shield. This requirement may be waived provided adequate radiological survey information is available per RP-AA-300, approval is granted by Rad Engineering and the RPS, and is noted in the TMI Radiation Protection Log.

c. The most recent radiological survey data should be available at the control point.

d. When entries are made into areas on top of D-Rings, on the operating floor, and inside the secondary shield a neutron rem instrument shall be used during the entry except as authorized by the RP Supervisor.

e. Neutron Dose Estimate is performed per RP-AA-210.

f. When pre-entry surveys don't exist then use a Neutron to Gamma ratio of:

• 1 for areas outside the posted high neutron area and for areas inside the D-rings.
• 1O for all other areas inside the posted high neutron area, or
• as determined by an ALARA Plan per RP-AA-401.

g. All entrances to the secondary shield will be locked per RP-AA-460 as determined by RP during power operation (~ 1 percent).

• When the reactor is critical or at power, neutron dosimetry is required for entry.
• The approval of the Shift Manager, Plant Manager, Radiation Protection Manager or designees, are required for entries within secondary shielding, inside the gates on top of the "D" rings, or within the Fuel Transfer Canal (including the reactor head area and along the east and west walkways adjacent to the Fuel Transfer Canal) when reactor power level is 1 percent or greater. The Polar Crane is considered as being included on the top of the D-Ring area. Approvals will be recorded on Attachment 6. Each individual will sign Attachment 6 (Approval for D-Ring Entries at Power) or give permission via telephone. The completed form will be filed with the original ALARA plan.

RP-TM-460-1007 Revision 8 Page 5of19 WARNING Reactor power level must not be increased without the permission of the Shift Manager, Plant Manager and Radiation Protection Manager or designees, while personnel are in these areas.

• Reactor Building entry personnel should review their lighting requirements prior to entry into the R.B. Attachment 5 provides directions for RB lighting controls. It is the responsibility of the RB entry team to de-energize the RB lighting after completion of their work activities if lighting is no longer required.

a. Reactor Building lighting normally energized for general RB entries:

If needed, RB operating floor dome lights are energized by closing D-14 #2 breaker (308' RB, north of the elevator) for RB lighting panel CV-3 (346' RB, next to the elevator).

                       #2 on D-14 for RB Ltg Pnl CV-3 (346 RB elevator).

If needed, RB Emergency Lighting (i.e., personnel airlock and RB stairwell lights) are operated by using the on/off switch located in the personnel airlock. If needed, RB 308' and RB 333' area lighting are operated by using the on/off switch located on the D-Ring wall straight in from the personnel airlock. If needed, RB 281' area lighting is energized from Power Panel CV-1 (breakers 1 though 7) located on the north wall of the elevator on 281' RB.

b. Additional Reactor Building lighting may be energized as noted on Attachment 5.

• Notify Security prior to entering the Reactor Building and after leaving the Reactor Building unless other arrangements have been made with Security Supervisor.
• Entries into the Reactor Building when containment integrity is in effect, requires Control Room Notification unless directed otherwise by Shift Manager or Control Room Supervisor. Exception: Control Room notification not required when personnel are stationed in the airlock to operate the doors.

RP-TM-460-1007 Revision 8 Page 6of19 INOTE:I Routine Reactor Building entries for operator surveillance will be made as defined by the Plant Operations Director. To the extent practical, routine preventive and corrective maintenance should be coordinated with this periodic entry in order to minimize RB entries with plant conditions above 200°F and 300 psig. Priority corrective maintenance and operational inspections required by the current conditions of the unit, as defined by Operations or Work Management Supervision, can be accomplished in the RB without waiting for the scheduled RB entry.

• Entries into the Reactor Building when the Reactor is critical require the Plant Operations Director approval if a Reactor Building Purge must be initiated prior to and/or during the entry.

3.4. Surveys

• Perform radiological/non-radiological surveys in the area of interest for routine inspections at power. Air sampling from RM-A2 if required, shall be in accordance with CY-TM-661-852, Sampling of Reactor Building Air.

a. All job specific surveys should include measurements of beta radiation. When high noble gas concentrations exist, ionization chambers may be wrapped to minimize noble gas infiltration.

b. General area beta measurements do not need to be performed for every routine survey in the Reactor Building at power. They should, however, be performed periodically to identify changing conditions.

The frequency and performance of these periodic surveys will be in accordance with the routine survey status system approved by the Radiation Protection Manager, or designee.

• For extended shutdowns, perform radiological surveys per RP-AA-300 and RP-AA-301 within 24 hours after Reactor shutdown (reactor subcritical) or as specified by the Radiation Protection Manager/RPS.

INOTE:I Post and barricade areas as necessary per RP-AA-376-1001. JNOTE:J During extended shutdown periods certain air survey requirements may be exempted by Radiological Engineering. 3.5. Urgent Unplanned Entrance to Reactor Building.

• Urgent unplanned emergency entrance into the Reactor Building will be made in accordance with RP-AA-460-003, "Access to HRAs/LHRAsNHRAs and Contaminated Areas in Response to a Potential or Actual Emergency".
• A minimum of two persons, at least one of whom shall be qualified RP Technician/RPS, shall make such entries.

RP-TM-460-1007 Revision 8 Page 7of19

• The Shift Manager shall submit a "Reactor Building Emergency Entrance Report" (Attachment 2) to the Plant Manger, with a copy to the Radiation Protection Manager after each such entry.
• RP shall ensure a RWP is processed to document the emergency entry, to record personnel involved and their exposures.

3.6. Planned Reactor Building Entry

• Two procedures have been created to enhance FME requirements for Reactor Building entry when containment is required.
• MA-TM-460-001 describes Rad Pro briefing expectations.
• MA-TM-460-002 is a checklist with sign-off steps designed to enhance human performance. Rad Pro has a sign-off section on this form.
• Refer to Maintenance procedure for planned containment entries and use the form provided in MA-TM-460-002 to record completion of the required briefing.

4. DOCUMENTATION 4.1. Retain completed Attachment 1 and 2 in accordance with the provisions of the station records management program.

4.2. Retain Attachment 6 with the original ALARA plan.

5. REFERENCES 5.1. OP-TM-823-406, RB Purge - Containment Closed 5.2. OP-TM-823-408, RB Purge - RB Doors And/Or Equipment Hatch Open 5.3. 1101-3, Containment Integrity and Access Limits 5.4. OP-TM-823-404, Placing Kidney Filter System In Operation 5.5. CY-TM-170-2012, Releasing Radioactive Gaseous Effluents Reactor Building Purges - TMl-1 5.6. RP-AA-300, Radiological Survey Program 5.7. RP-AA-301, Radiological Air Sampling Program 5.8. RP-AA-460, Controls for High and Locked High Radiation Areas

RP-TM-460-1007 Revision 8 Page 8of19 5.9. CY-TM-661-852, Sampling of Reactor Building Air 5.10. RP-AA-376-1001, Radiological Posting, Labeling, and Marking Standard 5.11. 6610-ADM-4250.10, Radiation Protection/Chemistry Actions When RMS Malfunctions 5.12. RP-AA-210, Dosimetry Issue, Usage, and Control 5.13. RP-AA-401, Operational ALARA Planning and Controls 5.14 MA-AA-716-008, Foreign Material Exclusion Program 5.15 RP-AA-460-003, Access to HRAs/LHRAsNHRAs and Contaminated Areas in Response to a Potential or Actual Emergency

RP-TM-460-1007 Revision 8 Page 9of19

6. ATTACHMENTS Attachment 1 - Reactor Building Entry Survey Log Attachment 2 - Reactor Building Emergency Entrance Log Attachment 3 - Operator Aids Attachment 4 - Estimating RB Airborne Radioactivity From RM-A2 Readings Attachment 5 - Reactor Building Lighting Controls Attachment 6 - Approval for D-Ring Entries at Power Attachment 7 - Airborne Iodine Action Levels

RP-TM-460-1007 Revision 8 Page 10of19 ATTACHMENT 1 Page 1 of 1 (Example) Reactor Building Entry Survey Log DATE: _ _ _ _ _ __ REACTOR POWER: _ _ _ _ _ _ _ % START TIME: _ _ __ TECHNICIAN:

                                                                            -----------~

Print/Sign

1. RM-A2 SAMPLE LAB RESULTS Air Sample Log #

PARTICULATE _ _ _ _ µCi/cc----- DAC FRACTION IODINE _ _ _ _ µCi/cc DAC FRACTION GAS _ _ _ _ µCi/cc DAC FRACTION TRITIUM (H3) _ _ _ _ µCi/cc DAC FRACTION OXYGEN (02) _ _ _ _ % on Gas Partitioner EXPLOSIVE GAS _ _ _ _ % on Gas Partitioner CARBON MONOXIDE _ _ _ _ (ppm)

2. Readings from inside Reactor Building (If Required)

DAC Fraction Air Sample Log# Particulate ________ µCi/cc (Gross f3y) Gaseous ________ µCi/cc Iodine ________ µCi/cc 3 ________ µCi/cc Tritium (H ) Oxygen (02) - - - - - - - - % CG/02 Meter _ _ _ _ _ _ _ _ % on Gas Partitioner Explosive Gas (H2)  % CG/0 2 Meter _ _ _ _ _ _ _ _ % on Gas Partitioner Carbon Monoxide - - - - - - - ( p p m ) See Attached HPGe Scan Results 0 Reactor Bldg. Purged Prior to Entry 0 Kidney Filter System Operated Prior to Entry a Iodines and Particulates < 30% DAC COMMENTS:-------------------------------~ REVIEWED BY: - - - - - - - - - - - - - - - - Shift Manager Print/Sign

                         - - - - - - - - - - - - - - - - Radiation Protection Manager/Supervisor Print/Sign

RP-TM-460-1007 Revision 8 Page 11 of 19 ATTACHMENT 2 Page 1 of 1 (Example) Reactor Building Emergency Entrance Log Entry Time_ _ _ __ Why Entry was made_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Personnel Involved Name Exposure Received Work and/or action completed _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Shift Manager Print/Sign Plant Manager Print/Sign cc: Radiation Protection Manager RWP File

RP-TM-460-1007 Revision 8 Page 12of19 ATTACHMENT 3 Page 1 of 2 (Example) Operator Aids Located on the Reactor Building Personnel Hatch REACTOR BUILDING PERSONNEL HATCH LIGHTS DURING ENTRY INTO REACTOR BUILDING - Before closing the outside hatch door. energize the RB Emergency Lighting System using the light switch located inside the personnel hatch. WHEN EXITING THE REACTOR BUILDING - Open the outer personnel hatch door BEFORE using the light switch located inside the personnel hatch to de-energize the RB Emergency Lighting.

RP-TM-460-1007 Revision 8 Page 13of19 ATTACHMENT 3 Page 2 of 2 (Example) Located inside Reactor Building Personnel Hatch near light switch. RB LIGHTING CONTROLS O Operating Floor Dome and Crane Lighting Operating floor dome lighting is energized from D-14 #2 breaker (308' RB, north of elevator) and polar crane lighting is energized from D-9 #1 breaker (308' RB, next to elevator). The operating floor dome lighting is powered locally from Power Panel CV-3. CV-3 is located at elevation 346 ft. of the Reactor Building, near the elevator. Reactor Building Crane lighting is powered locally from Power Panel D-9. D-9 is located at elevation 308' of the Reactor Building, north of the RB elevator. O Emergency Lighting (RB Stairwells) Reactor Building emergency lighting is controlled from an on/off switch located in the personnel access hatch near the page phone (Refer to Gilberts Dwg. 220-051). The emergency lighting, located on elevations 346 ft., 308 ft., 281 ft., and stairway areas, is powered from power panel CV-E. CV-E is located at elevation 308 ft. of the Reactor Building, on the south side of the elevator. 0 Elevation 308' and 333' Lighting (Outside D-Rings) Elevation 308 ft. and Mezzanine lights can be energized from an on/off switch located in the Reactor Building at Elevation 308 ft. near (across from) the personnel access hatch. Elevation 308 ft. and Mezzanine lighting is powered from Panel CV-2 which is located at elevation 346 ft. of the Reactor Building, near the elevator. 0 Basement Lighting (Outside D-Rings) Basement area lighting, elevation 281 ft., area lighting is powered and controlled from Power Panel CV-1 (breakers 1 through 7). CV-1 is located at elevation 281 ft. of Reactor Building on the north wall of the elevator. 0 D-Ring Lighting The D-Ring lights can be controlled from two on/off switch locations, one in the D-Ring entrance hallway elevation 281 ft., and at D-Ring NE platform elevation 365 ft. (Refer to Gilberts Dwg. No. 220-236, No. 220-237, and No. 220-238). D-Ring lighting is powered from Power Panel CV-2. CV-2 is located at elevation 346 ft. of the Reactor Building, near the elevator.

RP-TM-460-1007 Revision 8 Page 14of19 ATTACHMENT 4 Page 1 of 1 (Example) Estimating RB Airborne Radioactivity from RM-A2 Readings Particulate (RM-A2 Particulate Reading - RM-A2 Particulate Reading during last RB grab sample) x 2E-5 DAC/cpm + Particulate DAC value during last sample = DAC Example: RM-A2 Particulate reads 10,000 cpm. On the last sample RM-A2 read 4000 cpm and a DAC value of 0.1 DAC. This equates to: (10,000 - 4000) cpm x 2E-5 DAC/cpm + 0.1 DAC = 0.2 DAC Basis: RM-A2 sensitivity based on Cs-137. The last RM-A2 reading during a sample and sample results compensate for short lived radionuclide concentrations in the RB. Determine the count rate rise over a time period in hours from the chart. RM-A2 Count Rate Rise/Time (Hrs) x 3.42E-4 DAC-Hr/cpm = - - - - - - - - DAC Example: RM-A2 Iodine channel read 100 cpm at 01 :00. Then RM-A2 Iodine channel read 2100 cpm at 03:00 then: (2100-100) cpm /2 Hr x 3.42E-4 DAC-Hr/cpm = 0.34 DAC Basis: RM-A2 sensitivity based on 1-131. Gaseous (RM-A2 Gas Reading - RM-A2 Gas Reading during last RB Grab Sample) x 2.53E-4 DAC/cpm + Gas DAC Value during Last Sample = DAC Example: RM-A2 Gas Reading 10,000 cpm. On the last sample RM-A2 read 4000 cpm and had a DAC Value of 0.4 DAC. (10,000 - 4000) cpm x 2.53E-4 DAC/cpm + 0.04 DAC =1.9 DAC Basis: RM-A2 sensitivity based on Xe-133.

RP-TM-460-1007 Revision 8 Page 15of19 ATTACHMENT 5 Page 1 of 2 (Example) Reactor Building Lighting Controls Operating Floor Dome and Crane Lighting Operating floor dome lighting is energized from D-14 #2 breaker (308' RB, north of elevator) and polar crane lighting is energized from D-9 #1 breaker (308' RB, next to elevator). D-14 480V Distribution panel is located at elevation 308 of the Reactor Building north of the elevator. The operating floor dome lighting is powered locally from Power Panel CV-3. CV-3 is located at elevation 346 ft. of the Reactor Building, near the elevator. Reactor Building Crane lighting is powered locally from Power Panel D-9. D-9 is located at elevation 308' of the Reactor Building, north of the RB elevator. Emergency Lighting (RB Stairwells) Reactor Building emergency lighting is controlled from an on/off switch located in the personnel access hatch near the page phone (Refer to Gilberts Dwg. 220-051 ). The emergency lighting, located on elevations 346 ft., 308 ft., 281 ft., and stairway areas, is powered from power panel CV-E. CV-E is located at elevation 308 ft. of the Reactor Building, on the south side of the elevator. Elevation 308' and 333' Lighting (Outside D-Rings) Elevation 308 ft. and Mezzanine lights can be energized from an on/off switch located in the Reactor Building at Elevation 308 ft. near (across from) the personnel access hatch. Elevation 308 ft. and Mezzanine lighting is powered from Panel CV-2 which is located at elevation 346 ft. of the Reactor Building, near the elevator. Basement Lighting (Outside D-Rings) Basement area lighting, elevation 281 ft., area lighting is powered and controlled from Power Panel CV-1 (breakers 1 through 7). CV-1 is located at elevation 281 ft. of Reactor Building on the north wall of the elevator. Elevator Access at Elevation 365 and Platform Elevation 382 Lighting at the elevator access area of elevation 365 ft. and the platform above elevator at elevation 382 ft. is controlled from a local on/off switch on wall north of the elevator door on elevation 365 ft. (Refer to Gilberts Dwg. 220-081). D-Ring Area Lighting The D-Ring lights can be controlled from two on/off switch locations, one in the D-Ring entrance hallway elevation 281 ft., and at D-Ring NE platform elevation 365 ft. (Refer to Gilberts Dwg. No. 220-236, No. 220-237, and No. 220-238). D-Ring lighting is powered from Power Panel CV-2. CV-2 is located at elevation 346 ft. of the Reactor Building, near the elevator.

RP-TM-460-1007 Revision 8 Page 16of19 ATTACHMENT 5 Page 2 of 2 (Example) References

1. TMl-1 Operating Procedure No. 1107-1, Normal Electrical System

2. Gilberts Drawing No. 220-021, Lighting Layout, Reactor Containment Basement Floor

3. Gilberts Drawing No. 220-051, Lighting Layout, Reactor Containment Mezzanine Floor

4. Gilberts Drawing No. 220-081, Lighting Layout, Reactor Containment Operating Floor

5. Gilberts Drawing No. 220-222, Lighting Layout, Electrical Panel Wiring Diagram

6. Gilberts Drawing No. 220-236, Lighting Layout, Inside Secondary Shield Walls, EL 281

7. Gilberts Drawing No. 220-237, Lighting Layout, Inside Secondary Shield Walls, EL 306

8. Gilberts Drawing No. 220-238, Lighting Layout, Inside Secondary Shield Walls, EL 336 and EL 347' 7" including Miscellaneous Elevations

RP-TM-460-1007 Revision 8 Page 17of19 ATTACHMENT 6 Page 1 of 1 (Example) Approval for D-Ring Entries at Power Entry

Purpose:

Entry Date: WARNING Reactor power level must not be increased without the permission of the Shift Manager, Plant Manager and Radiation Protection Manager or designees, while personnel are in these areas. Approvals: Shift Manager: - - - - - - - - - - - - - - - - - - - - - - - - - - - ' - - - - - - - - Signature Date Radiation Protection Manager: Signature Date Plant Manager:---------------------------'-------~ Signature Date File the completed form with the original ALARA plan. ALARA P l a n - - - - - -

RP-TM-460-1007 Revision 8 Page 18of19 ATTACHMENT 7 Page 1 of 2 Airborne Iodine Action Levels Iodine actions apply to any airborne iodine area at TMI If the airborne iodine level is < 0.1 DAC, no special actions are required. If the airborne iodine level is ::::: 0.1 but< 0.3 DAC:

• Evaluate use of recognized risk contamination provisions in RP-AA-401 for all entries.
• Discuss need to track and/or assign DAC hours with Radiological Engineering; implement tracking and assigning process for all entries.
• Brief individuals prior to entry on potential for anticipated personnel contamination.
• Monitor for skin contamination from airborne iodine and prescribe hoods if required to minimize occurrence.

If the airborne iodine level is ::::: 0.3 but < 1 DAC, in addition to above:

• Post as Airborne Radioactivity Area.
• Notify Outage Management that iodine related contaminations are likely, which will impact RCA exit procedures.
• Hoods required for entry. Ensure all hair is under protective clothing is possible.
• Consider using facial PCs.

If the airborne iodine level is ::::: 1 but < 5 DAC, in addition to above:

• Clear the affected area of non-essential personnel as determined by outage management.
• Facial PCs should be used for all but the most stressful tasks.
• Perform TEDE ALARA determination and assign respiratory protection as appropriate to reduce total dose to individuals.

RP-TM-460-1007 Revision 8 Page 19of19 ATTACHMENT 7 Page 2 of 2 If the airborne iodine level is ;:::: 5 DAC, in addition to above:

• Entry into affected area shall be limited to critical outage or operational activities as determined by Outage Manager and Radiation Protection Manager.
• Facial PCs required as a minimum.
• Respiratory protection should be utilized unless TEDE ALARA benefit without respirators exceeds 10 mRem.

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. 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= 1O 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 0 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 hours to repair.

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

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

Time Critical Task: Yes Validation Time: 23 minutes ILT 16-01 NRC JPM SA4 NUREG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet SIMULATOR SETUP N/A ILT 16-01 NRC JPM SA4 NUREG 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 Time Critical Start Time:          -----

Performance Step: 1 Compares conditions to the EAL Table. "1 Standard: Examinee:

• Determines UNISOLABLE RCS leakage is present at 500 GPM.
• Reactor Building pressure peaks at 31 psig, then drops rapidly to 0 psig
• RM-G-23 reads 1.96 E+03 R/hr The examinee 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:

• Examinee locates EP-AA-112-100-F-01.
• Examinee 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 5of12 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR NOTE: The #1 Time Critical Stop Time is when the General Emergency is declared.

   #1 Time Critical Stop Time: _ _ _ __
   #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                                            NU REG 1021, Revision 10

Appendix C Page 6of12 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-112-100-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 NUREG 1021, Revision 10

Appendix C Page 7of12 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR CUE: Repeat Back any direction given to you with regards to EP-AA-112-1 OO-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-112-100-F-06. {Tab #2) Standard: Examinee hands out EP-AA-112-100-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 < 5REM 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)

Examines 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

-I Standard: Examines determines the following actions are required:

• Evacuate 2-mile radius, AND
• Evacuate 2-5 miles in the following downwind sectors:
• NE I ENE I EI ESE I SE I SSE I S Comment:

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

Appendix C Page 9of12 Form ES-C-1 PERFORMANCE INFORMATION EVALUATOR CUE: Repeat Back any direction given to you with regards to EP-MA-114-1 OO-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-01): (Tab 4) Release in Progress Determination Guidance EP-AA-114-F-01: (Tab 21) If 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
                              - Block 2: C- TMI
                              - Block 3: A- ONE
                              - Block 4: D- GENERAL EMERGENCY
                              - Block 5: Time and D~e 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 PA~THE RESULT OF A RAPIDLY PROGRESSING SEVERE ACCIDENT.
                          - Examinee hands the filled out form to the communicator.

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

Appendix C Page 10of12 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 NUREG 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 12 of 12 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 0 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 hours 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. Time Critical Yes ILT 16-01 NRC JPM SA4 NU REG 1021, Revision 10

Exelon Confidential/Proprietary Exelon Nuclear FC - Fuel Clad RC - Reactor Coolant System CT~ Containment Sub~ategory Loss Potential Loss Loss Potential Loss Loss Potential Loss

1. RCITS hot leg instruments indicate 3. UNISOLABLE RCS leakage > 1SOgpm.

1. RCS leakage results in <25° Sub Cooling 1. SG tube leakage> 150gpm O inches aner lowering trend. OR Margin AND AND

1. RCS or SG Tube Leakage None

2. In-core thermocouples are unavailable.

OR 4. a. RCS Pressure> 2450 psig. 2. UN1SOLABLE steam release from affected I None

2. Steam Generator tube RUPTURE that SIG to the environment AND AND requires/ results in an ESAS actuation.

3. ALL RCP's are secured. b. RCS Pressure not lowering.

1. Tcldd ~ 18QQGF,

2. > 25°F Superheat

2. Inadequate Heat AND

1. Tclold > 1400"F OR None None Removal HPl-PORV Cooling in effect. 2. EOP Restoration procedures .!1Q! effective

3. HPl-PORV Cooling in effect.

in< 15 minutes.

1. Containment radiation monitor (RM-G-22 or RM-G-23) reading> 1.95E+03 R/hr. Containment radiation monitor (RM-G-22 or

3. Containment Containment radiation monitor (RM-G-22 or Radiation I RCS OR I None RM-G-23) reading> 25 R/hr. None None RM-G-23) reading> 4.40E+03 R/hr.

Activity 2. Coolant activity> 300uCi/gm Dose Equivalent 1-131

1. Containment isolation is required and ANY 3. Reactor Building Pressure > 55 psig and of the following: rising.

a. UNPLANNED lowering in OR containment pressure following initial 4. Hydrogen Concentration in Containment pressure nse  :::_4%.

OR OR

b. Containment pressure or water level 5. a. Reactor Building pressure response.!!..!?! consistent With LOCA > 30 psig

4. Contamment None None None conditions. AND None Integrity or Bypass OR b. Reactor Building Emergency cooling is

c. UNISOLABLE pathway from less than ANY one of the following containment to the environment conditions:

exists. SPRAY COOLERS OR 2 0

2. Indication of RCS leakage outside of containment. 0 3 1 1

1. Any Condition in the opinion of the 2. Any Condition in the opinion of the 1. Any Condition in the opinion of the 2. Any Cond1t1on m the opinion of the 1. Any Condition m the opinion of the 2. Any Condition m the opinion of the

5. Emergency Emergency Director that indicates Potential Emergency Director that indicates Loss of Emergency Director that indicates Emergency Director that indicates Loss of Emergency Director that indicates Loss of Emergency Director that mdicates Potential Director Judgment Loss of the RCS Barrier.

the Fuel Clad Barrier. Potential Loss of the Fuel Clad Barrier. the RCS Barrier. the Containment Barrier. Loss of the Containment Barrier. Mode* 1 - Power Operations 2 -Startup 3 - Hot Standby 4 - Hot Shutdown 5 - Cold Shutdown 6- Refueling D- Defueled January 2017 HOT MATRIX TMI 2-3 HOT MATRIX EP-AA-1009 Addendum 3 (Rev 2)

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-01 Revision W xelon ti Page 1 of 24 Level 2 - Reference Use SHIFT EMERGENCY DIRECTOR CHECKLIST Section 1, Initial Actions 1.1, Unusual Event 1.2, Alert 1.3, Site Area Emergency 1.4, General Emergency 1.5, Dose Assessment 1.6, SAFER Response Plan Activation (Only applicable to Units that have implemented FLEX) Section 2, Ongoing Actions with Command and Control in Control Room Section 3, Ongoing Actions after Transfer of Command and Control Section 4, Closeout Actions NOTES: Steps in each section of this checklist may be performed in an order other than listed or they may be omitted if not applicable

1. INITIAL ACTIONS 1.1. If the event is classified as an Unusual Event, then PERFORM the following:

A. ANNOUNCE the event classification, possible escalation paths, D and declaration time to the Control Room staff. B. RECORD the EAL, threshold(s) (as applicable) and declaration time. EAL EAL Threshold(s) (as applicable) Declaration Time Document Retention SRRS 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-01 Revision W Page 2 of 24 SHIFT EMERGENCY DIRECTOR CHECKLIST NOTE: ERO activation is optional for non-security threat Unusual Event classifications. C. If the event is a Security Event, Unusual Event, then PERFORM the following:

1) If the Security Event information was received by a source other than the NRC, then ENSURE expedited NRC notification is made within 15 minutes of receiving the threat using appropriate station procedures.

2) DIRECT activation of the ERO using Scenario 3, "Actual D Event Alternative Facility Response," per EP-AA-112-100-F- Tab 2 06.

3) USE site-specific Operations/Security procedures for D announcements for Security events and CONSIDER limitations on personnel movement prior to sounding alarms or making announcements.

D. SELECT the Emergency Public Address Announcements from D the form and DIRECT performance of the public address Tab 1 announcement within 15 minutes of event classification. Time: E. If optional facility staffing is required, then DIRECT activation of D the ERO Notification using Scenario 1, "Actual Event Respond to Tab 2 Facility," per EP-AA-112-1 OO-F-06. Time: F. If the ERO has not been activated, then DIRECT activation of D the ERO Notification using Scenario 2, "Unusual Event," per EP-Tab 2 AA-112-1 OO-F-06. Time: Document Retention SRRS-ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-01 Revision W Page 3 of 24 SHIFT EMERGENCY DIRECTOR CHECKLIST NOTE: If a higher classification is made prior to transmitting an event notification, the notification for the higher classification can supersede the previous event notification, provided that it can be performed within the 15 minute timeframe of the previous event If the notification of a higher classification cannot be performed within the 15 minute timeframe of the previous event, the previous event notification is required within its 15 minute timeframe, and the subsequent event notification is required within its 15 minute timeframe. G. DIRECT performance of State/Local notifications within D 15 minutes of the event classification as required per the Notifications procedure. Notification Procedure: Tab 3 Notification form: Tab 4 Release In Progress Determination Guidance Tab 21 H. DIRECT performance of required NRC notifications O immediately following notification of the appropriate State and local agencies but not later than (1) hour after the time of classification per the Notifications procedure. Notification Procedure: Tab 20 Notification form: Tab 10 I. GO TO step 1.5 of this Checklist. D 1.2. If the event is classified as an Alert, then PERFORM the following: A. ANNOUNCE the event classification, possible escalation paths, D and declaration time to the Control Room staff. B. RECORD the EAL, threshold(s) (as applicable) and declaration time. EAL EAL Threshold(s) (as applicable) Declaration Time Document Retention SRRS-ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-01 Revision W Page 4 of 24 SHIFT EMERGENCY DIRECTOR CHECKLIST C. For Security events:

1) If the Security Event information was received by a source other than the NRC, then ENSURE expedited NRC notification is made within 15 minutes of receiving the threat using appropriate station procedures. D

2) USE site-specific Operations/Security procedures for announcements and CONSIDER the limitations the threat poses on personnel movement with Security prior to sounding alarms or making announcements.

D. SELECT the Emergency Public Address Announcements from D the form and DIRECT performance of the public address Tab 1 announcement within 15 minutes of event classification. Time: E. If the ERO has not been activated, then DIRECT activation of D the ERO Notification using Scenario 1, "Actual Event Respond Tab 2 to Facility," or Scenario 3, "Actual Event Alternative Facility Response," as appropriate, per EP-AA-112-100-F-06. Time: NOTE: If a higher classification is made prior to transmitting an event notification, notification for the higher classification can supersede the previous event notification, provided that it can be performed within the 15 minute timeframe of the previous event If the notification of a higher classification cannot be performed within the 15 minute timeframe of the previous event, the previous event notification is required within its 15 minute timeframe, and the subsequent event notification is required within its 15 minute timeframe. F. DIRECT performance of State/Local notifications within D 15 minutes of the event classification as required per the Notifications procedure. Notification Procedure: Tab 3 Notification form: Tab 4 Release In Progress Determination Guidance: Tab 21 Document Retention SRRS-ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-01 Revision W Page 5 of 24 SHIFT EMERGENCY DIRECTOR CHECKLIST G. DIRECT performance of required NRC notifications immediately O following notification of the appropriate State and local agencies but not later than (1) hour after the time of classification per the Notifications procedure. Notification Procedure: Tab 20 Notification form: Tab 10 H. GO TO step 1.5 of this Checklist. D 1.3. If the event is classified as a Site Area Emergency, then PERFORM the following: A. ANNOUNCE the event classification, possible escalation paths, D and declaration time to the Control Room staff. B. RECORD the EAL, threshold(s) (as applicable) and declaration time. EAL EAL Threshold(s) (as applicable) Declaration Time C. For Security events:

1) If the Security Event information was received by a source other than the NRC, then ENSURE expedited NRC notification is made within 15 minutes of receiving the threat using appropriate station procedures. D

2) USE site-specific Operations/Security procedures for announcements and CONSIDER the limitations the threat poses on personnel movement with Security prior to D sounding alarms or making announcements.

D. SELECT the Emergency Public Address Announcements from D the form and DIRECT performance of the public address Tab 1 announcement within 15 minutes of event classification. Time: E. If the ERO has not been activated, then DIRECT activation of D the ERO Notification using Scenario 1, "Actual Event Respond Tab 2 to Facility," or Scenario 3, "Actual Event Alternative Facility Response," as appropriate, per EP-AA-112-100-F-06. Time: Document Retention SRRS-ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-01 Revision W Page 6 of 24 SHIFT EMERGENCY DIRECTOR CHECKLIST NOTE: If a higher classification is made prior to transmitting an event notification, notification for the higher classification can supersede the previous event notification, provided that it can be performed within the 15 minute timeframe of the previous event If the notification of a higher classification cannot be performed within the 15 minute timeframe of the previous event, the previous event notification is required within its 15 minute timeframe, and the subsequent event notification is required within its 15 minute timeframe. F. DIRECT performance of State/Local notifications within D 15 minutes of the event classification as required per the Notifications procedure. Notification Procedure: Tab 3 Notification form: Tab4 Release In Progress Determination Guidance: Tab 21 G. If the event is based on a Security Threat or other hazardous D condition (i.e. hazardous condition from a nearby industrial facility, radiological, or severe weather conditions), then CONSIDER the limitations on performing (or not performing) accountability and/or evacuation. H. DIRECT Accountability per the Assembly I Site Evacuation D Procedure and DISPATCH personnel with bullhorns to make Tab 5 announcements should plant PA fail. Tab 22 (Mid-Atlantic only) RECORD time of Alarm I PA Announcement: RECORD time Accountability Completed: RECORD Number of persons "Unaccounted For": I. DIRECT performance of required NRC notifications immediately following notification of the appropriate State and local agencies 0 but not later than (1) hour after the time of classification per the Notifications procedure. Notification Procedure: Tab 20 Notification form: Tab 10 J. GO TO step 1.5 of this Checklist. D Document Retention SRRS-ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-01 Revision W Page 7 of 24 SHIFT EMERGENCY DIRECTOR CHECKLIST 1.4. If the event is classified as a General Emergency, then PERFORM the following: A. ANNOUNCE the event classification, possible escalation paths, D and declaration time to the Control Room staff. B. RECORD the EAL, threshold(s) (as applicable) and declaration time. EAL EAL Threshold(s) (as applicable) Declaration Time C. For Security events:

1) If the Security Event information was received by a source other than the NRG, then ENSURE expedited NRG notification is made within 15 minutes of receiving the threat using appropriate station procedures. D

2) USE site-specific Operations/Security procedures for announcements and CONSIDER the limitations the threat poses on personnel movement with Security prior to D sounding alarms or making announcements.

D. For Security events USE site-specific Operations/Security D procedures for announcements and CONSIDER the limitations the threat poses on personnel movement with Security prior to sounding alarms or making announcements. E. SELECT the Emergency Public Address Announcements from D the form and DIRECT performance of the public address Tab 1 announcement within 15 minutes of event classification. Time: F. If the ERO has not been activated, then DIRECT activation of D the ERO Notification using Scenario 1, "Actual Event Respond Tab 2 to Facility," or Scenario 3, "Actual Event Alternative Facility Response," as appropriate, per EP-AA-112-100-F-06. Time: Document Retention SRRS-ID - 5B.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-01 Revision W Page 8 of 24 SHIFT EMERGENCY DIRECTOR CHECKLIST G. DETERMINE the PAR per the Emergency Classification and O Protective Action Recommendations procedure. Emergency Classification and PAR Procedure: Tab 6 PAR Flowchart: Tab 7 NOTE: If a higher classification is made prior to transmitting an event notification, -notification for the higher classification can supersede the previous event notification, provided that it can be performed within the 15 minute timeframe of the previous event If the notification of a higher classification cannot be performed within the 15-minute timeframe of the previous event, the previous event notification is required within its 15 minute timeframe, and the subsequent event notification is required within its 15-minute timeframe. H. DIRECT performance of State/Local notifications within D 15 minutes of the event classification as required per the Notifications procedure. Notification Procedure: Tab 3 Notification form: Tab 4 Release In Progress Determination Guidance: Tab 21 I. If the event is based on a Security Threat or other hazardous condition (i.e. hazardous condition from a nearby industrial D facility, radiological, or severe weather conditions), then CONSIDER the limitations on performing (or not performing) accountability and/or evacuation. J. If accountability or site evacuation has not been performed D then DIRECT Accountability per the Assembly I Site Evacuation Procedure and DISPATCH personnel with bullhorns to make announcements should plant PA fail. Tab 5 Tab 22 (Mid-Atlantic only) RECORD time of Alarm I PA Announcement: RECORD time Accountability Completed at (time): RECORD the Number of persons "Unaccounted For": ~----- Document Retention SRRS-ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-F-09 Revision E Page 7of11 EMERGENCY PUBLIC ADDRESS ANNOUNCEMENTS

4. GENERALEMERGENCY OYSTER CREEK /PEACH BOTTOM I TMI SOUND the Station Emergency Alarm or equivalent prior to making announcements. (lni.)

4.2. PERFORM one of the following and IMPLEMENT PA speaker compensatory actions for the affected areas: A. If facility staffing has not been initiated and Accountability has not occurred, then MAKE the following Public Address system announcements:

        "Attention ALL personnel. A General Emergency has been declared due to (Brief Description)

Emergency Response Organization members report to your respective (lni.) emergency response facilities. Other station personnel, contractors and visitors standby to implement personnel accountability instructions. " REPEAT the announcement. OR (Time) (step continued on next page) Document Retention SR RS-ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-100-F-06 Exelon Generation Revision V Training ( Page 1 of 16 ERO NOTIFICATION OR AUGMENTATION 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 Section 4- Initiate Activation of Alternate Notification System using World Wide Web Section 5- Initiate Activation of Alternate Notification System using a Standard Phone Section 6- Initiate Activation I Termination of Notification System using Station-applicable Call Trees

1. INIIIATE A~TIVATIQt:j l TERMINATION OF NOTIFl~ATIQN SYSTEM USIN~ THE WQRLD WIDI; WEB 1.1. CIRCLE the appropriate station specific User Name and Station Password D number from the table below.

Station User Name Password Braidwood braidwood3 simulator01 # Byron blackhawk3 simulator02# Clinton clinton3 simulator03# Dresden dresden3 simulator04# LaSalle lasalle3 simulator05# Limerick limerick3 simulator06# Oyster Creek oystercreek3 simulator07# Peach Bottom peachbottom3 simulator08# Quad Cities quadcities3 simulator09# TMI threemileisland3 simulator10# I Document Retention SRRS ID - 58.100

Exelon Confidential/Proprietary EP-AA-112-1 OO-F-06 Revision V Page 2of16 ERO NOTIFICATION OR AUGMENTATION _) 1.2. CIRCLE the appropriate Activation I Termination Scenario event from the D table below. 01 - Actual Event 02-Unusual 03 - Actual Event 04- Event 05 - Activation Respond to Event Alternative Facility Termination Cancellation Facility Response Unusual Notification to all Notification to all For Alert, Site Events For Events with Off ERO Members, ERO Members, Area, or General excluding Site ERO reporting Station Station Emergency, or Security location requirements Management and Management Security Events Events as determined by the EOF Responders and EOF with On Site ERO (HU1) Emergency Director that event has Responders that reporting CM-1 been terminated. activation has

  *Optional for all                                                           been cancelled.

other unusual Events Document Retention SRRS ID - 5B.100

Exelon Confidential/Proprietary Three Mile Island PAR Flowchart EP-AA-111-F-09 Revision F Page 1 of4 Page 1 Table 1 Evacuate Shelter Shelter Initial Protective Action Recommendation ONLY WDFrom 2-5 Miles 2-5 Miles 5-10 Miles 350° to 011° ESE I SE I SSE IS I SSW I SW I ESE I SE I SSE/SI SSW /SW /WSW WSW I General Classification is a Emergency? I I No PARs Required 012° to 034° SE/SSE/ S/ SSW /SW /WSW w SE/SSE/ S/ SSW /SW /WSW/W SSE IS I SSW /SW I WSW I WI WNW No I 035° to 056° SSE IS I SSW /SW /WSW W/WNW 057° SI SSW /SW /WSW /W /WNW I NW

                    ~

to 079" SI SSW /SW I WSW W/WNW/NW ls this the initial I .. Goto Page 4 for Hostile Action Events 080° to 101° SSW/SW/WSW W/WNW/NW/NNW SSW I SW I WSW I WI WNW I NW I NNW I PAR? I No I . Page 3 for Rapidly Progressmg Severe Accidents Page 2 for all other General Emergency Declarations 102° 125° to to 124° 146° SW/WSW/N WSW/N/NNE W/WNW/NW/NNW W/WNW/NW/NNW SW/WSW/W/WNW/NW/NNW/N WSW /W /WNW I NW /NNW IN I

                    ~

And follow the instructions on each page. NNE Do NOT ret11rn to this page 147° to 169" N/NNE/NE W/WNW/NW/NNW WI Wt-NJ I NW I NNW I N I NNE I NE (See Note I) 170° to 191° N/NNE/NE/ENE WNW/NW/NNW WNW I NW /NNW IN /NNE I NE I

1. fs there a Loss of the Primary ENE Containment per the EALs? 192° to 214° N/NNE/NE/ENE/E NW/NNW NW/NNW/N/NNE/NE/ENE/E

                                       ~                                   ~

ls there a Hostile AND Action event m Is this PAR from the Control Room? I 215° to 237° N/NNE/NE/ENE/E/ESE NNW NNW IN I NNE I NE I ENE IE I ESE

2. Either of the following:

a. Are the C'ontamment Radiation Progress? I No I 238° to 259° N/NNE/NE/ENE/E/ESE/SE N/NNE/NE/ENE/E/ESE/SE Monitors.:::_ 4 40E+03 R/HR?

OR

                                                              ~                                     ~                                         260°  to   281°  NNE/NE/ENE/E/ESE/SE/

SSE NNE/NE/ENE/E/ESE/SE/SSE

b. Have the conditions for EAL 1. Release via a Controlled 202° to 304° NE/ENE/E/ESE/SE/SSE/S NE/ENE/E/ESE/SE/SSE/S RGI been met') Containment Vent with a 305° to 326° ENE/E/ESE/SE/SSE/S/ ENE/E/ESE/SE/SSE/S/SSW duration of< I hour? SSW

                    ~                          I Shelter 5 Mile Radius I                                 ~

AND

2. Dose Projections

                                                                                                                      " I Rem TEDE and 327°  to   349°  E I ESE I SE I SSE I S I SSW I SW                       E/ESE/SE/SSE/S/SSW/SW This constitutes a Rapidly Progressing Severe Accident                                                                                         < 5 Rem CDE l lln1md)                                    Table 2 WDFrom                                  Sectors i                                                                          (See Note 2)
                                                                                                                                  ~            350°    to 011°  ESE/ SE /SSE IS I SSW /SW /WSW 012°    to 034°  SE I SSE IS I SSW I SW I WSW I W (See Note 2)                                                         1. Evacuate 2 Mile Radius 035°    to 056°  SSE IS I SSW /SW I WSW I WI WNW

1. Evacuate 2 Mile Radius AND

2. Evacuate 2 - 5 miles downwind 057° to 079° SI SSW /SW /WSW /W /WNW I NW AND

2. Evacuate I Shelter 2 - 10 080° to 101° SSW I SW /WSW /W /WNW /NW /NNW (Table 2) miles downwind 102° to 124° SW /WSW /W /Wt-NJ I NW I NNW IN (Table I) 125° to 146° WSW /W /WNW /NW /NNW IN /NNE

1. Shelter 2 l\lile Radius Continue to evaluate Entry AND 147° to 169° W /WNW It-NJ I NNW IN I NNE I NE 170° to 191° WNW I NW /NNW /N /NNE /NE I ENE

                     ~                              Points on Page 4.                                              2. Shelter 2 - 5 miles Downwind                 192°    to 214°  NW/NNW/N/NNE/NE/ENE/E Continue to evaluate Entry                Do NOT return to this page.                                                                      215°    to 237°  NNW/N/NNE/NE/ENE/E/ESE Points on Page 3.

(Table 2) 238° to 259° N/NNE/NE/ENE/E/ESE/SE 260° to 281° NNE/NE/ENE/E/ESE/SE/SSE Do NOT return to this page. 2a2° to 304° NE/ENE/E/ESE/SE/SSE/S 305° to 326° ENE/E/ESE/SE/SSE/S/SSW Continue to e\*aluate Entry Notes Points on Page 2. 327° to 349° EI ESE /SE/SSE IS I SSW /SW 1 If the cond1t10ns for a Rapidly Progress mg Severe Accident cannot be unmediately confirmed, then ANSWER No Do NOT return to this page. 2 If the state has mformed you of 1mped1ments to evacuation, then Shelter mstead of Evacuate for any affected areas Document Retention SRRS-ID-58. I 00

Exelon Confidential/Proprietary Three Mile Island PAR Flowchart EP-AA-111-F-09 Revision F Page 2 of4 Page2 All Other General Emergencies Table A WOifrom\ Sectors cpanges in wind direction Conditions exist which Dose Assessment 350° to 011° SSE/S/SSW affecting new downwind would require the Results for Actual 012° to 034° $/SSW/SW areas classification of a General Release Exceed 035° to 056° SSW/SW/WSW (Table A) Emergency per the EALs. PAGs. 057° to 079° SW/WSW/W 080° to 101° WSW/W/WNW Do cond1t10ns exist 102° to 124° W/WNW/NW which would require 125° to 146° WNW/NW/NNW the classification of a

                                                   ~

147° to 169° NW /NNW /N General Emergency per the EALs? 170° to 191° NNW/N/NNE 192° to 214° N/NNE/NE

                                     ~                        Is this PAR from the 215°   to     237°   NNE/NE/ENE Control Room?                                                            238°   to     259°   NE/ENE/E Yes J 260°   to     281°   ENE IE/ESE
                                                                        ~                                                                 282° 305° to to 304° 326° E/ESE/SE ESE I SE I SSE

1. Is there a Release via a Controlled Contamment 327° to 349° SE/SSE IS Vent with a duration of< I hour m progress 7 AND

                                                                                                ~

2. Are Dose Projections

                                                  < I Rem TEDE and
                                                   < 5 Rem COE r11iyn1JJ')

(See Note I) F I. Shelter areas 2 - 5 miles

1. Evacuate 2 mile radius AND

2. Evaruate areas 2 - 5 miles downwind (Table A) downwind (Table A) I AND

3. Evacuate all areas where PA Gs were exceeded I

Contmue to Evaluate Entry Points on this I I page I Notes 1 If the state has informed you of 1mped1ments to evacuation, then: a Shelter instead of Evacuate for any newly affected area

b. Mamtam sheltering for all currently sheltered areas

c. Do NOT reduce any previously evacuated areas to shelter Document Retention SRRS-ID-58.100

Exelon Confidential/Proprietary Three Mile Island PAR Flowchart EP-AA-111-F-09 Revision F Page 3 of4 Table Y Page3 State HAS NOT Determined it is Safer to Begin Evacuation of Sheltered Areas Evacuate Shelter Shelter Ra~idly Progressing Severe Accident ONLY WO From 2-5 Miles 2-5 Miles 5-10 Miles 350° to 011° SSE IS I SSW SSE/S/SSW 012° to 034° S/SSW/SW S/SSW/SW Changes in wind direction Conditions exist which Dose Assessment The State has 035° to 056° SSW/SW/WSW SSW/SW/WSW affecting new downwind would require the Results for Actual determined it is safer 057° to 079° SW/WSW w SW/WSW/W areas class1ficat1on of a General Release Exceed to begin evacuation 080° to 101° WSW W/WNW WSW/W/WNW (Tables Y or Z) Emergency per the EALs. PAGs of sheltered areas at: 102° to 124° W/WNW/NW W/WNW/NW 125° to 146° WNW/NW/NNW WNW/NW/NNW 147° to 169° N NW/NNW NW/NNW/N (enter time) Do conditions exist 170° to 191° N/NNE NNW NNW/N/NNE which would requtre 192° to 214° N/NNE/NE N/NNE/NE the classificat1on of a 215° to 237° NNE/NE/ENE NNE/NE/ENE General Emergency per the EALs?

                                  ~                                                                                                   238° 260° to 259° to 281° NE/ENE/E ENE/E/ESE NE/ENE/E ENE IE I ESE Evacuate all remaining                  282°   to 304°   E/ESE/SE                                   EI ESE I SE
                      ~                 Has the State determined it 1s safer to begin evacuation                                I    sheltered areas     I        305°   to 326°   ESE/SE/SSE                                 ESE/SE/SSE 327°   to 349°   SE/SSE/$                                   SE/ SSE IS of sheltered areas')
                                                                       ~                                                                                 Table Z
                                                       ~

State HAS Determined it is Safer to Begin Evacuation of Sheltered Areas (S.eNote I) Evacuate

1. Shelter/Evacuate downwind areas. WO From 2-10 miles 350° to 011° SSE/Sf SSW (Table Y) 012° to 034° $/SSW/SW AND 035° to 056° SSW/SW/WSW

2. Shelter/Evacuate all areas where PA Gs 057° to 079° SW/WSW/W were exceeded (Direction Dependent) 080° to 101° WSW/W/WNW (Table Y) 102° to 124° W/WNW/NW 125° to 146° WNW/NW/NNW 147° to 169° NW/NNW/N (See Note I) 170° to 191° NNW/N/NNE I. Evacuate downwind areas 192° to 214° N/NNE/NE (Table Z) 215° to 237° NNE /NE I ENE 238° to 259° NE/ENE/E AND 260° to 281° ENE/E/ESE

2. Evacuate all areas where PA Gs 282° to 304° E/ESE/SE were exceeded 305° to 326° ESE/SE/SSE 321° to 349° SE/SSE/$

Notes I I Continue to Evaluate Entry Pomts on this page r-I If the state has informed you of impediments to evacuation, then: a Shelter mstead of Evacuate for any newly affected area b Mamtam sheltering for all currently sheltered areas c Do NOT reduce any prev10usly evacuated areas to shelter. Document Retention SRRS-!D-58. I 00

Exelon Confidential/Proprietary Three Mile Island PAR Flowchart E P-AA-111-F-09 Revision F Page 4 of 4 Page4 Hostile Action ONLY Termination of the Hostile I I Dose Assessment Results for Actual Release I I Action Event. Exceed PA Gs. l l Exit to Page 2 (See Note 1)

1. Evacuate 2 Mile Radius Do NOT Return to AND this Page. 2. Evacuate all other areas where PAGs were exceeded l

I Continue to Evaluate Entry Pomts on this page I Notes I If the state has informed you ofirnped1ments to evacuation, then:

a. Shelter mstead of Evacuate for any newly affected area

b. Maintain sheltering for all currently sheltered areas

c. Do NOT reduce any previously evacuated areas to shelter Document Retention SRRS-ID-58.100

Exelon Confidential/Proprietary EP-MA-114-100-F-01 Rev. P e Page 1 of 3 STATE/LOCAL EVENT NOTIFICATION FORM (OR ELECTRONIC FACSIMILE) UTILITY MESSAGE NO. _ _ _ EMERGENCY DIRECTOR APPROVAL: _ _ _ _ _ _ _ __ PERFORM INITIAL ROLL CALL PRIOR TO TRANSMITTING - Refer to Page 3 of Form Block 1: CALL STATUS D This is a DRILL 0 This is an ACTUAL EVENT Block 2: AFFECTED STATION DA- LIMERICK DB- PEACH BOTTOM DC-TMI Block 3: AFFECTED UNIT(S} DA-ONE DB-TWO DC-THREE Block 4: CLASSIFICATION 0A- UNUSUAL EVENT 0C- SITE AREA EMERGENCY DE- RECOVERY DB-ALERT DD- GENERAL EMERGENCY OF- TERMINATION Block 5: DECLARED AT: TIME: (24-hr clock) DATE: I I Block 6: THIS REPRESENTS A/AN: DA- INITIAL DECLARATION OB- ESCALATION De- No CHANGE OD- REDUCTION Block 7: EMERGENCY ACTION LEVEL (EAL} NUMBER: Block 8: A BRIEF NON-TECHNICAL DESCRIPTION OF THE EVENT D A- Abnormal Rad Levels I Radiological Effluent D D- Hazards and Other Conditions Affecting Plant Safety D B- Fission Product Barrier Degradation D E- Independent Spent Fuel Storage Installation Malfunction D C- System Malfunction D F- Cold Shutdown/Refueling System Malfunctions Block 9: RADIOLOGICAL RELEASE STATUS DA- NO radiological release in-progress DB- AIRBORNE radiological release in-progress DC- LIQUID radiological release in-progress OD- Radiological release TERMINATED Block 10: METEOROLOGICAL DATA: WIND DIRECTION is FROM: (degrees) WIND SPEED is: (miles per hour) Document Retention SRRS-ID - 5B.100

Exelon Confidential/Proprietary EP-MA-114-1 OO-F-01 Rev P Page 2 of 3 STATE/LOCAL EVENT NOTIFICATION FORM Block 11: PROTECTIVE ACTION RECOMMENDATION: DA- NONE (Proceed to Box 12) (Complete the following for Shelter or Evacuation for a General Emerqencv only for the applicable station): OB- The PROTECTIVE ACTION RECOMMENDATION (PAR) from the utility is: S =Shelter E =Evacuate [SI El 360 DEGREES FROM 0 MILES (SITE BOUNDARY) TO 2 MILES AND THE FOLLOWING SECTORS FROM 2 MILES TO 5 MILES: [ S I E ] N [ S I E ] E [ S I E ] S [ S I E ] w [ S I E ] NNE [ S I E ] ESE [ SI E ] SSW [ S I E ] WNW [ S I E ] NE [ S I E ] SE [ S I E ] SW [ S I E ] NW [ S I E ] ENE [ S I E ] SSE [SI E] WSW [ S I E ] NNW AND THE FOLLOWING SECTORS FROM 5 MILES TO 10 MILES: [ SI E ] N [ S I E ] E [ S I E ] S [SI E] W [ S I E ] NNE [ S I E ] ESE [ S I E ] SSW [SI E] WNW [ S I E ] NE [ S I E ] SE [ S I E ] SW [SI E] NW [ S I E ] ENE [ S I E ] SSE [SI E] WSW [ S I E ] NNW AND Potassium Iodide (Kl) be administered to the general public in accordance with state procedures and advise the remainder of the EPZ to Monitor and Prepare. AND This Protective Action Recommendation [IS] [IS NOT] the result of a Rapidly Progressing Severe Accident Block 12: CONCLUSION The current Time is Date: Block 13: COMMUNICATOR INFORMATION D This is a DRILL 0 This is an ACTUAL EVENT NAME: CALL BACK NUMBER

• PERFORM FINAL ROLL CALL UPON COMPLETION - Refer to Page 3 of Form
• ASK if there are any questions regarding message or repeat backs needed
• READ "This concludes the notification message" FAX completed copies of all form pages to the Control Room, TSC and EOF, as applicable.

INFORM the Shift Manager, Emergency Director, TSC Director or EOF Director, as applicable, when notification is completed to required contacts. Document Retention SR RS-ID - 5B.100

Exelon Confidential/Proprietary EP-MA-114-1 OO-F-01 Rev P Page 3 of 3 "15 Minute Notifications" "15 Minute Notifications" PEACH BOTTOM (833) LIMERICK (841)

  "Notification Line": Dial "833" for conference call. Stay on the line until agencies come on                                            Initial Roll Call                            Final Roll Call "3 Digit Extensions". Make these calls from 3-digit lines.          (Time Contacted: 24-hour clock)                          M "Commercial# From PBAPS": Make these calls from a 4-digit line. Dial" 1-Area Code-Number"                                                          Pennsylvania EMA                   D "Commercial# From 3-digit lines": Dial "7-1-1-Area Code-                            Ext. 116 or 1-800-424-7362 or Number" 1-717-651-2001 Initial Roll Call                            Final Roll Call (Time Contacted: 24-hour clock)                      (~)

Montgomery County D Ext. 117 or 1-610-631-6541 Pennsylvania EMA D Chester County D Ext. 216 or 1-800-424-7362 / Ext. 118 or 1-610-344-5100 1-717-651-2001 Maryland EMA D Berks County D Ext. 119 or 1-610-655-4931 Ext. 205 or 1-410-517-3600 Initial Roll Call Completed York County Ext. 219 or 1-717-854-5571 D *------------- "15 Minute Notifications" TMI (44) Harford County D "Notification Line": Dial "44" for all-call. If necessary, dial 3-digit extension #'s to notify individual agencies Ext. 214 or 1-410-638-3400 I Commercial or Toll-Free# From TMI: Dial the #'s as 1-410-638-4900 they appear below Cecil County D Commercial or Toll-Free# From EOF: Dial "9" and the

                                                                         #'s as they appear below Ext. 234 or 1-410-392-2010 Initial Roll Call                         Final Roll Call Lancaster County                  D                     (Time Contacted: 24-hour clock)                        ('i)

Ext. 217 or 1-800-808-5236 I Pennsylvania EMA D 1-717-664-1190 Ext. 315 or 1-800-424-7362 or 1-717-651-2001 Chester County D Ext. 218 or 1-610-344-5100 Cumberland County D Ext. 319 or 1-717-238-9676, 1-717-243-4121 Initial Roll Call Completed or 1-717- 532-8878 Lebanon County D Ext. 321 or 1-717-272-20251-76211-2054 FOLLOW-UP NOTIFICATIONS* (PEACH BOTTOM ONLY) Lancaster County D Ext. 318or1-717-664-1190 /-1200 [ ] Maryland Dept. of the Environment York County D Emergency ext. 292 or 235 Ext. 317 or 1-717-854-5571, 1-717-840-2955 1-866-633-4686 or 1-800-427-834 7 Contacted at: _____ (time: 24-hour clock) Dauphin County D Ext. 320 or 1-717-558-6900 [ ] PA State Police, York Barracks Ext. 284 or 1-717-428-1011 Initial Roll Call Completed Contacted at: (time: 24-hour clock) FOLLOW-UP NOTIFICATIONS* (TMI) [ ] York Haven Power Station

• NOT required within 15 minutes of Classification 1-717-266-3654 or 1-717-818-3962

                                                                   . Contacted at:                            (time: 24-hour clock)

Document Retention SR RS-ID - 58.100

Exelon.R EP-AA-114-F-01 Revision E Nuclear Page 1 of 2 PWR RELEASE IN PROGRESS DETERMINATION GUIDANCE PWR Airborne An "Airborne" release due to the event is defined as: Any airborne radioactive release (Particulate, Iodine or Noble Gas) that is a result of, or caused by, the emergency event. A steam release from a PWR secondary system is not considered a release in progress unless a pathway for reactor coolant to the secondary side to the offsite environment is present. Is there a leak of coolant from No the Reactor Coolant System? (1) Yes Does the resulting radioactive No material have an unmonitored pathway to the environment? 1* Yes Yes Is there a rise in an effluent radiation monitor to the environment? i No Has any airborne radioactivity (other than naturally occurring) been detected Yes by survey or sampling in site ventilation or building with an unmonitored pathway to the environment? No Yes Has any radioactivity (other than naturally occurring) been detected by survey or sampling in the environment?

                  '                                                                     No Is the release a direct result of      No
                                                               ~I or caused by the Emergency                                    ~1    No Release is in Progress        I Event? (Z)

Yes A Release is in Progress

1. For release determination, a loss or leak from a barrier is NOT equivalent to the Potential Loss or Loss as determined by the EAL Fission Product Barrier matrix.

2. If a release of radioactivity is identified, then it must be a direct result of, or caused by, the classified or a concurrent emergency event and not attributed to the normal operation or shutdown of plant systems to be considered a "Release in Progress."

EP-AA-114-F-01 Revision E Page 2 of 2 PWR RELEASE IN PROGRESS DETERMINATION GUIDANCE Liquid A "Liquid" release due to the event is defined as: The movement of radioactive liquid beyond the protected area boundary or beyond a spill berm for liquid storage outside of the protected area, that is a result of, or caused by, the emergency event No Is the liquid leak within the Yes protected area boundary? 1* 1* Is any radioactive liquid being Does the resulting radioactive material observed or expected to be Yes have an unmonitored pathway to the transported beyond the liquid spill - Yes environment? containment berm? AND

                                                          -               Is any unmonitored radioactive liquid No                                                  expected to be transported beyond the protected area boundary (for example, Yes                       entering storm sewers)?

Has any radioactivity (other than naturally occurring) been detected by No survey or sampling beyond the spill containment berm? ,, No Yes Is there a rise in a liquid effluent

                                                           ~

radiation monitor to the environment? No Release is in Progress No Has any radioactivity (other than Yes naturally occurring) been detected by

                                                           ~

survey or sampling beyond the protected area boundary? No

                   ,.                                                                            n No Is the release a direct result of or caused by the Emergency Event? ( J 1                             -         No Release is in Progress Yes A Release is in Progress

1. If a release of radioactivity is identified, then it must be a direct result of, or caused by, the classified or a concurrent emergency event and not attributed to the normal operation or shutdown of plant systems to be considered a "Release in Progress."

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 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 Bo ration Time Critical Task: No Validation Time: 4 minutes ILT16-01 NRC JPM A NU REG 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:

Y Initialize the simulator and go to run. Y INSERT malfunction RD0202 IMMEDIATELY, stuck rod Group 4. Y OVERRIDE MU-V-148 Open Pushbutton to OFF o 02A5S77-ZDIPBOMUV14B Y TRIP the Rx and carry out immediate manual actions. Y Stabilize the plant post trip Y INSERT malfunction MUR69, MU-V-14A Breaker Open Y 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 WAAT 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 fill 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/B will not manually operate. ILT16-01 NRC JPM A NU REG 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: Alternate Path Begins EXAMINER CUE: If the examinee asks the backup Emergency Boration source, inform them that the BAMT is the source. ILT16-01 NRC JPM A NUREG 1021, Revision 10

Appendix C Page 5 of 7 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-EOP-010, Guide 1, Step A.1 .../ 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 .../ Performance Step: 7 START boric acid pumps CA-P-1A and CA-P-1 B 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 1Bare running, the JPM can be terminated. STOP TIME: ILT16-01 NRC JPM A 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 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 NUREG 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

OP-TM-EOP-010 Revision 19 EB Page 10 of 40 RULES EMERGENCY BORATION IAAT any of the following conditions exist:

         -   Emergency boration is directed by procedure,
         -   Reactor is shutdown and .§11 control rods are not fully inserted,
         -   Reactor is shutdown and Neutron flux is not lowering as expected, then Emergency Borate as follows:

ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

1. WAAT one of the following conditions exist:

1% dk/k SHUTDOWN has been achieved for the expected plant condition IAW the Reactivity Data Sheet, 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 .§11 Control Rods are inserted, and Neutron flux is lowering as expected. then emergency boration may be terminated.

2. VERIFY a MU pump is operating. INITIATE OP-TM-AOP-041 "Loss of Seal Injection".

CONTINUED (over)

OP-TM-EOP-010 Revision 19 EB Page 11 of 40 RULE 5 EMERGENCY BORATION ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

3. Perform one of the following:

  -   OPEN MU-V-14A,
  -   OPEN MU-V-148,
  -    PERFORM Guide 1 "Emergency Bo ration Backup Methods".

4. VERIFY Total Injection (MU, SI and HPI) 1. INITIATE OP-TM-211-950, "Restoration

  > 50 gpm.                                     of Letdown Flow".

2. INITIATE OP-TM-211-441, "Increased Letdown Flowrates".

5. STOP any activities which may be diluting RCS boron concentration.

6. If SCM > 25 °F and neutron flux indication is rising, then STABILIZE RCS temperature.

OP-TM-EOP-010 Revision 19 Page 13 of 40 GUIDE 1 EMERGENCY BORATION BACKUP METHODS Page 1 of 1 If required per Rule 5, then perform either A or B. A. If the backup Emergency Boration source is the BAMT, then perform the following:

1. OPEN MU-V-51.

2. START boric acid pumps CA-P-1A and CA-P-1 B.

B. If Backup Emergency Boration source is the RBAT, then perform the following:

1. POSITION the "Boric Acid Injection" switch to "INJECT" (opens WDL-V-61 ).

2. MAXIMIZE the Batch Size and SELECT Run on the totalizer batch controller.

3. OPEN MU-V-10.

4. If using the 'A' RBAT, then perform the following:

(At Radwaste Panel in the Auxiliary Building), a) OPEN WDL-V-89. b) OPEN WDL-V-49. c) CLOSE WDL-V-93. d) ENSURE boric acid recycle pump WDL-P-13A is running.

5. If using the 'B' RBAT, then perform the following:

(At Radwaste Panel in the Auxiliary Building), a) OPEN WDL-V-92. b) OPEN WDL-V-50. c) CLOSE WDL-V-94. d) ENSURE boric acid recycle pump WDL-P-13B is running.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: 21101009 Task

Title:

Restoration of Letdown Flow JPM No.: ILT 16-01 NRC JPM B Following Temperature Closure of MU-V-3 KIA

Reference:

002A1.02 3.6/3.9 Bank JPM: TQ-TM-104-211-J100 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom Simulator x Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. Initial Conditions:

• 100% power
• You are the ARO
• The examiner will act as the CRS
• The booth operator will be the Auxiliary Operator
• MU-V-3 has automatically closed on high temperature due to problems while back-washing the ICCW coolers.
• Surveillance is complete, and ICCW flow to the letdown coolers has been returned to normal.
• Letdown line to the makeup tank has been assessed for integrity issues, SAT.
• All radiation monitoring indicates normal.
• The Shift Manager has given permission to re-open containment isolation valves.

Task Standard: Once letdown flow is established, and the examinee demonstrates the ability to control raising letdown at < 2.5 gpm/min, the JPM can be terminated. Required Materials:

• OP-TM-211-950, Rev 7, 'Restoration of Letdown Flow'
• OP-TM-541-461, Rev 10, 'IC & NS Temperature Control' ILT16-01 NRC JPM B NU REG 1021, Revision 10

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

References:

• OP-TM-211-950, Rev 7, 'Restoration of Letdown Flow'
• OP-TM-541-461, Rev 10, 'IC & NS Temperature Control' Initiating Cue: The CRS directs you to restore Letdown flow in accordance with OP-TM-211-950, "Restoration of Letdown Flow" Time Critical Task: No Validation Time: 18 minutes ILT16-01 NRG JPM B NUREG 1021, Revision 10

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

1. Reset the simulator to IC16 or Temporary IC 247 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. Place the simulator in "RUN".

3. Insert:

A. Remote MUR01 to OPEN on Event #1. B. Remote MUR89 to BYPASS on immediately. C. Remote MUR90 to BYPASS on immediately.

4. Secure BOTH ICCW Pumps in PTL.

5. When MAP D-2-1, LETDOWN CLRS OUTLET TEMP HI, is received, ensure MU-V-3, Letdown Isolation Valve (CIV) closes. Verify "closed" indication on CC and PCR for MU-V-3.

6. Once MAP D-2-1 is received and MU-V-3 is verified closed, restart ICCW pump 1A and place ICCW pump 1B in NAS.

7. Pull CROM Stator temperatures on STA PPG Screens (Area 10, Groups 31-37)

8. Restore letdown until temperature is -145F@ MU-TS-1&2. Allow MU-V-3 to close.

9. Freeze the simulator.

10. When the above steps are completed for this and other JPMs to be run concurrently, then validate the concurrently run JPMs using the JPM Validation Checklist.

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.

ILT16-01 NRC JPM B NUREG 1021, Revision 10

Appendix C Page 4 of 14 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark) START TIME: EVALUATORS CUE: Direct the examinee to restore letdown to 70 gpm, in accordance with OP-TM-211-950, 'Restoration of Letdown Flow' OP-TM-211-950, Step 3.3.1 Performance Step: 1 VERIFY ICCW flow> 550 GPM. Standard: Examinee verifies ICCW flow is >550 gpm on the total flow indicator on Console Right. Comment: OP-TM-211-950, Step 3.3.2 Performance Step: 2 VERIFY the following valves are Open:

                            - IC-V-2
                             - IC-V-3
                             - IC-V-4 Standard:                 Examinee verifies IC-V-2, IC-V-3 and IC-V-4 are open verifying amber indication for the valves on PCR.

Comment: ILT16-01 NRC JPM B NUREG 1021, Revision 10

Appendix C Page 5of14 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-950, Step 3.3.3 Performance Step: 3 VERIFY any of the following:

                             - ESAS defeated.
                             - ESAS did not actuate.
                             -AOP-046 was entered.

Standard: Examinee verifies that ESAS did not actuate by verifying ESAS is reset on CC and CR using PCR indications. Other two conditions are N/A Comment: OP-TM-211-950, Step 3.3.4 Performance Step: 4 VERIFY ICCW cooler outlet temperature < 100°F. Standard: Examinee verifies ICCW cooler outlet temperature is <100°F using the temperature indication on CR. Comment: EXAMINER NOTE: If the examinee asks or requests CRD temperatures, inform the examinee the STA will monitor CRD Temperatures. OP-TM-211-950, Step 3.3.5

• Performance Step: 5 VERIFY all CRD stator temperatures < 160°F or reactor is shutdown.

Standard: Verifies on PPC that CROM temperatures are < 160°F Comment: EXAMINER CUE: If the examinee asks if RM-L-1 has alarmed inform them that it has NOT alarmed. ILT16-01 NRC JPM B NUREG 1021, Revision 10

Appendix C Page 6 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-950, Step 3.3.6 Performance Step: 6 If RM-L-1 alarmed or ESAS actuated, then VERIFY the following:

                                 -   Integrity of letdown line to MU-T-1 has been assessed.
                                 -   RM-G-22 & 23 do not indicate excessive RCS activity.
                                 -   RM-A-6, RM-A-8, or portable radiation monitors are in service to detect any release that may result from opening containment isolation valves.

ED/SM has given permission to re-open containment isolation valves. Standard: Examinee verifies RM-L-1 has not alarmed by observing indication on PR. Comment: EXAMINER NOTE: The following Steps isolate BOTH Demineralizers and open the bypass around them to ensure hot Letdown water is NOT introduced to the resin beds as Letdown flow is restored. OP-TM-211-950, Step 4.1 --./ Performance Step: 7 If isolation was due to high letdown temperature, then perform the following:

1. CLOSE MU-V-6A.

Standard: Examinee pushes closed PB for MU-V-6A. MU-V-6A GREEN light LIT, RED light is NOT LIT. Comment: ILT16-01 NRC JPM B NUREG 1021, Revision 10

Appendix C Page 7 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-950, Step 4.1

..,/ Performance Step: 8      If isolation was due to high letdown temperature, then perform the following:

2. CLOSE MU-V-6B.

Standard: Examinee pushes closed PB for MU-V-68. MU-V-68 GREEN light LIT, RED light is NOT LIT. Comment: EXAMINER NOTE: MU-V-70A is located in the Auxiliary Building 305' elevation, in the mini valve alley. BOOTH CUE: When directed to open MU-V-70A, insert EVENT #1 to open MU-V-70A. OP-TM-211-950, Step 4.1

..,/ Performance Step: 9     If isolation was due to high letdown temperature, then perform the following:

3. OPEN MU-V-70A (MU Oemin Bypass) (AB 305: Mini Valve Alley).

Standard: Examinee contacts Primary AO to OPEN MU-V-70A. Comment: BOOTH CUE: When directed to bypass the MU-V-2A/2B high temperature interlock, wait 30 seconds and inform the examinee the interlock is in bypass. The interlock was bypassed as part of the setup. No booth action required. OP-TM-211-950, Step 4.1 ..,/ Performance Step: 10 If isolation was due to high letdown temperature, then perform the following:

4. PLACE MU-V-2A/B High Temperature bypass switches in BYPASS position (AB 305: 1B ES Valves MCC Unit 50).

Standard: Examinee contacts Primary AO to place MU-V-2A/2B HI Temperature Interlock in "BYPASS" on 1B ES Valves MCC Unit 50. Comment: ILT16-01 NRC JPM B NU REG 1021, Revision 10

Appendix C Page 8 of 14 Form ES-C-1 PERFORMANCE INFORMATION BOOTH CUE: When contacted as the Auxiliary Operator to bypass the MU-V-3 high temperature interlock wait 30 seconds and inform the examinee the interlock is bypassed. The interlock was bypassed as part of the setup, no booth action required here. EXAMINER NOTE: Terminal Box T-85 is located just outside the entrance to the Valve Alley on an I-beam OP-TM-211-950, Step 4.1 .../ Performance Step: 11 If isolation was due to high letdown temperature, then perform the following:

5. PLACE MU-V-3 High Temperature bypass switch in BYPASS position (AB 281: on terminal box T-85 near MU-V-3).

Standard: Examinee contacts Primary AO to place MU-V-3 High Temperature Interlock in "Bypass" on Terminal Box T-85 Comment: EXAMINER NOTE: Alarms D-3-2 MU Tank Level HI/LO and D-3-3 MU Tank Press HI/LO may actuate depending on the examinee's pace in restoring letdown. Additional action is not required by the examinee assuming that makeup tank pressure and level are still in the unrestricted operating area. Based on the knowing the reason for the alarms, the examinee can continue restoring letdown to correct them. OP-TM-211-950, Steps 4.2, 4.3, and 4.4 are not applicable. OP-TM-211-950, Step 4.5

.../ Performance Step: 12     ENSURE the following valves are Closed:
                                  -    MU-V-3 Standard:                Examinee ensures MU-V-3 is closed by verifying the GREEN/CLOSED lamp is lit and the RED/OPEN lamp is off on CC.

Comment: ILT16-01 NRC JPM B NUREG 1021, Revision 10

Appendix C Page 9 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-950, Step 4.5

...J Performance Step: 13     ENSURE the following valves are Closed:
                                  -   MU-V-4 Standard:                Examinee depresses the GREEN/CLOSED pushbutton for MU-V-4 on Console Center and verifies the GREEN/CLOSED light is on and the RED/OPEN light is off.

Comment:

...J OP-TM-211-950, Step 4.5 Performance Step: 14     ENSURE the following valves are Closed:
                                  - MU-V-5 or MU-V-97A (AB 281: MU Valve Alley)

Standard: Examinee rotates the dial setpoint for MU-V-5 to 0 % demand. Comment: OP-TM-211-950, Step 4. 6 is not applicable OP-TM-211-950, Step 4.7 ...J Performance Step: 15 ENSURE the following are Open:

                                  -  MU-V-1A
                                  -  MU-V-18 Standard:                Examinee verifies OPEN MU-V-1A and MU-V-1 B by observing on Console Center the RED/OPEN lights are LIT and the GREEN/CLOSED lights are NOT LIT.

If necessary the examinee will open either or close both of these valves to conform to the required condition stated in this step. Comment: ILT16-01 NRC JPM B NUREG 1021, Revision 10

Appendix C Page 10of14 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-950, Step 4.8.1 is not applicable OP-TM-211-950, Step 4.8 Performance Step: 16 2. ENSURE the following are Open:

                                -    MU-V-2A
                                -    MU-V-28 Standard:               The examinee will verify open both valves indicate OPEN.

RED light LIT and the GREEN/CLOSED lights are NOT LIT. Comment: OP-TM-211-950, Steps 4.8.3, 4.8.4 and 4.9.1 are not applicable. OP-TM-211-950 Step 4.9 ...J Performance Step: 17 Establish min flow path around block orifice as follows:

2. If MU-V-5 is remotely operable, then PLACE MU-V-5 at 10% Open Standard: Using the Letdown Flow Controller for MU-V-5 on Console Center, turns the dial in the lower portion of the controller to approximately 10% and monitors MU-V-5 demand signal rising.

Comment: OP-TM-211-950 Step 4.10 Performance Step: 18 ENSURE MU-V-8 is aligned to the THRU position. Standard: Observing on Console Center the RED/THRU light is LIT Comment: ILT16-01 NRC JPM B NUREG 1021, Revision 10

Appendix C Page 11 of 14 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-950 Step 4.11

.../ Performance Step: 19    Open MU-V-3 as follows:

1. If MU-V-3 closed on high temperature, then PUSH AND HOLD MU-V-3 open pushbutton until high letdown temperature alarm clears.

Standard: Examinee depresses and holds OPEN PB for MU-V-3 until alarm D-2-1; "LETDOWN CLRS OUTLET TEMP HI" clears. Observing on Console Center the RED/OPEN light is LIT and the GREEN/CLOSED light is NOT LIT. Comment: OP-TM-211-950, Steps 4.11.2 thru 5 are not applicable. EXAMINER CUE: Provide the examinee a copy of OP-TM-541-461 if requested OP-TM-211-950 Step 4.12 Performance Step: 20 CONTROL ICCW temperature IAW OP-TM-541-461 Standard: Step is left OPEN Comment: EXAMINER NOTE: With the setup of this JPM it is not expected that Letdown temperature will rise above 125°F or that ICCW temperature will rise above 100°F OP-TM-211-950 Step 4.13 Performance Step: 21 MAINTAIN letdown temperature< 125°F. Standard: Step is left OPEN Comment: ILT16-01 NRC JPM B NUREG 1021, Revision 10

Appendix C Page 12of14 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-950, Steps 4.14.1and4.14.2 are not applicable. OP-TM-211-950 Step 4.14.3 ...J Performance Step: 22 Raise letdown flow at < 2.5 gpm/min to desired flow as follows:

3. If MU-V-5 is remotely operable, then THROTTLE MU-V-5.

Standard: With MU-V-5 remotely operable the examinee opens MU-V-5 slowly (less than 2.5 gpm/min rise), until greater than 50-gpm-letdown flow is obtained on MU-4FI. Using the Letdown Flow Controller for MU-V-5 on Console Center, the dial in the lower portion of the controller is turned clockwise to raise MU-V-5's demand signal. Comment: Terminating Cue: Once the examinee demonstrates the ability control at< 2.5 gpm/min, the JPM may be terminated STOP TIME: ILT16-01 NRC JPM B NU REG 1021, Revision 10

Appendix C Page 13of14 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 NU REG 1021, Revision 10

Appendix C Page 14 of 14 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:

• 100% power
• You are the ARO
• The examiner will act as the CRS
• The booth operator will be the Auxiliary Operator
• MU-V-3 has automatically closed on high temperature due to problems while back-washing the ICCW coolers.
• Surveillance is complete, and ICCW flow to the letdown coolers has been returned to normal.
• Letdown line to the makeup tank has been assessed for integrity issues, SAT.
• All radiation monitoring indicates normal.
• The Shift Manager has given permission to re-open containment isolation valves.

INITIATING CUE: The CRS directs you to restore Letdown flow in accordance with OP-TM-211-950, "Restoration of Letdown Flow" TIME CRITICAL: No ILT16-01 NRC JPM B NU REG 1021, Revision 10

OP-TM-211-950 xe 'l,!; Revision 7 Page 1 of 9 Level EP RESTORATION OF LETDOWN FLOW 1.0 PURPOSE This procedure provides direction for restoring letdown following ESAS actuation, loss of ICCW, loss of AUTO power, loss of Instrument Air pressure or other unplanned isolation events. NOTE: The Letdown line may have been isolated by one or more of the following:

                 -   MU-V-1A & B Close on High ICCW temperature out of CROM > 160°F or Loss of Auto power.
                 -   MU-V-2A & B close on high temperature (145°F on MU-TS-0002),

ESAS actuation (1600# or 4#), or high radiation level (RM-L-1 ).

                 -   MU-V-3 closes on high temperature (135°F MU5-TS or 145°F MU-TS-0001 ), ESAS actuation ( 1600# or 4#), Loss of Auto power or Loss of Instrument air.
                 -   MU-V-4 and 5 close on loss of IA.

2.0 MATERIAL AND SPECIAL EQUIPMENT If MU-V-5 is not remotely operable, then a headset is required for MU Valve Alley communications with an operator at MU-V-98. 3.0 PRECAUTIONS, LIMITATIONS, AND PREREQUISITES 3.1 Precautions None 3.2 Limitations 3.2.1 To prevent letdown cooler leakage caused by thermal stress, the rate of change of letdown flow should be limited to 2.5 GPM/Min. If letdown flow indication is not available, then maximum open position of MU-V-5 is 50% or MU-V-98 Y2 turn. Open valve from closed to the maximum open position gradually over at least a 20 minute period.

OP-TM-211-950 Revision 7 Page 2 of 9 3.3 Prerequisites 3.3.1 VERIFY ICCW flow> 550 GPM. 3.3.2 VERIFY the following valves are Open:

     -   IC-V-2
     -   IC-V-3
     -   IC-V-4 3.3.3 VERIFY any of the following:
     -   ESAS defeated.
     -   ESAS did not actuate.
     -   AOP-046 was entered.

3.3.4 VERIFY ICCW cooler outlet temperature< 100°F. 3.3.5 VERIFY all CRD stator temperatures < 160°F or reactor is shutdown. 3.3.6 If RM-L-1 alarmed or ESAS actuated, then VERIFY the following:

     -   Integrity of letdown line to MU-T-1 has been assessed.
     -   RM-G-22 & 23 do not indicate excessive RCS activity.
     -   RM-A-6, RM-A-8, or portable radiation monitors are in service to detect any release that may result from opening containment isolation valves.
     -   ED/SM has given permission to re-open containment isolation valves.

OP-TM-211-950 Revision 7 Page 3 of 9 4.0 MAIN BODY 4.1 If isolation was due to high letdown temperature, then perform the following:

1. CLOSE MU-V-6A.

2. CLOSE MU-V-6B.

3. OPEN MU-V-70A (MU Demin Bypass) (AB 305: Mini Valve Alley).

4. PLACE MU-V-2A/B Letdown Cooler "A" and "B" MU-V-2A/B Temperature Interlock switches in BYPASS position (AB 305: 1BES Valves MCC Unit 50).

5. PLACE MU-V-3 Letdown Block Valve Temperature Interlock switch in BYPASS position (AB 281: on terminal box T-85 near MU-V-3).

4.2 If Aux Bldg IA pressure< 60 psig, then CLOSE the following: MU-V-3 MU-V-4 MU-V-6A MU-V-6B MU-V-11A MU-V-11 B 4.3 If Aux Bldg IA pressure < 60 psig, then OPEN the following: MU-V-70A (MU Demin Bypass) (AB 305: Mini Valve Alley). MU-V-110 (MU-F-1A/B Bypass) (281 AB: Decant Slurry Pump Rm).

OP-TM-211-950 Revision 7 Page 4 of 9 4.4 If ICS AUTO power is de-energized, then perform the following:

1. OBTAIN SM concurrence:

Shift Manager

2. DISCONNECT lead 7-3-3-16 (ICS/NNI cabinet #7) (MU-V-1A and MU-V-18).

CV Date

3. DISCONNECT lead 5-4-5-4 (ICS/NNI cabinet #5) (MU-V-3).

CV Date

4. IAAT two or more CRD stator temperatures exceed 160°F or ICCW flow to reactor building is lost, then CLOSE the following: D

         -   MU-V-3
         -   MU-V-2A
         -   MU-V-28 4.5  ENSURE the following valves are Closed:

MU-V-3 MU-V-4 MU-V-5 or MU-V-97A (AB 281: MU Valve Alley) 4.6 If MU-V-98 is Throttled Open IAW OP-TM-211-441, Increased Letdown Flowrates, then CLOSE MU-V-98. NOTE: If MU-V-1NB is open and 480 VAC power is lost, these valves will remain open.

4. 7 ENSURE the following are Open:

MU-V-1A MU-V-18

OP-TM-211-950 Revision 7 Page 5 of 9 4.8 Open MU-V-2A and MU-V-2B as follows:

1. If "Makeup & Purif' switch in RSTSP "B" is in the EMERG position, then OPEN the following at RSO Panel "B":

        -   MU-V-2A
        -   MU-V-2B

2. ENSURE the following are Open:

        -   MU-V-2A
        -   MU-V-2B

3. If MU-V-2A is closed, then perform the following:

A. OPEN MU-V-2A-BK (1 B ESV MCC Unit 40) B. Manually OPEN MU-V-2A (281 RB: Letdown Cooler Room).

4. If MU-V-2B is closed, then perform the following:

A. OPEN MU-V-2B-BK at (1 B ESV MCC Unit 50) B. Manually OPEN MU-V-2B (281 RB: Letdown Cooler Room). NOTE: For all MU-V-98 operations, headset communications should be used between operator at MU-V-98 and the control room. 4.9 Establish min flow path around block orifice as follows:

1. If MU-V-5 is not remotely operable, then THROTTLE MU-V-98 one-quarter turn Open.

2. If MU-V-5 is remotely operable, then PLACE MU-V-5 at 10% Open.

4.10 ENSURE MU-V-8 is aligned to the THRU position.

OP-TM-211-950 Revision 7 Page 6 of 9 4.11 Open MU-V-3 as follows:

1. If MU-V-3 closed on high temperature, then PUSH AND HOLD MU-V-3 open pushbutton until high letdown temperature alarm clears.

2. If aux bldg IA pressure< 60 psig, then UNLOCK and locally OPEN MU-V-3 (RCS Letdown RB lsol)

(281 AB: Non Mezzanine, Send).

3. If "Makeup & Purif' switch in RSTSP "A" is in the EMERG position, then OPEN MU-V-3 at RSD Panel "A"

4. ENSURE MU-V-3 is Open.

5. If MU-V-3 is closed, then UNLOCK and locally OPEN MU-V-3 (RCS Letdown RB lsol) (281 AB: Non Mezzanine, Send).

4.12 CONTROL ICCW temperature IAW OP-TM-541-461. D 4.13 MAINTAIN letdown temperature< 125°F. D 4.14 Raise letdown flow at< 2.5 gpm/min to desired flow as follows:

1. If letdown flow indication is not available, then perform the following:

A. LIMIT position of MU-V-98 to~ turn open or MU-V-5 to 50% demand. B. Gradually OPEN MU-V-98 or MU-V-5 over at least 20 minutes.

2. If MU-V-5 is not remotely operable, then THROTTLE MU-V-98.

3. If MU-V-5 is remotely operable, then THROTTLE MU-V-5.

OP-TM-211-950 Revision 7 Page 7 of 9 5.0 RETURN TO NORMAL 5.1 If primary Instrument Air pressure was less 60 psig, then perform the following:

1. When primary Instrument Air pressure is greater than 80 psig, then CONTINUE.

2. OPEN the following to_place the NORMAL demin in service:

MU-V-6A MU-V-6B

3. OPEN MU-V-11A.

4. CLOSE the following:

MU-V-?OA (MU Demin Bypass) (AB 305: Mini Valve Alley). MU-V-110 (MU-F-1A/B Bypass) (281 AB: Decant Slurry Pump Rm).

5. PRESS OPEN pushbutton for MU-V-3.

6. PLACE MU-V-3 handwheel in the Full Closed position (full clockwise direction) and LOCK handwheel.

CRIT IV Date

7. VERIFY MU-V-3 is Open.

5.2 If undefeatable "A" train ESAS actuation occurred and MU-V-3 was locally opened, then perform the following:

1. When "A" train ESAS actuation signal has cleared, then CONTINUE.

2. PRESS OPEN pushbutton for MU-V-3.

3. PLACE MU-V-3 handwheel in the Full Closed position (full clockwise direction) and LOCK handwheel.

CRIT IV Date

4. VERIFY MU-V-3 is Open.

OP-TM-211-950 Revision 7 Page 8 of 9 5.3 If undefeatable "B" train ESAS actuation occurred and MU-V-2A/B were locally opened, then perform the following:

1. When "B" train ESAS actuation signal has cleared, then CONTINUE.

2. CLOSE the following at 1B ESV MCC:

A. MU-V-2A-BK (1 B ESV MCC Unit 4D) GRIT IV Date B. MU-V-2B-BK at (1 B ESV MCC Unit 5D) GRIT IV Date

3. VERIFY the following are Open:

MU-V-2A MU-V-2B 5.4 If isolation was due to high letdown temperature, then perform the following:

1. If MU-V-?OA (MU Demin Bypass) is Open, then perform the following:

A. OPEN the following to_place the NORMAL demin in service:

               -   MU-V-6A
               -   MU-V-6B B. CLOSE MU-V-?OA. (AB 305: Mini Valve Alley).

2. PLACE MU-V-2A/B Letdown Cooler "A" and "B" MU-V-2A/B Temperature Interlock switches to NORMAL position.

3. PLACE MU-V-3 Letdown Block Valve Temperature Interlock switch to NORMAL position.

OP-TM-211-950 Revision 7 Page 9 of 9 5.5 If MU-V-5 was not remotely operable, then perform the following:

     -   When MU-V-5 is remotely operable (Instrument air and HAND power),

then transfer letdown flow control to MU-V-5 as follows: A. ENSURE MU-V-97A is Open. B. Slowly CLOSE MU-V-98 and OPEN MU-V-5 maintaining letdown flow as constant as possible. 5.6 Slowly ADJUST MU-V-5 to obtain approximately 50 GPM letdown flow.

5. 7 When pressurizer level is restored to the desired range and letdown flow is approximately 50 GPM, then perform the following:

     -   OPEN MU-V-4.

CLOSE MU-V-5. 5.8 If RCS temperature> 200°F, then MAKE Transient Cycle Logbook entry G11 for RCS Letdown Cooler Thermal Cycle. 5.9 If ICS AUTO power was de-energized, then perform the following:

     -   When ICS AUTO power is energized, then CONNECT the following lifted leads:
         -  Lead 7-3-3-16 (ICS/NNI cabinet #7) (for MU-V-1A and MU-V-18)

CV Date

         -  Lead 5-4-5-4 (ICS/NNI cabinet #5) (for MU-V-3)

CV Date

6.0 REFERENCES

6.1 FHAR Attachments 3-3 and 3-7 7.0 ATTACHMENTS None

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:

006 A2.13 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 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: 'B' ESAS signal is defeated, Makeup Pump 1C is secured, MU-V-16B is throttle 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 248.

2. ENSURE SI Flow is less than 40 gpm.

3. Insert:

a. MALFUNCTION ES08B 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 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 NRC JPM C NU REG 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.

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 NU REG 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-1 C (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 "8" 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 (1 S 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 NRC JPM C NU REG 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 the normal makeup (-40 gpm), 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 --./ 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 NRC JPM C 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 NUREG 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

OP-TM-AOP-046 Lon ti Revision 6 Page 1 of 69 Level EP INADVERTENT ESAS ACTUATION 1.0 ENTRY CONDITIONS All of the following:

     - Makeup and Purification System in the ES Standby Mode.
     - Any of the following:
          - ESAS 1600# RCS press actuation.
          - ESAS 500# RCS press actuation.
          - ESAS 4# RB press actuation.
     - No ESAS actuation setpoints have been exceeded.
     -   No fires in the following zones:
           -   AB-FZ-4: AB 281' Shield Wall Area
           -   CB-FA-3C: ESAS Room
           -   CB-FA-30: Relay Room
           -   CB-FA-4B: Control Room 2.0  IMMEDIATE ACTIONS I     ACTION/EXPECTED RESPONSE                      RESPONSE NOT OBTAINED 2.1    DEFEAT invalid ESAS signals.            1. If "A" train can not be defeated, then GO TO Section 4.0.

2. If "B" train can not be defeated, then GO TO Section 5.0.

2.2 STOP Makeup Pumps not required for seal injection. 2.3 THROTTLE MU-V-16s with HPI If any MU-V-16 with HPI flow can not flow to minimize and maintain be controlled from CR, then TRIP the MU PUMP FLOW > 115 gpm. reactor.

OP-TM-AOP-046 Revision 6 Page 2 of 69 THIS PAGE INTENTIONALLY BLANK

OP-TM-AOP-046 Revision 6 Page 35 of 69 5.0 ACTIONS IF UNABLE TO CLEAR "B" TRAIN ES SIGNAL ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5.1 SHUTDOWN "B" train Makeup Pump 1. TRIP the reactor and INITIATE not required for seal injection. EOP-001.

2. DISPATCH an operator to the 1 E 4160V Bus.

3. OPEN the breaker cubicle door and TRIP the breaker for desired Makeup Pump at the 1E 4160V bus using the trip PB on the breaker frame. (MU-P-1 C-BK:

Unit 1E8) (MU-P-1 B-BKE: Unit 1 E9).

4. GO TO Step 5.3.

5.2 If both of the following conditions exist:

       - MU-V-76A&B are Open
       - MU-V-16C or MU-V-160 are Open, then TRIP the reactor.

OP-TM-AOP-046 Revision 6 Page 36 of 69 THIS PAGE INTENTIONALLY BLANK

OP-TM-AOP-046 Revision 6 Page 37 of 69 NOTE The following components are transferred to the Remote Shutdown Panels when the "Makeup & Purif' switch in RSTSP "B" is placed in the EMERG position: MU-V-2A, MU-V-28, MU-V-18, MU-V-20, MU-P-1C, MU-V-16C, MU-V-160, MU-V-37, MU-V-148, MU-P-38, MU-P-3C, MU-V-8, seal injection flow switch indication. 5.3 If B side RSD system available, then perform the following:

1. OPEN RSTSP "B" using key

                   #98 (1 S 480V Bus Room).

2. PLACE "Makeup & Purif' transfer switch in the EMERG position.

OP-TM-AOP-046 Revision 6 Page 38 of 69 THIS PAGE INTENTIONALLY BLANK

OP-TM-AOP-046 Revision 6 Page 39 of 69 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5.4 If fill the following conditions exist:

                                       - MU-V-77A&B are Open
                                       - MU-V-76A&B are Closed
                                       - "A" train ESAS did not actuate, then perform the following:

1. RAISE SI flow to > 40 gpm THROTTLE MU-V-16B to establish a using setpoint controller. MU PUMP FLOW of> 115 gpm.

2. ENSURE 1. OPEN MU-V-36-BK MU-V-36 is Open. (1A ESV MCC Unit 20).

2. Manually OPEN MU-V-36 (281 AB: MU Valve Alley).

3. OPEN MU-V-37 at RSO 1. OPEN MU-V-37-BK Panel "B". (1 B ESV MCC Unit 20).

2. Manually OPEN MU-V-37 (281 AB: MU Valve Alley).

4. VERIFY MU-V-36 and MU-V-37 are Open.

5. RESTORE SI flow rate to

                                                                                  - 38 gpm using setpoint controller.

6 ENSURE MU-V-16B is Closed.

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 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 < 15 feet and lowering.

Task Standard: LPI flow balanced~ 2800 gpm. 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 Initiating Cue: The CRS has directed you to transfer the reactor building sump to recirculation mode IAW OP-TM-EOP-010, Guide 21 ILT16-01 NRCJPM D NUREG 1021, Revision 10

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

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-1B 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 Override DH-V-5A Red light "On": 02A6570-2LOPBDHV5A(2)RED ON PB-DH-V-5A o Override DH-V-5A Green light "Off': 02A6564-2LOPBDHV5A(1 )GRN OFF PB/DH-V-5B 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. o Monitor the following:

• dhvdhv6a
• dhvdhv5a

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 14.5 feet or the RB Flood Level is about 54 inches, 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 4of10 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 Performanc;~ 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: EVALUATORS NOTE: Reactor Building Flood Level will be reading about 50 to 52 inches at this time, which is where it should be for this event. 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-38B is closed, wait one minute and report back that both DH-V-38A and DH-V-39B is closed. ILT16-01 NRC JPM D NU REG 1021, Revision 10

Appendix C Page 5of10 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

...J Performance Step: 4   THROTTLE both DH-V-4A and DH-V-4B to the maximum controllable flow ~ 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 ~ 3000 gpm in each line Comment:

BOOTH CUE: When DH-V-6A is> 0.5 in monitor, set dhvdhv5a =0. EXAMINER CUE: As CRS acknowledge report of breaker trip for DH-V-6B 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 ...J 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 NRC JPM D NU REG 1021, Revision 10

Appendix C Page 6of10 Form ES-C-1 PERFORMANCE INFORMATION 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: 6 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 Bin PTL

3. Examinee obtains copy of OP-TM-211-901 and announces entry into procedure Comment:

OP-TM-211-901, Precautions, Prerequisites, and Limitations Performance Step: 7 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: ILT16-01 NRC JPM D NU REG 1021, Revision 10

Appendix C Page 7 of 10 Form ES-C-1 PERFORMANCE INFORMATION 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

'1 Performance Step: 8     IAAT DH-P- f DH-P-1 A or DH-P-1 B is not operating, then perform the following:

B. If DH-V-38A and B are accessible, then perform the following:

1) CLOSE DH-V-4 on the train with the inoperable DH pump Standard: Examines 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. OP-TM-211-901, Step 4.2.7.3.B '1 Performance Step: g 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. ILT16-01 NRC JPM D NU REG 1021, Revision 10

Appendix C Page 8of10 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-211-901, Step 4.2.7.3.8 Performance Step: 10 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 all 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 ...J Performance Step: 11 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: OP-TM-EOP-010, Rule 28, Step 1 RNO Step 1 is not applicable EXAMINER NOTE: The total minimum flow is 2500 gpm. OP-TM-EOP-010, Rule 28, Step 1 RNO

...J Performance Step: 12    2. If both DH-V-38A and DH-V-388 are Open, then THROTTLE both trains for balanced total flow ::;; 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 ::;; 2800 gpm, 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 STOP TIME: ILT16-01 NRC JPM D NUREG 1021, Revision 10

Appendix C Page 9 of 10 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 10 of 10 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 < 15 feet and lowering.

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

OP-TM-EOP-010 Revision 19 Page 30 of 40 GUIDE 21 TRANSFER TO RB SUMP RECIRCULATION Page 1 of 1 IAAT BWST level< 15 feet or RB Flood Level> 54 in, then perform the following: ACTION/EXPECTED RESPONSE

1. ANNOUNCE initiation of RB sump recirculation over the page and radio.

2. VERIFY RB Flood Level> 29 in.

3. VERIFY either DH-V-38A THROTTLE both DH-V-4A or DH-V-38B is Closed. and DH-V-4B for balanced total flow

                                                     ~ 2800 gpm as read on both DH-Fl-802A and DH-Fl-803A.

GO TO Step 5.

4. THROTTLE both DH-V-4A and DH-V-4B to the maximum controllable flow~ 3000 gpm in each line.

5. When BWST Level reaches 9.5 ft, 1 . PLACE affected DH pump in PTL.

or RB Flood Level > 56 inches, then OPEN the following: 2. PLACE affected BS pump in PTL. DH-V-6A

3. INITIATE contingency actions for DH-V-6B one DH pump IAW OP-TM-211-901, "Emergency Injection HPl/LPI".

6. When BWST Level reaches 6.33 ft, or RB Flood Level > 56 inches, then CLOSE the following:

DH-V-5A DH-V-5B

7. INITIATE Guide 22 "RB Sump Recirculation".

OP-TM-211-901 Revision 7 Lon ti Page 1 of 22 Level EP EMERGENCY INJECTION (HPl/LPI) 1.0 PURPOSE This procedure provides direction for operation of the active emergency injection systems, High Pressure Injection (i.e., MU system equipment which performs HPI function) and Low Pressure Injection (i.e., DH system equipment which performs LPI function). This procedure is used for manual initiation or for operations following automatic actuation of the system. 2.0 MATERIAL AND SPECIAL EQUIPMENT None 3.0 PRECAUTIONS, LIMITATIONS, AND PREREQUISITES 3.1 Precautions 3.1.1 To prevent MU pump damage from overheating, MU-V-36 and MU-V-37 must be Open when MU pump flow is reduced to less than 115 GPM/pump with DH-V-7 A and DH-V-78 Closed. 3.1.2 To prevent MU pump damage from overheating, RC-V-2 and RC-RV-2 must be Open when MU pump flow is reduced to less than 115 GPM/pump with DH-V-7A or DH-V-78 open. 3.1.3 To prevent MU tank rupture, MU-V-36 and 37 must remain Closed while in "piggyback" mode (DH-V-7 A or DH-V-78 open). 3.1.4 To start a MU pump, the breaker anti-pump logic must be cleared. If a MU pump is placed in PTL with an ES start signal present, the breaker will open, but the breaker anti-pump start logic will be actuated. The pump cannot be started again without first removing all start signals. 3.2 Limitations 3.2.1 If LPI flow > 1250 GPM can not be verified through each injection line, then HPI must remain in service.

OP-TM-211-901 Revision 7 Page 2 of 22 3.3 Prerequisites 3.3.1 VERIFY 1Dor1 E 4160V bus is energized. 3.3.2 VERIFY Make Up system was in ES standby IAW OP-TM-211-000, "Make Up and Purification". 3.3.3 VERIFY Decay Heat system was in ES standby IAW OP-TM-212-000, "Decay Heat Removal". 3.3.4 VERIFY a valid automatic actuation has occurred or a manual actuation of HPI is required.

OP-TM-211-901 Revision 7 Page 9 of 22 4.2.7 IAAT DH-P-1A or DH-P-18 fails to start or is shut down unexpectedly (e.g., D cavitation), then perform the following:

1. If DH-P-1A failed to start, then perform the following:

A VERIFY DC-P-1A is operating.

8. START DH-P-1A.

2. If DH-P-18 failed to start, then perform the following:

A VERIFY DC-P-18 is operating.

8. START DH-P-18.

3. If DH-P-1A or DH-P-18 is not operating, then perform the following:

A If DH-V-38A or 8 are inaccessible, then perform the following:

1) NOTIFY CRS and SM, "HPI must remain in service to compensate for loss of one train of LPI".

2) If HPI is not operating, then restore HPI as follows:

a) ENSURE MU-V-3 or [MU-V-2A and MU-V-28] are Closed. b) ENSURE MU-V-25 or MU-V-26 is Closed. c) ENSURE MU-V-36 or MU-V-37 is Closed. d) OPEN DH-V-?A or DH-V-78. e) ENSURE MU-V-32 or MU-V-20 is Closed. f) ENSURE MU-V-14A or MU-V-148 is Open. g) If MU-P-1A or MU-P-18-D is available, then perform the following:

1. ENSURE MU-V-16A and MU-V-168 are Open.

2. ENSURE closed cooling water system is operating.

3. START MU-P-1A or MU-P-18-D.

OP-TM-211-901 Revision 7 Page 10 of 22 h) If MU-P-1C or MU-P-1 B-E is available, then perform the following:

1. ENSURE MU-V-16C and MU-V-16D are Open.

2. ENSURE closed cooling water system is operating.

3. START MU-P-1C or MU-P-1 B-E.

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.

2) OPEN DH-V-38A and DH-V-38B (Aux. Bldg. 281' El).

3) THROTTLE DH-V-4A and DH-V-4B to balance LPI flow IAW Rule 2.

4.2.8 If DH-V-5A or DH-V-5B is not Open, then perform the following:

1. If DH-V-5A or DH-V-6A is not Open, then perform the following:

A If BWST level< 9.5 ft, then perform the following:

1) ENSURE DH-V-6A DISABLED PB light is Off.

2) OPEN DH-V-6A.

B. If BWST level > 6.33 ft, and DH-V-6A is not Open, then OPEN DH-V-5A. C. VERIFY DH-V-5A or DH-V-6A is Open.

2. If DH-V-5B or DH-V-6B is not Open, then PERFORM the following:

A If BWST level< 9.5 ft, then --perform the following:

1) ENSURE DH-V-6B DISABLED PB light is Off.

2) OPEN DH-V-6B.

B. If BWST level> 6.33 ft, and DH-V-6B is not Open, then OPEN DH-V-5B. C. VERIFY DH-V-5B or DH-V-6B is Open.

OP-TM-EOP-010 Revision 19 HPI Page 5 of 40 RULE2 LPI THROTTLING B IAAT LPI has been actuated, then perform the following: ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE

1. Maximum LPI flow limits are reduced by 100 gpm if RC-V-4 is Open.

2. In all cases, throttle using DH-V-4A and DH-V-4B and flow indications on DH-Fl-802A and DH-Fl-803A

1. VERIFY both DH-V-6A and DH-V-6B 1. If DH-V-38A or DH-V-38B is Closed Closed. and ECCS sump level is greater than RB flood level, then THROTTLE each train to the maximum controllable flow

S 3000 gpm.

2. If both DH-V-38A and DH-V-38B are Open, then THROTTLE both trains for balanced total flow~ 2800 gpm.

3. If DH-P-1A and DH-P-1 Bare operating, and ECCS sump level cannot be verified greater than RB flood level.

then THROTTLE each train to the maximum controllable flow :S 1500 gpm.

4. GO TO Step 4.

2. VERIFY DH-V-38A or DH-V-38B is 1. THROTTLE both trains for balanced Closed. total flow::; 3300 gpm.

2. GO TO Step 4.

3. THROTTLE each train to the maximum controllable flow :S 3300 gpm.

4. VERIFY RCS temperature> 31 O °F. THROTTLE both trains to MINIMIZE SCM.

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 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom - - - Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. 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 - ZLORRV1 BG to ON immediately

3) Insert override 03A6S1 O-ZLORRV1 BR to OFF immediately

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 Examinee 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. Wait 2 minutes and 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 NU REG 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

...J 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

...J 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 NU REG 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 B
                                 -   RR-V-4A                     -   RR-V-48
                                 -   RR-V-4C                     -   RR-V-4D
                                 -   RR-V-1A                     -   RR-V-1 B 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-1 B 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: Alternate Path Begins OP-TM-534-901, Steps 4.2.1 through 4.2.9 are not applicable. ILT16-01 NRC JPM E NU REG 1021, Revision 10

Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-534-901, Step 4.2.10

.../ Performance Step: 8     If RR-V-1 Bis 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

OP-TM-534-901 Revision 14 Lon ti n Page 1 of 12 Level EP RB EMERGENCY COOLING OPERATIONS 1.0 PURPOSE This procedure provides direction for emergency operations of Reactor Building Emergency Cooling System. This procedure is used for manual initiation or following automatic actuation of the system. NOTE: Actuation of RBEC will discharge corrosion protection chemicals from coolers into the river. Actuation of RBEC is not required to be reported to PaDEP under NPDES Permit PA 0009920 issued October 30, 2007. 2.0 MATERIAL AND SPECIAL EQUIPMENT None 3.0 PRECAUTIONS, LIMITATIONS, AND PREREQUISITES 3.1 Precautions None 3.2 Limitations 3.2.1 When the RR system is actuated, maintain RR cooler outlet pressure (RR-Pl-224, 225, 226) above 50 psig, on all in-service coolers. This ensures that the reactor river system pressure is greater than the maximum containment pressure during design basis events. 3.2.2 To prevent RB fan overload, operate RB fans in SLOW SPEED when RB pressure is greater than 2 psig. 3.3 Prerequisites 3.3.1 VERIFY Reactor Building Emergency River Water System was in ES standby IAW OP-TM-534-000, "Reactor Building Emergency Cooling Water System". 3.3.2 VERIFY 1600 psig ES actuation, RB pressure is approaching 2 psig or Emergency Director or Shift Manager has authorized use of RBEC. 3.3.3 VERIFY 1D or 1E 4160V Bus is energized.

OP-TM-534-901 Revision 14 Page 2 of 12 4.0 MAIN BODY NOTE: "Total RR system flow" is obtained by summing the indications of Computer Points A1049, A1050 and A1051. 4.1 Initiation of RB Emergency Cooling 4.1.1 DISPATCH an operator to CLOSE NS-V-85 (IB 295: S of RR Valve Room). NOTE: The sequence of actuation and verification of ES is not train dependent. Either train may be performed first or trains may be performed in parallel. 4.1.2 IAAT expected equipment response is not obtained when initiating the D desired train(s) of RBEC, then INITIATE Section 4.2, Contingency Actions. 4.1.3 START or VERIFY running: Train A Train A or Train B RR-P-1A "' Train B

                                                     "'  RR-P-1 B                "'

4.1.4 ENSURE OPEN: Train A Train A or Train B RR-V-3A "' Train B RR-V-3C "' RR-V-38 "' 4.1.5 ENSURE OPEN: Train A Train A or Train B RR-V-4A "' Train B "" RR-V-48 "' RR-V-4C RR-V-40 RR-V-1A RR-V-1 B 4.1.6 VERIFY the coolers in service are controlled at 50 - 75 psig:

     -    RR-Pl-224
     -    RR-Pl-225
     -    RR-Pl-226

OP-TM-534-901 Revision 14 Page 3of12 4.1.7 VERIFY the following fans are running (Fast or Slow speed): Train A Train A or .../ Train B AH-E-1A

                             "' Train B AH-E-1C                 AH-E-1 B          "'

4.1.8 GO TO Section 4.3.

OP-TM-534-901 Revision 14 Page 4of12 4.2 Contingency Actions 4.2.1 If RR-P-1A or RR-P-1 Bis not operating, then perform the following:

1. If RR-P-1 A is not operating and 1D 4160V bus is energized, then perform the following:

A. START RR-P-1A. B. If RR-V-10A and RR-V-1A are Closed, then OPEN RR-V-1A.

2. If RR-P-1 B is not operating and 1E 4160V bus is energized, then perform the following:

A. START RR-P-1 B. B. If RR-V-108 and RR-V-18 are Closed, then OPEN RR-V-18.

3. If neither RR-P-1A/B can be started, then CLOSE all RR-V-3's and 4's.

4.2.2 If RR-V-3A, RR-V-38 or RR-V-3C are not Open, then perform the following:

1. If AH-E-1A is available, then ENSURE RR-V-3A is Open.

2. If AH-E-1 Bis available, then ENSURE RR-V-38 is Open.

3. If AH-E-1C is available, then ENSURE RR-V-3C is Open.

NOTE: In the remaining steps, fans may be started or additional RR-V-4 opened while waiting to confirm RR-V-4 travel. 4.2.3 If AH-E-1A is not operating in SLOW SPEED, then perform the following:

1. If RB pressure> 2 psig, then ENSURE AH-E-1A is operating in SLOW SPEED.

2. If AH-E-1A is not operating, then START AH-E-1A in FAST SPEED.

4.2.4 If RR-V-4A is not Open, then perform the following:

1. OPEN RR-V-4A.

2. If RR-V-4A is not Open, then PLACE AH-E-1A in PTL.

OP-TM-534-901 Revision 14 Page 5of12 4.2.5 If AH-E-1 Bis not operating in SLOW SPEED, then perform the following:

1. If RB pressure> 2 psig, then ENSURE AH-E-1 Bis operating in SLOW SPEED.

2. If AH-E-1 Bis not operating, then START AH-E-1 Bin FAST SPEED.

4.2.6 If RR-V-4B is not Open, then perform the following:

1. OPEN RR-V-4B.

2. If RR-V-4B is not Open, then PLACE AH-E-1 Bin PTL.

4.2.7 If AH-E-1 C is not operating in SLOW SPEED, then perform the following:

1. If RB pressure > 2 psig, then ENSURE AH-E-1 C is operating in SLOW SPEED.

2. If AH-E-1C is not operating, then START AH-E-1C in FAST SPEED.

4.2.8 If RR-V-4C and RR-V-4D are not Open, then perform the following:

1. OPEN RR-V-4C or RR-V-4D.

2. If RR-V-4C and RR-V-4D are Closed, then PLACE AH-E-1C in PTL.

4.2.9 If RR-V-1A is Closed, then perform the following:

1. OPEN RR-V-1A.

2. If RR-V-1A is not Open, then PLACE RR-P-1A in PTL.

4.2.10 If RR-V-1 Bis Closed, then perform the following:

1. OPEN RR-V-1 B.

2. If RR-V-1 B is not Open, then PLACE RR-P-1 B in PTL.

4.2.11 If~ the following conditions exist: RR-V-10A is Open RR-P-1A is operating "Total RR system flow"< 4800 GPM, then CLOSE RR-V-10A by isolating the air signal regulator.

Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility: THREE MILE ISLAND Task No.: 73101008 Task

Title:

Transfer BOP Susses from 18 to 1A JPM No.: ILT 16-01 NRC JPM F Aux Transformer KIA

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 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 1B ?kV bus and the 1C 4160V bus successfully transferred to the 1A Auxiliary Transformer.

Required Materials:

• 1107-1, 'Normal Electrical System', Rev 98, Section 5.3
• 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 General

References:

• 1107-1, 'Normal Electrical System', Rev 98
• 1107-11, 'TMI Grid Operations', Rev 40 ILT16-01 NRC JPM F NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Initiating Cue: Place the 1B ?kV and the 1C 4kV busses on the 'A' Auxiliary Transformer IAW 1107-1, Section 5.3, Manual Hot Bus Transfers of 4kV or ?kV busses. Time Critical Task: No Validation Time: 23 minutes ILT16-01 NRC JPM F NU REG 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 NUREG 1021, Revision 10

Appendix C Page 4 of 12 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with a check mark) START TIME: EVALUATORS CUE: Direct the examinee to place the 18 7kV and 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 a. Verify that there is a DC control power available to the breakers by observing the red and green lights above their control switches Standard: Examinee verifies DC control power available. Comment: 1107-1, Prerequisites, Step 5.3.1 Performance Step: 2 b. Verify that the Aux Transformer that the bus will be transferred to is available to supply power to the bus. Ensure that the Aux Transformer trouble alarm (AA-2-7, AA-2-8) for that transformer is not in alarm. Standard: Examinee verifies 1A Aux Xfmr is available to supply the bus Comment: ILT16-01 NRC JPM F NUREG 1021, Revision 10

Appendix C Page 5of12 Form ES-C-1 PERFORMANCE INFORMATION 1107-1, Prerequisites, Step 5.3.1 Performance Step: 3 c. Verify switches A through D are in the Open position for the following:

                                        - 1A\50-51/46-A Test Switch A (RBB)
                                        - 18\50-51/46-A Test Switch B (RBA)

Standard: Examinee with verify the switches on the bottom of RBA and RBB are open (back of the simulator on the west side) Comment: 1107-1, Prerequisites, Step 5.3.1 Performance Step: 4 d. Notify the CRS/SM that a "Hot Bus Transfer" will be performed Standard: Examinee will notify the CRS (examiner) that a hot bus transfer is going to occur. Comment: EXAMINER NOTE: As soon as practical, after the alternate supply breaker has closed, the other supply breaker should be opened. DO NOT leave the Aux Transformers paralleled. 1107-1, Procedure, 5.3.2.A v Performance Step: 5 1. Turn the control switch for the alternate supply breaker to the CLOSE position and hold until the red light comes on, indicating that the breaker has successfully closed Standard: Examinee turns 1SA-72 (breaker from 1A Aux Transformer to 1B

                            ?kV bus) breaker control to the CLOSE position and holds until the RED CLOSED light comes on.

Comment: ILT16-01 NRC JPM F NU REG 1021, Revision 10

Appendix C Page 6 of 12 Form ES-C-1 PERFORMANCE INFORMATION 1107-1, Procedure, 5.3.2.A v Performance Step: 6 2. Turn the control switch for the other supply breaker to the TRIP position and hold until the green light comes on, indicating the breaker has opened Standard: Examinee turns 1SB-02 (breaker from 1B Auxiliary Transfer to 1B ?kV bus) breaker control to the TRIP position and holds until the GREEN TRIPPED light comes on Comment: 1107-1, Procedure, 5.3.2.A Performance Step: 7 3. Verify that the Main Annunciator, AA-3-7, "AUX XFMRS PARALLEL", is clear Standard: Examinee verifies that AA-3-7, "AUX XFMRS PARALLEL" clears Comment: EXAMINER NOTE: Rote-play as CRS/SM and acknowledge that a hot bus transfer been successfully performed for the 1A 7KV bus to the '8' Aux transformer. 1107-1, Procedure, 5.3.2.A Performance Step: 8 4. Notify the CRS/SM that the ?KV bus has been successfully transferred to the other Aux Transformer Standard: Examinee notifies the CRS/SM that the 1B ?KV bus has been successfully transferred to the 'A' Aux Transformer. Comment: ILT16-01 NRC JPM F NU REG 1021, Revision 10

Appendix C Page 7of12 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER CUE: Notify the examinee that the URO will be logging all events in the log book. 1107-1, Procedure, 5.3.2.A Performance Step: 9 5. Log the bus transfer in the Control Room Log (if more than 1 bus is being transferred at a time, the log book entry may wait for all transfers to be completed prior to it being logged) Standard: The examines will notify the examiner to make the required log. Comment: EXAMINER NOTE: The next section is for the 1C 4kV bus. 1107-1, Procedure, 5.3.2.B Performance Step: 10 1. At PR Panel, note tap changer positions: 1A 18- - - Standard: Examines notes tap changer positions for 1A and 1B at Panel PR Comment: 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: 11 2. Verify or place Aux Xfmr 1A load tap changer switch in manual IAW 1107-11, TMI Grid Operations.

3. Verify or place Aux Xfmr 1B load tap changer switch in manual IAW 1107-11, TMI Grid Operations.

Standard: Examines will request 1107-11 to place the 1A and 1B load tap changers in manual. Comment: ILT16-01 NRC JPM F NUREG 1021, Revision 10

Appendix C Page 8of12 Form ES-C-1 PERFORMANCE INFORMATION 1107-11, Procedure, 3.5.3.1.2 for both Load Tap Changers ..,/ Performance Step: 12 5. On panel PR SELECT "Manual" on the "Auto-Man" select switch for the Aux. Transformer LTC to be manipulated

6. 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: 1107-1, Procedure, 5.3.2.B Performance Step: 13 4. 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: 14 5. 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: ILT16-01 NRC JPM F NU REG 1021, Revision 10

Appendix C Page 9 of 12 Form ES-C-1 PERFORMANCE INFORMATION EXAMINER NOTE: A momentary high voltage alarm is acceptable. 1107-1, Procedure, 5.3.2.B Performance Step: 15 6. 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: 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 1B Auxiliary Transformer should be done in rapid succession (less than 2 seconds). 1107-1, Procedure, 5.3.2.B ..,/ Performance Step: 16 8. Close the feeder breaker from the transformer being loaded. Standard: Examinee turns 1SA-C2 breaker control to the CLOSE position and holds until the RED CLOSED light comes on. Comment: ..,/ Performance Step: 17 9. Open the feeder breaker from the transformer being loaded. Standard: Examinee turns 1SB-C2 breaker control to the TRIP position and holds until the GREEN TRIPPED light comes on. Comment: ILT16-01 NRC JPM F NU REG 1021, Revision 10

,~ Appendix C Page 10 of 12 Form ES-C-1 PERFORMANCE INFORMATION 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 11 of 12 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 12 of 12 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 1B ?kV and the 1C 4kV busses 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 NU REG 1021, Revision 10

Number 1011 TMI - Unit 1 1107-1 Title Revision No. Normal Electrical S stem 98 Applicability/Scope USAGE LEVEL Effective Date TMI Division 1 05/11/16 This document is within QA plan scope Yes No 50.59 Applicable Yes No List of Effective Pages Page Revision Page Revision Page Revision Page Revision 1 98 41 98 81 98 121 98 2 98 42 98 82 98 122 98 3 98 43 98 83 98 123 98 4 98 44 98 84 98 124 98 5 98 45 98 85 98 125 98 6 98 46 98 86 98 126 98 7 98 47 98 87 98 127 98 8 98 48 98 88 98 128 98 9 98 49 98 89 98 129 98 10 98 50 98 90 98 130 98 11 98 51 98 91 98 131 98 12 98 52 98 92 98 132 98 13 98 53 98 93 98 133 98 14 98 54 98 94 98 134 98 15 98 55 98 95 98 135 98 16 98 56 98 96 98 136 98 17 98 57 98 97 98 137 98 18 98 58 98 98 98 19 98 59 98 99 98 20 98 60 98 100 98 21 98 61 98 101 98 22 98 62 98 102 98 23 98 63 98 103 98 24 98 64 98 104 98 25 98 65 98 105 98 26 98 66 98 106 98 27 98 67 98 107 98 28 98 68 98 108 98 29 98 69 98 109 98 30 98 70 98 110 98 31 98 71 98 111 98 32 98 72 98 112 98 33 98 73 98 113 98 34 98 74 98 114 98 35 98 75 98 115 98 36 98 76 98 116 98 37 98 77 98 117 98 38 98 78 98 118 98 39 98 79 98 119 98 40 98 80 98 120 98

Number TMI - Unit 1 1107-1 Title Revision No. Normal Electrical S stem 98 TABLE OF CONTENTS Section

1.0 REFERENCES

5 1.1 Systems Description 5 1.2 GAi Drawings 5 1.3 Other Operating Procedures 6 1.4 Manufacturers' Instruction Manuals 6 1.5 Tech Specs 6 1.6 Other Documents 6 2.0 LIMITS AND PRECAUTIONS 6 2.1 Hazards 6 2.2 Precautions 6 2.3 Administrative 9 3.0 OPERATING PROCEDURE 12 3.1 Placing the 1A ?KV bus in service 12 3.2 Placing the 1B 7KV bus in service 13 3.3 Placing the 1A 4KV bus in service 14 3.4 Placing the 1B 4KV bus in service 16 3.5 Placing the 1C 4KV bus in service 18 3.6 Placing the 1F 4KV bus in service 20 3.7 Placing a single transformer 480 volt bus in service (1 E, 1F, 1N) 21 3.8 Placing a dual transformer 480 volt bus in service 22 (1C/1D, 1G/1H, 1J/1K, 1L/1M) 3.9 Placing the 1U 480 volt bus in service 26 2

Number TMI - Unit 1 0 1107-1 Title Revision No. Normal Electrical S stem 98 5.3 Manual Hot Bus Transfers of 4KV or 7KV busses NOTE DO NOT leave the Aux transformers paralleled when the reactor is critical. CAUTION During power operation, aligning both 4 KV ES Susses to a single aux transformer is prohibited. If the aux transformer will not be able to supply the vital 4 KV loads, it will be necessary to load it on its emergency diesel immediately. 5.3.1 Prerequisites

a. Verify that there is a DC control power to the breakers is available by observing the red and green lights above their control switches.

b. Verify that the Aux Transformer that the bus will be transferred to is available to supply power to the bus. Ensure that the Aux Transformer trouble alarm (AA-2-7, AA-2-8) for that transformer is not in alarm.

c. Verify switches A through D are in the Open position for the following:

1A\50-51/46-A Test Switch A (RBB). 18\50-51/46-A Test Switch A (RBA).

d. Notify CRS/SM that a "Hot Bus Transfer" will be performed.

5.3.2 Procedure NOTE As soon as practical, after the alternate supply breaker has closed, the other supply breaker should be opened. DO NOT leave the Aux Transformers oaralleled. A. 7KV Hot Bus Transfers

1. Turn the control switch for the alternate supply breaker, to the CLOSE position and hold, until the red light comes on, indicating that the breaker has successfully closed.

2. Turn the control switch for the other supply breaker, to the TRIP position and hold, until the green light comes on, indicating the breaker has opened.

3. Verify that the Main Annunciator, AA-3-7, "AUX XFMRS PARALLEL" is clear.

39

Number TMI - Unit 1 1107-1 Title Revision No. Normal Electrical S stem 98

4. Notify the CRS/SM that the 7KV bus has been successfully transferred to the other Aux Transformer.

5. Log the bus transfer in the Control Room Log. (If more than 1 bus is being transferred at a time, the log book entry may wait for all transfers to be completed, prior to it being logged.)

B. 4KV Hot Bus Transfers NOTE 4 kV voltage fluctuations due to load changes associated with cross ties and bus transfers during manual LTC operation can lead to the LTC controller latching into "lower" mode. This will result in the AA-2-7 alarm. Clearing this condition will require reset via the "HHRS" pushbutton located at the aux transformer.

1. At PR Panel, note tap changer positions:

1A 1B

2. Verify or place Aux Xfmr 1A load tap changer switch in manual IAW 1107-11, TMI Grid Operations.

3. Verify or place the Aux Xfmr 1B load tap changer switch in manual IAW 1107-11, TMI Grid Operations.

4. Verify that the 230KV buses are cross-tied.

At least one cross-tie is required.

5. 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.

NOTE Momentarv Low Voltaqe Alarm is acceptable.

6. 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.).

NOTE Momentarv Hioh Voltaoe Alarm is acceptable.

7. If these criteria can not be achieved, then obtain Engineering advice.

40

Number TMI - Unit 1 0 1107-1 Title Revision No. Normal Electrical S stem 98 NOTE Steps 8 and 9 are to be performed in rapid succession (less than 2 seconds).

8. Close feeder breaker from the transformer being loaded.

9. Open feeder breaker from the transformer being unloaded.

10. Repeat Steps 5 thru 9, as needed, for all buss( es) being transferred.

11. Verify that Main Annunciator, AA-3-7, "Aux. Xfmrs. Parallel" is clear.

12. Place both Load Tap Changers in Auto JAW 1107-11, TMI Grid Operations.

13. Notify CRS/SM that the 4KV Buss(es) have been successfully transferred to the other Aux. Transformer.

14. Log bus transfer(s) in the Control Room Log.

41

Number E TMI - Unit 1 Operating Procedure 1107-11 Title Revision No. TMI Grid Operations 40 Applicability/Scope USAGE LEVEL Effective Date TMI Division M 01/17/17 This document is within QA plan scope Yes No 50.59 Applicable Yes No List of Effective Pages Page Revision Page Revision Page Revision Page Revision 1 40 41 40 81 40 2 40 42 40 82 40 3 40 43 40 83 40 4 40 44 40 84 40 5 40 45 40 85 40 6 40 46 40 86 40 7 40 47 40 87 40 8 40 48 40 88 40 9 40 49 40 10 40 50 40 11 40 51 40 12 40 52 40 13 40 53 40 14 40 54 40 15 40 55 40 16 40 56 40 17 40 57 40 18 40 58 40 19 40 59 40 20 40 60 40 21 40 61 40 22 40 62 40 23 40 63 40 24 40 64 40 25 40 65 40 26 40 66 40 27 40 67 40 28 40 68 40 29 40 69 40 30 40 70 40 31 40 71 40 32 40 72 40 33 40 73 40 34 40 74 40 35 40 75 40 36 40 76 40 37 40 77 40 38 40 78 40 39 40 79 40 40 40 80 40

Number TMI - Unit 1 Operating Procedure 1107-11 Title Revision No. TMI Grid Operations 40 TABLE OF CONTENTS Section

1.0 REFERENCES

4 1.1 References 4 2.0 LIMITS AND PRECAUTIONS 5 3.0 OPERATING PROCEDURES 6 3.1 Startup - LEVEL 1 6 3.2 Normal Operations 8 3.2.1 Substation Voltage Control - LEVEL 2 8 3.2.2 Generator Reconciliation - LEVEL 3 16 3.3 Shutdown 16 3.4 Grid Related Conditions - LEVEL 2 17 3.4.1 Low Grid Voltage Response 17 3.4.2 High Grid Voltage Response 20 3.4.3 Response to RTO Emergency Information 22 3.4.4

• Solar Magnetic Disturbances 28 3.4.5 Response to RTO Minimum Generation Alert and Emergency 29 3.4.6 Response to RTO" Post Trip Contingency Voltage Alarm" Message 30 3.4.7 FirstEnergy (Transmission Owner) Interface for a "Grid Disturbance" 34 3.4.8 Operation with one 230 kV line in service 34 3.5 Component Operations 37 3.5.1 Removing Aux Transformer Fans From Service - LEVEL 1 37 3.5.2 Placing Aux Transformer Fans in Service - LEVEL 1 38 3.5.3 Load Tap Changer Ops - LEVEL 2 40 3.5.4 Closing Operations of the No Load Disconnects - LEVEL 2 47 3.5.5 Opening Operations of the No Load Disconnects - LEVEL 2 49 3.5.6 No Load Disconnect Emergency Operations - LEVEL 2 50 2

Number TMI - Unit 1 Operating Procedure 1107-11 ~itle Revision No. TMI Grid Operations 40 3.5.3 Load Tap Changer Ops - LEVEL 2 NOTE The Load Tap Chanqers (L TC) will normally be in "Auto" .. NOTE Information on LTC Accuracy The LTC is set to control the 4KV voltage between 4162 and 4218 volts. Given the accuracy of the LTC controller actual voltage could range from a low of 4151 volts to a high of 4228 volts. The Control Room typically uses PPC Points A 1039 and A 1038 to observe the 1D and 1E bus voltages. Given the accuracy of the indication loop and the accuracy of the LTC controller the indicated voltage could range to a low of 4139 volts to a high of 4240 volts. Despite the inaccuracies the total control range at any given time should be about 56 volts. 3.5.3.1 Transferring LTC from Auto to Man 3.5.3.1.1 Prerequisites Manual control of plant voltage is required, or loss of automatic control of the LTC. Computer point L2577(1 A) and/or L2578(1 B) are clear (not in alarm) indicating power is available to the LTC controller. 40

Number TMI - Unit 1 Operating Procedure 1107-11 Title Revision No. TMI Grid Operations 40 3.5.3.1.2 Procedure NOTE The following steps also satisfy compliance with notification requirements of OP-TM-108-107-1002, TMI SWITCHYARD OPERATIONS.

1. NOTIFY FirstEnergy RCC TSO that TMl-1 will be taking Manual control of LTC.

NOTE When required by NERC Standards or Agreements to communicate information to RTO TMI communicates the information to Generation Dispatch (GD) and it is Generation Dispatch's responsibility to communicate with RTO.

2. NOTIFY Generation Dispatch (GD) that TMl-1 will be taking Manual control of LTC.

3. NOTIFY the NDO that TMl-1 will be taking Manual control of LTC.

4. LOG conversations with FirstEnergy RCC TSO, NDO, and Generation Dispatch (GD) in the Control Room Logbook.

5. On panel PR SELECT "Manual" on the "Auto-Man" select switch for the Aux. Transformer LTC to be manipulated.

6. While monitoring voltage (e.g., A1039/A1038, system 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.

7. If RCC TSO or Generation Dispatch (GD) reports that on loss of TMl-1, post LOCA contingency (Emergency Low) voltage alarm will be :5 223 on the TMI 230 kV bus, then REFER TO Section 3.4.6 for actions.

NOTE The lower voltage control range during light load conditions will limit inverter cycling between DC and AC inputs. The higher voltage control range for Power Operations allows for voltage decrease on generator trip and fast transfer upon loss of an auxiliary transformer. 41

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 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 hours 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 NUREG 1021, Revision 10

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

• 100% IC16

1. Ensure NR-P-1A/C are running.

2. Place NR-P-1 B 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-1 B

4. Open NR-V-4A and NR-V-4B 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-1C.

6. Insert LO Overrides to illuminate NR-V-4A/B closed lights:

• 04A2S04-ZLONRV4BG GRN NR-V-4BG Value - ON
• 04A2S08- ZLONRV4BR RED NR-V-4BR Value - OFF
• 04A2S11-ZLONRV4AG GRN NR-V-4AG Value - ON
• 04A2S15-ZLONRV4AR RED NR-V-4AR Value - OFF
• 08A1S40-ZLOPCRNRV4A(1) BLU Value - ON
• 08A1S40-ZLOPCRNRV4A(2) AMBValue - OFF
• 08A3S17-ZLOPCRNRV48(1) BLU Value - ON
• 08A3S17-ZLOPCRNRV48(2) AMBValue - OFF

7. Perform OP-TM-EOP-001 IMA's and execute OP-TM-AOP-031 up through Step 3.9

8. 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)

9. Adjust MUT level for current plant conditions (MUMMT to 27500)

10. Set Event 1 to close the following breakers:

• RWR47 1A ES SHMCC Unit 2A (NR-V-1) Value - CLOSE
• RWR19 1A ES SHMCC Unit 2B (NR-V-3) Value - CLOSE
• RWR20 1A ESV MCC Unit 80 (NR-V-5) Value - CLOSE
• RWR21 1B ESV MCC Unit 1OD (NR-V-6) Value - CLOSE
• RWR48 1B ES SHMCC Unit 2A (NR-V-7) Value - CLOSE

11. Place the simulator in FREEZE ILT 16-01 NRC JPM G NUREG 1021, Revision 10

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

12. 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.

13. This completes the setup for this JPM.

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

Appendix C Page 5of11 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: Notes both NR-V-4A and 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 6of11 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 2B)
• NR-V-7-BK (1 BES Screen house MCC Unit 2A)
• NR-V-5-BK (1A ES Valves MCC Unit 8D)
• NR-V-6-BK (1 BES Valves MCC Unit 1OD)

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 NUREG 1021, Revision 10

Appendix C Page 7 of 11 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

..J Performance Step: 6     ENSURE the third Secondary River pump is operating.

Standard: Starts the third SR pump SR-P-1 A by rotating extension control clockwise (CL) observes RED light on GREEN light off. Comment: OP-TM-541-901, Step 4.7

..J 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 ..J 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 NUREG 1021, Revision 10

Appendix C Page 8 of 11 Form ES-C-1 PERFORMANCE INFORMATION OP-TM-541-901, Step 4.9 .J 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: .J OP-TM-541-901, Step 4.10 Performance Step: 10 WAAT 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 NU REG 1021, Revision 10

Appendix C Page 9 of 11 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 NUREG 1021, Revision 10

Appendix C Page 10of11 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 11 of 11 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 hours in to a 36-hour outage.
• NR-P-1C 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

   "' I 7                                                                   OP-TM-541-901 Revision 3 Page 1 of 5 Level EP CROSS-TIE SECONDARY RIVER TO SUPPLY NUCLEAR RIVER 1.0     PURPOSE This procedure provides direction for supplying Secondary River (SR) to the Nuclear Service (NS) and Intermediate Closed (IC) heat exchangers.

2.0 MATERIAL AND SPECIAL EQUIPMENT None 3.0 PRECAUTIONS, LIMITATIONS, AND PREREQUISITES 3.1 Precautions None 3.2 Limitations To prevent SR pump motor overload, maintain secondary river header pressure (as read on SR-Pl-134) greater than 21 psig. 3.3 Prerequisites 3.3.1 VERIFY one of the following conditions: Reactor is shutdown, TS 3.0.1 action statement has been entered.

OP-TM-541-901 Revision 3 Page 2 of 5 4.0 MAIN BODY 4.1 IAAT Secondary Closed cooler outlet temperature is greater than 90 °F, then LOWER reactor power. D 4.2 ENSURE NR-V-4A or NR-V-48 is Closed. 4.3 ENSURE discharge valves are Closed on all NR or SR pumps which are shutdown. 4.4 DISPATCH an Operator to Close the following breakers: NR-V-2-BK (1A ES SCREEN HOUSE MCC UNIT 2A) NR-V-3-8K (1A ES SCREEN HOUSE MCC UNIT 28) NR-V-7-8K (18 ES SCREEN HOUSE MCC UNIT 2A) NR-V-5-8K (1A ES VALVES MCC UNIT 8D) NR-V-6-8K(18 ES VALVES MCC UNIT 10D) 4.5 IAAT NR piping between NR-V-3 and NR-V-5 is ruptured or blocked, then CLOSE the following valves: D

1. NR-V-3

2. NR-V-5 4.6 ENSURE the third Secondary River pump is operating.

4. 7 ENSURE SR pump discharge valves are OPEN.

4.8 WAAT NR-V-2-8K (1A ES SCREEN HOUSE MCC UNIT 2A) is CLOSED, then OPEN NR-V-2. CJ 4.9 WAAT NR-V-7-8K (18 ES SCREEN HOUSE MCC UNIT 2A) is CLOSED, then OPEN NR-V-7. CJ 4.10 WAAT NR-V-6-8K (18 ES VALVES MCC UNIT 10D) is CLOSED, then OPEN NR-V-6. CJ NOTE: Available river system capacity above that required to maintain NS & IC temperature within limits may be distributed between SR, IC & NS. 4.11 THROTTLE SR-V-2 to maintain Secondary River discharge pressure (SR-Pl-134) above 21 psig.

OP-TM-541-901 Revision 3 Page 3 of 5 4.12 THROTTLE OPEN NR-V-16A, 8, C, D to maintains NS cooler outlet temperature less than 95 °F. 4.13 THROTTLE OPEN NR-V-15A, B to maintain IC cooler outlet temperature less than 100 °F. 4.14 When at least one NR pump and flowpath to NS heat exchanger are available, then GO TO Section 5.0, "Return To Normal".

Appendix C Page 1 of 9 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 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: Actual Performance: x Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. 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: Once control tower ventilation is on emergency recirculation via AH-E-18A, the JPM can be terminated. 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: ILT 16-01 NRC JPM H NUREG 1021, Revision 10

Appendix C Page 2 of 9 Form ES-C-1 PERFORMANCE INFORMATION SIMULATOR SETUP

1. Reset the simulator to IC 16

2. Insert the following Malfunctions:

RM01G, AH-E-17A fails to trip on interlock, insert immediately 13A6S06ZDICSAHE188(5) str to OFF, AH-E-188 fails to start, insert immediately Set RM24 =3000 on EVENT #1 Set RM27 =4020 on EVENT #1

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 NU REG 1021, Revision 10

Appendix C Page 3 of 9 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 9 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-17 A 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 NUREG 1021, Revision 10

Appendix C Page 5 of 9 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: OP-TM-826-901, Step 4.1.6 Performance Step: 9 START AH-E-188 (A) if AH-E-17A (8) was previously operating. Standard:

• Attempts to start AH-E-188 (H&V 8), by rotating extension control to start and waiting for discharge damper to drive to the open position, recognizes it does not start.

Comment: ILT 16-01 NRC JPM H NU REG 1021, Revision 10

Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION Alternate Path Begins EXAMINER NOTE: The 'B' train, which is the standby train, will not start. 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" . ..J EVALUATORS CUE: TIME AH-E-18A is started: (must be greater than 2 mins) OP-TM-826-901, Step 4. 1. 7 ..J Performance Step: 10 If the opposite train of ventilation is unavailable, then WAIT 5 minutes after AH-E-17A (B) was shutdown and START AH-E-18A (B). Standard:

• Waits 2 minutes
• 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 7 of 9 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-18A has been started and the order has gone out to an NLO to start AH-E-90/91, the JPM may be terminated. ILT 16-01 NRC JPM H 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 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 9 of 9 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 NUREG 1021, Revision 10

MAP C-1-1 OP-TM-MAP-C0101 RADIATION Revision 3 LEVEL System 661 Page 1 of 53 HI Level 2 - Reference Use 1.0 SETPOINTS None 2.0 CAUSES

    -   Alert or High Alarm on any of the following:
    -   RM-G-1 through RM-G-7
    -   RM-G-9 through RM-G-20
    -   RM-G-24 through RM-G-27
    -   RM-L-1 through RM-L-7
    -   RM-L-9
    -   RM-A-1 , RM-A-2
    -   RM-A-4 through RM-A-9 RM-A-15 3.0  AUTOMATIC ACTIONS None 4.0  MANUAL ACTIONS REQUIRED 4.1  DETERMINE radiation monitor in alarm as indicated on PRF.

4.2 GO TO Attachment for radiation monitor in alarm.

RADIATION MAP C-1-1 OP-TM-MAP-C0101 LEVEL Revision 3 HI System 661 Page 2 of 53 RM-A-1 Control Room Page 1 of 1 1.0 SETPOINTS Refer to 1101-2.1, "Radiation Monitoring System Setpoints". 2.0 CAUSES Airborne Radioactivity in the Control Room 3.0 AUTOMATIC ACTIONS

    -   The following trip on a Hi Alarm:
        -   AH-E-1 ?A/B, AH-E-20A/B, AH-E-21, AH-E-26, AH-E-93A/B, AH-E-94A/B, AH-E-95A/B
    -   AH-D-28 and AH-D-617 Close on a Hi Alarm 4.0  MANUAL ACTIONS REQUIRED 4.1  ANNOUNCE alarm over plant page and radio.

4.2 NOTIFY Radiation Protection to verify the alarm and determine the source. 4.3 IAAT High alarm is Lit, then perform the following: D

1. PERFORM OP-TM-826-901, "Control Building Ventilation System Radiological Response Operations":

2. EVALUATE donning SCBAs.

3. REQUEST SM to evaluate Emergency Action Levels (EALs).

OP-TM-826-901 Revision 3 n Page 1 of 3 Level EP CONTROL BUILDING VENTILATION SYSTEM RADIOLOGICAL RESPONSE OPERATIONS 1.0 PURPOSE This procedure provides direction for control building ventilation system operation if a radiological event has occurred. This procedure is used following a High Alarm on RM-A-1 or 4 psig ESAS RBI signal, or if a radiological release has occurred and the control room environment is potentially threatened. 2.0 MATERIAL AND SPECIAL EQUIPMENT None 3.0 PRECAUTIONS, LIMITATIONS, AND PREREQUISITES 3.1. Precautions None 3.2. Limitations None 3.3. Prerequisites 3.3.1. VERIFY the control building ventilation was operating in the normal configuration IAW 1104-19. 3.3.2. VERIFY RM-A-1 High Alarm or 4 psig ESAS signal have actuated, or Unit Supervisor has determined that pressurized re-circulation of the control tower is necessary.

OP-TM-826-901 Revision 3 Page 2 of 3 4.0 MAIN BODY 4.1. Aligning the System for Emergency Recirc 4.1.1. If RM-A-1 high alarm or 4 psig ESAS did not actuate, then NOTIFY chemistry and ANNOUNCE over the page and radio, the intent to shift CB ventilation 4.1.2. ENSURE the following fans are shutdown: AH-E-17A and AH-E-17B AH-E-95A and AH-E-95B AH-E-20A and AH-E-20B 4.1.3. SHUTDOWN AH-E-19A and AH-E-19B. 4.1.4. ENSURE AH-D-28 or AH-D-617 are CLOSED. 4.1.5. PLACE ext. control for AH-E-93/94A and AH-E-93/94B to the OFF position. 4.1.6. START AH-E-18B (A) if AH-E-17A (B) was previously operating. 4.1.7. If the opposite train of ventilation is unavailable, then WAIT 2 minutes after AH-E-17A (B) was shutdown and START AH-E-18A (B). 4.1.8. ENSURE AH-E-19A or B is operating. 4.1.9. ENSURE AH-E-95A or B is operating. 4.1.10. START AH-E-90 and AH-E-91 at AH-E-90-EX? (FHB 305: hallway next to Hot Tool Room). 4.1.11. IF CB return flow (FR-271) < 36000 SCFM, then ENSURE AH-D-41 on the IDLE train is closed (CB 380: A or B fan room, by the door, 25' overhead).

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 BankJPM: TQ-TM-105-411-J100 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance: x Actual Performance: Classroom Simulator Plant x READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this Job Performance Measure will be satisfied. 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 "I/ 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 NUREG 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 NUREG 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 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 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 NUREG 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

OP-TM-411-451 Revision 7 Page 9 of 12 ATTACHMENT 7.1 Local Operation of TBVs (MS-V-3s) Page 1of2 Auto to Manual Operation of MS-V-3s:

1. ESTABLISH communications with Control Room.

2. TURN handwheel to align holes in sleeve with hole in stem (either set of holes in sleeve will work).

3. INSERT pin into sleeve/stem.

NOTE: Auto/Manual switch for MS-V-3s is located on side of positioner box.

4. PRESS and ROTATE Auto/Manual switch, 90 degrees counterclockwise to Manual position.

5. OPEN Actuator Pressure Equalizing valve for the desired TBV (N/A valves not used):

A MS-V-1160 (MS-V-3A) B. MS-V-1161 (MS-V-3B) C. MS-V-1162 (MS-V-3C) D. MS-V-1163 (MS-V-30) E. MS-V-1164 (MS-V-3E) F. MS-V-1165 (MS-V-3F)

6. MAINTAIN Turbine Header Pressure within limits by adjusting TBV I ADV handwheel.

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 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 NU REG 1021, Revision 10

Appendix C Job Performance Measure Form ES-C-1 Worksheet Validation Time: 8 minutes SIMULATOR SETUP N/A ILT16-01 NRC JPM J NUREG 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 NUREG 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 NRC JPM J 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 NRCJPMJ NUREG 1021, Revision 10

OP-TM-541-921 Revision 2 n ti Page 1of8 Level EP EMERGENCY MAKEUP TO NS-T-1 1.0 PURPOSE 1.1 Provide alternate methods for filling NS-T-1 when DW-P-1 is not available. The methods are:

1. Fill from Condensate system

2. Gravity fill from DW-T-1.

3. Fill from Emergency Feedwater System 2.0 MATERIAL AND SPECIAL EQUIPMENT 2.1 Approx. 50 ft of hose (rated pressure > 160 psig) with 1" Female NPT connectors on each end (IB 295: Near EF-V-4 & 5 in AOP Box #4) "Long hose assembly" 2.2 Orifice and support bracket assembly (18 295: Near EF-V-4 & 5 in AOP 8ox#4) 2.3 Approx. 6 ft of hose (rated pressure> 1500 psig) with 1" Female NPT connectors on each end, (IB 295: Near EF-V-4 & 5 in AOP Box #4) "Short hose assembly" 2.4 Wrenches for installing above.

2.5 Ladder for CO-V-170 access. 3.0 PRECAUTIONS. LIMITATIONS. AND PREREQUISITES 3.1 Precautions 3.1.1 To prevent potential hose rupture, ensure NS-V-118 is open before EF-V-278 is opened and do not close NS-V-118 until EF-V-278 is closed. 3.2 Limitations None 3.3 Prerequisites 3.3.1 VERIFY DW-P-1 unavailable. 3.3.2 VERIFY EFW system is in the standby mode IAW OP-TM-424-000.

OP-TM-541-921 Revision 2 Page 2 of 8 4.0 MAIN BODY INOTE:I Section 4.2 may proceed in parallel with Section 4.1. 4.1 If NS makeup capability from DW-P-1 is lost or at risk, then connect temporary mod to fill NS from EFW as follows: 4.1.1 OBTAIN SM concurrence to install hose from EFW to NS. (Attachment 1) 4.1.2 VERIFY CLOSED EF-V-27B. (IB 295: drain valve below EF-V-30B) 4.1.3 VERIFY CLOSED NS-V-118. (IB 295: drain valve in room South of IA-P-1A) 4.1.4 ATTACH (C clamp) orifice assembly to bldg support. (IB 295: vertical angle iron 1 FT West of EF-V-30B} 4.1.5 CONNECT (1" pipe thread) short hose assembly at EF-V-27B. 4.1.6 CONNECT (1" pipe union) short hose assembly to orifice assembly. 4.1.7 CONNECT (1" pipe union) long hose assembly to orifice assembly. 4.1.8 CONNECT (1" pipe thread) long hose at NS-V-118. 4.1.9 SECURE hose to IA-V-2105 support pedestal with tie wraps. 4.1.10 ENSURE hose is free of kinks. 4.1.11 Independently VERIFY configuration IAW Attachment 1. 4.1.12 ATTACH Attachment 2 to Control Room Drawing 302-610. INOTE:I The following two steps should be performed when time and resources allow. The remainder of the procedure may be performed in parallel. 4.1.13 LOG TCC installation in the TCC Tracking Log. 4.1.14 ENSURE TCC tags are applied to the hoses and orifice assembly. 4.2 If a condensate pump is operating, then makeup from Condensate to Nuclear Services Closed as follows: 4.2.1 VERIFY CLOSED SC-V-115 (355' TB NW side SC surge tank 4' above floor). 4.2.2 OPEN CO-V-170. (305' TB 10' SE of CO-P-2C 12' above floor).

OP-TM-541-921 Revision 2 Page 3 of 8 4.2.3 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) 4.2.4 When DW-P-1 is available, then GO TO Return to Normal. INOTE:I At this condition (no condensate pump running), Section 4.3 or 4.4 may be used to fill NS-T-1. 4.3 If DW-T-1 level is above low alarm (i.e. PPC L2623 Clear) and flow path from DW-T-1 to NS-T-1 is available, then Gravity fill from DW-T-1 to NS-T-1 as follows: 4.3.1 VERIFY the Reactor is shutdown. 4.3.2 CLOSE IA-V-49 (SFP area, W of NS-T-1 on wall). CAUTION Ear protection is necessary while venting NS-T-1. INOTE:I As NS-T-1 pressure lowers, level in tank should rise due to DW-T-1 head ( - 8 psig in NS-T-1 ). 4.3.3 OPEN NS-V-100 (top of tank) to reduce NS-T-1 air pressure. INOTE:I DW-V-10 (322' TB on wall near elevator) may be used in lieu of NS-V-102 in the following two steps. 4.3.4 When NS-T-1 at 6 feet (NS-Ll-800/801 on CC), then CLOSE NS-V-102. (SFP area, 2' W of NS-T-1, 3' above floor) 4.3.5 Throttle OPEN NS-V-102 as needed to maintain NS-T-1 level between 3 and 6 feet. (NS-Ll-800/801 on CC). 4.4 If a condensate pump is not available, then makeup to NSCCW from EFW as follows: 4.4.1 OPEN NS-V-118.

          \

4.4.2 VERIFY NS-V-29B is OPEN. 4.4.3 VERIFY no hose leakage and minimal leakage at connections. 4.4.4 VERIFY EF-P-1, 2A or 2B is operating. 4.4.5 VERIFY two EFW pumps are available or required steady state EFW flow to OTSGs is less then 200 GPM.

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 4.414.0 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 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 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: 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 'B' pressure has lowered and

• Notifies Shift Management
• Goes to Section 3.17 to terminate Gas release ILT16-01 NRC JPM K NUREG 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-~,, 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 ...J 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 NUREG 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 ..,/ 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 ..,/ 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 for WDG-T-1 C.

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 NUREG 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 NUREG 1021, Revision 10

Number TMI - Unit 1 Operating Procedure 1104-27 Title Revision No. Waste Disposal - Gaseous EVALUATOR COPY 87 ENCLOSURE 2 Page 1 of 1 Waste Gas Release Data Sheet Permit NOTE Slight changes in Auxiliary Building pressure/temperature may affect waste gas tank pressure. Shift Management should make a determination if the gas release should be terminated.

1. 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. RELEASE RM-A-8 TANK PRESSURES TIME RATE RM-A-7 PART IODINE GAS A B r. /¥-60 () 7dt/ ~ ))- ~t_) 71.L,' '72-, (.) 0 hroo <"?,a ¥~b yo /,[.; ,76~ 1~,.9'  ?;;.o 0 /6t-~O <<, :J ~q> ~-'6 /'2- '2< -* tt::6.t'{). '/J./O D ,,.., 0.. \../'1 ?t'J ~ ~ n

    /
                  ~" 7            j/--ffO       ~(-*        ;_.("'       f/..()     ~91h.

Release C o m p l e t e - - - - - - - - - - - - - - - - - - - - Operator Signature Date 65

Number TMI - Unit 1 Operating Procedure 1104-27 Title Revision No. Waste Disposal - Gaseous 87 ENCLOSURE 2 Page 1 of 1 Waste Gas Release Data Sheet Permit NOTE Slight changes in Auxiliary Building pressure/temperature may affect waste gas tank pressure. Shift Management should make a determination if the gas release should be terminated.

1. 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. RELEASE RM-A-8 TANK PRESSURES TIME RATE RM-A-7 PART IODINE GAS A B c J~t?C> 0 '?Ob ¥-0 /~ ¥0 7X.;; 7~~6 D 7,,0 ¥,?p If 35* '/:J/7 0 1-L-r'oo 11'-0  ?,;:!_, 0

/600       ~/~              4Lt:O       <o           I~         -
                                                                 ,:J...    £,I, t>      ?,.J,t>        ()

Release C o m p l e t e - - - - - - - - - - - - - - - - - - - - - Operator Signature Date 65

Number TMI - Unit 1 Operating Procedure 1104-27 Title Revision No. Waste Disposal - Gaseous 87

3. Close gas recycle valve WDG-V-25 (27 or 29), using the pushbuttons on the L.W.D. panel in the Auxiliary Building.

4. Vent the remaining 10 psig of gas in Waste Gas Decay Tank WDG-T-1A (1 B or 1C) if desired to the Station Ventilation Stack per Section 3.7 prior to refilling the Waste Gas Decay Tank. Note that this is only necessary if it is desired to fully depressurize the Waste Gas Tank.

Signature Reviewed By SRO or RO License. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Date_ _ _ _ _ _ _ __ Signature CAUTION All releases to the vent stack must be accomplished with an approved waste cias release permit. NOTE If a gas release is terminated for any reason prior to being empty, ensure it is re-started within 12 hours if possible to prevent 4 to 6 hours of additional work by Chemistry and Rad Con to re-analyze the tank contents. Per CY-TM-170-2011 gas releases may be secured for up to 12 hours without re-samplinci for a new cias release permit.

     @         Waste Gas Decay Tank (WDG-T-1A) Disposal - Level 1 Prerequisites
                        ~              WDG-T-1A is isolated IAW section 3.14
                         ~             The WCS/CRS/SM verified that WDG-T-1A has had a hold time to ensure compliance with ODCM, Section 2.2.2.

During release of gaseous waste from WDG-T-1A, the following conditions must be met: ENSURE requirements of ODCM Part 1, Section 2.1.2 are satisfied using Waste Gas Discharge monitor, RM-A-7, and/or Auxiliary and Fuel Handling Building Exhaust monitor, RM-A-8. Waste gas decay tank discharge valve, WDG-V-47, must be operable. WDG-FR-123 must be operable. 23

Number TMI - Unit 1 Operating Procedure 1104-27 Title Revision No. Waste Disposal - Gaseous 87 Verify that RM-A-7, WDG-FT-123 and WDG-V-47 are in service and that there are no "Equipment Deficiency" tags on the equipment that affect operability. Verify that the Aux/FH Bldg. Ventilation system is in service. Verify the following interlock tests are current.

• WDG-V-47/RM-A-7
• WDG-V-47/RM-A-8
• WDG-V-47/FT-123
• WDG-V-47/AH-E-14A/B/C/D Verify the following valve lineup:

WDG-V-67 Locked Open WDG-V-68 Locked Open WDG-V-31 Locked Closed WDG-V-32 Locked Closed

         @        Procedure - Level 1 nb "k           Obtain page 1 of Exhibit 2 in procedure CY-TM-170-2011 and complete operations input to gas release permit.
                 ~ ::~:;::p::::::*::::I:::~::::::::::ry
                  ~           Rad. Con. performed dose calculations for the release.
                  ~           Verify that IA-V-1213 is OPEN and the instrument air system is available.
                 ~            Source check RM-A-7 (Waste gas discharge monitor) by Method 1 or 2: (NIA

(~ Method not used)

                 <fl!!;>      Method 1:

d\ l_? OBTAIN RM-A-7 check source (source #1662 or equivalent) from Radiological Protection.

                          ~                 NOTIFY Control Room of the intent to source check RM-A-7.
                           ~                REMOVE lead plug located on top of the RM-A-7 sampler.

r;J!5 INSERT rod source. 24

Number TMI - Unit 1 Operating Procedure 1104-27 Title Revision No. Waste Disposal - Gaseous 87 VERIFY RM-A-7 ratemeter reading in the Control Room qualitatively increases. REMOVE rod source from the sampler. INSERT lead plug in the RM-A-7 sampler. RETURN RM-A-7 check source location as directed by Radiological Protection. RECORD time and date on charts for the following equipment to indicate the source check:

• WDG-FR-123
• RM-A-7 Method 2:

1. Power down RM-A-7 at the ratemeter.

2. Remove the lead cover from RM-A-7 (if necessary).

3. Remove the detector from the sampler.

4. Attach primary calibration source, #318A, to the face of the detector using the source cup holder.

5. Replace the detector in the sampler.

6. Power up RM-A-7 at the ratemeter.

7. Confirm that RM-A-7 ratemeter reading increases significantly.

8. Power down RM-A-7 at the ratemeter.

9. Remove the detector from the sampler.

10. Remove the calibration source from the face of the detector.

11. Replace the detector in the sampler.

12. Replace all fasteners.

13. Replace the lead cover.

14. Power up RM-A-7 at the ratemeter.

Verify that the RM-A-7 interlock defeat switch is in "ENABLE." Verify that the RM-A-8 interlock defeat switch is in "NORMAL." 25

Number TMI - Unit 1 Operating Procedure 1104-27 Title Revision No. 87 Verify that the "TEST/NORMAL" switch on WDG-FR-123 is in the "NORMAL" position. Hang the "Gas Release in Progress" signs at the following locations.

• In the Control Room on PRF at the RM-A-7 ratemeter.
• On the radwaste panel on the WDG-V-47 air controller.

NOTE If the alarm setpoint per WG permit is 8.5 cfm., a total of 8 ~complete revolutions will be required. An eight (8) will be showing in the window above the dial and the dial itself will be set at fift 50 . Set the WDG-FR-123 alarm setpoint to the value that corresponds to the flow rate specified in the Waste Gas Release Permit by using the dial behind the recorder inside the radwaste panel. Sign the space on the release permit for setting WDG-FR-123 setpoint. Record the WDG-T-1 A pressure prior to the start of the release on the Waste Gas Release Permit. NOTE Channel #1 is activity (RM-A-7) and Channel #2 is the release flow rate WDG-FR-123 . Verify that WDG-V-47 is closed. Unlock and Open WDG-V-30. Operations Supervisor PERFORM Independent Verification that WDG-V-30 is Unlocked and Open.

         ~              Notify the Control Room of the change in the locked valve position.

NOTE WDG-V-47 has no positioner to amplify signal air from the manual loader. Therefore, operation of WDG-V-47 should be gradual to prevent overshooting the maximum allowable release rate when stem drag is initial! overcome. Adjust the hand loader for WDG-V-47 to zero. Record RM-A-7G, RM-A-8P, RM-A-81, RM-A-8G, and FR-123 readings on the Waste Gas Release Permit prior to the release. 26

Number TMI - Unit 1 Operating Procedure 1104-27 Title Revision No. Waste Disposal - Gaseous 87 NOTE Rad Waste Panel Alarm (RWA-1-6) "Waste Gas to Atmosphere Terminated" should be expected until WDG-V-47 is open far enough to satisf the circuit. Depress the Open PB for WDG-V-47 on the radwaste panel. Set the control air to WDG-V-47 to the value that corresponds to the flow rate (CFM) specified on the Waste Gas Release Permit. (WDG-V-47 will gradually open by air loading.) Sign the space provided on the Waste Gas Release Permit for WDG-V-47 loaded. Record the date/time that the release was started on the Waste Gas Release Permit. NOTE Gas tank releases average around 13 to 14 hours for release duration. If the gas tank being released requires substantially more time to release, then a problem may exist in the release flow path.

                 ~ Monitor the tank pressure, release rate, and radiation monitors hourly
                ~ throughout the release and record on Enclosure 2.

NOTE Slight changes in Auxiliary Building pressure/temperature may affect waste gas tank pressure. Shift Management should make a determination if the qas release should be terminated. 3.7.2.27 If at any time any gas tank has a pressure decrease other than the tank being released, then perform the following: (N/A if not met) Inform Shift Management of the problem. Go to Section 3.17 to terminate the gas release. 27

Number TMI - Unit 1 Operating Procedure 1104-27 Title Revision No. Waste Disposal - Gaseous 87 3.7.2.28 Record RM-A-7G, RM-A-8P, RM-A-81, RM-A-8G, and FR-123 readings on the Waste Gas Release Permit at the following intervals during the release:

• The release is X complete
• The release is ~ complete
• The release is % complete
• The release is complete
• The highest reading during the release 3.7.2.29 Vent WDG-T-1A until the pressure is zero.

3.7.2.30 When WDG-T-1A has been vented, complete the following:

1. Bleed off air from WDG-V-47 by adjusting the hand loader for WDG-V-47 to 0 psig.

2. Close WDG-V-47 by depressing the Close PB.

3. Reset WDG-FR-123 setpoint to "O".

4. Close and lock closed WDG-V-30.

CV

5. Remove the "Equipment Status Tag" from IA-V-598 for WDG-V-24.

6. Open IA-V-598 for WDG-V-24.

7. Open manual inlet valve WDG-V-77.

3.7.2.31 Purge RM-A-7 per Section 3.11 to reduce counts to approximate level prior to the release. 3.7.2.32 Record the following information in the appropriate sections of the Waste Gas Release Permit:

• Time/Date the release stopped.
• Total duration of the release in minutes
• WDG-T-1 A pressure at the end of the release

                             *           ~ pressure between the beginning and end of the release 28

Number TMI - Unit 1 Operating Procedure 1104-27 Title Revision No. Waste Disposal - Gaseous 87 3.7.2.33 Remove the "Gas Release in Progress" signs from the following locations.

• In the Control Room on PRF at the RM-A-7 ratemeter.
• On the Radwaste panel on the WDG-V-47 air controller.

3.7.2.34 Return the Waste Gas Release Permit and Waste Gas Release Data Sheet to the WCS/CRS. 3.7.2.35 Forward the completed release permit to Rad. Engineering. 3.7.2.36 Forward the completed 1104-27 to the Operations office. Process Complete Date_ _ _ _ _ _ _ __ Operator Reviewed By SRO/RO License _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Date_ _ _ _ _ _ _ __ Signature 29

Number TMI - Unit 1 Operating Procedure 1104-27 Title Revision No. Waste Disposal - Gaseous 87 3.17 Termination of Waste Gas Decay Tank due to a pressure drop in any other gas tank not being released - LEVEL 1 3.17.1 Prerequisites 3.17 .1.1 A Waste Gas Decay Tank is being released to the atmosphere. 3.17.1.2 Per Enclosure 2, a Waste Gas Decay Tank has lowering pressure and it is not being released to the atmosphere. 3.17 .2 Procedure - Level 1 3.17.2.1 Bleed off air from WDG-V-47 by adjusting the hand loader for WDG-V-47 to 0 psig. 3.17.2.2 Close WDG-V-47 by depressing the Close PB. 3.17.2.3 Reset WDG-FR-123 setpoint to "O". 3.17.2.4 Close and lock closed the applicable manual outlet valve on the tank being released. (NIA the valves not open) Close and lock closed WDG-V-30 for WDG-T-1A. CV Close and lock closed WDG-V-31 for WDG-T-1 B. CV Close and lock closed WDG-V-32 for WDG-T-1 C. CV 3.17 .2.5 Notify the Control Room to update the locked valve entry. 3.17.2.6 Purge RM-A-7 per Section 3.11 to reduce counts to approximate level prior to the release. 3.17.2.7 Record the following information in the appropriate sections of the Waste Gas Release Permit:

• Time/Date the release stopped.
• Total duration of the release in minutes
• RM-A-7G, RM-A-8P, RM-A-81, RM-A-8G, and FR-123 readings
• Applicable WDG-T-1 pressure when the release was terminated

                                *             ~  pressure between the beginning and end of the release 3.17.2.8    Notify the Control Room to contact Chemistry to sample the gas tank that had the pressure drop and was not being intentionally released.

56

Number TMI - Unit 1 Operating Procedure 1104-27 Title Revision No. Waste Dis osal - Gaseous 87 3.17.2.9 Remove the "Gas Release in Progress" signs at the following locations.

• In the Control Room on PRF at the RM-A-7 ratemeter.
• On the radwaste panel on the WDG-V-47 air controller.

3.17.2.10 N/A the steps not completed in the section of the procedure that was in use prior to the gas release termination to ensure it is closed out properly. 3.17 .2.11 Return the Waste Gas Release Permit and Waste Gas Release Data Sheet to the WCS/CRS. 3.17.2.12 Forward the completed release permit to Rad. Engineering. 3.17.2.13 Forward the completed 1104-27 to the Operations office. 3.17.2.14 Submit Issue Report to identify the gas tank pressure decrease. Performed By Date_ _ _ _ _ _ _ __ Signature Reviewed By SRO/ RO License _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Date _ _ _ _ _ _ _ __ Signature 57}}