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Hat 2016-301 Exam Final Items - Delay Release 2 Yrs
	ML17187A227
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Issue date:	07/06/2017
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Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 10-1 Op-Test No.: 2016-301 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at 85% RTP. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written. RCIC is inoperable, RAS written. A Type Secondary Containment with both RF plugs removed.

Turnover: IAW 34SO-E51-001-2, unisolate RCIC and place in standby. 34SV-E51-001-2, RCIC Pump Operability, will be performed at the end of the next shift. After RCIC is placed in standby, increase Reactor power to 90% RTP using Recirc.

Event Event Event Malf. No.

No. Type* Description 1 N/A N (BOP) IAW 34SO-E51-001-2, unisolate RCIC and place in standby.

2 N/A R (ATC) Raise Reactor power to 90% using Recirc.

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

3 mfB21_130F TS (SRO) (Critical Task) 4 mfC11_31A C (ATC) CRD Flow Control Valve 2A Failure mfG31_242 C (BOP) Leak in Drywell requiring DW venting. First SBGT started will fail 5 EGT46-11 TS (SRO) to start, must use opposite train to vent the Drywell.

EGT46-12 C (ATC) Recirc Pump 2A High Vibration requiring reducing reactor power in 6 mfB31_41A TS (SRO) an attempt to clear alarm. Alarm remains in until pump is tripped.

7 mfG31_242 M (ALL) Leak worsens in Drywell causes High Drywell pressure scram.

diE11-F016A RHR 2E11-F016A/B stuck closed requiring swapping to other loop 8 C (ATC) diE11-F016B of DW spray (Critical Task)

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

Page 27 of 29 Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 10-1 Op-Test No.: 2016-301 Examiners: Operators: SRO RO BOP Initiating Conditions: Unit 2 is operating at 85% RTP. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written. RCIC is inoperable, RAS written. A Type Secondary Containment with both RF plugs removed.

Turnover IAW 34SO-E51-001-2, unisolate RCIC and place in standby. 34SV-E51-001-2, RCIC Pump Operability, will be performed at the end of the next shift. After RCIC is placed in standby, increase Reactor power to 90% RTP using Recirc.

Summary:

Event 1: Normal; IAW 34SO-E51-001-2, unisolate RCIC and place in standby.

Event 2: Reactivity; The ATC will raise Reactor power to 90% RTP.

Event 3: Instrument; SRV 2F (LLS) cycles open and close until fuses are removed.

(Critical Task)

Event 4: Component; The CRD FCV 2A will slowly fail causing a loss of CRD. The operator will take manual actions to swap FCV and return the CRD system to normal.

Event 5: Component/TS; A leak in the Drywell causes DW pressure to increase. The team will receive a P603 alarm that will direct DW venting to be placed in service. BOP operator will attempt to start Standby Gas Treatment (SBGT). The first SBGT system the operator attempts to start will fail. The opposite SBGT train will then be started and DW venting will be aligned.

The SRO will address TS for an inoperable train of SBGT.

Event 6: Component/TS; Recirc Pump 2A will experience high vibration requiring reducing reactor power in an attempt to clear the alarm. Alarm remains in until pump is tripped. The SRO addresses TS for single loop operation. The plant will be operating in the Immediate Exit Region of the Power-to-Flow map. The ATC operator will insert control rods to exit the Immediate Exit Region of the P/F map.

Event 7: Major; Pipe leak in Drywell worsens causing a High Drywell pressure scram.

Event 8: Component; When Torus pressure exceeds 11 psig, the operator will attempt to spray the Drywell but one RHR DW spray valve will NOT open. The other loop of RHR will be used to spray the Drywell. The first DW spray valve attempted will NOT open but the other loop of RHR DW spray valve will work. (Critical Task)

Page 28 of 29 Critical Tasks NRC FINAL Facility: E. I Hatch Scenario No.: 10-1 Op-Test No.: 2016-301 Critical Tasks

SRV 2F (LLS) valve cycles open/close and then remains open until the fuses are removed which will preclude a failure that will result in challenging Primary Containment integrity if manual action is not taken in a timely manner (prior to exceeding the BIIT curve) or challenge exceeding the Tech Spec cooldown rate limit. (Event 3)

RHR 2E11-F016A (B) is stuck closed requiring the operator to swap to other loop of RHR to spray the Drywell while in the safe region of the Drywell Spray Initiation Limit (DSIL), prior to exceeding 340°F. (Event 8)

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 6 1. SRV 2F cycles open and closed (Event 3)

2. CRD FCV 2A failure (Event 4)

3. SBGT 2A(2B) failure (Event 5)

4. Recirc Pump 2A high vibration (Event 6)

5. RWCU pipe break LOCA (Event 7)

6. 2E11-F016A(B) fails to open (Event 8)

2. Malfunctions After 1-2 1 1. 2E11-F016A(B) fails to open (Event 8)

EOP Entry

3. Abnormal Events 2-4 4 1. SRV 2F cycles open and closed (Event 3)

2. CRD FCV 2A failure (Event 4)

3. SBGT 2A(2B) failure (Event 5)

4. Recirc Pump 2A high vibration (Event 6)

4. Major Transients 1-2 1 1. RWCU pipe break LOCA (Event 7)

5. EOPs entered, 1-2 2 1. 31EO-EOP-010-2, RC (Non ATWS) (Event 7) requiring substantive 2. 31EO-EOP-012-2, PC (Event 7) actions

6. EOPs contingencies 0-2 0 N/A requiring substantive actions

7. EOP Based 2-3 2 1. Remove fuses for SRV 2F (Event 3)

Critical Tasks 2. Spray the Drywell (Event 8)

ILT 10 NRC FINAL Scenario 1 SHIFT TURNOVER Safety Focus UNIT 1 STATUS Plant Conditions: Unit 1 is operating at 100% RTP.

UNIT 2 STATUS

Unit 2 is operating at 85% RTP.

RCIC has been isolated for maintenance. Maintenance is Plant Conditions:

complete and RCIC is ready to be placed in Standby.

A Type Secondary Containment with both RF plugs removed.

Protected Train: EOOS:

Division I Green Orange Division II Yellow Red Scheduled IAW 34SO-E51-001-2, unisolate RCIC and place in standby.

After RCIC is placed in standby, increase Reactor power to 90%

evolutions: RTP using Recirc (No fuel preconditioning limitations).

Surveillances due NONE; 34SV-E51-001-2, RCIC Pump Operability, will be performed at the end of the next shift.

this shift:

Inop Equipment: 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written RCIC, RAS written Active tagouts: NONE Rod Configuration: See RWM

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 1 Page 2 of 29 Event

Description:

IAW 34SO-E51-001-2, unisolate RCIC and place in standby.

Time Position Applicant's Actions or Behavior Directs BOP to unisolate RCIC and place in standby IAW 34SO-E51-001-2, 10 Min SRO RCIC System, starting at step 7.1.1.36.

NOTE: The RCIC Steam Line can be warmed and pressurized by performing either step 7.1.1.36.1 (2E51-F007)

OR 7.1.1.36.2 (2E51-F008).

If the BOP chooses step 7.1.1.36.1, (2E51-F007), then the following steps are applicable.

Pressurizing RCIC steam supply with 2E51-F007:

Confirm closed 2E51-F007, Steam Supply Isol Valve.

Opens 2E51-F008 Steam Supply Line Isol Valve.

Opens 2E51-F054 Steam Line Drain Valve.

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

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

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

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

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

Completes Attachment 1 and notifies SRO to be verified.

BOP Notifies SSS to complete verification of Attachment 1.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 1 Page 3 of 29 Event

Description:

IAW 34SO-E51-001-2, unisolate RCIC and place in standby.

Time Position Applicant's Actions or Behavior NOTE: The RCIC Steam Line can be warmed and pressurized by performing either step 7.1.1.36.1 (2E51-F007)

OR BOP 7.1.1.36.2 (2E51-F008).

If the BOP chooses step 7.1.1.36.2, (2E51-F008), then the following steps are applicable.

Pressurizing RCIC steam supply with 2E51-F008:

Confirm closed 2E51-F008, Steam Supply Line Isol Valve.

Opens 2E51-F007 Steam Supply Isol Valve.

Opens 2E51-F054 Steam Line Drain Valve.

Slowly throttles open 2E51-F008 Steam Supply Line Isol Valve.

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

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

Closes 2E51-F054, Steam Line Drain Valve, if RCIC TURBINE INLET DRAIN POT LEVEL HIGH, (602-308), was in alarm and clears, otherwise closes 2E51-F054.

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

Completes Attachment 1 and notifies SRO to be verified.

SRO May notify SSS to complete verification of Attachment 1.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 2 Page 4 of 29 Event

Description:

Raise Reactor power to 90% using Recirc.

Time Position Applicant's Actions or Behavior

Directs ATC to increase reactor power to 90% by increasing Recirc flow.

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

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

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

IAW 34SO-B31-001-2 (step 7.1.5) & 34GO-OPS-005-2, the ATC increases Recirc pump speed, NOT to exceed 10 MWE per minute by depressing the RAISE SLOW or RAISE MEDIUM pushbuttons on the Master (P603 panel) or Individual controls (P602 panel) until reactor power is 90%.

ATC

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

Monitors power increase by observing APRM and generator output indications.

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

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

ATC

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

< 70% of rated core flow; AND

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

> 70% of rated core flow.

ATC Notifies the SRO that reactor power has been increased to 90%.

Simulator Operator, at the Chief Examiners direction OR after power has been increased to 90%, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 3 Page 5 of 29 Event

Description:

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

Time Position Applicant's Actions or Behavior Simulator operator: At the Chief Examiners direction, INSTRUCT the ATC operator by phone to stay on the line until told to hang up, then ENTER (RB-3) mfB21_130F, Main Steam Relief Valve Fails Open.

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

Receive alarms:

ALL

SAFETY/BLOWDOWN VALVE LEAKING, (603-122)

SAFETY BLOWDOWN PRESSURE HIGH, (602-311)

Directs operator to enter 34AB-B21-003-2, Failure of Safety/Relief Valves SRO

Enters a RAS for TS LCO 3.6.1.6, Condition A, for 2 or more LLS valves inop, which requires the unit to be in mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and mode 4 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Enters 34AB-B21-003-2, Failure of Safety/Relief Valves

Determines SRV 2F is cycling open then close.

Cycles the SRV 2F Control Switch several times.

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

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

BOP

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

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

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

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

Receives DRYWELL/TORUS RCDR R627 TEMP HIGH, (650-204) alarm BOP

Determines Torus Water Temp (Point 2) is high at 98°F

When the SRV is closed Point 2 starts decreasing.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 3 Page 6 of 29 Event

Description:

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

Time Position Applicant's Actions or Behavior Simulator Operator, if requested to remove fuses for SRV 2F, wait 4 minutes, then DELETE mfB21_130F, 2F LLS Valve or Scenario EGB21-12, then ENTER (RB-1), rfB21_305, to simulate removing the fuses for SRV 2F.

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

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

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

Torus water level increase has stopped.

Torus temperature increase has stopped.

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

BOP

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

Confirms that the Amber SRV indicating lights have Extinguished.

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

Informs the SRO that SRV 2F is closed.

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

SRO/

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

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

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 3 Page 7 of 29 Event

Description:

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

Time Position Applicant's Actions or Behavior NOTE:

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

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

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

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

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

BOP

Enters 34SO-E11-010-2, Residual Heat Removal

Places RHRSW in service

Prelube RHRSW pump.

Overrides 2E11-F068B Low Discharge Pressure Interlock.

Positions 2E11-F068B to 45% OPEN.

Starts RHRSW pump B.

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

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

BOP

IF desired to start a SECOND RHRSW pump,

Throttles 2E11-F068B to achieve max flow rate (not to exceed 4400 GPM).

Opens 2E11-F068B an additional 5%.

Starts second RHRSW Pump.

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 3 Page 8 of 29 Event

Description:

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

Time Position Applicant's Actions or Behavior BOP

Places RHR B Loop in Torus cooling per the placard by performing the following steps:

Opens 2E11-F048B.

Closes 2E11-F047B.

Opens 2E11-F003B.

Starts RHR Loop B pump

Receives alarm, RHR LOW FLOW, (601-222).

Opens 2E11-F028B.

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

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

Throttles OPEN 2E11-F024B.

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

Opens 2E11-F047B.

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

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

May place the second pump in service.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 4 Page 9 of 29 Event

Description:

CRD FCV 2A Slow Failure; Places standby FCV in service Time Position Applicant's Actions or Behavior 12 Min Simulator operator: At the Chief Examiners direction, ENTER (RB-4) mfC11_31A, CRD Flow Control Valve Failure.

Receives the following annunciator:

ALL

CRD HYDRAULIC TEMP HIGH, (603-140).

Determines that the CRD Flow Control Valve A has failed closed.

Notifies SRO that the CRD Flow Control Valve A has failed closed.

ATC

Enters:

CRD HYDRAULIC TEMP HIGH, (603-140).

34AB-C11-001-2, Loss of CRD System.

NOTE: With the loss of the CRD FCV, the ATC may FIRST address 34AB-C11-001-2, Loss of CRD System.

Dispatches a SO & Maintenance to investigate the cause of the FCV failing closed.

Directs the operator to perform actions per the ARP and SRO 34AB-C11-001-2, Loss of CRD System.

May direct operator to swap Flow Control Valves at this time, or may wait for report from SO, before ordering the swap.

IAW CRD HYDRAULIC TEMP HIGH, (603-140):

ATC

Dispatches a SO to monitor CRD temperatures locally at 2C11-R018 (130 Rx Bldg).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 4 Page 10 of 29 Event

Description:

CRD FCV 2A Slow Failure; Places standby FCV in service Time Position Applicant's Actions or Behavior Simulator Operator, wait 2 minutes and report, as SO at the FCV, that the FCV has failed closed due to an air leak on the supply line, and that you have isolated the air line and stopped the leak.

Simulator Operator, IF/WHEN requested and if CRD HYDRAULIC TEMP HIGH is illuminated, as the SO checking CRD temps, report that 2 CRD drives are >250°F; 30-11 and 22-35 at 260°F and some others are slowly increasing.

SRO Directs operator to shift Flow Control Valves

Enters 34SO-C11-005-2, CRD Hydraulic System, section 7.1.6, to shift Flow Control valves:

ATC

Confirms 2C11-R600 is in AUTO.

Directs the SO to locally shift CRD FCV to B IAW step 7.1.6.1.2 through 7.1.6.1.9.

Simulator Operator, ENTER (RB-2) rfC11_24, CRD Flow Control F002 to B, then as the SO, report that the CRD FCVs have been shifted locally.

Simulator Operator, If asked, as SO, INFORMS ATC that local controller is in Automatic.

Returns CRD System to normal configuration:

Places 2C11-R600 to MANUAL.

ATC

Adjusts 2C11-R600 to desired flow (~50 gpm).

Places 2C11-R600 to AUTO.

Confirms system parameters are normal.

CRD HYDRAULIC TEMP HIGH, (603-140) alarm clears.

ATC

Reports to SRO that CRD flow control valves have been shifted and the CRD System has been restored to normal configuration.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 5 Page 11 of 29 Event

Description:

Leak in Drywell requiring DW venting. First SBGT started will fail to start, must use opposite train to vent the Drywell.

Time Position Applicant's Actions or Behavior 10 Min Simulator operator: At the Chief Examiners direction, ENTER (RB-5) mfG31_242, RWCU Non-Isol Leak in Drywell (final 0.02, ramp 100).

Recognizes increasing Drywell Pressure from the following alarm:

ALL

PRIMARY CNMT PRESSURE HIGH, (603-115).

Directs an operator to enter 34AB-T23-002-2, Small Pipe Break Inside Primary Containment.

SRO

When venting is required; Directs the BOP to vent the drywell with BOTH loops of CAD.

Simulator Operator, if asked to perform 34SV-SUV-019-2, Leakage Determination, INFORM that you will get another operator to perform the determination and will contact you back later for assistance.

IAW 34AB-T23-002-2, performs the following using Placard:

Trips RWCU Pump 2B.

Places control switch for 2G31-F001 to close.

ATC

Places control switch 2G31-F004 to the close.

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

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

NOTE: EVENT TRIGGERS EGT46-11 & EGT46-12 will INSERT overrides to keep the first SBGT fan from starting and then remove the event trigger from the opposite SBGT train. The applicant will not be successful with the first SBGT train; however, the second SBGT train will work.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 5 Page 12 of 29 Event

Description:

Leak in Drywell requiring DW venting. First SBGT started will fail to start, must use opposite train to vent the Drywell.

Time Position Applicant's Actions or Behavior

Enters 34SO-T48-002-2, Containment Atmosphere Dilution System or uses placard to vent the Drywell.

Enters 34SO-T46-001-2, Standby Gas Treatment System, procedure or uses placard to start SBGT 2A or 2B.

BOP

Opens 2T46-F001 (A or B) and/or 2T46-F003 (A or B).

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

Receives alarm 2B (OR 2A) SBGT SWITCH NOT IN AUTO, (654-076) or (657-091).

Determines that the first SBGT fan will not start.

At this time, may inform SRO that SBGT (A or B) cannot be started or may wait until other SBGT is in service (either is acceptable).

Vents with the opposite train of SBGT per 34SO-T46-001-2 SBGT System procedure or uses placard.

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

BOP

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

(Placard)

Receives alarm 2B (OR 2A) SBGT SWITCH NOT IN AUTO, (654-076) or (657-091).

Confirms 2T46-F002 (A or B) OPENS.

Confirms SBGT Heater red light illuminates.

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

Receives alarm DW VENT EXH BYPASS VLV OPEN, (654-002) or (657-008).

Receives alarm DRWL/TORUS N2 M/U 2 INCH ISOL VALVES OPEN, BOP (654-035) or (657-042).

(Placard)

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

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

Monitors DW pressure.

Notifies SRO DW venting is in progress and of the SBGT failure (if not notified previously).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 5 Page 13 of 29 Event

Description:

Leak in Drywell requiring DW venting. First SBGT started will fail to start, must use opposite train to vent the Drywell.

Time Position Applicant's Actions or Behavior

Reviews TS 3.6.4.3, Standby Gas Treatment System.

IAW TS 3.6.4.3 Condition B,

Declares SBGT fan A or B inoperable,

Must restore SBGT fan A or B to operable status within 7 days AND SRO 30 days from discovery of failure to meet the LCO.

Direct that maintenance be contacted to determine problem with failed SBGT fan.

IAW TRM T3.4.1 if RWCU is isolated performs conductivity monitoring requirements.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 6 Page 14 of 29 Event

Description:

Recirc Pump 2A High Vibration requiring reducing reactor power in an attempt to clear alarm. Alarm remains in until pump is tripped.

Time Position Applicant's Actions or Behavior Simulator operator: At the Chief Examiners direction, contact BOP and as 18 Min Chemistry REQUEST Off-Gas Flow, and then ENTER (RB-6) mfB31_41A, Recirc Pump A High Vibration.

Receives the following annunciator:

ALL

RECIRC PUMP A HIGH VIBRATION, (602-104)

Simulator operator: If dispatched to the ASD locally, wait two minutes and report, as SO, that you have not found anything yet, but will continue monitoring.

IAW RECIRC PUMP A HIGH VIBRATION, (602-104):

Depresses the High vibration reset pushbutton and determines that the alarm does NOT clear.

ATC

Notifies the SRO that the vibration alarm did NOT clear.

Notifies the SRO that the ARP requires reducing Recirc flow UNTIL the alarm will clear when the reset pushbutton is depressed.

Directs the operator to reduce Reactor Power with Recirc flow per 34GO-OPS-005-2 and 34SO-B31-001-2, section 7.1.6, Two Loop SRO Operation From Rated To Minimum Speed.

Notifies Plant Management, Load Dispatcher, and Engineering that Recirc Pump 2A is experiencing a high vibration condition.

NOTE: IAW 34GO-OPS-005-2, Power Changes, Limitation 5.2.3, entry into the Immediate Exit Region is ALLOWED during a manual OR automatic power reduction initiated in response to an equipment problem.

NOTE: IAW 34GO-OPS-005-2, Power Changes, a rapid power reduction may be performed at a rate > 10 MWE/min to put the plant in a safe condition.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 6 Page 15 of 29 Event

Description:

Recirc Pump 2A High Vibration requiring reducing reactor power in an attempt to clear alarm. Alarm remains in until pump is tripped.

Time Position Applicant's Actions or Behavior

IAW 34GO-OPS-005-2, Power Changes:

Decreases Recirc Pump speed per 34SO-B31-001-2, Reactor Recirc System.

ATC

IAW 34SO-B31-001-2, Reactor Recirc System:

Decreases Recirc pump speed by depressing the desired LOWER pushbuttons on the Master or Individual controls.

Periodically stops the power reduction and depresses the High vibration reset pushbutton.

Monitors power decrease by observing APRM and generator output indications.

ATC

Notifies SRO when BOTH Recirc Pump speeds are at minimum.

Notifies the SRO that the vibration alarm DID NOT clear after reducing BOTH Recirc pumps.

Notifies SRO of entering Region of Potential Instabilities/Immediate Exit Region of Power to Flow Map.

NOTE: RECIRC PUMP A HIGH VIBRATION, (602-104) will NOT remain clear UNTIL the 2A Recirc Pump is tripped.

IAW 34GO-OPS-005-2, Power Changes, Step 5.2.14, notifies Chemistry of BOP 15% power change in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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

NOTE: 15% power change sample required IAW 34GO-OPS-005-2, Limitation 5.2.14.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 6 Page 16 of 29 Event

Description:

Recirc Pump 2A High Vibration requiring reducing reactor power in an attempt to clear alarm. Alarm remains in until pump is tripped.

Time Position Applicant's Actions or Behavior

Directs the ATC operator to shutdown ASD A IAW 34SO-B31-001-2, section 7.2.1.3, Abnormal Recirc Pump/ASD A Shutdown.

SRO

As time allows, directs the BOP operator to secure one Condensate and one Condensate Booster Pump plus one RFPT.

IAW 34SO-B31-001-2, Reactor Recirc System:

Places ASD A control switch 2B31-S002A to Pull to Lock.

OR depresses the ASD A Shutdown pushbutton and places ASD A control switch to Pull to Lock on panel 2H11-P602.

Enters 34AB-B31-001-2, Reactor Recirculation Pump(s) Trip, Recirc Loops Flow Mismatch, Or ASD Cell Bypass, for single Recirc pump trip.

ATC

Closes 2B31-F031A, Pump Discharge Valve.

Time: _________

After 4-5 minutes, throttles 2B31-F031A, Pump Disch Valve OPEN.

Time: _________

Receives the following annunciators:

ASD A TRIP WARNING, (602-101).

ALL

ASD A FATAL FAULT, (601-102).

ASD A TROUBLE, (601-108).

RECIRC LOOP A OUT OF SERVICE, (601-127).

NOTE: IAW 34AB-B31-001-2, During single loop operation, WHEN the speed of the running pump decreases below approximately 35% speed, positive flow through the idle pump loop due to natural circulation overcomes the negative flow due to reverse flow. The total core flow summing circuitry will continue to subtract this positive idle loop flow from the running loop flow AND give a misleading LOW core flow indication. Total core flow can be calculated by adding the JET PUMP LOOP "A" AND the JET PUMP LOOP "B" flows.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 6 Page 17 of 29 Event

Description:

Recirc Pump 2A High Vibration requiring reducing reactor power in an attempt to clear alarm. Alarm remains in until pump is tripped.

Time Position Applicant's Actions or Behavior

Determines that the plant is in the Immediate Exit Region of the Power to ATC Flow map.

NOTE: IF the crew makes the decision to SCRAM the Reactor, at the Chief Examiners direction, PROCEED to the MAJOR EVENT.

EXAMINER NOTE: Log time when Region of Instabilities/Immediate Exit Region has been ENTERED. Time: _________

NOTE: IAW 34GO-OPS-005-2, Power Changes, Limitation 5.2.3.1:

If the Region Of Potential Instabilities (RPI) is entered, IMMEDIATELY initiate actions to exit the (RPI), to return operation to the Analyzed Region of the Power/Flow Map outside of the RPI.

If the Immediate Exit Region is entered, within 5 minutes the operators are to initiate control rod movement to return to the Analyzed Region.

Operation within the Analyzed Region AND outside of the RPI must be restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Directs ATC operator to insert rods to exit the RPI and Immediate Exit Region to return operation to the Analyzed Region of the Power/Flow Map.

SRO

References Tech Spec 3.4.1.A.1 and has 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to meet requirements for Single Loop Operation.

NOTE: RBM Downscale alarm may alarm during this movement due to the significant rod worth of these rods. The RBM Downscale and Rod Out Block alarms may be flagged.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 6 Page 18 of 29 Event

Description:

Recirc Pump 2A High Vibration requiring reducing reactor power in an attempt to clear alarm. Alarm remains in until pump is tripped.

Time Position Applicant's Actions or Behavior

Inserts control rods per 34GO-OPS-065-0, Control Rod Movement:

Inserts control rods per the Reactivity Briefing Sheet and rod pull sheets.

Selects first Rod to be inserted Group 45 26-11.

Places Control Rod movement switch to the IN position.

Verifies Rod moves using Rod display information and Rx and ATC Generator power decreasing.

Releases Rod movement switch so that the control rod stops 1 position before the insert limit, unless the insert limit is 00.

Initials Rod movement Sheet.

Verifier, if available, Initials Rod movement sheet.

Notifies the SRO when they are out of the RPI.

If required, adjust 2C11-F003 to get 220 - 280 psid drive water dp EXAMINER NOTE: Log time when Region of Instabilities/Immediate Exit Region has been EXITED. Time: _________

NOTE: AFTER Control Rods are being inserted, at the Chief Examiners direction, PROCEED to the MAJOR EVENT.

May remove condensate pumps (CP & CBP) from service prior to CBP discharge pressure < 525 psig OR power <70% OR as soon as practical.

For removal of CBP:

If 2C is to be removed, removes the Hydrogen Injection System from service.

Sends SO to closed selected pumps discharge valve.

BOP

Prior to discharge valve being full closed, trips pump and places control switch in Auto or PTL.

Has SO complete the procedure.

For removal of CP:

Sends SO to closed selected pumps discharge valve.

Trips pump and places control switch in Auto or PTL.

If pump left in Standby, has SO reopen discharge valve.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 6 Page 19 of 29 Event

Description:

Recirc Pump 2A High Vibration requiring reducing reactor power in an attempt to clear alarm. Alarm remains in until pump is tripped.

Time Position Applicant's Actions or Behavior NOTE: IAW 34GO-OPS-005-2, WHEN Feedwater flow is less than 7 mlbm/HR AND two Reactor Feed Pumps are running, one Reactor Feed Pump MAY be shutdown Enters 34SO-N21-007-2, Condensate And Feedwater System, section 7.2.1, First Reactor Feed Pump Shutdown and Leaving in Standby.

Confirms Feedwater Flow is less than 7 Mlbm/hr.

Confirms RFPT 2A AND RFPT 2B are in Automatic control on 2C32-R600, Master Controller.

BOP

Places 2C32-R601A (2C32-R601B), RFP A (B) M/A Station, in Manual, by depressing the 'M' pushbutton until it illuminates, panel 2H11-P603.

Slowly decrease RFPT 2A (2B) speed with RFP A (B) M/A Station until the other RFP is controlling RWL.

NOTE: At this point the operator may stop here with the RFPT NOT injecting and continue with this section as time allows.

When the other RFP has control of water level, slowly decrease RFPT 2A (2B) speed with RFP A (B) M/A Station until no speed decrease is observed AND/OR place the RFPT A (B) TMR switch to SS AND confirm Speed Setter yellow light illuminates.

BOP

Slowly lower RFPT 2A (2B) Speed Setter switch until RFPT speed is at 1000 rpm, at 2H11-P650.

IF desired, reduce the RFPT 2A (2B) speed to minimum AND allow the RFPT to windmill, provided seal water, steam seals, AND lube oil systems remain in service.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the MAJOR EVENT.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 7 Page 20 of 29 Event

Description:

Leak worsens in Drywell causes High Drywell pressure scram Time Position Applicant's Actions or Behavior Simulator Operator, at the Chief Examiners direction, MODIFY mfG31_242, 10 RWCU Non-Isol Leak in Drywell:

Min

Final 1.0

Ramp 1000 Recognizes increasing Containment Pressure from the following alarms:

PRIMARY CNMT HIGH PRESSURE TRIP, (603-106).

ALL

PRIMARY CNMT PRESSURE HIGH, (603-115).

DRYWELL PRESSURE HIGH, (602-210).

NOTE: The SRO may direct the BOP to vent the Drywell, but there will NOT be time to complete the task before the LOCA signal is received.

With Drywell pressure increasing and alarms PRIMARY CNMT PRESSURE HIGH, (603-115) and DRYWELL PRESSURE HIGH, (602-210), alarms being received, directs the ATC enter 34AB-C71-001-2, Scram Procedure, and Scram the reactor.

SRO

Assigns the ATC to perform RC-1.

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

Enters 31EO-EOP-010-2, RC (Non ATWS) &31EO-EOP-012-2, PC Control, EOP flow charts.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 7 Page 21 of 29 Event

Description:

Leak worsens in Drywell causes High Drywell pressure scram Time Position Applicant's Actions or Behavior Simulator Operator, WHEN the reactor is scrammed, ENSURES EVENT TRIGGER EGC71-12 MODIFIES mfG31_242 Final to 1.5 with a ramp of 1000 AFTER 180 seconds.

Performs RC-1 consisting of:

Inserts a manual scram.

Places the mode switch to SHUTDOWN.

Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display.

Notifies SRO of rod position check.

ATC

Places SDV isolation valve switch to "isolate" & confirms closed.

If NOT tripped, places the Recirc pumps at minimum speed.

Inserts SRMs and IRMs.

Shifts recorders to read IRMS, when required.

Ranges IRMS to bring reading on scale.

Notifies the SRO when the above actions are complete.

Performs RC-2 actions consisting of:

Confirms proper Level Control response:

Checks ECCS Injection Systems and secure as necessary.

BOP

Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.

IF set down does NOT auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 7 Page 22 of 29 Event

Description:

Leak worsens in Drywell causes High Drywell pressure scram Time Position Applicant's Actions or Behavior

Controls HPCI operation for level control by performing one or more of the following:

Adjusts 2E41-R612, HPCI Flow Control, to the desired injection rate.

Transfers the flow controller to manual and adjust its speed demand output to obtain the desired pump flow.

BOP

Shutdown HPCI by:

Depresses and holds the HPCI Turbine Trip pushbutton.

When HPCI turbine has stopped, places 2E41-C002-3, HPCI Aux Oil Pump, in Pull-To-Lock.

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

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

1.5 mlbm/hr), then:

Opens 2N21-F125.

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

BOP

Closes 2N21-F110.

May attempt to restart the CRD pumps.

May attempt maximize CRD flow IAW 34SO-C11-005-2.

Controls RWL with the HPCI/FW System.

Notifies SRO if RWL gets outside assigned band.

NOTE to EXAMINER: SRVs actuate in LLS at 1120 psig and then control pressure between 850 - 990 psig.

Performs RC-3 consisting of:

Monitors RPV pressure.

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

If necessary, verifies LLS actuates at 1120 psig

Maintains RPV Pressure between 1074 and 800 psig.

Notifies SRO of pressure control system operation.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 7 Page 23 of 29 Event

Description:

Leak worsens in Drywell causes High Drywell pressure scram Time Position Applicant's Actions or Behavior NOTE: The SRO may select a RPV pressure band which will lower the driving head of the leak while maintaining <100°F/hr RPV cool down (typically between 500 psig & 920 psig).

As time allows, may;

Direct the ATC to decrease reactor pressure to reduce the driving head of SRO the leak using EHC pressure set.

Remove RWCU from service IAW 34AB-T23-002-2, Small Pipe Break in Primary Containment.

Enters Attachment 11 of 34SO-N30-001-2, Main Turbine, or 34GO-OPS-013-2, Normal Plant Shutdown, and at the DEHC panel computer, performs ONE of the following:

1. Throttle Pressure Set

Selects the Control psi- load screen.

Selects the *Ramp Rate* button.

ATC

Enters a ramp rate.

Selects the *Pressure* button.

Enters desired target pressure.

2. Bypass Valve Jack Positioning.

Control BPV position by intermittently using the *Raise* /

Lower* buttons until BYPASS VALVE JACK STATUS changes to *ACTIVE* AND desired cooldown rate is established.

ATC Notifies the SRO that RPV Pressure is at the target psig.

Simulator Operator PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 8 Page 24 of 29 Event

Description:

RHR 2E11-F016A/B stuck closed requiring swapping to other loop of DW spray Time Position Applicant's Actions or Behavior

Per the PC flowchart, verifies Torus level is <285 inches and directs an SRO operator to place Torus Sprays in service.

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

Places Cnmt Spray Vlv Cntl switch in the MANUAL position.

ATC

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

Opens 2E11-F028A/B.

Throttles Open 2E11-F027A/B.

Notifies SRO that RHR is in Torus Sprays.

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

Simulator Operator, ENSURE Event Triggers EGE11-4 & EGE11-5 is ACTIVATED when the operator positions 2E11-F016A or B to open.

When Torus pressure exceeds 11 psig, verifies that Torus Level is <215 inches, in the safe area of Graph 8 (DWSIL) and directs an operator to:

SRO

Place all DW cooling fans to OFF.

Place both Recirc pumps to PTL OFF.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 8 Page 25 of 29 Event

Description:

RHR 2E11-F016A/B stuck closed requiring swapping to other loop of DW spray Time Position Applicant's Actions or Behavior

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

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

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

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

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

2T47-C001B, Drywell Cooling Return Air Fan.

ATC

2T47-C002B, Drywell Cooling Return Air Fan.

2T47-B010B, Drywell Cooling EL 114 Unit.

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

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

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

2T47-C001A, Drywell Cooling Return Air Fan.

2T27-C002A, Drywell Cooling Return Air Fan.

2T47-B010A, Drywell Cooling EL 114 Unit.

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

SRO

Directs an operator to spray the Drywell.

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

Places Cnmt Spray Vlv Cntl switch in the Manual position.

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

Opens 2E11-F021A or B.

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

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

Opens 2E11-F021A or B.

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

Confirms Drywell pressure is reducing.

Notifies SRO that RHR is in Drywell Sprays.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-1 Event No.: 8 Page 26 of 29 Event

Description:

RHR 2E11-F016A/B stuck closed requiring swapping to other loop of DW spray Time Position Applicant's Actions or Behavior Notifies the SSS to perform actions for RHR per 31EO-EOP-114-2.

IAW 31EO-EOP-114-2, the operator performs the following:

CLOSES RHR OUTBD INJ VLV, 2E11-F017A.

CLOSES RHR OUTBD INJ VLV, 2E11-F017B.

Notifies SSS to OPEN links & INSTALL jumpers for 2E11-F017A.

Notifies SSS to OPEN links & INSTALL jumpers for 2E11-F017B.

BOP

Confirms/CLOSES RHR OUTBD INJ VLV, 2E11-F017A.

Confirms/CLOSES RHR OUTBD INJ VLV, 2E11-F017B.

Confirms/CLOSES INBD DISCHARGE VLV, 2E21-F005A.

Confirms/CLOSES INBD DISCHARGE VLV, 2E21-F005B.

Trips Core Spray pump A, 2E21-C001A.

Trips Core Spray pump A, 2E21-C001B.

Notifies SRO 31EO-EOP-114-2 actions for RHR & CS are complete.

As time allows, directs H2/O2 Analyzers placed in service IAW SRO 34SO-P33-001-2.

If directed, places H2/O2 Analyzers in service IAW 34SO-P33-001-2 or Placard by performing the following at 2H11-P700 panel:

Confirms closed 2P33-F605.

Places 2P33-S16, LOCA Override to Bypass.

Places 2P33-S17, LOCA Override to Bypass.

ATC

Confirms analyzers are running by either red analyzer lights illuminated or values indicated on the Primary Display of SPDS.

If analyzers red light is off, depresses Channel A and Channel B Reset pushbuttons on 2H11-P700 panel.

Notifies SRO H2/O2 Analyzers are running.

With Chief Examiners Permission, the scenario should be terminated when the crew has sprayed the Drywell with the other Loop of RHR.

Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 10-2 Op-Test No.: 2016-301 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at 100% RTP. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Turnover: IAW 34SO-N62-001-2, swap Cooler Condensers from 2N62-B003A to 2N62-B003B, starting at step 7.2.2. System has been aligned for 15 minutes. Once complete, lower Reactor power to

~95% RTP to support Turbine Testing.

Event Malf. No. Event Event No. Type* Description Swap Cooler Condensers from 2N62-B003A to 2N62-B003B 1 N/A N (BOP)

IAW 34SO-N62-001-2, starting at step 7.2.2.

2 N/A R (ATC) Lower reactor power to ~95% RTP using Recirc aoN40R600 UAT 2B Hi temp/lower reactor power/swap house loads/remove from 3 mf65111604 C (BOP) service mf65111605 mf65021482 C (ATC) 2B PSW pump overload - manually trip 2B PSW pump & start 2D 4 (ON)

TS (SRO) PSW pump.

mfP41_292 5 mf65702215 C (BOP) RF Vent Filter 2T41-D007 high dP requiring swapping to D008 mfE51_114 C (ATC) 6 diE51A-S17 RCIC Inadvertent start with Trip pushbutton failure.

TS (SRO) mfE51_250 svoE51074 Unisolable RCIC Steam leak in Reactor Building requiring a Reactor 7 svoE51075 M (ALL)

Manual scram. RCIC Group 4 signal failure.

diT41-B009 diT41-B026 Emergency Depress when Max Safe exceeded in more than one area.

8 N/A M (ALL)

(Critical Task).

mfE11_202B RHR & CS LOCA logic failure, SULCV closed - manual actions are 9 mfE21_202A C (BOP) required for proper RHR/CS & Cond/FW operation ensuring adequate mfN21_99 core cooling. (Critical Task)

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

Page 24 of 26 Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 10-2 Op-Test No.: 2016-301 Examiners: Operators: SRO RO BOP Initiating Conditions: Unit 2 is operating at 100% RTP. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Turnover IAW 34SO-N62-001-2, swap Cooler Condensers from 2N62-B003A to 2N62-B003B, starting at step 7.2.2.

Summary:

Event 1: Normal; Swap Cooler Condensers from 2N62-B003A to 2N62-B003B IAW 34SO-N62-001-2.

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

Event 3: Component; UAT 2B will experience a Hi temperature requiring the removal from service.

Event 4: Component/TS; 2B PSW pump overload requiring manual trip of 2B PSW pump &

starting 2D PSW pump.

Event 5: Component; RF Vent Filter 2T41-D007 high dP requiring swapping to D008.

Event 6: Component/TS; RCIC will experience an inadvertent start with Trip pushbutton failing to trip RCIC. Operator will shutdown RCIC by either; closing T&TV or placing flow controller in manual and lowering speed to prevent injection.

Event 7: Major; Unisolable RCIC Steam leak in Reactor Building requiring a Reactor Manual scram.

Event 8: Major; Emergency Depress when > Max Safe in more than one area. (Critical Task)

Event 9: RHR & CS LOCA logic failure, SULCV closed - manual actions are required for proper RHR/CS & Cond/FW operation ensuring adequate core cooling. (Critical Task)

Page 25 of 26 Critical Tasks NRC FINAL Facility: E. I Hatch Scenario No.: 10-2 Op-Test No.: 2016-301 Critical Tasks

Emergency Depress when > Max Safe in more than one area. (Event 8)

SULCV closed, RHR & CS LOCA logic failure - manual actions are required for proper RHR/CS

& Cond/FW operation ensuring adequate core cooling. (Event 9)

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 6 1. UAT 2B Hi temp (Event 2)

2. 2B PSW pump overload (Event 4)

3. RF Vent Filter 2T41-D007 high dP (Event 5)

4. RCIC inadvertent start (Event 6)

5. Unisolable RCIC Steam leak (Event 7)

6. RHR & CS LOCA logic failure, SULCV closed (Event 9)

2. Malfunctions After 1-2 1 1. RHR & CS LOCA logic failure, SULCV closed EOP Entry (Event 9)

3. Abnormal Events 2-4 3 1. 2B PSW pump overload (Event 4)

2. RF Vent Filter 2T41-D007 high dP (Event 5)

3. RCIC inadvertent start (Event 6)

4. Major Transients 1-2 2 1. Unisolable RCIC Steam leak (Event 7)

2. Emergency Depress (Event 8)

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

6. EOPs contingencies 0-2 1 1. CP-1 (Event 8) requiring substantive actions

7. EOP Based 2-3 2 1. Emergency Depress (Event 8)

Critical Tasks 2. Manual actions for adequate core cooling.

(Event 9)

ILT 10 NRC FINAL Scenario 2 SHIFT TURNOVER Safety Focus UNIT 1 STATUS Plant Conditions: Unit 1 is operating at 100% RTP.

UNIT 2 STATUS Plant Conditions: Unit 2 is operating at 100% RTP.

Protected Train: EOOS:

Division I Green Orange Division II Yellow Red Scheduled evolutions: IAW 34SO-N62-001-2, swap Cooler Condensers from 2N62-B003A to 2N62-B003B, starting at step 7.2.2. System has been aligned for 15 minutes. Once complete, lower Reactor power to ~95% RTP to support Turbine Testing.

Surveillances due this None shift:

Inop Equipment: 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written Active tagouts: NONE Rod Configuration: See RWM

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 1 Page 2 of 26 Event

Description:

IAW 34SO-N62-001-2, swap Cooler Condensers from 2N62-B003A to 2N62-B003B, step 7.2.2.

Time Position Applicant's Actions or Behavior Directs BOP to swap Cooler Condensers from 2N62-B003A to 2N62-B003B 10 Min SRO IAW 34SO-N62-001-2, step 7.2.2.

The BOP will perform the following at 2N62-P001 panel.

NOTE: ALARM 600-020, Inlet Flow To Stack High, may alarm when 2N62-F025B is opened. This is normal for this condition and the alarm will clear in approximately one minute.

Monitors 2N62-R605, Glycol Pump Disch pressure indicator

Opens the following valves:

BOP

2N62-F026B, Glycol Sys To Cndsr B (Already OPEN in setup).

2N62-F071B, Glycol Sys From Cndsr B (Already OPEN in setup).

2N62-F025B, Clr Cndsr B Inlet

Closes the following valves:

2N62-F026A, Glycol Sys To Cndsr A.

2N62-F071A, Glycol Sys From Cndsr A.

2N62-F025A, Clr Cndsr A Inlet.

BOP

Stops 2N62-C001B, Glycol Sys Pump B.

Confirms Glycol Pump discharge pressure remains at 10 to 20 psig, on 2N62-R605, Glycol Pump Disch pressure.

Notifies SRO that the Cooler Condensers have been swapped.

Simulator Operator - PROCEEDS with the next event at the Chief Examiners request.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 2 Page 3 of 26 Event

Description:

Reduce Reactor power to ~ 95% RTP to support Turbine Testing.

Time Position Applicant's Actions or Behavior

Directs ATC to decrease reactor power to 95% by decreasing Recirc flow.

10 Min SRO Power decreases are NOT to exceed 10 MWe/min.

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

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

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

ATC

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

Monitors power decrease by observing APRM and generator output indications.

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

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

ATC

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

< 70% of rated core flow; AND

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

> 70% of rated core flow.

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

Simulator Operator, at the Chief Examiners direction OR after power has been decreased to 95%, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 3 Page 4 of 26 Event

Description:

UAT 2B Hi temp and removal from service Time Position Applicant's Actions or Behavior Simulator Operator At Lead Examiners direction, ACTIVATE: (RB-2)

mf65111604, Unit Aux Xfmr 2B Misc Alarm (Annunciator On)

aoN40R600, Gen & Transformer Temps, final of 110, ramp 100 15 Min THEN, 2 minutes later ACTIVATE: (RB-1)

mf65111605, Unit Aux Xfmr 2B Winding Temp High (Annunciator On)

UNIT AUX XMFR 2B MISC ALARM, (651-116), annunciates ALL Two minutes later, UNIT AUX XMFR 2B WINDING TEMP HIGH, (651-117) annunciates.

Responds to alarm UNIT AUX XMFR 2B MISC ALARM, (651-116)

Notifies GCC of the alarm.

Dispatches an operator to check the transformer local panel in the Low Voltage Switchyard, 2H21-P214.

BOP

Responds to alarm UNIT AUX XMFR 2B WINDING TEMP HIGH, (651-117).

Notifies the SRO that per the ARPs Rx Power will need to be reduced if the winding temperature is increasing and to Transfer the loads to Startup Transformer (SUT) 2C, if the oil temperature is high.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 3 Page 5 of 26 Event

Description:

UAT 2B Hi temp and removal from service Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR:

3 minutes from being dispatched, call the control room as the operator dispatched to the Unit 2B UAT and report that the 2B UAT oil temperature is 93°C and that the winding temperature is 106°C and both are slowly increasing.

If asked, Transformer fans and oil pumps are running.

DO NOT PROMPT TO TRANSFER LOADS

If more updates of temperature are required, increase both temps 1°C/min EACH UPDATE, until load is transferred.

Temps will eventually stabilize above the setpoints.

When the UAT is unloaded, temps will slowly decrease, however the afore mentioned alarms will NOT clear until locally reset.

Directs BOP operator to enter 34SO-R22-001-2 for transferring 4160VAC SRO buses from Unit Aux Transformer (UAT) 2B to Start-Up transformer (SUT) 2C.

BOP

Enters 34SO-R22-001-2, 4160 VAC System.

Swapping of 2A 4160VAC from the UAT to the SAT.

BOP

Confirms power is available to Startup Aux XFmr 2C as indicated by the potential lights on panel 2H11-P651.

Confirms OPEN ACBs 135544, 135564 and 135584 (2H11-P652).

Places 135434/135454 Station Svc Interlock Cutout switch in OFF-(DOWN).

BOP

Places Sync Switch (SSW) ACB 135454 in ON.

Confirms the sources of power to 4160V Bus 2A are synchronized and voltage is normal on Start-Up Aux Transformer 2C.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 3 Page 6 of 26 Event

Description:

UAT 2B Hi temp and removal from service Time Position Applicant's Actions or Behavior

Closes ACB 135454, 4160V Bus 2A Alternate Supply, AND confirms that current increases from Startup Auxiliary Transformer 2C.

Trips ACB 135434, 4160V Bus 2A Normal Supply.

BOP

Places Sync Switch (SSW) ACB 135454 in OFF.

Places 135434/135454 Station Svc Interlock Cutout switch in NORMAL-(UP) .

Swapping of 2B 4160VAC from the UAT to the SUT

Confirms power is available to Startup Aux XFmr 2C as indicated by the BOP potential lights on panel 2H11-P651.

Confirms OPEN ACBs 135544, 135564 and 135584 (2H11-P652).

Places 135444/135464 Station Svc Interlock Cutout switch in OFF-(DOWN).

Places Sync Switch (SSW) ACB 135464 in ON.

Confirms the sources of power to 4160V Bus 2B are synchronized and voltage is normal on Start-Up Aux Transformer 2C.

Closes ACB 135464, 4160V Bus 2B Alternate Supply, AND confirms that current increases from Startup Auxiliary Transformer 2C.

Trips ACB 135444, 4160V Bus 2B Normal Supply.

Places Sync Switch (SSW) ACB 135464 in OFF.

BOP

Places 135444/135464 Station Svc Interlock Cutout switch in NORMAL-(UP).

Notifies the SRO that 4160 VAC 2A and 2B buses have been transferred from the UAT to SUT 2C.

SIMULATOR OPERATOR, after UAT 2B is removed from service, MODIFIES Override aoN40-R600 to a Final of 50 with a 5 ramp rate.

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 4 Page 7 of 26 Event

Description:

2B PSW pump overload - manually trip2B PSW pump & start 2D PSW pump.

Time Position Applicant's Actions or Behavior At the Chief Examiners direction, Simulator Operator; Contact BOP and instruct to stay on the phone until told to hang, then 10 Min ENTERS (RB-4) malfunction mf65021482 - Window 20 PSW PUMP 2B OVLD/LOCKOUT RELAY TRIP (ANNUNCIATOR ON).

Annunciator PSW PUMP 2B OVLD/LOCKOUT RELAY TRIP, ALL (650-220) alarms .

Announces alarm to the SRO.

Enters ARP 650-220.

ATC

Determines that the 2B PSW pump is still running.

Informs the SRO that the 2B PSW pump failed to trip.

Directs the BOP to Trip the 2B PSW pump and place the 2D PSW pump is service.

SRO

Notifies Maintenance (if BOP has NOT) to investigate 2B PSW pump.

Enters Tech Specs LCO 3.7.2 and determines that a 30 day RAS is required IAW TS 3.7.2.A.

Trips PSW Pump 2B And Verifies Green light illuminates.

WHEN PSW Div. II pressure, as indicated on 2P41-R601B reaches 95 PSIG (decreasing), panel 2H11-P650, STARTS PSW Pump 2D. (Standby ATC pump start failure may not be recognized if PSW 2D is started before low header pressure is received).

As time allows, may enter 34AB-P41-001-2, Loss of Plant Service Water.

Notifies Maintenance (if SRO has NOT) to investigate 2B PSW pump.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 5 Page 8 of 26 Event

Description:

RF Vent Filter 2T41-D007 high dP requiring swapping to D008.

Time Position Applicant's Actions or Behavior Simulator Operator, at the direction of the Chief Examiner, ENTERS: (RB-5) malfunction mf65702215 RF D007 Filter Diff Pressure High alarm and 8 Min override 2T41-R618P4. EGT41-2 will be used to clear alarm after filter swap.

On the 2H11-P650 panel alarm, PANEL 2H11-P657 SYSTEM ALL TROUBLE, (650-224), is received.

Acknowledges and enters, RF VENT FLTR 2T41-D007 DIFF PRESS HIGH, (657-036) and performs the following:

BOP

Dispatches a SO/Maintenance to confirm the Refuel Floor Vent Filter differential pressure is > 7 WC as indicated on 2T41-dpi-R004A.

SIMULATOR OPERATOR, when dispatched to confirm Refuel Floor Vent Filter differential pressure as indicated on 2T41-dpi-R004A, wait two minutes and REPORT, as SO, that differential pressure is > 10 WC.

If the crew decides to enter section 4.3.7 of 34SO-T41-006-2, as Shift Manager, INFORM that Maintenance cannot support section 4.3.7 at this time.

Enters 34SO-T41-006-2 step 4.3.3 to remove 2T41-D007, Refueling Floor BOP Vent Filter, from service and performs the following:

Places 2T41-C005A, Refuel Flr Vent Exh Fan, control switch, in OFF

Confirms 2T41-C005B, Refuel Flr Vent Exh Fan, starts.

Places 2T41-C005B, Refuel Flr Vent Exh Fan, control switch, in RUN.

Dispatches a SO to adjust 2T41-R032 and 2T41-R037, Flow Controller, to obtain approximately 15 KCFM through 2T41-C002A Refueling Floor Supply Fan AND 2T41-C005B, Refueling Floor Exhaust Fan.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 5 Page 9 of 26 Event

Description:

RF Vent Filter 2T41-D007 high dP requiring swapping to D008.

Time Position Applicant's Actions or Behavior Simulator Operator, when dispatched, DEPRESS RB-3, which modifies RF Supply flow indication, THEN waits approximately 2 minutes and reports to the BOP, as a SO, that you have adjusted 2T41-R032 and 2T41-R037, to approximately 15 KCFM.

Confirms 0.25 inches water negative pressure on the Refueling Floor as indicated on2T46-R604A AND 2T46-R604B, Sec Cnmt Diff Press A&B, on 2H11-P700.

Closes 2T41-F041A, Refuel Flr Vent Filter D007 Inlet Damper.

Notifies SRO Vent Filter D007 is out of service and 657-036 has cleared.

Dispatches a SO/Maint to determine why the RF Fan D007 experienced a SRO high dP.

Simulator Operator proceeds to the next event at the Chief Examiners direction.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 6 Page 10 of 26 Event

Description:

RCIC Inadvertent start with Trip pushbutton failure.

Time Position Applicant's Actions or Behavior At the Chief Examiners direction, Simulator Operator; 6 Mins Contact BOP and request EDG 1A Main Fuel Oil Storage tank level, ACTIVATE: (RB-6) to ENTERS mfE51_114 and diE51A-S17 to off.

Recognizes that RCIC has started.

ALL

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

ATC

Determines RCIC has auto started and that RWL is normal.

May tell ATC that RWL is normal.

SRO

Directs operator to trip RCIC.

Attempts to Trip RCIC by depressing the RCIC Trip pushbutton and recognizes that the Trip pushbutton is failed.

Notifies the SRO that the RCIC trip pushbutton has failed and Trips RCIC by ONE of the following methods:

Closes the Trip and Throttle valve, 2E51-F524.

ATC OR

Places controller 2E51-R612 to Manual and reduces output to lower RCIC discharge pressure to below reactor pressure.

Receives RCIC TURBINE BRG OIL PRESS LOW, (602-304) &

RCIC PUMP DISCHARGE FLOW LOW, (602-322).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 6 Page 11 of 26 Event

Description:

RCIC Inadvertent start with Trip pushbutton failure.

Time Position Applicant's Actions or Behavior

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

Enters 34SO-E51-001-2, RCIC System.

Dispatches RO/Maintenance to determine cause of initiation signal and the ATC cause of the Trip pushbutton failure.

May attempt to reset the Initiation signal.

Will close 2E51-F524, Trip and Throttle Vlv, if not already closed.

Notifies SRO that RCIC is shutdown.

May have the operator run the Trip and Throttle Valve down to in case RCIC is needed later.

SRO

Enters TS RAS for RCIC 3.5.3 Condition A, which requires verifying HPCI is operable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restoring RCIC in 14 days.

NOTE: It is intended that RCIC is left in its current condition and not returned to standby.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 7 Page 12 of 26 Event

Description:

Unisolable RCIC Steam leak in Reactor Building requiring a Reactor Manual scram. RCIC Group 4 signal failure.

Time Position Applicant's Actions or Behavior At the Chief Examiners direction, Simulator operator, ENTER (RB-7) mfE51_250, RCIC Steam Line, break 70/3.5, diT41-B009 & diT41-B026 to off.

NOTE: SVOs svoE51074 (2E51-F007 Stuck Open) and svoE51075 (2E51-15 F008 Stuck Open), are activated at the beginning.

Min NOTE: It takes approximately 3 minutes for the first alarm, LEAK DET DIFF TEMP HIGH, (601-321), to alarm.

NOTE: SIMULATOR OPERATOR, AFTER the crew scrams the reactor, ENSURES Event Trigger EGC71-13 modifies mfE51_250 Ramp rate to 7.0 with a Final of 100.

Receives the following:

LEAK DET DIFF TEMP HIGH, (601-321) in 3 minutes.

RCIC ISOL TIMER INITIATED, (602-303) in 3.5 minutes.

LEAK DET AMBIENT TEMP HIGH, (601-327) in 4 minutes.

ALL

RCIC ISOLATION SIGNAL LOGIC A INITIATED, (602-307) after timer times out.

RCIC ISOLATION SIGNAL LOGIC B INITIATED, (602-313) after timer times out.

Orders BOP to evaluate leak detection alarms on 2H11-P601.

Orders RCIC to be isolated.

SRO

Orders BOP to evacuate the Reactor Building.

May notify Maintenance for assistance in closing RCIC valves if ATC/BOP does not.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 7 Page 13 of 26 Event

Description:

Unisolable RCIC Steam leak in Reactor Building requiring a Reactor Manual scram. RCIC Group 4 signal failure.

Time Position Applicant's Actions or Behavior

Responds to RCIC alarms.

Observes RCIC Isolation valves have failed to close.

Places 2E51-F007, RCIC Isolation valve switch to Close.

ATC/BOP

Places 2E51-F008, RCIC Isolation valve switch to Close.

Notifies SRO of RCIC valve failures.

May notify Maintenance for assistance in closing RCIC valves if SRO does NOT.

Respond to annunciator LEAK DET DIFF TEMP HIGH, (601-321).

Addresses 2G31-R604 OR 2G31-R608 on 2H11-P614.

Identifies the following points on R604 increasing:

113, TORUS NW WALL is ~ 112°F.

114, TORUS SE WALL is ~ 97°F.

115, TORUS VENT AIR DIFF is ~ 31°F.

116, TORUS VENT AIR DIFF is ~ 18°F.

BOP

Identifies the following points on R608 increasing:

115, TORUS WEST WALL is ~ 112°F.

116, TORUS NE WALL is ~ 98°F.

117, TORUS VENT AIR DIFF is ~ 31°F.

118, TORUS VENT AIR DIFF is ~ 18°F.

119, MAIN STEAM TNL ~ 140°F.

Reports temperatures to the SRO.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 7 Page 14 of 26 Event

Description:

Unisolable RCIC Steam leak in Reactor Building requiring a Reactor Manual scram. RCIC Group 4 signal failure.

Time Position Applicant's Actions or Behavior

Enters the SC flow chart.

Progresses down each path.

Proceeds down the SC/T path, directing:

All available area coolers are operated.

SRO

Operate the refueling floor ventilation.

Operate the reactor building ventilation.

Isolate all systems discharging into the area except those needed for ACC, shutdown the reactor, suppress a fire, maintain primary containment.

Orders the reactor shutdown before any area exceeds Max Safe operating temperatures or delta temps since a primary system (RCIC) is discharging SRO into Secondary Containment. (May direct this prior to Max Safe received).

Assigns the ATC to perform RC-1.

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

SRO

Enters 31EO-EOP-010-2, RC EOP flow chart if RWL decreases below 3 inches or if any area exceeds Max Safe.

Directs RWL band of 3 to 50 inches.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 7 Page 15 of 26 Event

Description:

Unisolable RCIC Steam leak in Reactor Building requiring a Reactor Manual scram. RCIC Group 4 signal failure.

Time Position Applicant's Actions or Behavior

Performs RC-1 consisting of:

Inserts a manual scram.

Places the mode switch to shutdown.

Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display.

Notifies SRO of rod position check.

Places SDV isolation valve switch to "isolate" & confirms closed.

ATC

If not tripped, places the Recirc pumps at minimum speed.

Inserts SRMs and IRMs.

Shifts recorders to read IRMS, when required.

Ranges IRMS to bring reading on scale.

Notifies the SRO when the above actions are complete.

NOTE: SIMULATOR OPERATOR, AFTER the crew scrams the reactor, modify mfE51_250 Ramp rate to 7.0 with a Final of 100.

Performs RC-2 actions consisting of:

Confirms proper Level Control response:

Checks ECCS Injection Systems (will not be in service if RWL >-35 inches).

Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.

If Set down does not auto function, manually reduces FW Master Controller setpoint to approximately 9 inches.

BOP

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

( 1.5 mlbm/hr), then:

Confirms/Opens 2N21-F125.

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

Closes 2N21-F110.

If RFPTs are no longer available, will transition to HPCI to control RWL.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 7 Page 16 of 26 Event

Description:

Unisolable RCIC Steam leak in Reactor Building requiring a Reactor Manual scram. RCIC Group 4 signal failure.

Time Position Applicant's Actions or Behavior

If necessary, starts HPCI for level control by performing the following at 2H11-P602 panel:

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

Opens 2E41-F059.

Starts Barom Cndsr Vac Pump.

Opens 2E41-F001.

BOP

Starts Aux Oil Pump.

Opens 2E41-F006.

Confirms TCV.

and

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

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 7 Page 17 of 26 Event

Description:

Unisolable RCIC Steam leak in Reactor Building requiring a Reactor Manual scram. RCIC Group 4 signal failure.

Time Position Applicant's Actions or Behavior

Performs RC-3 consisting of:

Monitoring RPV pressure.

Confirms proper operation of pressure control system (TBV, LLS, etc.), at 2H11-P650 panel, by confirming TBVs are responding to control reactor pressure at the desired pressure setpoint.

Maintains RPV pressure between 1074 and 800 psig until a different band is directed.

Notifies SRO of pressure control system operation.

If the MSIVs are closed, then the operator will perform the following:

Confirms closed Inboard MSIVs (2B21-F022A-D) and places control switches to close.

Confirms closed Outboard MSIVs (2B21-F028A-D) and places BOP control switches to close.

If directed to lower the driving head of the leak, opens SRVs to maintain RPV pressure in band.

If the MSIVs are still open, SRO orders Anticipate Emergency Depress, then the operator will perform the following:

At P650 HMI screen,

Selects Control.

Selects Bypass Valve.

Inserts Ramp Rate of 100 then OK.

Inserts BPV position of 100 then OK.

Ensures Bypass Valve Jack Status is Active (controlling)

Notifies SRO that Bypass Valves are opening.

May order a lower Reactor pressure band to reduce the driving head IAW RC/P Path of the RC (Non-ATWS) flowchart.

SRO

May direct an operator to perform Rx Power, Level, and Pressure control, so that the other operator can address Secondary Containment parameters.

Simulator operator PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 8 Page 18 of 26 Event

Description:

Emergency Depress when Max Safe exceeded in more than one area.

Time Position Applicant's Actions or Behavior

Provides periodic updates on temperature readings and delta temp readings to the SRO.

Reports R604 points 115 is above Max Safe.

ATC

Reports R608 points 120 & 117 are above Max Safe.

When a second temperature or delta temp exceeds Max Safe levels, informs the SRO.

May order a lower Reactor pressure band to reduce the driving head.

SRO

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

Provides periodic updates on temperature readings and delta temp readings to the SRO.

ATC

When a second temperature or delta temp exceeds max safe levels, informs the SRO.

SRO

Transitions to CP-1 and orders 7 ADS valves open for emergency depress.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 8 Page 19 of 26 Event

Description:

Emergency Depress when Max Safe exceeded in more than one area.

Time Position Applicant's Actions or Behavior

Places the switches for 7 ADS valves in the open position.

(Critical Task - Open 7 SRVs when Max Safe exceeded in more than one area. Critical task is met when 5 SRVs have been opened).

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

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

Operator secures all injection other than CRD.

Enters Primary Containment Control (PC) EOP flow chart.

SRO

IAW PC/T path directs Torus Cooling to be placed into service. If Torus temperature is <100°F only one loop of RHR will be placed in Torus Cooling. If Torus temperature is >100°F both loops of RHR will be placed in Torus Cooling.

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

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

Enters 34SO-E11-010-2, Residual Heat Removal, AND places RHRSW in service IAW Placard;

Prelubes RHRSW pump.

Overrides 2E11-F068B Low Discharge Pressure Interlock.

ATC

Positions 2E11-F068B to 45% OPEN.

Starts RHRSW pump B.

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

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 8 Page 20 of 26 Event

Description:

Emergency Depress when Max Safe exceeded in more than one area.

Time Position Applicant's Actions or Behavior

IF desired to start a SECOND RHRSW pump,

Throttles 2E11-F068B to achieve max flow rate (not to exceed 4400 GPM).

ATC

Opens 2E11-F068B an additional 5%.

Starts second RHRSW Pump.

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

IAW 34SO-E11-010-2, Placard;

IF RWL <2/3 core height, (-193 inches), PLACE the Cnmt Spray Vlv Cntl 2/3 Core Ht Permis keylock in the MANUAL OVERRD. (Not needed)

IF required by EOPs AND LOCA signal present, PLACE Cnmt Spray Vlv Cntl switch in the MANUAL position. (Not needed)

ATC

OPENS 2E11-F048A (2E11-F048B).

IF SPC is not required per the EOPs, CLOSE 2E11-F047A (2E11-F047B).

(Not needed)

OPENS 2E11-F003A (2E11-F003B).

IF power is being provided by EDG, CHECK EDG loading prior to start of RHR pump(s).

STARTS RHR Loop A(B) pump(s).

OPENS 2E11-F028A (2E11-F028B.

THROTTLES OPEN 2E11-F024A (2E11-F024B).

OPEN 2E11-F047A (2E11-F047B).

ATC

IF it is desired to provide cooling of the Torus rather than mixing, ensure RHR flow is < 11,500 GPM, THEN CLOSES 2E11-F048A (2E11-F048B).

THROTTLES 2E11-F068A OR 2E11-F068B to maintain 20 PSID Hx A(B) dp.

REFERS to 34SO-E11-010-2.

Simulator operator the next event was activated at the beginning of the scenario.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 9 Page 21 of 26 Event

Description:

RHR & CS LOCA logic failure, SULCV closed - manual actions are required for proper RHR/CS & Cond/FW operation ensuring adequate core cooling.

Time Position Applicant's Actions or Behavior NOTE: mfE11_202B (LOCA Signal failure) & mfE21_202A (LOCA Signal failure) was inserted at beginning.

At panel 2H11-P601, Confirms the 4 RHR pumps did NOT auto start.

If a LOCA signal is received, notifies SRO of RHR pump logic failure and BOP starts (Critical Task is met if one RHR pump is started) the 4 RHR pumps.

At panel 2H11-P601, Confirms 2 CS pumps did NOT auto start and starts (Critical Task is met if one CS pump is started) the CS pumps.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 9 Page 22 of 26 Event

Description:

RHR & CS LOCA logic failure, SULCV closed - manual actions are required for proper RHR/CS & Cond/FW operation ensuring adequate core cooling.

Time Position Applicant's Actions or Behavior Simulator Operator, At the Chief Examiners direction AND AFTER the ADS valves have been opened (Event 8); when Reactor pressure is < 500 psig, ENSURE EGB21-5 INSERTS mfN21_99, SULCV fails closed.

(Critical Task) - Throttle open 2N21-F110 for vessel injection to maintain RWL greater than -180 inches.

If 2N21-F110 is NOT used, then a NEW Critical Task will be to align RHR/Core Spray systems for vessel injection to maintain RWL greater than -

180 inches.

EITHER IS ACCEPTABLE.

The BOP recognizes the SULCV has failed closed.

Performs ONE or MORE of the following to inject water into the reactor.

BOP

Throttles open Condensate System, 2N21-F110, and injects water into the reactor (Critical Task).

NOTE: mfE21_202A (LOCA Signal failure) inserted at beginning.

OR

If a LOCA signal is received, notifies SRO of CS pump logic failure and starts 2A (2B) Core Spray Pump. (Critical Task)

Confirm discharge pressure >265 psig.

Confirm 2E21-F031A (B) closes when flow >950 gpm.

Confirm a CS and RHR room cooler automatically starts.

When RPV pressure is <425 psig, throttles open 2E21-F005A(B).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-2 Event No.: 9 Page 23 of 26 Event

Description:

RHR & CS LOCA logic failure, SULCV closed - manual actions are required for proper RHR/CS & Cond/FW operation ensuring adequate core cooling.

Time Position Applicant's Actions or Behavior NOTE: mfE11_202B (LOCA Signal failure) inserted at beginning.

OR

At panel 2H11-P601, Confirms the 4 RHR pumps did NOT auto start and ONLY 2 Core Spray pumps are running.

If a LOCA signal is received, notifies SRO of RHR pump logic failure and starts (Critical Task) is met if one RHR pump is started) the 4 RHR pumps.

When RPV pressure is <425 psig, throttles open 2E11-F015A (B).

Reports SULCV problem to the SRO.

With Chief Examiners Permission, the Scenario will be terminated when reactor water is being controlled following the Emergency Depressurization, with reactor pressure below 50 psig or as directed by the Chief Examiner.

Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 10-3 Op-Test No.: 2016-301 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at 60% RTP. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Turnover: Continue startup and place RFPT 2A in service, starting at step 7.1.11.2.8 of 34SO-N21-007-2. Once RFPT 2A is in service, notify Maintenance to perform walk down of RFPT 2A piping.

Once Maintenance walk down is complete, increase Reactor power to 75% RTP using Recirc.

Event Malf. No. Event Event No. Type* Description Continue startup and place RFPT 2A in service, starting at step 1 N/A N (BOP) 7.1.11.2.8 of 34SO-N21-007-2.

mfP51_222C loP51-C001BGl 2 C (BOP) SSAC 2C Trips - 2B fails unloaded, 2A must be manually started.

loP51- C001BR2 diP51- C001B mfE51_250 C (ATC) RCIC Steam Line breaks in the Rx bldg.

3 svoE51075 TS (SRO) RCIC isolation valves fail to auto close (Critical Task) mf60131136 C (BOP) 2B Loop of Core Spray experiences high discharge pressure (valve 4 TS (SRO) leakage). Perform ARP & restore.

aoE21R600B svoB21036 One (1) Reactor Pressure ATTS trip unit causes a half scram and I (ATC) 5 mf60211154 Control Rod 22-27 scrams in due to a blown fuse. The control rod mfC12_26_22-27 TS (SRO) fuse is repaired (Time Compress) and the rod is withdrawn.

mf65702209 Earthquake requiring scram prior to 98 inches in Torus with a loss of 6 mf65702227 R (ATC) Unit 1 SAT 1D. Reduce reactor power to between 40% & 50% due to mf65321987 earthquake.

svoT48140(70/.75) svoT48142(50/10) svoT48143(50/10) M (ALL)

Emergency Depress prior to Torus level reaches 98 inches.

7 (Critical Task) svoT48147(50/10) svoT48148(50/10) mfB21_129A mfB21_129E mfB21_129L ALL ADS valves fail to open when Emergency Depress is required, 8 mfB21_129M C (ATC) mfB21_129C EOP-108. (Critical Task) mfB21_129K mfB21_129H

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

Page 27 of 29 Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 10-3 Op-Test No.: 2016-301 Examiners: Operators: SRO RO BOP Initiating Conditions: Unit 2 is operating at 60% RTP. 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written.

Turnover Continue startup and place RFPT 2A in service, starting at step 7.1.11.2.8 of 34SO-N21-007-2. Once RFPT 2A is in service, notify Maintenance to perform walk down of RFPT 2A piping. Once Maintenance walk down is complete, increase Reactor power to 75% RTP using Recirc.

Summary:

Event 1: Normal; The 2A RFPT will be placed into service IAW 34SO-N21-007-2.

Event 2: Component; SSAC 2C Trips - 2B fails unloaded, 2A manually started. The "2C" Station Service Air Compressor (SSAC) trips due to an equipment malfunction. "2B" SSAC auto starts but does not supply any air to the system because its loader system is malfunctioning. The crew will manually start "2A" SSAC, which does return the air system to normal pressures.

Event 3: Component/TS; A RCIC steam line will break outside of Primary Containment. The outboard isolation valve is failed open and cannot be closed. Both isolation valves fail to automatically close on an automatic isolation signal and must be manually closed. (Critical Task) The SRO addresses Tech Specs for inoperable Primary Containment Isolation Valve.

Event 4: Component/TS; 2B Loop of Core Spray experiences high discharge pressure (valve leakage). When ARP is performed, system pressure is restored.

Event 5: Component; One (1) Reactor Pressure ATTS trip unit causes a half scram and a control rod to scram in due to a blown fuse. The control rod fuse is repaired (Time Compress) and the rod is withdrawn.

Event 6: Major; Earthquake requiring scram prior to 98 inches in Torus with a loss of Unit 1 SAT 1D.

Event 7: Reactivity; Reduce reactor power to between 40% & 50% due to earthquake.

Event 8: Major; Emergency Depress prior to 98 inches in the Torus. (Critical Task)

Event 9: Component; ALL ADS valves fail to open when Emergency Depress is required, 31EO-EOP-108. (Critical Task)

Page 28 of 29 Critical Tasks NRC FINAL Facility: E. I Hatch Scenario No.: 10-3 Op-Test No.: 2016-301 Critical Tasks

Manually isolate the RCIC isolation valves within 5 minutes of receiving 602-302 and 602-313.

(Event 3)

Emergency Depress prior to Torus level reaches 98 inches. (Event 8)

Reduce and maintain RPV pressure to <50 psig using SRVs and 31EO-EOP-108. (Event 9)

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 6 1. SSAC 2C Trips - 2B fails unloaded, 2A manually started (Event 2)

2. RCIC steam line will break (Event 3)

3. 2B Loop of CS high pressure (Event 4)

4. ATTS Scram with CR blown fuse (Event 5)

5. Earthquake with SAT 1D loss (Event 6)

6. All ADS valves fail (Event 9)

2. Malfunctions After 1-2 1 1. All ADS valves fail (Event 9)

EOP Entry

3. Abnormal Events 2-4 4 1. SSAC 2C Trips - 2B fails unloaded, 2A manually started (Event 2)

2. RCIC steam line will break (Event 3)

3. ATTS Scram with CR blown fuse (Event 5)

4. Earthquake with SAT 1D loss (Event 6)

4. Major Transients 1-2 2 1. Earthquake requiring scram prior to 98 inches in Torus (Event 6)

2. Emergency Depress prior to 98 inches in Torus (Event 8)

5. EOPs entered, 1-2 2 1. RC (Event 6) requiring substantive 2. PC (Event 7) actions

6. EOPs contingencies 0-2 1 1. Emergency Depress prior to 98 inches in Torus requiring substantive (Event 7) actions

7. EOP Based 2-3 3 1. RCIC steam line will break (Event 3)

Critical Tasks 2. Emergency Depress prior to 98 inches in Torus (Event 8)

3. ALL ADS valves fail to open when Emergency Depress is required, EOP-108. (Event 9)

ILT 10 NRC FINAL Scenario 3 SHIFT TURNOVER Safety Focus UNIT 1 STATUS Plant Conditions: Unit 1 is operating at 100% RTP.

UNIT 2 STATUS Plant Conditions: Unit 2 is operating at 60% RTP.

Protected Train: EOOS:

Division I Green Orange Division II Yellow Red Scheduled evolutions: Place RFPT 2A in service, starting at step 7.1.11.2.8 of 34SO-N21-007-2 Once RFPT 2A is in service, Maintenance will perform walk down of RFPT 2A piping Once Maintenance walk down is complete, increase Reactor power to 75% RTP using Recirc Surveillances due this None shift:

Inop Equipment: 2B21-F013D, SRV 2D, is inoperable for LLS, RAS written Active tagouts: NONE Rod Configuration: See RWM

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 1 Page 2 of 29 Event

Description:

Place the RFPT 2A in service, starting at step 7.1.11.2.7 of 34SO-N21-007-2.

Time Position Applicant's Actions or Behavior 15 Orders Operator to place RFPT 2A in service, starting at step 7.1.11.2.8 of SRO Mins 34SO-N21-007-2.

BOP

Enters 34SO-N21-007-2 at step 7.1.11.2.8.

Confirms M/A station is tracking actual Speed Setter (RFPT) speed.

Places the TMR Mode switch to M/A.

Confirms the M/A Station green light illuminates.

NOTE: Alarm RFP C005A DISCH FLOW LOW, (656-039), will clear when RFPT 2A is placed into service. MULTIPOINT TEMP RCDR 2T47-R611 TEMP HIGH, (657-072) may come in and clear. All are expected for this plant condition. If dispatched to RFPT area, SIMULATOR OPERATOR, wait 2 minutes, NOTIFY BOP there are no steam leaks in the RFPT area. This is a normal condition and the alarm will clear as the temperature decreases.

Slowly changes the RFPT 2A M/A station to match RFP 2A AND the RFP 2B flow match.

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

Depresses the PF key AND read the controller output (PF lamp lit).

Depresses the PF key so the input to the controller is displayed (PF lamp is off).

Adjusts the manual output lever until the input AND output are matched on P603 panel.

Monitors RWL, RFPT 2A discharge pressure and RFPT 2A & 2B speed.

NOTE: Alarm 656-039, RFP C005A Disch Flow Low will clear when RFPT 2A is placed into service. Alarm 650-135, Heater Trouble may come in and clear. This is expected for this plant condition.

Places RFP A M/A station in AUTO

As required, adjusts RFP A Speed Control Bias Setting to maintain RFPT 2A and 2B speed within 100 RPM.

Alarm RFPT CONTROLLER TROUBLE, (656-039) clears.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 1 Page 3 of 29 Event

Description:

Place the RFPT 2A in service, starting at step 7.1.11.2.7 of 34SO-N21-007-2.

Time Position Applicant's Actions or Behavior

Informs SRO that the 2A RFPT is in service in Automatic control.

SRO

Informs ATC to increase power with Recirc to 75% power.

Simulator operator proceeds to the next event at the Chief Examiners direction

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 2 Page 4 of 29 Event

Description:

SSAC 2C Trips - 2B fails unloaded, 2A must be manually started.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, at direction of the Chief Examiner, NOTIFY the ATC by phone and request Off-Gas flow reading, then ACTIVATES: (RB-2) malfunction mfP51_222C. ENSURE Event Trigger EGP51-3 ACTIVATES the following when the "B" air compressor red light is on:

loP51-C001BG1 to OFF, 7 Min loP51-C001BR2 to ON, mfP51_222B, EGP51-4.

ONCE "2B" SSAC is placed in PTL, ENSURE Event Trigger EGP51-4 DELETES: loP51-COO1BG1, loP51-C001BR2, and mfP51_222B.

The following annunciators are received:

ALL

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

AIR CMPSR 2C TRIPPED/SHUTDOWN, (700-233).

Acknowledges 2H11-P700 panel alarm on 2H11-P650.

Acknowledges AIR CMPSR 2C TRIPPED/SHUTDOWN, (700-233), on 2H11-P700 and notifies the SRO of the alarm.

Confirms/starts 2B SSAC on P650 panel.

Determines air pressure is continuing to decrease.

BOP

Starts 2A SSAC on P650 panel IAW (700-233) or 34AB-P51-001-2.

Dispatches SO/Maintenance locally to investigate 2C SSAC tripping and 2B SSAC not maintaining air pressure.

As time allows, contacts Health Physics after starting Standby SSACs.

May receive CONTROL BLG SERVICE AIR PRESS LOW, (700-222).

May direct BOP into 34AB-P51-001-2, Loss of Instrument and Service Air SRO System or Water Intrusion into the Service Air System.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 2 Page 5 of 29 Event

Description:

SSAC 2C Trips - 2B fails unloaded, 2A must be manually started.

Time Position Applicant's Actions or Behavior Simulator Operator: 2 minutes after being dispatched to investigate SSAC 2C tripping and SSAC 2B not maintaining air pressure (unless SSAC 2A was started), and with Lead Examiners permission, INFORM the BOP; SSAC 2C has a low oil pressure shutdown indication AND IF SSAC 2B IS STILL RUNNING that SSAC 2B is running unloaded and you cannot locally get it to LOAD.

OR IF SSAC 2B IS NOT RUNNING that SSAC 2B is off and NOT in automatic mode locally (auto light not lit).

Simulator Operator: If requested to crosstie air, REPORT Unit 1 crosstie is not available.

IF dispatched locally as Maintenance, if SSAC 2B IS RUNNING, as Maintenance, request SSAC 2B Shutdown for troubleshooting.

Notifies SO/Maintenance (if BOP has not) to investigate SSAC 2C tripping and SSAC 2B not maintaining air pressure and initiates a condition report.

SRO

Directs the BOP to start the 2A SSAC IAW AIR CMPSR 2C TRIPPED/SHUTDOWN, (700-233).

Directs the BOP to start the SSAC 2B.

May request to crosstie air with Unit 1.

Places SSAC 2B switch to PTL on P650 panel.

BOP

As time allows, dispatches SO to perform step 7.5.1.6 of 34SO-P51-001-2.

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 3 Page 6 of 29 Event

Description:

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

Time Position Applicant's Actions or Behavior Simulator Operator: Call BOP and request 2C Main Fuel Oil Storage tank level, ENTER RB-3 to starts the following RCIC steam leak:

mfE51_250 (RCIC Leak) 100/7 15 Min.

svoE51075 (F008 stuck open)

NOTE: It takes approximately 3.0 minutes for the 601-321, Leak Det Diff Temp High to alarm.

Determines 2T41-B009, Secondary Stm. Chase Cooler is NOT running

Monitors Steam Tunnel temps.

BOP

Enters 34AB-T22-001-2, Primary Coolant System Pipe Break - Rx Building.

Dispatches operator to ATTS for Steam Chase Temperatures.

Acknowledges LEAK DET DIF TEMP HIGH, (601-321) and reports to SRO.

BOP Enters 601-321 and starts investigating.

Confirms which area is producing alarm using Temperature Recorder on 2H11-P614:

R604, Pt. 115 is reading approximately 32°F delta-T.

R608, Pt. 117 is reading approximately 32°F delta-T.

Enters 34AB-T22-003-2, Secondary Containment Control.

NOTE: It will take about 30 minutes for a Group 1 isolation to occur. At direction of the Chief Examiner, if P603-2 Group 1 System A Trip alarms, IMMEDIATELY DELETE mfE51_250.

Enters the 31EO-EOP-014-2, Secondary Containment EOP Flowchart on Secondary Containment High Differential Temperature.

SRO

Has an operator monitor Sec Cont. Temps.

Has operators monitor systems for source of the leak.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 3 Page 7 of 29 Event

Description:

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

Time Position Applicant's Actions or Behavior BOP

Enters 34AB-T22-003-2, Secondary Containment Control.

SIMULATOR OPERATOR:

If 2E51-F007 is CLOSED DO NOT ENTER (RB-10):

SIMULATOR OPERATOR: When EOP SC flowchart is ENTERED and Chief Examiner concurs ENTER (RB-10) mfE51_113 (RCIC Auto Isolation E51-F008)

As time allows the crew will enter the following ARPs:

RCIC STEAM LINE DIFF PRESS HIGH, (602-302).

RCIC TURBINE TRIP, (602-301).

ATC

RCIC ISOLATION SIGNAL LOGIC A, (602-307).

RCIC ISOLATION SIGNAL LOGIC B, (602-313).

Time:_____________

Responds to failure of RCIC Isolation:

Places 2E51- F008 control switch to CLOSE.

Places 2E51- F007 control switch to CLOSE.

(Critical Task is to position 2E51-F007 control switch to close within 5 minutes of receiving 602-302, 602-307 and 602-313 listed ATC above OR may close before alarms are received).

Time:_____________

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

Dispatches operator/Maintenance to investigate the leak.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 3 Page 8 of 29 Event

Description:

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

Time Position Applicant's Actions or Behavior Reviews Tech Specs section 3.6.1.3, Primary Containment Isolation Valves Condition A.1 and A.2 and determines:

2E51-F008 Inop

2E51-F007 must be closed and deactivated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND

2E51-F007/F008 penetration must be verified ISOLATED every 31 SRO days.

As time allows, contacts the Shift Support Supervisor to draft a Danger Tagout for 2E51-F007.

Enters TS RAS for RCIC 3.5.3 Condition A, which requires verifying HPCI is operable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restoring RCIC in 14 days.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 4 Page 9 of 29 Event

Description:

2B Loop of Core Spray experiences high discharge pressure (valve leakage). When ARP is performed, system pressure is restored.

Time Position Applicant's Actions or Behavior At the Chief Examiners direction, Simulator Operator enters (RB-4) 10 Min malfunction mf60111061 Window 25 Core Spray B Disch Pipe Press High (ON) and aoE21-R600B to 465 psig.

Enters ARP 34AR-601-125-2.

Confirm validity of alarm using Disch Press indicator, 2E21-R600B

(~465 psig).

Confirm the following valves are CLOSED.

2E21-F037B, Testable Check Bypass Vlv.

BOP

2E21-F005B, Inbd Discharge Vlv.

Closes 2E21-F004B, Outbd Discharge Vlv.

Opens 2E21-F005B.

Closes 2E21-F005B, to reseat.

Opens 2E21-F004B to open.

Directs operator to enter 601-113 ARP.

Reviews TS 3.5.1, ECCS and Enters Condition A since 2E21-F004B is closed.

SRO

TS 3.5.1.A requires the ECCS pump to restored to operable status in 7 days.

Reviews TS 3.6.1.3, PCIV.

Enters TS 3.5.1, ECCS Operating, and determines that with Core Spray B Jockey Pump Sys Water Level Low, 601-114, received, declares CS 2B pump inop:

SRO

TS 3.5.1.A requires the ECCS pump to restored to operable status in 7 days.

NOTE: If addressed, 2E21-F004B is NOT a PCIV and TS 3.6.1 for PCIVs is not applicable.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 4 Page 10 of 29 Event

Description:

2B Loop of Core Spray experiences high discharge pressure (valve leakage). When ARP is performed, system pressure is restored.

Time Position Applicant's Actions or Behavior Simulator Operator, ENSURE Event Trigger EGE21-6 activates when 2E21-F015B is placed to open position. This will clear CS B Disch Press High alarm & return 2E21-R600B to normal.

IAW ARP 601-125, may perform the following:

Slightly opens 2E21-F015B to lower CS Discharge pressure.

Confirms 601-125 clears.

BOP

When pressure is approximately 100 psig, closes 2E21-F015B.

If 601-114, Core Spray B Jockey Pump Sys Water Level Low, is received directs an SO to vent the B Loop of Core Spray IAW 34SV-SUV-017-2.

Monitors Core Spray B Loop pressure for subsequent increases.

NOTE: If pressure is NOT relieved, then a follow-up question on PCIV leakage TS 3.6.1.3.D may be appropriate.

NOTE: If pressure IS relieved on Core Spray Loop B, and pressure is NOT monitored, then a follow-up question on a high pressure condition of the inner system piping may be appropriate.

Simulator Operator, at the Chief Examiners request, proceeds to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 5 Page 11 of 29 Event

Description:

One (1) Reactor Pressure ATTS trip unit causes a half scram and Control Rod 22-27 scrams in due to a blown fuse. The control rod fuse is repaired (Time Compress) and the rod is withdrawn.

Time Position Applicant's Actions or Behavior At the Chief Examiners direction, Simulator operator, ENTER (RB-5) 20 min svoB21036 (final value of 1200 with ramp of 1000). EGB21-26 will insert malfunctions mf60211154 and mfC12_26_22-27.

The following annunciators are received:

REACTOR VESSEL HIGH PRESSURE TRIP, 603-105.

REACTOR AUTO SCRAM SYSTEM A TRIP, 603-117.

ALL CRD ACCUMULATOR PRESS LOW OR LEVEL HIGH, 603-148.

RMCS / RWM ROD BLOCK OR SYSTEM TROUBLE, 603-239 (when control rod 22-27 is selected).

ROD DRIFT, 603-247.

ECCS/RPS DIVISION I TROUBLE, 602-110.

Determines that reactor pressure has not changed.

Announces to SRO that a half-scram in the A channel has occurred due ATC to an invalid high reactor pressure signal.

Informs the SRO that control rod 22-27 has scrammed in.

Simulator Operator: When dispatched to check the ATTS panel reactor pressure instruments, report ONE MINUTE LATER that 2B21-N678A has a red trip light and gross failure light illuminated.

Dispatches personal to the ATTS panels to determine which reactor pressure instrument has tripped.

Contacts maintenance to repair ATTS card 2B21-N678A (2B21-N078A is transmitter).

SRO

Contacts maintenance to check and replace the fuse in the RPS B channel for control rod 22-27.

Notifies Rx Engineering or STA to check thermal limits if the SRO has not already contacted them.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 5 Page 12 of 29 Event

Description:

One (1) Reactor Pressure ATTS trip unit causes a half scram and Control Rod 22-27 scrams in due to a blown fuse. The control rod fuse is repaired (Time Compress) and the rod is withdrawn.

Time Position Applicant's Actions or Behavior Simulator Operator: When contacted as Reactor Engineering with the following question from 34AB-C11-004-2, Contact Reactor Engineering to determine what thermal limits were exceeded during the event AND what recovery actions are necessary. Answer NO thermal limits have been exceeded.

Refers to the following Tech Specs:

LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and SRO determines that 2B21-N678A requires entry into RAS 3.3.1.1.A to place the channel in trip or the A trip system in trip in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Simulator Operator: AFTER the TS call is made DELETES mfC12_26_22-27; this will cause the scram light for the rod to extinguish.

AND REPORTS as Maintenance that control rod 22-27 had a fuse blown, which has been replaced.

Simulator Operator: After being dispatched to repair ATTS card 2B21-N678A AND AFTER the SRO has determined the Tech Spec RAS, DELETE svoB21036 and mf60211154, THEN REPORT to the SRO that time compression has been used and that 2B21-N678A has been repaired and returned to service.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 5 Page 13 of 29 Event

Description:

One (1) Reactor Pressure ATTS trip unit causes a half scram and Control Rod 22-27 scrams in due to a blown fuse. The control rod fuse is repaired (Time Compress) and the rod is withdrawn.

Time Position Applicant's Actions or Behavior NOTE: The following annunciators and actions may not be taken in the same sequence as listed below.

Addresses annunciator, Reactor Auto Scram System A Trip, 603-117.

Confirm scram group A 1 2 3 4 lights for Trip System A on panel 2H11-P603 are extinguished.

Determine the cause of the trip.

ATC

Attempt to correct or bypass the cause of the trip.

Using the Process Computer obtains an OD-7 and determines that control rod movement has occurred.

(May reset half scram before performing OD-7).

Resets RPS Channel A using 2C71-S5, Reactor Scram Reset switch, on panel 2H11-P603, per step 5.2.3 of 34AR-603-117-2.

ATC

Determines that section 4.7 of 34AB-C11-004-2 is required to be used to recover control rod 22-27.

Addresses annunciator ROD DRIFT, (603-247)

At panel 2H11-P603, confirms that one or more Rod Drift lights are illuminated on the full core display.

Selects the drifting rod and confirms that RPIS indicates the rod is not at an even reed switch position.

ATC

Notifies the Shift Supervisor and the STA.

Refers to 34AB-C11-004-2, Mis-positioned Control Rods, for recovery of drifting OR mis-positioned control rod.

When directed by the Shift Supervisor, resets the rod drift using the Rod Drift Alarm reset switch on Panel 2H11-P603.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 5 Page 14 of 29 Event

Description:

One (1) Reactor Pressure ATTS trip unit causes a half scram and Control Rod 22-27 scrams in due to a blown fuse. The control rod fuse is repaired (Time Compress) and the rod is withdrawn.

Time Position Applicant's Actions or Behavior

Refers to Attachment 1 of 34AB-C11-004-2 for the proper actions to take.

Are >4 rods mispositioned? NO

Is the reactor sub-critical? NO ATC

Is reactor power < LPSP (21%)? NO

Are Thermal Limits acceptable? YES

Performs Action 1.

Refer to Attachment 2 for restoration steps.

Simulator Operator: When Reactor Engineering is notified for a recovery plan, provide the SRO with the marked up copy of Attachment 2 of 34AB-C11-004-2.

Refers to Attachment 2 to recover the control rod.

Withdraws the control rod to position 48 using the Rod Movement ATC switch and Rod Out Notch Override switch (RONOR).

Performs coupling check on control rod.

Simulator operator proceeds to the next event at the Chief Examiners direction.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 6 Page 15 of 29 Event

Description:

Earthquake with a loss of Unit 1 SAT 1D requiring Reactor power to be reduced to between 40 - 50% RTP.

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

(Earthquake - malfunctions to (ON):

10 Min mf65702209 Window 30 SEISMIC PEAK SHOCK RECORDER HIGH G LEVEL & mf65702227 Window 48 SEISMIC INSTRUMENTATION TRIGGERED mf65321987 Window 18 230 KV BREAKER TRIP (ANNUNCIATOR ON)

The following annunciators are received:

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

ALL

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

SEISMIC INSTRUMENTATION TRIGGERED, (657-048).

230 KV BREAKER TRIP, (653-218).

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

BOP

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

Communicates both alarms to the SRO.

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

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

As time permits, may notify GCC of tripped PCBs.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 6 Page 16 of 29 Event

Description:

Earthquake with a loss of Unit 1 SAT 1D requiring Reactor power to be reduced to between 40 - 50% RTP.

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

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

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

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

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

May have the Unit 1 RO check the following:

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

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

BOP

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

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

May inform the Shift Manager to evaluate an Emergency Classification.

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 6 Page 17 of 29 Event

Description:

Earthquake with a loss of Unit 1 SAT 1D requiring Reactor power to be reduced to between 40 - 50% RTP.

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

12.7 Hz Amber lights (> 0.08g, OBE)

AND

12.7 Hz Red lights (> 0.15g, DBE)

AND

Unit 1 has scrammed AND

SAT 1D de-energized 1B EDG started.

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

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

Determines that all electrical power is NOT available.

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

Contacts switchyard maintenance to assist in switchyard damage assessment .

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

SRO

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

1P11-F167, CST Sump to Radwaste Drain.

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

2P11-F051, Retaining Wall Drain.

2P11-F100, Transfer Pump Wall Drain.

Dispatches personnel to inspect the plant for damage.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 6 Page 18 of 29 Event

Description:

Earthquake with a loss of Unit 1 SAT 1D requiring Reactor power to be reduced to between 40 - 50% RTP.

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

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

Determines that all electrical power is available.

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

Contacts switchyard maintenance to assist in switchyard damage assessment.

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

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

1P11-F167, CST Sump to Radwaste Drain.

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

2P11-F051, Retaining Wall Drain.

2P11-F100, Transfer Pump Wall Drain.

Dispatches personnel to inspect the plant for damage.

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 6 Page 19 of 29 Event

Description:

Earthquake with a loss of Unit 1 SAT 1D requiring Reactor power to be reduced to between 40 - 50% RTP.

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

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

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

ATC

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

Monitors power decrease by observing APRM and generator output indications.

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

Simulator Operator enters the next event after power has been decreased between 40% to 50% or at the Chief Examiners request.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 7 Page 20 of 29 Event

Description:

Emergency Depress prior to Torus level reaches 98.

Time Position Applicant's Actions or Behavior Simulator Operator, after reactor power is reduced between 40-50% RTP and at Chief Examiners direction, ACTIVATE (RB-1)

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

LOOK ahead, This leak will be modified at 142 inches in the Torus (EGT48-1) and ALL ADS SRVs fail closed.

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

The following annunciators are received:

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

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

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

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

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

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

ALL

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

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

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

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

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

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

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

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

BOP

Directs SO/Maintenance to investigate the leak.

Directs BOP to 2H11-P657 panel.

SRO

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 7 Page 21 of 29 Event

Description:

Emergency Depress prior to Torus level reaches 98.

Time Position Applicant's Actions or Behavior Simulator Operator: Four minutes after being dispatched to check for leaks in the Torus section of the Reactor Building, report to the crew:

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

602-235, TORUS WATER LEVEL HIGH/LOW, annunciates ALL

Recognizes that Torus level is decreasing.

Dispatches personnel to determine the location of the Torus leak.

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

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

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

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

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

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

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

Dispatches personnel to the Torus to determine source of leakage

Notifies SRO of ECCS TS requirements when closing valves.

ATC

Closes 2E21-F019B, Torus Suction Vlv.

Closes 2E11-F065B, Torus Suction Vlv.

Closes 2E11-F065D, Torus Suction Vlv.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 7 Page 22 of 29 Event

Description:

Emergency Depress prior to Torus level reaches 98.

Time Position Applicant's Actions or Behavior

Checks Torus water level and determines the Torus level is continuing to decrease with the above valves closed ATC

Closes 2E41-F051, HPCI Torus Suction Vlv.

Opens 2E21-F019B, Torus Suction Vlv.

Opens 2E11-F065B, Torus Suction Vlv.

Opens 2E11-F065D, Torus Suction Vlv.

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

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

Opens 2E41-F051, HPCI Torus Suction Vlv.

Closes 2E51-F003, RCIC Torus Suction Vlv.

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

ATC

Opens 2E51-F003, RCIC Torus Suction Vlv.

Closes 2E21-F019A, Torus Suction Vlv.

Closes 2E11-F065A, Torus Suction Vlv.

Closes 2E11-F065C, Torus Suction Vlv.

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

ATC

2E21-F019A, Torus Suction Vlv.

2E11-F065A, Torus Suction Vlv.

2E11-F065C, Torus Suction Vlv.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 7 Page 23 of 29 Event

Description:

Emergency Depress prior to Torus level reaches 98.

Time Position Applicant's Actions or Behavior

IAW the PC flowchart, prior to water level reaching 98 inches, determines that the reactor is required to be shutdown and enters the RC flowchart at point A.

Assigns the ATC to perform RC-1.

SRO

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

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

Directs RWL Band of 3 to 50 inches.

Performs RC-1 consisting of:

Inserts a manual scram.

Places the mode switch to shutdown.

Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display.

Notifies SRO of rod position check.

ATC

Places SDV isolation valve switch to "isolate" & confirms closed.

If not tripped, places the Recirc pumps at minimum speed.

Inserts SRMs and IRMs.

Shifts recorders to read IRMS, when required.

Ranges IRMS to bring reading on scale.

Notifies the SRO when the above actions are complete.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 7 Page 24 of 29 Event

Description:

Emergency Depress prior to Torus level reaches 98.

Time Position Applicant's Actions or Behavior

Performs RC-2 actions consisting of:

Confirms proper Level Control response:

Checks ECCS Injection Systems.

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

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

BOP

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

( 1.5 mlbm/hr), then:

Opens 2N21-F125.

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

Closes 2N21-F110.

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

Performs RC-3 consisting of:

Monitor RPV pressure.

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

BOP

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

Maintain RPV pressure between 1074 and 800 psig.

Notify SRO of pressure control system operation.

If the need to Emergency Depressurize is recognized in time, then Anticipates Emergency Depressurization.

SRO

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

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 7 Page 25 of 29 Event

Description:

Emergency Depress prior to Torus level reaches 98.

Time Position Applicant's Actions or Behavior

On the DEHC panel

Selects the Control > Bypass Valve screen.

Inserts a ramp rate of 100, then presses OK.

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

Checks that the Bypass Valve Jack status is active.

ATC/BOP

Recognizes that 3 Bypass Valves open.

Reports to the SRO 3 Bypass Valves are open.

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

ATC

Provides periodic updates on Torus level to the SRO.

Transitions to CP-1 and orders 7 ADS valves open for Emergency SRO Depress. (GO TO EVENT 8)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-3 Event No.: 8 Page 26 of 29 Event

Description:

ALL ADS valves fail to open when Emergency Depress (ED) is required, EOP-108 used to ED.

Time Position Applicant's Actions or Behavior Simulator Operator, failure of ALL ADS SRVs to open, has been ACTIVE since the start of scenario.

Places the switches for 7 ADS valves in the open position.

Determines that NONE of the ADS valves open.

Either informs SRO or continues opening other LLS SRVs.

Only 4 SRVs (LLS) will open

Notifies SRO that 4 SRVs open and failure of ALL ADS SRVs fail to open.

(Critical Task - Critical task is met when 4 SRVs (LLS SRVs) have been opened ATC/BOP and RPV pressure is <50 psig using SRVs and 31EO-EOP-108.

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

NOTE: If RPV pressure is below approximately 300psig, the SRV amber lights will not illuminate for SRV position confirmation. The operator can verify that the SRVs have opened by observing SRV tailpipe temperature increase.

If the Operator notifies the SRO that 7 SRVs failed to open and that only 4 LLS valves are open, the SRO directs the operator to enter 31EO-EOP-108.

SRO

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

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

Operator secures all injection other than CRD.

With Chief Examiners Permission the Scenario will be terminated when Reactor pressure is within 50 psig of Torus pressure or as directed by the Chief Examiner.

Page 1 of 29 Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 10-04 Op-Test No.: 2016-301 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at 90% RTP. 2D11-K615B, Offgas Post Treatment Radiation Monitor, failed Downscale. RAS written.

Turnover: Hydrogen Seal Oil System is currently aligned with the Emergency Seal Oil pump in service.

After turnover restore to Normal Hydrogen Seal Oil System Lineup starting at step 7.3.3.2.5 of 34SO-N42-001-2. Once Hydrogen Seal Oil is returned to Normal lineup, increase reactor power to 100% RTP using the Recirculation System and control rods.

Event Malf. No. Event Event No. Type* Description Restoration To Normal Hydrogen Seal Oil System Lineup starting at 1 N/A N (BOP) step 7.3.3.2.5 of 34SO-N42-001-2 R (ATC) Recirc 2B ASD Cell Bypass; 2B Recirc speed decreases resulting 2 mfB31_135B TS (SRO) in a flow mismatch mf65031541 RFPT loop seal failure requiring manual opening of bypass valve to 3 C (ATC) prevent Main Turbine trip on low vacuum mfN61_73 2C SSAC high temp condition 4 mf70022407 C (BOP) 2A & 2B SSACs are manually started by BOP svoT48140 svoT48142 svoT48143 C (BOP) A leak develops from the HPCI Torus suction line downstream of 5 TS (SRO) 2E41-F051 and can be isolated by closing 2E41-F051 (Critical Task) svoT48147 svoT48148 mfB31_39A mfB31_45A C (ATC) Recirc Pump A seal leakage causes DW leakage.

6 rfB31_29 TS (SRO) Pump is secured and isolated mf60213160 7 mfS11_161 M (ALL) Loss of Offsite Power mfR43_239C 2C EDG fails to auto tie, 1B EDG will NOT operate & 2A EDG will 8 mfR43_49B C (ATC) tie after resetting Shutdown (Critical Task to energize at least one mfR43_62A emergency bus)

HPCI 2E41-F001 stuck closed, RCIC 2E51-F013 Fails to Auto Open 9 rfE51_234 C (BOP) requiring manual operation of 2E51-F013 to inject prior to RWL reaching -180 inches (Critical Task)

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

Page 27 of 29 NRC FINAL Scenario Summary Facility: E. I Hatch Scenario No.: 10-04 Op-Test No.: 2016-301 Initiating Conditions:

Unit 2 is operating at 90% RTP. 2D11-K615B, Offgas Post Treatment Radiation Monitor, failed Downscale. RAS written.

Turnover Hydrogen Seal Oil System is currently aligned with the Emergency Seal Oil pump in service. After turnover restore to Normal Hydrogen Seal Oil System Lineup starting at step 7.3.3.2.5 of 34SO-N42-001-2. Once Hydrogen Seal Oil is returned to Normal lineup, increase reactor power to 100% RTP using the Recirculation System.

Summary:

Event 1: Normal; The BOP will return Hydrogen Seal Oil to a Normal lineup IAW the system operating procedure.

Event 2: Reactivity/Component/TS; A 2B Recirculation Pump ASD Cell will auto bypass.

This will result in a flow and power reduction. The ASD Cell Bypass and Recirc flow mismatch will be addressed by annunciator response procedures and an abnormal procedure. The SRO will address TS for Recirc flow mismatch.

Event 3: Component; The RFPT loop seal will experience a low level condition causing condenser vacuum to degrade. The ATC operator will isolate the loop seal drain which stops condenser vacuum decreasing. Once the loop seal level is restored, the operator returns the loop seal system to normal lineup.

Event 4: Component; The 2C Station Service Air Compressor (SSAC) will receive a high discharge air temp alarm. The operator will start the 2A & 2B SSACs and shutdown 2C SSAC.

Event 5: Component/TS; A leak develops from the HPCI Torus suction line downstream of 2E41-F051 and can be isolated by closing 2E41-F051. Torus water level will continue to decrease until 2E41-F051 is isolated. (Critical Task)

Event 6: Component/TS; The 2A Reactor Recirculation pump seals will sequentially develop a failure that results in reactor coolant leaking into the Drywell (DW). Initially, only the Number 1 seal fails, followed a few minutes later by a Number 2 Seal failure. The ATC operator will trip and isolate the 2A Reactor Recirc pump. The SRO will address TS for coolant leakage and single Recirc loop operation.

Event 7: Major; The plant will experience a Loss of Offsite power.

Event 8: Component; 2C EDG fails to auto tie to the emergency bus and must have its frequency lowered, then raised to force the 2C EDG output breaker to close. 2A EDG will tie after Shutdown is manually reset. (Critical Task to energize at least one emergency bus)

Event 9: HPCI F001 stuck closed and RCIC 2E51-F013 Fails to Auto Open requiring manual operation of 2E51-F013 to inject prior to RWL reaching -180 inches. (Critical Task)

Page 28 of 29 NRC FINAL Critical Task List Facility: E. I Hatch Scenario No.: 10-04 Op-Test No.: 2016-301 Critical Tasks

A leak develops from the HPCI Torus suction line downstream of 2E41-F051 and can be isolated by closing 2E41-F051. Torus water level will continue to decrease until 2E41-F051 is isolated.

Starts/ties either 2A or 2C EDG after a LOSP

Maintains RWL above TAF or opens 7 ADS valves prior to reaching -180 inches ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 8 1. ASD 2B Cell bypass (Event 2)

2. RFPT Loop Seal failure (Event 3)

3. SSAC 2C High temperature (Event 4)

4. Leak from HPCI Torus suction line (Event 5)

5. Recirc Seal leakage (Event 6)

6. LOSP (Event 7)

7. 2 EDG failures (Event 8)

8. HPCI F001 fail shut/ RCIC F013 manual open (Event 9)

2. Malfunctions After 1-2 2 1. Loss of EDGs (Event 8)

EOP Entry 2. HPCI F001 fail shut/ RCIC F013 manual open (Event 9)

3. Abnormal Events 2-4 4 1. Diesel Generator Recovery (Event 8)

2. Reactor Recirculation Pump(S) Trip, Or Recirc Loops Flow Mismatch (Event 5)

3. Scram (Event 7)

4. Pipe Break in Sec. Containment(Event 6)

4. Major Transients 1-2 1 1. Station Blackout (Event 7)

5. EOPs entered, 1-2 2 1. RC (Non-ATWS) requiring substantive 2. Primary Containment actions

6. EOPs contingencies 0-2 0 1. None requiring substantive actions

7. EOP Based 2-3 3 1. Leak from HPCI Torus suction line (Event 5)

Critical Tasks 2. Ties either 2A or 2C EDG after a LOSP (Event 8)

3. Maintains RWL above TAF or opens 7 ADS valves before -180 inches RWL (Event 9)

ILT-10 NRC Operating Exam Scenario 4 SHIFT TURNOVER Safety Focus UNIT 1 STATUS Plant Conditions: Unit 1 is operating at 100% power Activities in progress: Maintaining Rated Thermal Power UNIT 2 STATUS Plant Conditions: Unit 2 is operating at 90% RTP.

Protected Train: EOOS:

Division I Green Orange Division II Yellow Red Scheduled Hydrogen Seal Oil System is currently aligned with the Emergency Seal Oil pump in service. After turnover restore to evolutions: Normal Hydrogen Seal Oil System Lineup starting at step 7.3.3.2.5 of 34SO-N42-001-2.

Once Hydrogen Seal Oil is returned to Normal lineup, increase reactor power to 100% RTP using the Recirculation System and control rods.

Surveillances due None this shift:

2D11-K615B, Offgas Post Treatment Radiation monitor has failed Inop Equipment:

Downscale. IAW TS/TRM, I&C has placed 2D11-K615B in the trip condition while maintaining the function of 602-405, Post Treatment O/G Radiation Hi-Hi-Hi/Inop. A Caution Tag is attached to 2D11-K615B switch.

Active tagouts: None Rod Configuration: See RWM

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 1 Page 2 of 29 Event

Description:

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

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

Seal Oil Vacuum Pump Separator Tank oil level is between the High AND Low Oil Level on 2N42-LG-R306, Separator Tank Sight Glass 10

2N42-F042, Vacuum Tank Inlet Valve, open Mins

Oil level in the Vacuum Tank is above the bottom of the lower observation window

Seal Oil Vacuum Pump shaft has been manually rotated.

Enters Restoration To Normal Hydrogen Seal Oil System Lineup at step 7.3.3.2.5

Starts 2N42-C001, H2 Seal Oil Vacuum Pump, (2H11-P651).

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

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

BOP

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

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

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

Holds control switch for ESOP in OFF Pull To Lock position until pump stops as indicated by its extinguished red AND green lights

Alarm EMERG SEAL OIL PUMP RUNNING, (651-216) will clear after the SO resets the local panel.

AFTER pump stops, releases control switch.

Confirm its green light is illuminated.

Simulator Operator, when contacted as SO, report the following:

2N42-R300, Seal Oil Pump Disch Press, is 105 psig

2N42-R301, Seal Oil / Machine Gas dP, pressure, is 8 psig above generator gas pressure.

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 1 Page 3 of 29 Event

Description:

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

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

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

REPORT Local alarm, EMERG SEAL OIL PUMP RUNNING, (N43-105) has been reset

Confirms the following by contacting SO locally:

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

BOP

2N42-R301, Seal Oil / Machine Gas dP, pressure, is being maintained 7 - 9 psig above generator gas pressure.

Simulator Operator, at the Chief Examiners request, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 2 Page 4 of 29 Event

Description:

2B Recirculation Pump ASD Cell will auto bypass.

Time Position Applicant's Actions or Behavior Simulator Operator, At Chief Examiners direction, press (RB-2) to activate:

10 min

mfB31_135B, Recirc ASD B Cell Bypass

Direct Maintenance to be contacted to determine cause of Recirc speed decrease.

SRO

Evaluates TS LCO/RAS Recirculation Loops Operating and enters TS 3.4.1 Condition A.1 to restore within limits within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

NOTE: With the ASD 2B Cell Bypassed, the operator may enter 34AB-B31-001-2, Reactor Recirculation Pump(s) Trip, Recirc Loops Mismatch, OR ASD Cell Bypass, first due to Recirc flow mismatch.

Respond to ASD B TROUBLE, (602-208), Annunciator

Diagnose Recirc pump speed mismatch.

Confirm that an ASD cell has failed and is bypassed using SPDS or by having it verified locally at the ASD cabinet.

Enter 34AB-B31-001-2, Reactor Recirculation Pump(s) Trip, Recirc Loops Mismatch, or ASD Cell Bypass.

ATC

Confirm the SPD HLD RESET pushbutton is illuminated.

Enter section III of 34AB-B31-001-2.

If Recirc speed mismatch >5%, inform SRO of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months limit to balance Recirc Pump flows.

If the SRO decides to increase Recirc flow to match flow, then the following (increase) actions will be taken, otherwise skip this part and go to the (decrease) actions.

SRO If asked, Reactor Engineering guidance for increasing power is:

Limit the rate of power change to 10 MWe/minute.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 2 Page 5 of 29 Event

Description:

2B Recirculation Pump ASD Cell will auto bypass.

Time Position Applicant's Actions or Behavior ATC

If directed by SRO to increase:

Depress the respective B SPD HLD RESET pushbutton indicating lamp.

Increase speed of the Recirc Pump 2B per 34SO-B31-001-2, Reactor Recirc System, by depressing SLOW Raise or MEDIUM Raise pushbutton on ASD 2B.

After 34AB-B31-001-2 has been addressed entered, the operator will depress the Fault Reset pushbutton to reset the ASD B TROUBLE, (602-108), alarm.

If the SRO decides to decrease Recirc flow to match flow, then the following actions will be taken, otherwise skip.

If directed by SRO to decrease:

Depress the respective B SPD HLD RESET pushbutton indicating lamp.

Decrease speed of the Recirc Pump 2A per 34SO-B31-001-2, Reactor ATC Recirc System, by depressing SLOW Lower or MEDIUM Lower pushbutton on ASD 2A.

After 34AB-B31-001-2 has been addressed entered, the operator will depress the Fault Reset pushbutton to reset the ASD B TROUBLE, (602-208), alarm.

NOTE to Examiners: TS SR 3.4.1.1 requires Recirc flow mismatch be less than 5% if operating at greater than or equal to 70% rated core flow, and mismatch be less than 10% if operating at less than 70% rated core flow.

Simulator Operator, When the crew has diagnosed that possibly an ASD Cell is bypassed, then with Chief Examiners concurrence:

Call the Control Room as I&C with the following message:

The Recirculation Pump ASD 2B has automatically bypassed a cell, conditions at the ASD are normal.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 3 Page 6 of 29 Event

Description:

RFPT loop seal failure.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR: At the direction of the Chief Examiner, ACTIVATE (RB-3) 10

mf65031541 RFP Loop Seal Level Low (Annunciator On)

Min

mfN61_73 Main Condenser Air In-leakage NOTE: It takes approximately 28 minutes for vacuum to decrease to 25.9 inches.

ATC

Recognize RFP LOOP SEAL LEVEL LOW, (650-319), annunciator.

Respond to annunciator RFP LOOP SEAL LEVEL LOW, (650-319)

Dispatches an SO to 2H21-P216 to confirm 2N22-F398, RFP Bracket Drain Loop Seal Fill Valve is open.

Monitors vacuum at 2H11-P650, on 2N21-R602.

ATC

Dispatches an SO to confirm seal water lineup and pressures IAW 34SO-N21-007-2, Condensate and Feedwater System.

SIMULATOR OPERATOR: When requested NOTIFY the ATC that Seal water pressures are normal.

Recognize PRETREATMENT O/G RADIATION DOWNSCALE/INOP, ATC (601-428), annunciator.

Monitors Inlet Flow to Stack on 2N62-P600.

BOP

Receives INLET FLOW TO STACK HIGH, (600-020).

Monitors Inlet flow to Stack at 2N62-P600, on 2N21-R604.

May direct entry into 34AB-N61-002-2, Main Condenser Vacuum Low, SRO abnormal.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 3 Page 7 of 29 Event

Description:

RFPT loop seal failure.

Time Position Applicant's Actions or Behavior If directed, may REDUCE reactor power per 34GO-OPS-005-2, Power BOP Changes, to establish and maintain vacuum greater than 25 in. Hg.

SIMULATOR OPERATOR: ENSURE Event Trigger EGN21-2 deletes mfN61_73 when

2N21-F265 is closed Then 45 seconds later, DELETES mf65031541.

With seal water pressures normal, will be required to close 2N21-F265, RFP Loop Seal Outlet Isol Vlv after 5 minutes of alarm RFP LOOP SEAL LEVEL LOW, (650-319), being received.

ATC

With vacuum degrading may close 2N21-F265 sooner to reverse degrading vacuum condition.

Opens 2N21-F265 when RFP LOOP SEAL LEVEL LOW, (650-319)

ATC clears.

Alarm INLET FLOW TO HOLDUP LINE HIGH, (600-020), clears when BOP flow returns to normal.

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 4 Page 8 of 29 Event

Description:

2C SSAC high temp condition and secured. 2A & 2B SSACs are manually started.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR:

At the direction of the Chief Examiner ACTIVATE (RB-4)

mf70022407 Control Bldg Aftclr B001C Disch Temp High (Alarm On)

aoP52-R600 Service Air Pressure 5 Min.

aoP51-R600 Control Air Pressure NOTE: SSAC 2B will fail to auto start on lowering pressure. Event Trigger (EGP51-2) will remove this failure when SSAC 2B is manually started.

SIMULATOR OPERATOR:

When the operator dispatches a SO locally , wait 2 minutes, then NOTIFY operator that local temp on 2P51-R312C is 125°F and 2P51-R302C is reading 385°F.

If requested by operator, report standby SSAC oil levels are normal and Aftercooler/Intercooler drains have been cycled.

Responds to annunciator CONTROL BLDG AFTCLR B001C DISCH TEMP HIGH, (700-216):

Sends SO to locally confirm temperature is > 120 degrees F on 2P51-R312C and 2P51-R302C.

BOP

Starts the 2A and/or 2B Service Air Compressor.

Secures the 2C Service Air Compressor by placing its control switch in Pull-to-Lock when the local report is given or earlier as directed by the SRO.

Dispatches SO/Maintenance to investigate high temperature alarm.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 4 Page 9 of 29 Event

Description:

2C SSAC high temp condition and secured. 2A & 2B SSACs are manually started.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR: When the operator secures the 2C Service Air Compressor, ENSURE Event Trigger (EGP51-1) is ACTIVATED:

DELETES the following:

aoP52-R600 Service Air Pressure

aoP51-R600 Control Air Pressure mf70022407 Control Bldg Aftclr B001C Disch Temp High (Annunciator On) 30 seconds later.

Annunciator CONTROL BLDG AFTCLR B001C DISCH TEMP HIGH, BOP (700-216) clears.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 5 Page 10 of 29 Event

Description:

A leak develops from the HPCI Torus suction line downstream of 2E41-F051 and can be isolated by closing 2E41-F051.

Time Position Applicant's Actions or Behavior Simulator Operator, at Chief Examiners direction, ACTIVATE (RB-5) 12 Min Torus leak at (3/4 inch) 0.75 inch/min) svoT48140 (70/.75), svoT48142 (50/10), svoT48143 (50/10), svoT48147 (50/10), svoT48148 (50/100)

The following annunciators are received:

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

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

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

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

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

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

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

ALL

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

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

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

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

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

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

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

BOP

Directs SO/Maintenance to investigate the leak.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 5 Page 11 of 29 Event

Description:

A leak develops from the HPCI Torus suction line downstream of 2E41-F051 and can be isolated by closing 2E41-F051.

Time Position Applicant's Actions or Behavior

Directs BOP to 2H11-P657 panel.

SRO

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

Simulator Operator:

Four minutes after being dispatched to check for leaks in the Torus section of the Reactor Building, report to the crew:

A leak has been identified on the HPCI suction line and I cant tell where the leak is exactly.

TORUS WATER LEVEL HIGH/LOW, (602-235) annunciates ALL

Recognizes that Torus level is decreasing.

Dispatches personnel to determine the location of the Torus leak.

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

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

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

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

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 5 Page 12 of 29 Event

Description:

A leak develops from the HPCI Torus suction line downstream of 2E41-F051 and can be isolated by closing 2E41-F051.

Time Position Applicant's Actions or Behavior

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

Dispatches personnel to the Torus AND SE Diagonal to determine source of leakage.

ATC

Notifies SRO of ECCS TS requirements when closing valves.

Closes 2E21-F019B, Torus Suction Vlv.

Closes 2E11-F065B, Torus Suction Vlv.

Closes 2E11-F065D, Torus Suction Vlv.

Simulator Operator: ENSURE Event Trigger EGE41-4 MODIFIES the following when 2E41-F051 is closed:

svoT48140 (r:0.0), svoT48142 (0/10), svoT48143 (0/10), svoT48147 (0/10),

svoT48148 (0/10)

Checks Torus water level and determines the Torus level is continuing to decrease with the above valves closed ATC

Closes 2E41-F051, HPCI Torus Suction Vlv.

Opens 2E21-F019B, Torus Suction Vlv.

Opens 2E11-F065B, Torus Suction Vlv.

Opens 2E11-F065D, Torus Suction Vlv.

Checks Torus water level and determines the Torus level has stopped decreasing ATC

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

Notifies SRO that the Torus leak stopped after 2E41-F051 was closed.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 5 Page 13 of 29 Event

Description:

A leak develops from the HPCI Torus suction line downstream of 2E41-F051 and can be isolated by closing 2E41-F051.

Time Position Applicant's Actions or Behavior

Reviews TS 3.6.2.2, Suppression Pool Water Level.

IAW TS 3.6.2.2 Condition A.

Must restore within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

Reviews TS 3.5.1, ECCS/RCIC.

SRO

IAW TS 3.5.1 Condition C,

Declares HPCI inoperable,

Must verify within one hour that RCIC is operable by administrative means.

Must restore HPCI to operable status within 14 days.

NOTE: This TS would be appropriate if the applicant elects to perform 31EO-EOP-100-2, Section 4.7 to override high Torus level suction

Reviews TS 3.3.5.1, ECCS Instrumentation.

IAW TS 3.3.5.1 Condition D, SRO

Only applicable if HPCI is not aligned to the Suppression Pool, Declares HPCI inop within one hour.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 6 Page 14 of 29 Event

Description:

Recirc Pump A seal leakage causes DW leakage. Pump is secured and isolated Time Position Applicant's Actions or Behavior Simulator Operator, with Chief Examiners Permission:

12

Call control room BOP operator and tell them to stay on the phone Min until directed to hang up.

ACTIVATE: (RB-6) to start Recirc Pump 2A seal leakage, mfB31_39A Final 100, Ramp of 10

Receives Annunciator, PUMP A SEAL STAGING FLOW HIGH/LOW, (602-122) in approximately 3 minutes.

Observes and compares 2B31-R603A, Seal A No. 1 pressure indicator, AND 2B31-R602A, Seal A No. 2 pressure indicator, to determine the Inner (#1) seal has failed (No. 1 pressure normal with No. 2 pressure >

normal).

ATC

Notifies SRO that the Inner (#1) Seal on Recirc A has failed.

Directs a System Operator to confirm seal water flow to Pump A is between 1.6 to 2.2 gpm locally (this indication not available in the Control Room).

Assigns an extra operator to perform 34SV-SUV-019-2, Surveillance Checks, to determine the magnitude of leakage.

May monitor Drywell pressure.

Simulator Operator, After the ATC operator has started executing steps in the Pump A Seal Staging Flow High/Low ARP, THEN Instruct the BOP operator to hang up the phone.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 6 Page 15 of 29 Event

Description:

Recirc Pump A seal leakage causes DW leakage. Pump is secured and isolated Time Position Applicant's Actions or Behavior Simulator Operator; After 3 minutes from 602-122, NOTIFY the Chief Examiner AND then press (RB-1) to ACTIVATE: mfB31_45A (10/20), Recirc A Outer Seal Failure.

(**IMPORTANT**)

Ensure the ATC responds to the Outer Seal A Leak Detection Flow High, (602-116) and performs the next set of actions (Trip and isolate the 2A Recirc Pump). ENSURE the BOP operator is the person assigned to vent the Drywell.

Receives Annunciators:

OUTER SEAL A LEAK DETECTION FLOW HIGH, (602-116).

DRYWELL/TORUS RCDR R627 TEMP HIGH, (650-204).

ALL

PANEL 2H11-P654 SYSTEM TROUBLE, (650-214).

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

DRYWELL FLOOR DRAINS SUMP LEAK HIGH-HIGH, (602-408).

Observes and compares 2B31-R603A, Seal A No. 1 pressure indicator AND 2B31-R602A, Seal A No. 2 pressure indicator, to determine the outer seal has now failed (No. 1 and No. 2 seal pressure decreases).

Notifies SRO that the Outer (#2) Seal on 2A Recirc has also failed.

Has an extra operator perform 34SV-SUV-019-2, Surveillance Checks, to determine magnitude of leak.

ATC

Monitors 2D11-R630, Fission Products Monitor recorder, to determine IF primary system coolant is leaking from seals.

Monitors Drywell pressure.

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

MULTIPOINT TEMPERATURE RCDR 2T47-R626 TEMPERATURE HIGH (657-025).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 6 Page 16 of 29 Event

Description:

Recirc Pump A seal leakage causes DW leakage. Pump is secured and isolated Time Position Applicant's Actions or Behavior

Receives the following alarms

PRIMARY CONTAINMENT PRESS HIGH, (603-115).

ALL

DRYWELL FLOOR DRAINS SUMP LEAK HIGH, (602-408).

Directs Operator to Check DW Leakage.

SRO

Directs the BOP to vent the DW with SBGT, when DW pressure approaches 0.65 psig.

Simulator Operator; As the operator checking DW leakage, report:

DW Equipment drain leakage is stable at 1.7 gpm

Floor drain leakage has increased from 0.8 gpm to 12.1 gpm.

SIMULATOR OPERATOR; If the crew inserts a Reactor Scram during Event 5, PROCEED to Major Event 7.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 6 Page 17 of 29 Event

Description:

Recirc Pump A seal leakage causes DW leakage. Pump is secured and isolated Time Position Applicant's Actions or Behavior SRO

Directs BOP to Vent the DW using both Loops of CAD.

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

These steps assume the Placard is used. The 2A or 2B CAD Loop valves will be used first.

IAW 34SO-T48-002-2, Placard, the BOP performs the following:

Opens 2T48-F334A and/or 2T48-F334B

The following alarms will be received:

DRYWELL VENT EXHAUST BYPASS VALVES OPEN, (657-008).

DRWL/TORUS N2 M/U 2 INCH ISOL VALVES OPEN, (657-042).

DRYWELL VENT EXHAUST BYPASS VALVES OPEN, (654-002).

BOP

DRWL/TORUS N2 M/U 2 INCH ISOL VALVES OPEN, (654-035).

Opens 2T48-F335A and/or 2T48-F335B.

Opens 2T48-F336A and/or 2T48-F336B using 2T48-R615A and/or R615B, Drywell Flow Controller for F336A and/or F336B.

Monitors DW pressure .

Confirms Drywell and Torus O2 concentration is <4%, on 2P33-R603,Pri Cnmt Oxygen Recorder (P602) OR by lab sample.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 6 Page 18 of 29 Event

Description:

Recirc Pump A seal leakage causes DW leakage. Pump is secured and isolated Time Position Applicant's Actions or Behavior

Per (602-116) and 34SO-B31-001-2, Recirc System, Performs one of the following to secure the Reactor Recirc Pump:

Either (actions for Immediate Shutdown)

Place the ASD A control switch in Pull to Lock (P602).

Depress the ASD A Shutdown pushbutton (P602).

OR (Actions for Shutdown in a Timely Manner)

Depress the ASD A Shutdown pushbutton (P602).

Confirm ASD A speed ramps to ~370 RPM (2B31-R660) or 22%

(2B31-R661).

Confirm Recirc Pump A goes to 0 RPM (2B31-R660) or 22%

ATC (2B31-R661) and drive coasts to 0 gpm (2B31-R614 or R617).

Confirm ASD A Start pushbutton illuminates.

Place ASD A control switch 2B31-S002A to Pull-To-Lock (P602).

Closes 2B31-F031A, Reactor Recirc A Pump Disch Vlv .

Closes 2B31-F023A, Reactor Recirc A Pump Suction Vlv .

Dispatches SO to close Seal Injection To Pump A Header Isolation Valve, 2B31-F008A.

Enters 34AB-B31-001-2 Reactor Recirculation Pump(s) TRIP, Recirc Loops Flow mismatch, Or ASD Cell Bypass.

Notify Plant Management and Load Dispatcher.

Receives and Acknowledges the following Annunciators:

RECIRC LOOP A OUT OF SERVICE, (602-127).

ASD A TRIP WARNING, (602-101).

ASD A TROUBLE, (602-108).

ATC

ASD A FATAL FAULT, (602-102).

RBM DOWNSCALE, (603-211).

ROD OUT BLOCK, (603-238).

HEATER TROUBLE ALARM, (650-135) (may come in and clear).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 6 Page 19 of 29 Event

Description:

Recirc Pump A seal leakage causes DW leakage. Pump is secured and isolated Time Position Applicant's Actions or Behavior NOTE TO EXAMINER:

SRO may direct exiting the Region of Potential Instabilities and a follow-up question may be needed to address Tech Spec requirements.

Directs operator to shutdown and isolate Recirc pump A

Enters Tech Specs:

3.4 Reactor Coolant System.

3.4.1 Recirculation Loops Operating

Condition: 3.4.1.A, Requirements of the LCO not met.

(i.e. single loop operations).

Required Action: Satisfy requirements of the LCO.

Completion time: 24 hrs.

SRO

Condition: 3.4.4.A, Unidentified leakage not within limit OR total leakage not within limit.

Required Action: Reduce leakage to within limits.

Completion time: 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Condition 3.4.4.B, Unidentified leakage increase not within limit.

Required Action: Reduce leakage increase to within limits.

Completion time: 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Notifies STA or Reactor Engineering that new limits apply for APLHGR, MCPR, LHGR, and APRMs Simulated Thermal power - New Setpoints are required within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 6 Page 20 of 29 Event

Description:

Recirc Pump A seal leakage causes DW leakage. Pump is secured and isolated Time Position Applicant's Actions or Behavior Simulator Operator; AFTER the suction and discharge valves are closed for the 2A Recirc pump, and you are requested to close 2B31-F008, THEN:

AND THEN press (RB-9) to ACTIVATE:

rfB31_29, Recirc mini purge B31-F016A closure (simulates B31-F008A being closed)

mf60213160, Outer Seal A Leak Detection Flow High - Annunciator Off (602-116)

AND THEN REPORT that 2B31-F008A is closed.

Simulator Operator; If another DW leakage check is requested, report:

Drywell floor drain leakage has decreased to 1.8 gpm.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 7 Page 21 of 29 Event

Description:

Loss of Offsite Power with EDGs failures.

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

ALL Recognize a Loss Of Offsite Power.

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

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

SRO

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

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

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

Assigns the ATC to perform RC-1.

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

If time allows assigns TC-1 to be performed.

SRO

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

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

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 7 Page 22 of 29 Event

Description:

Loss of Offsite Power with EDGs failures.

Time Position Applicant's Actions or Behavior

Performs RC-1 consisting of:

Inserts a manual scram.

Places the mode switch to shutdown.

Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display.

ATC

Notifies the SRO of rod position check.

Places SDV isolation valve switch to "isolate" & confirms closed.

Inserts SRMs and IRMs.

Shifts recorders to read IRMS, when required.

Ranges IRMS to bring reading on scale.

Notifies the SRO when the above actions are complete.

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

BOP

Checks ECCS Injection Systems and verifies no initiation signal present.

Performs RC-3 consisting of:

Monitor RPV pressure.

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

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

Maintain RPV pressure between 1074 and 800 psig.

Notify SRO that LLS is the pressure control system.

Simulator Operator, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 8 Page 23 of 29 Event

Description:

2C EDG auto starts but fails to tie/must lower then raise frequency to energize bus (fails to auto tie), 1B EDG will NOT run & 2A EDG will start

& tie after manipulating Start switch.

Time Position Applicant's Actions or Behavior

Directs ATC to address the plant electrical systems and enter the following:

SRO

34AB-R22-003-2, Station Blackout.

34AB-R43-001-2, Diesel Generator Recovery.

The ATC may start first with any of the Diesel Generators.

ATC Reviews EDG 2A annunciators and determines EDG 2A failed to Start.

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

Determines the EDG is not running.

Determines the Auto Start System Operative Light is lit.

Places EDG 2A Start/Stop switch to START.

Confirms EDG 2A has started and tied.

Reports to SRO Bus 2E is now energized.

Reviews EDG 1B annunciators and determines alarms 652-211, Lube Oil ATC Press Low and 652-229, Emergency Engine Shutdown.

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

EDG 1B has a break on the oil pump discharge line IAW 34AB-R43-001-2, Diesel Generator Recovery, for EDG 2C:

Determines the EDG is running.

Confirm Normal and alternate supply breakers OPEN.

ATC

Lowers EDG frequency to 57 Hz, then Raise to 60 Hz. (Critical Task)

Confirms EDG 2G output breaker closed.

Reports to SRO Bus 2G is now energized.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 8 Page 24 of 29 Event

Description:

2C EDG auto starts but fails to tie/must lower then raise frequency to energize bus (fails to auto tie), 1B EDG will NOT run & 2A EDG will start

& tie after manipulating Start switch.

Time Position Applicant's Actions or Behavior The following can be performed in any order.

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

RPS MG Set 2A - restarted.

SSAC 2A local breaker - reclosed.

Division I Station Service Battery Chargers.

(may have been previously performed).

Vital AC Alternate Power Supply returned to service.

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

RPS MG Set 2B - restarted.

RPS Alternate Supply from 2B Essential Cabinet - restarted.

SSAC 2B local breaker - reclosed.

Division II Station Service Battery Chargers.

(may have been previously performed)

Vital AC Battery Charger returned to service.

SRO Once power is restored, may direct operator to place Torus Cooling in service.

Enters 34SO-E11-010-2, Residual Heat Removal or uses placard on 2H11-P601.

Places RHRSW in service.

Prelubes RHRSW B pump.

Overrides 2E11-F068B Low Discharge Pressure Interlock.

BOP

Positions 2E11-F068B to 45% OPEN.

(Placard) - RHR HX B Diff Press Low (601-215) alarms.

Starts RHRSW pump B.

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

Positions 2E11-F068B to obtain < 4400 GPM AND < 450 PSIG.

RHR HX B Diff Press Low (601-215) alarm clears.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 8 Page 25 of 29 Event

Description:

2C EDG auto starts but fails to tie/must lower then raise frequency to energize bus (fails to auto tie), 1B EDG will NOT run & 2A EDG will start

& tie after manipulating Start switch.

Time Position Applicant's Actions or Behavior

Place RHR loop B in Suppression Pool Cooling.

Does NOT position the 2/3 Core Height Permissive switch.

(RWL will NOT be lowered to below 2/3 core height).

Does NOT place the Containment Spray valve Control switch in the manual position. (LOCA signal is not present).

BOP

Confirm open 2E11-F048B, HX Bypass Vlv.

(Placard)

Close 2E11-F047B, Hx Inlet Vlv.

Confirm open 2E11-F003A, HX Outlet Vlv.

Start RHR pump 2B.

- SEC System Auto Initiation Signal Present (650-234) alarms.

- Auto Blow Down CS or RHR Press Permissive (602-312) alarms.

- RHR Flow Low (601-215) alarms.

Open 2E11-F028B, Torus Spray or Test Vlv.

Throttle open 2E11-F024B, Full Flow Test Line Vlv. and establish RHR flow of less than or equal to 7700 gpm (R603B).

- RHR Flow Low (601-215) alarm clears.

Open 2E11-F047B, Hx Inlet Vlv.

Close 2E11-F048B, Hx Bypass Vlv.

Reports to SRO that RHR has been placed in Suppression Pool Cooling mode.

Simulator Operator, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-04 Event No.: 9 Page 26 of 29 Event

Description:

HPCI 2E41-F001 stuck closed, RCIC 2E51-F013 Fails to Auto Open requiring manual operation of 2E51-F013 to inject prior to RWL reaching -

180 Time Position Applicant's Actions or Behavior The malfunction for this event was in at the beginning of the scenario (rfE51_234 Final Value of BYPASS). The operator may start RCIC OR HPCI first; either is acceptable, however 2E41-F001 is stuck closed, making HPCI unavailable.

Starts RCIC for level control by performing the following at 2H11-P602 BOP panel:

Depresses RCIC Manual Initiation P/B.

Confirms/Opens 2E51-F046.

Confirms/Starts Barom Cndsr Vac Pump.

Confirms/Opens 2E51-F045.

Confirms/Opens 2E51-F019.

Confirms/Closes 2E51-F019 at flow > 79.3 gpm.

Realizes 2E51-F013 did not auto open.

Opens 2E51-F013 (Critical Task to maintain RWL >-180 inches).

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

Starts HPCI for level control by performing the following at 2H11-P602 panel:

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

Starts 2E41-C002-2, Barometric Condenser Vacuum Pump.

BOP

Realizes 2E41-F001, Turbine Steam Supply Vlv, will not open.

Takes 2E41-C002-3, Aux Oil Pump, control switch to the START position. (May place switch in Pull To Lock Off)

As time allows, notifies Maintenance of 2E41-F001 failure.

Informs SRO of 2E41-F001 failure.

With Chief Examiners Permission, the Scenario will be terminated when Reactor water level is controlled in band and One Emergency bus is energized or as directed by the Chief Examiner.

Page 1 of 27 Appendix D Scenario Outline Form ES-D-1 NRC FINAL Facility: E. I Hatch Scenario No.: 10-05 Op-Test No.: 2016-301 Examiners: Operators: SRO RO BOP Initial Conditions. Unit 2 is operating at approximately 5% RTP preparing to swap Steam Packing Exhausters IAW step 7.3.1 of 34SO-N33-001-2. 2B21-F013M is inop for its mechanical lift setpoint, RAS written.

Turnover: Continue with the Startup IAW 34GO-OPS-001-2 at step 7.4.1.

Event Malf. No. Event Event No. Type* Description 1 Swap operating Steam Packing Exhausters IAW step 7.3.1 of N/A N (BOP) 34SO-N33-001-2.

2 N/A R (ATC) Withdraw Control Rods to increase power.

3 Reactor Building Exhaust fan failure with the Standby Exhaust mfT41_147 C (BOP) fan failing to start. Standby Exhaust fan manually started or SBGT fan started to re-establish Rx. Bldg. dP. (Critical Task) 4 CRD Flow Controller fails in Auto requiring manual operation mfC11_299 C (ATC) to re-establish CRD flow.

loE21-C001AG1 5 loE21-C001AR2 diE21-C001A TS (SRO) CS pump 2A DC breaker tripped and cannot be reclosed.

loE21-C001A_SIW1 6 C (BOP) HPCI Room fire N/A TS (SRO) 7 mfN21_88B I (ATC) Feedwater pump 2B cooling water controller failure.

8 The Backup SDV valves will close due to a small air leak on rfC11_141 TS (SRO) 2C11-F040 requiring the SRO declare a TS Required Action Statement.

9 Circ Water Leak Causing Con Bay Flooding/Loss of N71_70 M(ALL)

Vacuum/Loss of CRD pumps loB21-F022BG1 10 loB21-F022BR2 loB21-F022BMG1 loB21-F022BMR2 loB21-F028BG1 BPV #3 Main Turbine Bypass Valve fails 25% open, B MSL loB21-F028BR2 loB21-F028BMG1 C (BOP) fails to isolate automatically on low vacuum, manual isolation loB21-F028BMR2 required. (Critical Task) loB21-F022B_AC1 loB21-F022B_DC1 loB21-F028B_AC1 loB21-F028B_DC1

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

Page 25 of 27 NRC FINAL Scenario Summary Facility: E. I Hatch Scenario No.: 10-05 Op-Test No.: 2016-301 Initiating Conditions: Unit 2 is operating at approximately 5% preparing to swap Steam Packing Exhausters per step 7.3.1 of 34SO-N33-001-2. 2B21-F013M is inop for its mechanical lift setpoint, RAS written.

Turnover Continue with the Startup IAW 34GO-OPS-001-2 at step 7.4.1.

Summary:

Event 1: Normal; Swap Steam Packing Exhausters IAW 34SO-N33-001-2, Seal Steam System.

Event 2: Pull control rods to continue Startup to ~ 9% power, raise pressure set to 920.

Event 3: Component; Reactor Building Exhaust fan failure with the Standby Exhaust fan failing to start. The operator takes manual control to place the Standby Exhaust fan or SBGT in service to re-establish the required Reactor Building dP. (Critical Task)

Event 4: Component; CRD Flow Controller fails closed causing a loss of normal CRD flow.

The ATC will place the controller in manual and restore CRD flow.

Event 5: TS; CS pump 2A DC breaker tripped and cannot be reclosed.

Event 6: Component; HPCI Room Fire.

Event 7: Instrument; Feedwater pump 2B cooling water controller will fail requiring the ATC to maintain cooling water manually.

Event 8: TS; The Backup SDV valves will close due to a small air leak on 2C11-F040 requiring the SRO declare a TS Required Action Statement.

Event 9: Major; Condenser Bay Flooding is received which de-energizes 4160V 2A & 2B, requiring the operator to insert a manual scram. B MSL fails to automatically close; manual works.

Event 10: B MSL fails to isolate automatically on low vacuum, manual isolation required.

(Critical Task)

Page 26 of 27 NRC FINAL Critical Task List Facility: E. I Hatch Scenario No.: 10-05 Op-Test No.: 2016-301 Critical Tasks

Standby Exhaust fan manually started or SBGT fan started to re-establish Rx Bldg dp. (Event 3)

B MSL fails to isolate automatically on low vacuum, manual isolation required to prevent release to Turbine Building. (Event 10)

ES 301-4 Attributes Required Actual Items

1. Total Malfunctions 5-8 6 1. Reactor Building Exhaust fan failure (Event 3)

2. CRD Flow Controller fails closed (Event 4)

3. HPCI room fire (Event 6)

4. RFP 2B cooling water failure (Event 7)

5. Condenser Bay flooding (Event 9)

6. MSIV line fails to isolate (Event 10)

2. Malfunctions After 1-2 1 1. MSIV line fails to isolate (Event 10)

EOP Entry

3. Abnormal Events 2-4 3 1. 34AB-T22-002-2, Loss of Sec Cont Integrity (Event 3)

2. 34AB-X43-001-2, Fire Procedure, (Event 6)

3. 34AB-C71-001-2, Scram Procedure (Event 9)

4. Major Transients 1-2 1 1. Condenser Bay Flooding-Scram (Event 9)

5. EOPs entered, 1-2 1 1. RC (Non-ATWS) (Event 9) requiring substantive actions

6. EOPs contingencies 0-2 0 1. None requiring substantive actions

7. EOP Based 2-3 2 1. Stby Exh fan manually started or SBGT fan Critical Tasks started to re-establish Rx Bldg dp. (Event 3)

2. B MSL fails to isolate automatically on low vacuum, manual isolation required to prevent release to Turbine Building. (Event 10)

ILT-10 NRC Operating Exam Scenario 5 SHIFT TURNOVER Safety Focus UNIT 1 STATUS Plant Conditions: Unit 1 is operating at 100% power Activities in progress: Maintaining Rated Thermal Power UNIT 2 STATUS Plant Conditions: Unit 2 is operating at approximately 5% preparing to swap Steam Packing Exhausters per step 7.3.1 of 34SO-N33-001-2.

FWLC System is operating in Single element Mode.

2B21-F013M is inop for its mechanical lift setpoint, RAS written.

Protected Train: EOOS:

Division I Green Orange Division II Yellow Red Scheduled evolutions: Continue with the Startup IAW 34GO-OPS-001-2 at step 7.4.1.

Continue with control rod withdrawal at Step 31 (06-23).

When Step 31 rods are at position 24, Continuous Rod withdrawal is allowed.

Surveillances due this None shift:

Inop Equipment: 2B21-F013M is inop for its mechanical lift setpoint.

Active tagouts: Normal Supply Breakers to 4160V 2A, 2B, 2C & 2D Rod Configuration: See RWM

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 1 Page 2 of 27 Event

Description:

Swap Steam Packing Exhausters IAW 34SO-N33-001-2, Seal Steam System.

Time Position Applicant's Actions or Behavior

Places 2N33-C001 Stm Pkg Exh Blower 2A Control Switch to the OFF position.

Opens 2N33-F025B, SPE Blower Disch Vlv, UNTIL Red OPEN 3 Min BOP indicating light ILLUMINATES.

Places 2N33-C001 Stm Pkg Exh Blower 2B the Control Switch to the RUN.

Throttles OPEN 2N33-F025B, SPE Blower Disch. Vlv, UNTIL Steam Packing Exhauster Vacuum indicates between 10-20 inches of water vacuum as read on 2N33-R601B.

Closes 2N33-F025A, SPE Blower Disch Vlv.

Places the control switches in STOP for 2N33-F025A & B.

Simulator Operator enters the next event after surveillance is complete OR at the Chief Examiners request.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 2 Page 3 of 27 Event

Description:

Withdraw control rods to ~9% power and transfer the Reactor Mode Switch to Run Time Position Applicant's Actions or Behavior 12 SRO Directs ATC to continue rod withdrawal (06-23) to approximately 9% power Min NOTE: IAW Turnover sheet, Notch withdrawal is used to position 24 and then continuous notch withdrawal is allowed.

Starting at Step 31, withdraws all control rods within a step to the withdraw limit.

ATC

Initials for control rod withdrawal.

Dates for control rod withdrawal.

Notifies SRO that reactor power is approximately 9%.

Directs:

SRO

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

BOP confirm operable APRM DOWNSCALE trips are clear .

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

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

Depress the ETC key.

BOP

UNTIL TRIP STATUS option ILLUMINATES.

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

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

Confirms no IRMs are UPSCALE by observing:

2H11-P606 upscale lights not illuminated OR BOP/ATC

2H11-P603 upscale lights not illuminated OR

2H11-P603 annunciator 603-221, IRM Upscale not illuminated.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 2 Page 4 of 27 Event

Description:

Withdraw control rods to ~9% power and transfer the Reactor Mode Switch to Run Time Position Applicant's Actions or Behavior Confirms APRM/OPRM Operability:

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

AND

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

AND SRO

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

Confirms surveillances are current:

57SV-C51-001-0, APRM Functional Test.

57SV-C51-005-0, APRM Calibration.

57SV-C51-003-0, APRM Two Out of Four Logic Module FT.

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

Simulator Operator: If contacted for APRM status, inform the SS all APRMs are operable and all surveillances are current.

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

SRO

603-232, MAIN STEAM LINE PRESS A LOW.

603-233, MAIN STEAM LINE PRESS B LOW.

ATC If directed, reports annunciators 603-232 and 603-233 are clear.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 3 Page 5 of 27 Event

Description:

Reactor Building Exhaust fan (2T41-C007A) failure, broken coupling.

Time Position Applicant's Actions or Behavior 15 At Lead Evaluators direction the Simulator Operator ENTERS (RB-3)

Min mfT41_147, Rx Bldg Exhaust Fan A fails & standby does not auto start On the 2H11-P650 panel alarms 650-214, Panel 2H11-P654 Panel System Trouble and 650-224, Panel 2H11-P657 Panel System Trouble are received.

BOP

Announces the alarm to the SRO.

The SRO repeats the alarm and dispatches the BOP operator to the SRO 2H11-P654 & P657 panels.

NOTE: This failure will require entry into the SC EOP Flow Chart as well as two Abnormal procedures. The success path is to restore Rx.

Bldg Ventilation or place SBGT in service.

When the operator enters 657-081, then the following actions will be addressed to place Rx Bldg Exhaust Fan back in service.

Acknowledges 657-081, RB Exhaust Fan 2T41-C007A/B Flow Low BOP alarm and enters 657-081.

Confirms the Standby Rx Bldg Vent Exhaust Fan has not automatically started the operator will place the control switch for 2T41-C007A to OFF AND 2T41-C007B to Run.

Confirm the following dampers are OPEN:

2T41-F044A, R/B Inboard Isol Dampers Inacc. Areas Exhaust Fans Disch on 2H11-P657.

2T41-F044B, R/B Outboard Isol Dampers Inacc Areas Exhaust Fans Dish on 2H11-P654.

2T41-F028, Rx Bldg Vent Filter D005 Inlet Damper on 2H11-P657.

Confirm RB Exhaust flow on 2T41-R618 point 2 is indicating approximately 6.5 KCFM.

Once RB Exhaust and Supply flows have stabilized, confirms 654-001, RB Inside To Outside Air Diff Press Low, clears and notifies SS.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 3 Page 6 of 27 Event

Description:

Reactor Building Exhaust fan (2T41-C007A) failure, broken coupling.

Time Position Applicant's Actions or Behavior NOTE: If 657-081 actions are not performed, crew would enter 34AB-T22-003-2 and 31EO-EOP-014-2, SC flowchart. Operators would secure Rx Bldg Ventilation IAW 34SO-T41-005-2 and place SBGT in service IAW 34SO-T46-001-2 (Placard).

Enters 34AB-T22-003-2, Secondary Containment Control.

Monitors secondary containment parameters.

Notifies the SS to enter 31EO-EOP-014-2, EOP Secondary BOP Containment flowchart due to low RB dp.

Dispatches a SO/Maint to investigate the low RB dp.

Enters 34AB-T22-002-2, Loss of Secondary Containment Integrity.

Simulator Operator, at Chief Examiners direction, move on to the next Event

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 4 Page 7 of 27 Event

Description:

CRD Flow Controller fails in Auto requiring manual operation to re-establish CRD flow.

Time Position Applicant's Actions or Behavior 10 Min At the Chief Examiners direction, Simulator Operator ENTERS (RB-4),

mfC11_299.

Receives CRD HYD TEMP HIGH, (603-140) alarm.

Determines that the CRD Flow Control Valve A has closed.

Determines 2C11-R600, CRD Flow Controller, output is at minimum and ATC has failed downscale.

Notifies SRO that the CRD Flow Controller has failed downscale.

Notifies I & C (if SRO does NOT) to investigate 2C11-R600.

NOTE: The ATC may immediately place the controller in manual IAW 31GO-OPS-021-0, Manipulation and Control of Equipment OR NMP-OS-007-001, Conduct of Operations Standards and Expectations, responding to a failed controller.

Enters:

CRD HYD TEMP HIGH, (603-140).

34AB-C11-001-2, Loss Of CRD System.

ATC

IAW 31GO-OPS-021-0, Places 2C11-R600 controller in Manual.

Increases output of controller until CRD flow is approximately 50 gpm.

Dispatches I & C to investigate 2C11-R600.

SRO

Dispatches a SO to monitor CRD drive temperatures.

Directs operator to perform actions of the ARP and 34AB-C11-001-2.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 5 Page 8 of 27 Event

Description:

CS pump 2A DC breaker tripped and cannot be reclosed.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR, with Chief Examiners direction, DEPRESSES 11 min RB-11 (turns green light off to CS 2A & places pump switch to off), then NOTIFIES the Shift Supervisor, as the SO on Outside rounds, that the DC Control power breaker for Core Spray pump 2A is tripped.

Directs BOP/ATC to confirm CS 2A light status on 2H11-P601 panel.

SRO

Notifies Maintenance to investigate tripped breaker.

Refers to TS for CS 2A being INOP.

3.5 ECCS and RCIC System.

SRO

3.5.1 ECCS Operating.

Enters a 7 day RAS per TS 3.5.1.A.1 to restore low pressure ECCS injection/spray subsystem to OPERABLE status.

SIMULATOR OPERATOR, if directed to reclose DC Control Power breaker for CS 2A, REPORT the DC Control Power breaker will not stay closed.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 6 Page 9 of 27 Event

Description:

HPCI Room Fire.

Time Position Applicant's Actions or Behavior Simulator Operator; Prior to placing the Mode Switch to the Run position AND with Chief 11 min Examiners direction, NOTIFY the Shift Supervisor, as the SO on rounds, that heavy smoke is coming from the Unit 2 HPCI room and you cannot see what is actually burning. You are leaving the area.

Directs BOP to enter 34AB-X43-001-2, Fire Procedure, and make the SRO announcement.

NOTE: Operator performing Section 4.0 will be making appropriate notifications below.

Enters 34AB-X43-001-2, Fire Procedure, and performs the following:

Sounds the fire alarm (SIREN) over the plant PA system, (repeats 2 times - may get U1 operator to handle repeats).

BOP

Notifies Rad Waste Control room that Reactor Building floor drain sump pumps are in Automatic.

Notifies Radiation Protection to respond to the fire area.

Notifies Security to merge the Plant PA system.

Transitions to section 8.0 for Fire in Reactor Bldg.

Stops the following equipment at Panels 2H11-P654 & P657:

2T41-C001A, Rx Bldg Supply Fan.

2T41-C001B, Rx Bldg Supply Fan.

2T41-C007A, Rx Bldg Exhaust Fan.

2T41-C007B, Rx Bldg Exhaust Fan.

2T41-C002A, Refuel Flr Vent Supply Fan.

2T41-C002B, Refuel Flr Vent Supply Fan.

2T41-C005A, Refuel Flr Vent Exh Fan.

2T41-C005B, Refuel Flr Vent Exh Fan.

Acknowledges annunciators at Panels 2H11-P654 & P657:

Refueling Floor Outside Air Diff Press Low (657-001).

RB Inside to Outside Air Diff Press Low (654-001).

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 6 Page 10 of 27 Event

Description:

HPCI Room Fire.

Time Position Applicant's Actions or Behavior

Transitions to section 8.5 for Fire in South Half of Reactor Bldg.

Transitions to section 8.5.6 for Fire in HPCI Room.

Places 2T41-B005A HPCI Pump Rm Cooler in Off, P657.

BOP

Places 2T41-B005B HPCI Pump Rm Cooler in Off, P654.

Places HPCI Aux Oil pump in PTL Off, P601.

Dispatches a SO to open Brkr 6 in 2R25-S002.

Simulator Operator When directed to open Brkr 6 in 2R25-S002, insert malfunctions mfE41_235A and mfE41_235B (RB-5).

Closes the following HPCI Valves on P601.

2E41-F002, HPCI Isolation Valve.

2E41-F003, HPCI Isolation Valve.

2E41-F041, HPCI Torus Suction Valve.

2E41-F042, HPCI Torus Suction Valve.

Simulator Operator, Once the above HPCI valves are closed, NOTIFY the Shift Supervisor that the fire in the HPCI room is OUT. A storage locker under the stairwell was on fire. We put out the fire without spraying water on any HPCI components. Ventilation and HPCI can be restored to normal.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 6 Page 11 of 27 Event

Description:

HPCI Room Fire.

Time Position Applicant's Actions or Behavior

Announces to the crew the fire is out.

As time allows, directs the operator to leave the HPCI Aux oil pump in PTL Off.

Refers to TS for HPCI INOP.

3.5 ECCS and RCIC System.

3.5.1 ECCS Operating.

Enters a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months RAS per TS 3.5.1.C.1 to verify by admin means RCIC SRO is operable and per TS 3.5.1.C.2 to restore HPCI to operable status within 14 days.

Enters a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months RAS per TS 3.5.1.D.1 to restore HPCI to operable status OR D.2 to restore low pressure ECCS injection/spray subsystem to OPERABLE status.

As time allows, Refer to TRM 3.7.2.D.1, ECCS and RCIC Room Coolers and immediately declares HPCI INOP.

SRO

Orders the Rx Bldg Ventilation system re-started IAW 34SO-T41-005-2.

BOP

Enters 34SO-T41-005-2 and performs the following actions:

Momentarily depresses Rx Bldg Supply Fans Reset.

Momentarily depresses Rx Bldg Recirc Fan 2T41-B017 Reset.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 6 Page 12 of 27 Event

Description:

HPCI Room Fire.

Time Position Applicant's Actions or Behavior Simulator Operator, when requested to perform the following, inform the operator that the Unit 1 pushbuttons have been depressed.

BOP

Requests U1 to depress 1T41/2T41, Rx Bldg/Rf Flr ISOL DMPR RESET A pushbutton, panel 1H11-P657.

Requests U1 to depress 1T41/2T41, Rx Bldg/Rf Flr ISOL DMPR Reset B pushbutton, panel 1H11-P654.

Momentarily depresses 2T41-D005, Reactor Building Filter, Deluge reset.

Opens 2T41-F028, Rx Bldg Vent Filter D005 Inlet Damper.

Confirms Open/Opens 2T41-F044A, Rx Bldg Inboard Isol Dampers Inaccessible Areas Exhaust Fans Disch.

BOP

Confirms Open/Opens 2T41-F044B, Rx Bldg Outboard Isol Dampers Inaccessible Areas Exhaust Fans Disch, panel 2H11-P654.

Places in RUN 2T41-C007B, Rx Bldg Vent Exhaust Fan.

Places in STBY 2T41-C007A, Rx Bldg Vent Exhaust Fan.

(Fan Broke may be left in off).

Confirms Open/Opens 2T41-F011A, Rx Bldg Inboard Isol Dampers Supply Fans Disch.

BOP

Confirms Open/Opens 2T41-F011B, Rx Bldg Outboard Isol Dampers Supply Fans Disch, panel 2H11-P654.

Places in RUN 2T41-C001A or 2T41-C001B, Rx Bldg Supply Fan.

Places in STBY 2T41-C001B or 2T41-C001A, Rx Bldg Supply Fan.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 6 Page 13 of 27 Event

Description:

HPCI Room Fire.

Time Position Applicant's Actions or Behavior BOP

Dispatches a SO to perform the following:

ADJUST 2T41-FC-R027 to maintain Rx Bldg Vent Exhaust Flow approximately 6.5 KCFM as indicated by the green pen on 2T41-R618, flow recorder, located on 2H11-P657.

ADJUST 2T41-FC-R022 to maintain Rx Bldg Vent Supply Flow approximately 5.3 KCFM as indicated by the red pen on 2T41-R618, flow recorder, located on 2H11-P657.

While maintaining approximately 6.5 KCFM for Rx Bldg Vent Exhaust Flow and 5.3 KCFM Bldg Vent Flow respectively,

ADJUSTS Flow Controllers 2T41-FC-R027 and 2T41-FC-R022 to obtain 0.25 inches water pressure on 2T46-DPR-R604A&B.

BOP

Informs the SRO that the Rx Bldg dp has returned to normal.

Orders the RF Floor Ventilation system re-started IAW SRO 34SO-T41-006-2.

Simulator Operator, when requested to perform the following, inform the operator that the Unit 1 pushbuttons have been depressed.

BOP

Requests U1 to depress 1T41/2T41, Rx Bldg/Rf Flr ISOL DMPR RESET A pushbutton, panel 1H11-P657.

Requests U1 to depress 1T41/2T41, Rx Bldg/Rf Flr ISOL DMPR Reset B pushbutton, panel 1H11-P654.

Momentarily depresses Refuel Floor Vent Fans Reset, 2T41-SR2.

Momentarily depress 2T41-PB2, Refueling Floor Exh Fil Train 2T41-D007, Deluge reset.

Momentarily depress 2T41-PB3, Refueling Floor Exh Fil Train 2T41-D008, Deluge reset.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 6 Page 14 of 27 Event

Description:

HPCI Room Fire.

Time Position Applicant's Actions or Behavior Simulator Operator, when requested to perform Refueling Floor Unit Heater Fan positioning and Temperature Indicating Controller setup, INFORM the operator that the Refueling Floor Unit Heater Fan positioning and Temperature Indicating Controller setup has been performed..

Opens 2T41-F004A, Spent Fuel Pool Area Damper.

Opens 2T41-F004C, Refuel Floor Area Damper.

Confirms 2T41-F023A, Refuel Flr Isol Dmprs Exhaust Fans Suction, is OPEN.

BOP

At panel 2H11-P654, confirms 2T41-F023B, Refuel Flr Exh Fans Suction Outboard Isol Damper, is OPEN.

Confirms 2T41-F003A, Refuel Flr Isol Dmprs Supply Fans Disch, is OPEN.

At panel 2H11-P654, confirms 2T41-F003B, Refuel Flr Supply Fans Disch Outboard Isol Damper, is OPEN.

Places 2T41-C005A or 2T41-C005B, Refuel Flr Vent Exh Fan, control switch, in RUN.

Places 2T41-C002A or 2T41-C002B, Refuel Flr Vent Supply Fan, control switch, in RUN.

BOP

Places 2T41-C005B or 2T41-C005A, Refuel Flr Vent Exh Fan, control switch, in STBY.

Places 2T41-C002B or 2T41-C002A, Refuel Flr Vent Supply Fan, control switch, in STBY.

BOP Dispatches SO to perform the following:

Adjust 2T41-R032 and 2T41-R037, Flow Controllers, to obtain approximately 30 KCFM through 2T41-C002A or 2T41-C002B, Refueling Floor Supply Fan, and 2T41-C005A or 2T41-C005B, Refueling Floor Exhaust Fan.

Adjust 2T41-R032 or 2T41-R037, Flow Controllers, to obtain 0.25 inches water negative pressure on the Refueling Floor as indicated on 2T46 DPR R604A and 2T46-DPR-R604B.

BOP

Informs the SRO that the RF Ventilation dp has returned to normal.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 7 Page 15 of 27 Event

Description:

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

Time Position Applicant's Actions or Behavior At the Chief Examiners direction, Simulator Operator, INSTRUCT the BOP 8 Min operator by phone to stay on the line until told to hang up, THEN ENTER:

(RB-6) mfN21_88B, Feedwater Pump Lube Oil Cooling System Failure.

The following alarms will annunciate:

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

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

ALL

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

NOTE: The ATC may immediately place the controller in manual IAW 31GO-OPS-021-0, Manipulation and Control of Equipment OR NMP-OS-007-001, Conduct of Operations Standards and Expectations, responding to a failed controller.

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

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

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

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

ATC

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

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

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 8 Page 16 of 27 Event

Description:

The Backup SDV valves will close due to a small air leak on 2C11-F040 requiring the SRO declare a TS Required Action Statement.

Time Position Applicant's Actions or Behavior Simulator Operator, at the Chief Examiners direction, ENTERS (RB-9) rfC11_141, SDV Outboard Valves close 10 Min AND 3 minutes later ENSURES Event Trigger EGC11-4 ACTIVATES mf60311307, SDV Not Drained, alarm.

When the SDV NOT DRAINED, (603-119), alarm is received, recognizes ALL that the SDV Outboard Valves have closed.

(May recognize prior to alarm by scanning the control boards).

Enters 603-119 and performs the following:

Determines that 2C11-F035A, 2C11-F035B and 2C11-F037 have closed.

Determines status of all Scram Valves (blue lights are not lit) on P603 display.

Determines status of SCRAM VLV PILOT AIR HDR PRESS ATC HIGH/LOW, (603-131), (NOT LIT)

Determines if any Rod Drift lights on P603 (None).

Confirms Scram Disch Vol Isol Test Switch in Normal.

Dispatches SO to the CRD drives to check for leaking Scram Outlet Valves.

Dispatches SO/Maintenance to determine if an air leak exists on the SDV valve piping.

Enters Tech spec 3.1.8 Condition A which requires the SDV line to be isolated within 7 days.

SRO

May inform Maintenance to correct the associated air leak.

Simulator Operator, at the Chief Examiners direction, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 9 Page 17 of 27 Event

Description:

Circ Water Leak Causing Con Bay Flooding/Loss of Vacuum/Loss of CRD pumps Time Position Applicant's Actions or Behavior Simulator Operator: At Lead Evaluators direction, press (RB-7) to 15 min ACTIVATE: mfN71_70, Circulation Water System Leak (0 - 100,000 gpm),

Final 100, Ramp 1000.

All

Recognizes that Condenser Water Box A R602A dP is approaching 0.

As time allows, dispatches a SO to locally investigate the reduced Circ SRO Water dP and for a possible leak.

When 650-164, Condenser Room Flooding, alarm is received, directs the ATC enter 34AB-C71-001-2, Scram Procedure, and scram the reactor.

Assigns the ATC to perform RC-1.

SRO

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

Enters 31EO-EOP-010-2, RC EOP flow chart.

Assigns a RWL band between 3 inches and 50 inches.

Simulator Operator:

Ensure EGC71-1 INSERTS mfN61-73 when mode switch is taken to Shutdown, (Final of 100, Ramp 1000) and svoN37227 BPV#3 to25% open AND EGC71-14 INSERTS overrides both CRD pumps (diC11B-S3A & S3B to STOP).

Performs RC-1 consisting of:

Inserts a manual scram.

Places the mode switch to shutdown.

Confirms all rods are inserted by observing full in lights, SPDS, or the RWM display.

ATC

Notifies SRO of rod position check.

Places SDV isolation valve switch to "isolate" & confirms closed.

If not tripped, places the Recirc pumps at minimum speed.

Inserts SRMs and IRMs.

Ranges IRMS to bring reading on scale.

Notifies the SRO when the above actions are complete.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 9 Page 18 of 27 Event

Description:

Circ Water Leak Causing Con Bay Flooding/Loss of Vacuum/Loss of CRD pumps Time Position Applicant's Actions or Behavior

Performs RC-2 actions consisting of:

Confirms proper Level Control response:

Checks ECCS Injection Systems and secure as necessary.

BOP

Ensures FW Master Controller setpoint reduces to 9 inches and output reduces to 25% of previous value.

IF set down does not auto function, then manually reduces FW Master Controller setpoint to approximately 9 inches.

When feed flow is less than the capacity of the S/U level control valve (§ 1.5 mlbm/hr), then:

Opens 2N21-F125.

BOP

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

Confirms closed 2N21-F110.

At 2H11-P603 maximizes CRD flow by:

May Reset the LOCA pushbuttons for the pump being started.

Places 2C11-R600, CRD Flow Control, in manual at zero output.

Starts CRD pump 2C11-C001A(B).

BOP

Realizes the selected CRD pump will not start.

As time allows, notifies SRO that Both CRD pumps will not start.

As time allows, dispatches SO/Maintenance to investigate Reset the LOCA pushbutton for the Standby CRD Pump.

EXAMINER NOTE: SRVs actuate in LLS at 1120 psig and then control pressure between 850 - 990 psig.

Performs RC-3 consisting of:

Monitor RPV pressure.

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

If necessary, verifies LLS actuates at 1120 psig.

Maintain RPV pressure between 1074 and 800 psig.

Notify SRO of pressure control system operation.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 9 Page 19 of 27 Event

Description:

Circ Water Leak Causing Con Bay Flooding/Loss of Vacuum/Loss of CRD pumps Time Position Applicant's Actions or Behavior

Enters 31EO-EOP-010-2, RC EOP flow chart.

SRO

If time permits, directs the ATC to reset the scram.

ATC

If directed, resets the scram IAW 34SO-C71-001, Scram Procedure.

Starts RCIC for level control by performing the following:

Depresses RCIC Manual Initiation P/B.

Confirms Open 2E51-F046.

BOP

Confirms Start of Barom Cndsr Vac Pmp.

Confirms Open 2E51-F045.

Confirms Open 2E51-F013.

Adjusts RCIC flow controller to maintain RWL.

May direct BOP to unisolate HPCI and place in-service IAW 34SO-E41-001-SRO 2, HPCI System.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 9 Page 20 of 27 Event

Description:

Circ Water Leak Causing Con Bay Flooding/Loss of Vacuum/Loss of CRD pumps Time Position Applicant's Actions or Behavior NOTE: The BOP will perform the following at 2H11-P601 panel.

IAW 34SO-E41-001-2 Section 7.1.4, HPCI System Standby;

Places the Auto Isolation Signal A keylock switch to the RESET position AND returns to NORMAL. (Verifies Auto Isolation Signal white light is EXTINGUISHED).

Places the Auto Isolation Signal B keylock switch to the RESET position AND returns to NORMAL. (Verifies Auto Isolation Signal white light is EXTINGUISHED).

Confirms the following alarms are cleared:

HPCI ISOLATION TRIP LOGIC A INITIATED (601-115).

HPCI ISOLATION TRIP LOGIC B INITIATED (601-121).

Determines which HPCI valve to use:

IF necessary, warm AND pressurize the HPCI Steam Line by performing either:

step 7.1.40.1 (Pressurizing HPCI steam supply with 2E41-F002).

OR step 7.1.40.2 (Pressurizing HPCI steam supply with 2E41-F003).

BOP (Step 7.1.40.1)

Confirms closed 2E41-F002, Inbd Steam Isol Valve.

Opens 2E41-F003, Outbd Steam Isol Valve.

Opens 2E41-F054, Drain Pot Trap Byp Valve.

Slowly throttles open 2E41-F002.

Fully Opens 2E41-F002 when turbine steam inlet pressure (2E41-R602) is within 50 psig of reactor pressure on 2B21-R623A or B (P601 panel), then places control switch to stop position.

HPCI ISOLATION VLV F002/F003 NOT FULLY OPEN, 601-217, will clear.

Closes 2E41-F054, Steam Line Drain Valve when annunciator 601-110, HPCI Turbine Inlet Drain Pot Level High is clear (not expected to be received).

NOTE: 601-110 may not alarm.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 9 Page 21 of 27 Event

Description:

Circ Water Leak Causing Con Bay Flooding/Loss of Vacuum/Loss of CRD pumps Time Position Applicant's Actions or Behavior (Step 7.1.40.2)

Confirms closed 2E41-F003, Outbd Steam Isol Valve.

Opens 2E41-F002, Inbd Steam Isol Valve.

Opens 2E41-F054, Drain Pot Trap Byp Valve.

Slowly throttles open 2E41-F003.

Fully Opens 2E41-F003 when turbine steam inlet pressure (2E41-R602) is within 50 psig of reactor pressure on 2B21-R623A or B (P601 panel), then places control switch to stop position.

HPCI ISOLATION VLV F002/F003 NOT FULLY OPEN, 601-217, will clear.

Closes 2E41-F054, Steam Line Drain Valve when annunciator 601-110, HPCI Turbine Inlet Drain Pot Level High is clear (not expected to be received).

NOTE: 601-110 may not alarm.

Per CP-1:

Order BOP to Inhibit ADS (if not previously done).

Orders BOP to start ALL RHR & Core Spray pumps.

SRO

Orders emergency depressurization once RWL decreases below -155 inches and prior to -180 inches.

Orders all available Table L-1 systems injecting until RWL raises above

-155 inches.

As time permits, directs Torus Cooling to be placed in service.

Starts ALL RHR & Core Spray pumps (P601) by placing switches to start BOP IAW placard.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 9 Page 22 of 27 Event

Description:

Circ Water Leak Causing Con Bay Flooding/Loss of Vacuum/Loss of CRD pumps Time Position Applicant's Actions or Behavior

Opens 7 ADS valves prior to RWL reaching -180 inches by:

Placing switches for the ADS valves to OPEN.

Confirms ALL ADS valve red lights illuminate.

ATC

Confirms ALL ADS valve yellow lights illuminate.

Confirms Reactor pressure is decreasing.

Notifies the SRO that ALL ADS valves are open.

Opens RHR and Core Spray injection valves open once the Reactor Pressure Low 500 psig alarm illuminates.

Verifies injection from Core Spray and RHR pumps begins as soon as BOP reactor pressure decreases below the shut off head of the pumps.

When RWL is restored above Top OF Active Fuel throttles flow for C/S and RHR per the SRO directions.

NOTE: The operator may place torus cooling in service by using the Placard that's available or using the appropriate section of the procedure. These steps assume the Placard is used. The A and/or B loop of RHR may be used depending on Torus temperature. The ATC following steps are written assuming "B" loop and "B" pump is used. If/When "A" loop is used, substitute "A" for "B" for valves and if "B" pump is not used substitute "A", "C", or "D" for "B" pump.

Enters 34SO-E11-010-2, Residual Heat Removal

Places RHRSW in service.

Prelube RHRSW pump.

Overrides 2E11-F068B (A) Low Discharge Pressure Interlock.

ATC

Positions 2E11-F068B (A) to 45% OPEN.

Starts RHRSW pump B (A).

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

Positions 2E11-F068B (A) to obtain < 4400 gpm AND

< 450 psig.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 9 Page 23 of 27 Event

Description:

Circ Water Leak Causing Con Bay Flooding/Loss of Vacuum/Loss of CRD pumps Time Position Applicant's Actions or Behavior

IF desired to start a SECOND RHRSW pump,

Throttles 2E11-F068B (A) to achieve max flow rate (not to exceed 4400 GPM).

ATC

Opens 2E11-F068B (A) an additional 5%.

Starts second RHRSW Pump.

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

Places RHR B (A) Loop in Torus cooling per the placard by performing the following steps:

Opens 2E11-F048B (A).

Closes 2E11-F047B (A).

Opens 2E11-F003B (A).

Starts RHR Loop B (A) pump.

Opens 2E11-F028B (A).

ATC

Receives annunciator Auto Blowdown CS OR RHR Press.

Receives annunciator "SEC System Auto Initiation Signal Present."

Throttles OPEN 2E11-F024B (A).

Opens 2E11-F047B (A).

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

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

May place the second pump in service.

Simulator Operator, PROCEEDS to the next event.

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2016-301 Scenario No.: 10-05 Event No.: 10 Page 24 of 27 Event

Description:

BPV #3 Main Turbine Bypass Valve fails open, B MSL fails to isolate automatically on low vacuum, manual isolation required.

Time Position Applicant's Actions or Behavior SIMULATOR OPERATOR ENSURES EGB21-1 & EGB21-2 for deleting overrides for MSIV lights is ACTIVATED when the 2B21-F022B AND F028B is positioned to close.

Recognizes the B MSL failed to isolate on low condenser vacuum and ALL places both control switches for 2B21-F022B and F028B to close.

Directs operator to place B MSL control switches, 2B21-F022B and SRO F028B, to close and confirm valves indicate close.

Places B MSL control switches, 2B21-F022B and F028B, to close and BOP confirms valves indicate closed. (Critical Task)

As time allows, directs entry into 34AB-N71-001-2, Circulating Water System SRO Failure

Confirms Closed MSIVs.

BOP

Confirms Closed MSL Drains.

Confirms close 2N11-F004A and 2N11-F004B, RSSV's.

With Chief Examiners Permission, the Scenario will be terminated when reactor water is being controlled using RCIC/HPCI or RHR/CS following an Emergency Depressurization, with reactor pressure below 50 psig or as directed by the Chief Examiner.

Page 1 of 13 Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 1 (RO & SRO-I)

Title MOVE CONTROL RODS USING SINGLE NOTCH (STUCK ROD)

Pen and Ink Changes incorporated. Revision conforms to as-administered version of JPM.

Author: Media Number: Time Anthony Ball CR-SIM 1 2016-301 20 Minutes Reviewed By: Date:

N/A N/A Reviewed by Instructional Technologist or designee Date:

N/A N/A Approved By Date Ed Jones 05/30/2016

CR-SIM 1 2016-301 Page 2 of 13 Course Number Program Name Media Number OPERATIONS TRAINING CR-SIM 1 2016-301 Authors Sups Rev. No. Date Reason for Revisions Initials Initials 00 03/10/97 Initial development RAB RSG 01 09/26/97 Revised based on feedback from the 1997 Requal annual exam. SCB DHG 02 09/16/98 Added amplifying instructions for the simulator Operator. SCB DHG 03 01/18/99 Revised malfunction numbers for the new simulator computer. SCB DHG 04 03/21/00 Format modification, change time allowance based on running RAB DHG average, procedure change, correct simulator setup 05 06/01/00 Incorporate instructor comment, change the Group to Step RAB DHG through out the JPM 06 11/03/00 Include objective number RAB DHG 07 03/19/02 Include initial Operator statement RAB RAB 08 01/17/03 Update to current pull sheets & sim model DNM DHG 09 06/27/05 Revised Initial License statement for successful completion RAB RAB 10 06/23/06 Remove Response Cues RAB RAB 11 10/13/08 Step 19 was changed to require double clutch mode of rod JWP RAB movement.

12 10/27/08 Modified setup to match current rod pull sequence. Added type of rod ADY RAB movement double clutch, added clarification of critical task.

12.1 10/17/11 Reviewed JPM against current procedure. Added pass / fail criteria. MMG ALS Added Fundamental question to new Attachment 1. Modified JPM to pull the last two rods in step 25 prior to transferring the Mode Switch to RUN.

12.2 Modified JPM against current procedure. Removed ARB ELJ fundamental question and changed Media # to CR-SIM 1 2016-301 & use on the 2016-301 NRC Exam.

CR-SIM 1 2016-301 Page 3 of 13 Line Contributors The following individuals contributed to the development of this lesson plan.

Rev. No. List of Contributors 12.1 MMG

CR-SIM 1 2016-301 Page 4 of 13 UNIT 1 ( ) UNIT 2 (X)

TASK TITLE: Move Control Rods Using Single Notch (Stuck Rod)

JPM NUMBER:

CR-SIM 1 2016-301 TASK STANDARD:

The task shall be completed when controls rods in the specified sequence have been withdrawn to the required position per 34GO-OPS-065-0.

TASK NUMBER:

001.010 OBJECTIVE NUMBER:

001.010.A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.57 SRO 3.52 K/A CATALOG NUMBER: 201003A201 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.40 SRO 3.60 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 2 34GO-OPS-065-0 (current version) 34AB-C11-003-2 (current version)

REQUIRED MATERIALS: Unit 2 34GO-OPS-065-0 (current version) 34AB-C11-003-2 (current version)

Control Rod Movement Sequence Sheet APPROXIMATE COMPLETION TIME: 20 Minutes SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

CR-SIM 1 2016-301 Page 5 of 13 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to 7%, Xfer to RUN or SNAP 2016-301 JPM CR 1 and leave in FREEZE.

2. INSERT the following MALFUNCTION & EVENT TRIGGER:

MALF # TITLE FINAL RAMP ACT.

VALUE RATE TIME mfC12_22_30_47 Stuck Rod 00000 22_07 EGC11-10 Deletes Stuck Rod

3. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A. Ensure that drive water dP is ~260 psid and stable B. Mark up the Pull Sheet in Step 31 (Student will be pulling the last six rods in this step).

4. PLACE the Simulator in FREEZE until the INITIATING CUE is given.

5. ESTIMATED Simulator SETUP TIME: 15 Minutes NOTE: The simulator Operator will act as second verifier for rod movement and read the pre-job brief to the Operator.

Page 6 of 13 EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. A normal plant startup is in progress per 34GO-OPS-001-2, Plant Startup, and is currently at Step 7.4.3.

2. Rod withdrawal to achieve 6-7% on the APRMs is in progress.

3. There are 6 rods left to withdraw in Step 31 of the Pull Sequence to complete that step.

4. Rod Worth Minimizer is operable and has been loaded with the correct movement sequence, which has been approved by the Reactor Engineering Supervisor.

5. Permission has been granted to use Notch Override in this group of rods.

INITIATING CUES:

Perform Control Rod manipulations IAW Step 31 of Control Rod Movement Sheets.

CR-SIM 1 2016-301 Page 7 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

START TIME:

1. Operator identifies the procedure Operator has identified the correct needed to perform the task. procedure as 34GO-OPS-065-0.

2. Operator reviews the procedures Operator has reviewed the precautions and limitations. precautions and limitations.

3. Operator identifies the materials that Operator has identified the are required. required materials and where to obtain them.

PROMPT: WHEN the Operator addresses an approved copy of the Control Rod Movement Sequence Sheet, GIVE the Operator the Control Rod Movement Sequence Sheet.

- 4. Select the next control rod 06-31 in At panel 2H11-P603, the Rod Step 31. push-button is DEPRESSED on CONTROL ROD SELECT Matrix for selected control rod 06-31 in Rod Step 31.

(** Indicates critical step)

CR-SIM 1 2016-301 Page 8 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 5. Withdraw the control rod 06-31 to the At panel 2H11-P603, ROD withdrawal limit. MOVEMENT CONTROL switch is used to withdraw the rod 06-31 and then performs a rod coupling check.

6. Confirm the proper control rod 06-31 At panel 2H11-P603, the movement. Operator VERIFIES that the rod 06-31 withdraws.

7. Complete the line, for the selected rod, On the Control Rod Movement on the Control Rod Movement Sequence sheet, on the line for Sequence sheet. the selected rod (Withdrawn side of sheet), the Operator has:

Filled in INIT block.

Filled in DATE block.

- 8. Select the next control rod 22-07 in At panel 2H11-P603, the Rod Step 31. push-button is DEPRESSED on CONTROL ROD SELECT Matrix for selected control rod 22-07 in Rod Step 31.

Withdraw the control rod 22-07 to the At panel 2H11-P603, ROD withdrawal limit. MOVEMENT CONTROL switch is used to withdraw the rod 22-07 Pen and Ink Change and then performs a rod coupling check.

Confirm the proper control rod 22-07 At panel 2H11-P603, the movement. Operator VERIFIES that the rod Pen and Ink Change 22-07 withdraws.

Complete the line, for the selected rod, On the Control Rod Movement on the Control Rod Movement Sequence sheet, on the line for Sequence sheet. the selected rod (Withdrawn side of sheet), the Operator has: Pen and Ink Change Filled in INIT block.

Filled in DATE block.

(** Indicates critical step)

CR-SIM 1 2016-301 Page 9 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

Select the next control rod 30-47 in At panel 2H11-P603, the Rod Step 31. push-button is DEPRESSED on CONTROL ROD SELECT Pen and Ink Change Matrix for selected control rod 30-47 in Rod Step 31.

ALTERNATE PATH STARTS HERE (Step 13)

- 9. Operator attempts to withdraw control At panel 2H11-P603, ROD rod 30-47 22-07 to its withdraw limit MOVEMENT CONTROL switch and recognizes that control rod 30-47 is used to withdraw the rod and 22-07 has not moved. the operator has RECOGNIZED Pen and Ink Change that rod position indicator for rod 30-47 22-07 indicates 12 on the Four- Rod Display and/or RWM.

10. Operator enters the abnormal Operator OBTAINS procedure for inability to move a 34AB-C11-003-2, Inability to control rod. Move a Control Rod.

11. Operator confirms that the inability to At panel 2H11-P603, the move the rod is NOT caused by a rod Operator VERIFIES:

block.

White select light for the affected rod is illuminated.

White ROD OUT permissive light is illuminated.

Annunciator RMCS/RWM ROD BLOCK OR SYS TROUBLE (603-239) is clear.

12. Operator confirms the proper At panel 2H11-P603, the operation of the CRD Hydraulic Operator VERIFIES proper System indication for:

CLG WTR FLOW 2C11-R605 CHG WTR PRESS 2C11-R601 CLG WTR dP 2C11-R603 DR WTR dP 2C11-R602

(** Indicates critical step)

CR-SIM 1 2016-301 Page 10 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

NOTE: The Operator may attempt to move the control rod again to verify the proper RMCS and CRD Drive flow indications. However the Operator may accomplish this step by having observed rod motion on the previous rod movements.

13. Operator confirms that the RMCS At panel 2H11-P603, the timer is operating properly. Operator VERIFIES the proper indications on the ROD IN, ROD OUT, and ROD SETTLE lights.

14. Operator confirms drive water insert At panel 2H11-P603, the and withdraw flows. Operator VERIFIES:

Drive water insert flow is approximately 4 gpm.

Drive water withdraw flow is approximately 2 gpm.

NOTE: If operator momentarily causes Event Trigger to fire early, SIMULATOR OPERATOR RE-INSERT (EVENT TRIGGER EGC11-10) AND mfC12_22_30-47 22-07 f:1 d:0, into the scenario. This will allow the operator to move the rod at 350 psid.

15. Operator increases CRD drive water At panel 2H11-P603, the pressure to 300 psid. Operator ADJUSTS DRIVE PRESS CNTL VLV 2C11-F003 to obtain 300 psid as indicated on DR WTR dP 2C11-R602.

16. Withdraw the control rod to position At panel 2H11-P603, ROD 48 using the Rod Movement Control MOVEMENT CONTROL switch switch. is used to withdraw the rod 30-47 Pen and Ink Change 22-07. Operator RECOGNIZES that rod position indicator still indicates 12.

NOTE: (EVENT TRIGGER EGC11-10), when Drive Water dP is increased to 350 psig, mfC12_22_30_47 22-07 will be DELETED. This will allow the operator to move the rod at 260 psid.

(** Indicates critical step)

CR-SIM 1 2016-301 Page 11 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 17. Operator increases CRD drive water At panel 2H11-P603, the pressure to 350 psid. Operator ADJUSTS DRIVE PRESS CNTL VLV 2C11-F003 to obtain 350 psid as indicated on DR WTR dP 2C11-R602.

- 18. Withdraw the control rod to position At panel 2H11-P603, the ROD 14 using the Rod Movement Control MOVEMENT CONTROL switch switch. is used for rod withdrawal to position 14. Critical task is withdrawing the Rod.

19. Operator reduces Drive Water At panel 2H11-P603, the pressure to 260 psid. Operator ADJUSTS DRIVE PRESS CNTL VLV 2C11-F003 to obtain 260 psid as indicated on DR WTR dP 2C11-R602.

20. Operator acknowledges procedure Operator acknowledges procedure exited and CR initiated. exited and CR initiated.

PROMPT: WHEN the Operator addresses resuming control rod movement, INFORM the Operator that another Operator will continue with Control Rod Movement.

END TIME:

NOTE: The terminating cue shall be given to the Operator when:

Operator completes step 24 20 of this JPM.

Pen and Ink Change With NO reasonable progress, the Operator exceeds double the allotted time.

The Operator has withdrawn rod 30-47 22-07 to its withdrawal limit and completed the initial and date blocks.

Pen and Ink Change

(** Indicates critical step)

CR-SIM 1 2016-301 Page 12 of 13 Summary of JPM Attributes JPM CR-SIM 2 2016-301:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 8 Step 4 Selects 06-31 Proper rod in withdraw sequence.

Step 5 Withdraws 06-31 Proper rod in withdraw sequence.

Step 8 Selects 22-07 Proper rod in withdraw sequence.

Step 9 Withdraws 22-07 Proper rod in withdraw sequence.

Step 12 Selects 30-47 Proper rod in withdraw sequence.

Step 13 9 Recognizes 30-47 22-07 fail Proper rod operation.

Step 21 17 Adjust dP to 350 psig Required to move control rod.

Step 22 18 Withdraws 30-47 Proper rod in withdraw sequence.

Number of JPM Steps

<30 25 Time to Perform JPM

<45 min 20 min Normal / Faulted /

Alternate Path Alternate Path Control rod 30-47 22-07 is stuck and will require entering 34AB-C11-003-2 to increase dP to 350 psig to move the control rod.

Setting (administered)

Simulator Is LOD 1 or 5 NO NO

CR-SIM 1 2016-301 Page 13 of 13 UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. A normal plant startup is in progress per 34GO-OPS-001-2, Plant Startup, and is currently at Step 7.4.3.

2. Rod withdrawal to achieve 6-7% on the APRMs is in progress.

3. There are 6 rods left to withdraw in Step 31 of the Pull Sequence to complete that step.

4. Rod Worth Minimizer is operable and has been loaded with the correct movement sequence, which has been approved by the Reactor Engineering Supervisor.

5. Permission has been granted to use Notch Override in this group of rods.

INITIATING CUES:

Perform Control Rod manipulations IAW Step 31 of Control Rod Movement Sheets.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 2 (ALL)

Title:

Perform RC-2, HPCI Injection (Alternate Path)

Author: Media Number: Time:

Anthony Ball CR-SIM 2 2016-301 15 Minutes Line Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee (N/A for minor revisions) Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date:

Ed Jones 05/30/2016

This page intentionally left blank Page 3 of 13 Course Number Program Name Media Number N/A OPERATIONS TRAINING CR-SIM 2 2016-301 Authors Sups Rev. No. Date Reason for Revisions Initials Initials Revised LR-JP-00505 to be an Alternate Path JPM for use on 2016-301 NRC Exam. Reviewed JPM against current procedure. Changed Media 3.0 05/30/16 ARB ELJ Number to CR-SIM 2 2016-301. After NRC Exam, Media Number will be changed to new LR-JP-00505D (Alt Path).

Page 4 of 13 Line Contributors The following individuals contributed to the development of this lesson plan.

Rev. No. List of Contributors

CR-SIM 2 2016-301 Page 5 of 13 UNIT 1 () UNIT 2 (X)

TASK TITLE: Perform RC-2, HPCI Injection (Alternate Path)

JPM NUMBER: CR-SIM 2 2016-301 TASK STANDARD: The task shall be completed when the operator has manually started HPCI with a flow controller failure to restore RWL to > +3 inches.

TASK NUMBER: 005.005 OBJECTIVE NUMBER: H-OP005.005 PLANT HATCH JTA IMPORTANCE RATING:

RO X.XX SRO X.XX K/A CATALOG NUMBER: 295031EA1.08 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.8 SRO 3.9 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 Unit 2 NA 34AB-C71-001-2, Ver 12.5 34SO-E41-001-2, Ver 30 REQUIRED MATERIALS: Unit 1 Unit 2 NA 34AB-C71-001-2, Ver 12.5 34SO-E41-001-2, Ver 30 APPROXIMATE COMPLETION TIME: 15 Minutes SIMULATOR SETUP: Refer to simulator setup sheet on the following page.

CR-SIM 2 2016-301 Page 6 of 13 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to 90% power or SNAP 612 and leave in FREEZE.

2. ACTIVATE THE FOLLOWING EVENT TRIGGERS:

Trigger # DESCRIPTION CONDITIONS EGE41-1 Inserts E41_106 - HPCI flow controller output fails low aoE41-R610.aivToPanel >.65

3. INSERT the following MALFUNCTIONS:

Activator MALF # TITLE FINAL RAMP VALUE RATE EGE41-1 mfE41_106 HPCI flow controller output fails low ST 0 mfC11-299 CRD Flow Control Fails Low ST-0 mfE42_235A HPCI Fails to start on RWLs ST 0 rfE41_152 HPCI High RWL Bypassed BYPASS ST 0 mfN21_87A A Feedwater Pump trip TRIP ST 0 mfN21_87B B Feedwater Pump trip TRIP ST 0 mfE51_110 RCIC Turbine Trip TRIP ST 0 mfB21_132 ADS Fails To Initiate

4. PLACE the Simulator in FREEZE until the INITIATING CUE is given.

5. PLACE DANGER TAGS on the following equipment:

MPL # COMPONENT TAGGED POSITION NONE

6. ESTIMATED Simulator SETUP TIME: 7 Minutes

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 has Scrammed.

2. RFPTs are unavailable.

3. RCIC is unavailable.

4. Pre-Job Brief is NOT required.

INITIATING CUES:

Maintain RWL in a band of +3 to +50 inches using HPCI.

CR-SIM 2 2016-301 Page 8 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

Start Time:_________

NOTE: The following JPM steps are written assuming the Operator starts HPCI using the HPCI Placard.

1. IF required, Operator DETERMINES that a depress the High Water Level Reset High RWL condition has not Pushbutton occurred (no white light). It is permitted to depress the (Placard Step 1) pushbutton but is not required.

2. OPEN 2E41-F059 At 2H11-P601, the Operator OPENS LUBE OIL CLG WTR VLV, 2E41-F059, red light (Placard Step 2) illuminated.

3. START Barom Cndsr Vac Pump At 2H11-P601, the Operator STARTS HPCI BAROM CNDSR VACUUM PUMP, (Placard Step 3) 2E41-C002-2, red light illuminated.

PROMPT: IF the operator addresses posting High Radiation Areas, as the Shift Supervisor, ACKNOWLEDGE the report to post the areas.

(** Indicates critical step)

CR-SIM 2 2016-301 Page 9 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 4. Perform the following in rapid At 2H11-P601, the Operator succession: PLACES CS for the TURB Place 2E41-F001 CS in OPEN, STEAM SUPPLY VLV, 2E41-F001 in the OPEN position.

AND AND

. (Placard Step 4)

5. Perform the following in rapid At 2H11-P601, the Operator succession: VERIFIES 2E41-F001 red light is

., illuminated.

AND VERIFY red light illuminates, AND

. (Placard Step 4)

- 6. Perform the following in rapid At 2H11-P601, the Operator succession: STARTS the AUX OIL PUMP,

., 2E41-C002-3, red light illuminated.

AND AND START Aux Oil Pump (Placard Step 4)

- 7. OPEN 2E41-F006 At 2H11-P601, the Operator OPENS PUMP DISCHARGE (Placard Step 5) VLV, 2E41-F006, red light illuminated.

8. CONFIRM TCV and TSV OPEN At 2H11-P601, the Operator CONFIRMS that the:

TURBINE CONTROL VLV and TURBINE STOP VLV (Placard Step 6) are OPEN, red light illuminated.

(** Indicates critical step)

CR-SIM 2 2016-301 Page 10 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

ALTERNATE PATH STARTS HERE (Step 9).

9. Confirm the HPCI Turbine comes up At panel 2H11-P601, the operator to speed as directed by the Turbine RECOGNIZES HPCI turbine has Flow Controller, 2E41-R612. NOT increased to rated speed and that the HPCI FLOW CONTROL 2E41-R612 has failed LOW.

NOTE: The following step is NOT sequence sensitive and may be performed at any point during the performance of this JPM.

- 10. Operator takes manual control of the At panel 2H11-P601, HPCI HPCI Flow Controller. FLOW CONTROL 2E41-R612 Manual (M) pushbutton has been DEPRESSED, Manual (M) amber light illuminated.

- 11. Operator increases HPCI Turbine At panel 2H11-P601, HPCI speed. FLOW CONTROL 2E41-R612 level is TAKEN to the Open (O) direction until: PUMP DISCH PRESS 2E41-R601 is greater than Reactor pressure and the desired flow is obtained.

12. CONFIRMS 2E41-F012 CLOSES at At 2H11-P601, the Operator flow > 790 gpm CONFIRMS MIN FLOW VLV, 2E41-F012 is CLOSED when HPCI pump flow is > 790 gpm, (Placard Step 7) green light illuminated.

- 13. ADJUST controller for desired flow At 2H11-P601, the Operator ADJUSTS HPCI FLOW CONTROL, 2E41-R612 to control rate of RWL level (Placard Step 8) increase to maintain >+3 and

<+111 inches.

(** Indicates critical step)

CR-SIM 2 2016-301 Page 11 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

14. ADJUST controller for desired flow At 2H11-P601, the Operator ADJUSTS HPCI FLOW CONTROL, 2E41-R612 to control rate of RWL level (Placard Step 8) increase to maintain >+3 and

<+50 inches.

15. Confirm 2E41-F001 is full OPEN At 2H11-P601, the Operator CONFIRMS 2E41-F001 is fully (Placard Step 9) OPEN.

PROMPT: IF the operator addresses Maintenance investigating the failed HPCI Flow controller, as the Shift Supervisor, INFORM the operator that Maintenance will be notified.

PROMPT: IF the operator addresses maintain RWL, as the Shift Supervisor, INFORM the operator that another operator will maintain the appropriate RWL band.

End Time: _________

NOTE: The terminating cue shall be given to the operator when:

Operator completes step 15 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

CR-SIM 2 2016-301 Page 12 of 13 Summary of JPM Attributes JPM CR-SIM 2 2016-301:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 5 Step 4 Open 2E41-F001 Opening the steam supply valve is required to provide motive force.

Step 6 Start Aux Oil Pump Required to provide oil pressure to open the TCV and TSV.

Step 7 Open 2E41-F006 Opening the discharge valve is required to allow for injection.

Step 10 Controller in Manual Allows manual control of output Step 11 Increase output Required to obtain injection Step 13 Adjust for >+3 inches Required to reset Scram Number of JPM Steps <30 15 Time to Perform JPM <45 min 15 min Normal / Faulted /

Alternate Path Alternate Path Manual start of HPCI with a Flow controller failure requiring the operator to manually adjust controller to inject into the RPV. HPCI will NOT auto start on low RWL or high DW pressure.

Setting (administered)

Simulator Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 has Scrammed.

2. RFPTs are unavailable.

3. RCIC is unavailable.

4. Pre-Job Brief is NOT required.

INITIATING CUES:

Maintain RWL in a band of +3 to +50 inches using HPCI.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 3 (RO & SRO-I)

Title:

OVERRIDE THE MSIVS IN AN EMERGENCY Author: Media Number: Time:

Anthony Ball CR-SIM 3 2016-301 30.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee: Date:

N/A N/A Approved By (Training Program Supervisor, Lead Instructor or Line Supervisor) Date:

Ed Jones 05/30/16

Page 2 of 14 This page intentionally left blank

Page 3 of 14 Course Number Program Name Media Number N/A OPERATIONS TRAINING CR-SIM 3 2016-301 Authors Sups Rev. No. Date Reason for Revisions Initials Initials 01 08/24/92 General revision and format change WMM SCB 02 08/16/93 General revision, word processor change RAB RSG 03 08/19/94 Modify simulator setup, adjust format RAB SMC 04 03/28/96 Format change RAB DHG 05 04/10/97 Revised based on feedback from the 1996 Requal SCB RSG annual exam.

06 02/07/00 Format modification, change time allowance based on RAB DHG running average, upgrade to the new simulator operating system 07 11/02/00 Include objective number RAB DHG 08 03/11/02 Include initial operator statement RAB RAB 09 03/17/05 Deleted S from procedure numbers, changed ARB DHG Revision and Rev. numbers to Current Version.

Changed to Nuclear Plant Operator. Updated Simulator IC# and MSIV position.

10 06/13/05 Revised Initial License statement for successful RAB RAB completion 11 04/18/06 Remove Response Cues RAB RAB 12 11/06/06 Correct MPLs and Switch labels on Unit 1 BKW RAB 13 06/07/12 Revision for use on 2012-301 CR-SIM 3 and updated ARB CME procedure changes. After NRC Exam, Media Number will be changed to LR-JP-14.14.

Reviewed JPM against current procedure for use on 2016-301 NRC Exam. Changed Media Number to 14 05/30/16 CR-SIM 3 2016-301. After NRC Exam, Media ARB ELJ Number will be changed to the next revision of LR-JP-14.14 and U1 material will be added back.

3

CR-SIM 3 2016-301 Page 4 of 14 UNIT 1 (X) UNIT 2 (X)

TASK TITLE: OVERRIDE THE MSIVS IN AN EMERGENCY JPM NUMBER: CR-SIM 3 2016-301 TASK STANDARD: The task shall be completed when the MSIVs have been opened per 31EO-EOP-111-1/2.

TASK NUMBER: 014.014 OBJECTIVE NUMBER: 014.014.A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.85 SRO 3.16 K/A CATALOG NUMBER: 239001A4.01 K/A CATALOG JTA IMPORTANCE RATING:

RO 4.20 SRO 4.00 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 Unit 2 31EO-EOP-111-1 31EO-EOP-111-2 31EO-EOP-011-1 31EO-EOP-011-2 (current versions) (current versions)

REQUIRED MATERIALS: Unit 1 Unit 2 31EO-EOP-111-1 31EO-EOP-111-2 (current version) (current version)

APPROXIMATE COMPLETION TIME: 30.0 Minutes SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

CR-SIM 3 2016-301 Page 5 of 14 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to IC #113 or Snap 613 and leave in FREEZE.

2. ACTIVATE THE FOLLOWING EVENT TRIGGERS:

Trigger # DESCRIPTION CONDITIONS EGB21-17 Delete mf60321350 Group I System A Trip diA71B-S32.aivToPanel<1 EGB21-18 Delete mf60321351 Group I System B Trip diA71B-S33.aivToPanel<1

3. INSERT the following MALFUNCTIONS:

MALF # TITLE FINAL RAMP ACT.

VALUE RATE TIME mfC11_211 Scram Discharge Volume ATWS (Var) 20 100 00000 mfE41_235A HPCI Fails to Auto Start on Low Level 00000 mfE41_235B HPCI Fails to Auto Start on Hi Drywell Press 00000 Spur Ann -- LOW CONDENSER VACUUM 00000 mf60321383 A BYPASS Spur Ann -- LOW CONDENSER VACUUM B 00000 mf60321384 BYPASS mf60321350 Group I System A Trip 00000 mf60321351 Group I System B Trip 00000

4. INSERT the following SIMULATOR VALUE OVERRIDES (SVO):

SVO # DESCRIPTION FINAL RAMP ACT.

VALUE RATE TIME svoB21005 LT-N081A Group I/II Isolation -110 100 00000 svoB21006 LT-N081B Group I/II Isolation -110 100 00000

5. INSERT the following REMOTE FUNCTIONS:

REM # DESCRIPTION STATUS rfN11045 SJAE A Steam CLOSE rfB21148 Grp 1 Low Rx Water Level Bypass ORIDE rfC71279 Group 1 Isolation Oride Jumpers ORIDE

CR-SIM 3 2016-301 Page 6 of !Syntax Error, !

6. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A. Take simulator out of FREEZE and perform RC-1, RC-2 and TC-1.

B. Place 2N11-F004A & F004B control switches in CLOSED & ENSURE they are CLOSED.

C. Place 2N33-F003 control switch in CLOSED & ENSURE it is CLOSED D. Place the MSIV control switches in CLOSED.

E. Enter Remote Functions WHEN Torus temperature reaches 109°F or greater.

F. Inhibit ADS and inject SBLC.

G. Acknowledge annunciators.

7. PLACE the Simulator in FREEZE until the INITIATING CUE is given.

8. ESTIMATED Simulator SETUP TIME: 15 Minutes 6

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. The Condenser Low Vacuum and Low RWL isolations have been bypassed.

2. Main Condenser is in operation with Circ Water and Condensate Systems in operation.

3. An ATWS condition exists and 31EO-EOP-011-2 (RCA) is in progress.

4. EHC is in operation.

INITIATING CUES:

Open the MSIVs to re-establish Main Condenser as the heat sink using 31EO-EOP-111-2.

CR-SIM 3 2016-301 Page 8 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

START TIME:_________

1. Place MSIV Control Switches to At panel 2H11-P601, confirms CLOSED. the following OUTBOARD MSIV switches are in CLOSED:

MSIV 2B21-F028A MSIV 2B21-F028B MSIV 2B21-F028C MSIV 2B21-F028D

2. Place MSIV Control Switches to At panel 2H11-P602, confirms CLOSED. the following INBOARD MSIV switches are in CLOSED:

MSIV 2B21-F022A MSIV 2B21-F022B MSIV 2B21-F022C MSIV 2B21-F022D

3. Confirm A & B RFPTs are tripped. At panel 2H11-P650, Operator has determined BOTH RFPTs are TRIPPED by:

Checking annunciators(650-325

& 326) are ILLUMINATED

(** Indicates critical step)

CR-SIM 3 2016-301 Page 9 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

PROMPT: IF the operator addresses isolation bypasses, as the Shift Supervisor, INFORM the operator that the Condenser Low Vacuum and Low Water Level isolations are bypassed.

- 4. Reset Group I Isolation. The GR ISOL RESET switch has been taken to GR I RESET position at panels 2H11-P601 and 2H11-P602.

5. Bypass the High Flow isolation on Operator has determined it is 2P70-F004 and F005, if necessary. NOT necessary to bypass the High Flow Isolation by:

Checking annunciators OR Checking INBD INLET ISOL 2P70-F004 and F005 red lights illuminated on panel 2H11-P700.

NOTE: It is acceptable for operator to have the High Flow Isolation bypassed. IF operator decides to bypass the High Flow Isolation, as the Shift Support Supervisor, INFORM the operator that it has been bypassed.

6. Confirm closed Inboard MSIVs. At panel 2H11-P602, the following INBOARD MSIVs are CLOSED, green light illuminated:

MSIV 2B21-F022A MSIV 2B21-F022B MSIV 2B21-F022C MSIV 2B21-F022D.

- 7. Open Outboard MSIVs. At panel 2H11-P601, the following switches are in OPEN SLO TEST, red light illuminated:

MSIV 2B21-F028A MSIV 2B21-F028B MSIV 2B21-F028C MSIV 2B21-F028D.

(** Indicates critical step)

CR-SIM 3 2016-301 Page 10 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

8. Check differential pressure across Operator has determined Inboard MSIVs. differential pressure is greater than 200 psid using:

REACTOR PRESSURE indicator A(B,C) 2C32-R605A(B,C) on panel 2H11-P603 AND MAIN STEAM PRESS "A"("B")

2N32-R654A(B) indicator on Turbine EHC Panel or recorder PRESS TO STOP VLVS 1 & 4 2N11-R601 OR

Monitor* *steam pressure*

2N32-K4001A OR 2N32-K4001B.

NOTE: Any valid indication of Reactor Pressure and Steam Line Pressure can be used for Step 7.

9. Confirm/Close valves The operator has ADDRESSED 2N11-F001A & B. contacting a SO to verify/close SJAE 2A(2B) MAIN STEAM ISOL VALVE at panel 2H21-P216.

PROMPT: WHEN the operator addresses valves 2N11-F001A and B, as the SO, INFORM the operator that the valves 2N11-F001A & B are closed.

10. Confirm the following valves are At panel 2H11-P650, the closed: following valves are CLOSED, 2N11-F004A green light illuminated:

2N11-F004B 2ND STG A & B MSR RHTR STM SPLY VLV 2N11-F004A 2N33-F003 2ND STG C & D MSR RHTR STM SPLY VLV 2N11-F004B MAIN STM FEED VLV 2N33-F003.

(** Indicates critical step)

CR-SIM 3 2016-301 Page 11 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 11. Open the following valves: The following valves are OPEN, 2B21-F016 red lights illuminated:

2B21-F019 MSL DRAIN VLV, 2B21-F016, at panel 2H11-P602 MSL DRAIN VLV, 2B21-F019, at panel 2H11-P601

12. Open the following valve: The following valve is OPEN, red 2B21-F020 lights illuminated:

DRAIN VLV, 2B21-F020, at panel 2H11-P602

13. Verify differential pressure across Operator has determined MSIVs is less than 200 psid. differential pressure is less than 200 psid using:

REACTOR PRESSURE indicator A(B,C) 2C32-R605A(B,C) on panel 2H11-P603 AND MAIN STEAM PRESS "A"("B")

2N32-R654A(B) indicator on Turbine EHC Panel or recorder PRESS TO STOP VLVS 1 & 4 2N11-R601 OR

Monitor* *steam pressure*

2N32-K4001A OR 2N32-K4001B.

NOTE: Any valid indication of Reactor Pressure and Steam Line Pressure can be used for Step 11.

- 14. Open Inboard MSIVs. At panel 2H11-P602, the following switches are in OPEN SLO TEST, red light illuminated:

MSIV 2B21-F022A MSIV 2B21-F022B MSIV 2B21-F022C MSIV 2B21-F022D.

(** Indicates critical step)

CR-SIM 3 2016-301 Page 12 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

NOTE: It is acceptable if the operator uses the Open Fast Test switch position.

PROMPT: WHEN the operator addresses the Main Condenser Vacuum System, as the Shift Supervisor, INFORM the operator that another operator will place it in service and monitor vacuum.

PROMPT: IF the operator addresses system restoration, as the Shift Supervisor, INFORM the operator that restoration is not required at this time.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when any one of the following is met:

After JPM step #13 is complete.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR - PICK UP the Initiating Cue sheet.

(** Indicates critical step)

CR-SIM 3 2016-301 Page 13 of 14 Summary of JPM Attributes JPM CR-SIM 3 2016-301:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 4 Step 4 Reset Group I Isolation The Group I Isolation is required to be reset to re-open the MSIVs Step 7 Open the Outboard MSIVs Opening the Outboard MSIVs is required to re-establish the Main Condenser as the heat sink, and to reduce differential pressure across the Inboard MSIVs less than 200 psid.

Step 11 Open 2B21-F016 & F019 The MSL Drain valves are opened to reduce differential pressure across the Inboard MSIVs less than 200 psid.

Step 14 Open the Inboard MSIVs Opening the Inboard MSIVs is required to re-establish the Main Condenser as the heat sink.

Number of JPM Steps <30 14 Time to Perform JPM <45 min 30.0 min Normal / Faulted /

Alternate Path Normal Open the MSIVs using 31EO-EOP-11-2.

Setting (administered)

Simulator Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. The Condenser Low Vacuum and Low RWL isolations have been bypassed.

2. Main Condenser is in operation with Circ Water and Condensate Systems in operation.

3. An ATWS condition exists and 31EO-EOP-011-2 (RCA) is in progress.

4. EHC is in operation.

INITIATING CUES:

Open the MSIVs to re-establish Main Condenser as the heat sink using 31EO-EOP-111-2.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 4 (RO & SRO-I)

Title:

REACTOR PRESSURE CONTROL WITHIN BAND WITH BPVs & SRVs Author: Media Number: Time:

Anthony Ball CR-SIM 4 2016-301 20.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee: Date:

N/A N/A Approved By (Training Program Supervisor, Lead Instructor or Line Supervisor) Date:

Ed Jones 05/30/16

This page intentionally left blank Page 3 of 13 Course Number Program Name Media Number N/A OPERATIONS TRAINING CR-SIM 4 2016-301 Authors Sups Rev. No. Date Reason for Revisions Initials Initials Initial development for use on 2011-301 NRC 00 5/26/11 ARB CME Exam.

Reviewed JPM against current procedure for use on 2016-301 NRC Exam. Changed Media 0.1 05/30/16 Number to CR-SIM 4 2016-301. After NRC ARB ELJ Exam, Media Number will be changed to a new LR-JPM.

3

CR-SIM 4 2016-301 Page 4 of 13 UNIT 1 () UNIT 2 (X)

TASK TITLE: REACTOR PRESSURE CONTROL WITHIN BAND WITH BPVs & SRVs JPM NUMBER: CR-SIM 4 2016-301 TASK STANDARD: The task will be completed when the operator is controlling Reactor pressure in a band using SRVs per 34SO-B21-001-2.

TASK NUMBER: 200.034 OBJECTIVE NUMBER: 200.034.C PLANT HATCH JTA IMPORTANCE RATING:

RO SRO K/A CATALOG NUMBER: 239001A2.01 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.8 SRO 3.9 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 2 34SO-N30-001-2 (current version) 34SO-B21-001-2 (current version)

REQUIRED MATERIALS: Unit 2 34SO-N30-001-2 (current version) 34SO-B21-001-2 (current version)

APPROXIMATE COMPLETION TIME: 20.0 Minutes SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

CR-SIM 4 2016-301 Page 5 of 13 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to IC #113 or Snap 614 and leave in FREEZE.

2. INSERT the following MALFUNCTIONS and EVENT TRIGGERS:

KEY MALF # DESCRIPTION FINAL RAMP DELAY ST-0 mfB21_129A SRV A Fails Stuck 0000 ST-0 mfB21_129B SRV B Fails Stuck 0000 ST-0 mfB21_129C SRV C Fails Stuck 0000 ST-0 mfB21_129D SRV D Fails Stuck 0000 ST-0 mfB21_129E SRV E Fails Stuck 0000 ST-0 mfB21_129F SRV F Fails Stuck 0000 ST-0 mfB21_129G SRV G Fails Stuck 0000 ST-0 mfB21_129H SRV H Fails Stuck 0000 ST-0 mfB21_129K SRV K Fails Stuck 0000 ST-0 mfB21_129L SRV L Fails Stuck 0000 ST-0 mfB21_129M SRV M Fails Stuck 0000 ST-0 mfE41_104 HPCI Turbine Trip 0000 ST-0 mfE51_110 RCIC Turbine Trip 0000 ST-0 mfN21_87A Feedwater Pump A Trip 0000 ST-0 svoB21053 PT-N127A SRV Electrical open 1000 1000 0000 ST-0 svoB21054 PT-N127B SRV Electrical open 1000 1000 0000 ST-0 svoB21055 PT-N127C SRV Electrical open 1000 1000 0000 ST-0 svoB21056 PT-N127D SRV Electrical open 1000 1000 0000 ST-0 mfB21_226A Low-Low Set A Fails Inop 0000 ST-0 mfB21_226B Low-Low Set B Fails Inop 0000 ST-0 mf60131129 Leak Det Diff Temp Hi 0000 ST-0 mf60131135 Leak Ambient Temp Hi 0000 5

CR-SIM 4 2016-301 Page 6 of 13 RB-1 mfN37_134 ALL Bypass Valves Fail CLOSED 9999 RB-1 diN32-C001A EHC Pump 2A Switch Trip 9999 RB-1 diN32-C001B EHC Pump 2B Switch Trip 9999 ACTIVATE THE FOLLOWING EVENT TRIGGERS:

Trigger # DESCRIPTION CONDITIONS EGB21-21 SRV B Stuck, opens when control switch is in OPEN diB21-F013B.iivPanel=1 EGB21-22 SRV G Stuck, opens when control switch is in OPEN diB21-F013G.iivPanel=1 EGB21-23 SRV F Stuck, opens when control switch is in OPEN diB21-F013F.iivPanel=1 EGB21-24 SRV D Stuck, opens when control switch is in OPEN diB21-F013D.iivPanel=1 EGN37-1 RPV pressure <800 psig closes BPVs & trips off EHC aoC32-R605B.anvToPanel<.667 pumps

3. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS OR RUN SCENARIO FILE and EVENT TRIGGER (current rev) CR-SIM 4 2016-301:

A. Perform RC-1 and RC-2 actions such that the 2N21-F110 is closed and the SULCV is in auto and set at +20.

B. Perform TC-1; ensuring 2N11-F004A and B are closed.

C. Lower Pressure Set to 825 psig.

D. Ensure Reactor pressure stabilizes at ~825 psig.

E. Ensure BYPASS VALVE screen and SPEED screen is called up.

F. Place RPV Pressure (B025) in the P603 plasma display.

4. PLACE the Simulator in FREEZE until the INITIATING CUE is given.

5. ESTIMATED Simulator SETUP TIME: 15 minutes 6

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 Reactor has been scrammed.

2. Other operators are performing scram actions.

3. A Reactor pressure reduction is required due to an unisolable steam leak in the Reactor Building.

4. You have the sole responsibility for Reactor Pressure Control.

INITIATING CUES:

LOWER AND THEN MAINTAIN Reactor pressure between 700 and 800 psig using the Bypass Valves.

(** Indicates critical step)

CR-SIM 4 2016-301 Page 8 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

START TIME:__________

1. Operator identifies the procedure Operator has obtained procedure needed to perform the task. 34GO-OPS-013-2, step 7.5.5 or uses Placard at Turbine Panel.

NOTE: For Steps 2 through 8 all indication will be on panel 2H11-P650 using HMI Screens 2N32-K4001A or B.

2. Selects *Control* / *psi-load* The operator has SELECTED the screen *Control* screen and also has SELECTED the *psi-load*

button on 2N32-K4001A or B.

3. Selects *Ramp Rate* button The operator has SELECTED the

Ramp Rate* button on 2N32-K4001A or B.

NOTE: An acceptable Ramp Rate results in a cooldown rate NOT exceeding 100ºF/hr OR RWL exceeding +100 inches.

- 4. Enters a ramp rate The operator has ENTERED a ramp rate >0 and <100 displayed on 2N32-K4001A or B.

(** Indicates critical step)

CR-SIM 4 2016-301 Page 9 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 5. Selects *Pressure* button The operator has SELECTED the

Pressure* button on 2N32-K4001A or B.

- 6. Enters desired target pressure The operator has ENTERED a target pressure between 700 and 800 psig on 2N32-K4001A or B.

- 7. Adjusts *Ramp Rate* AND/OR the The operator has VARIED the

Pressure* setpoints to maintain ramp rate/pressure to maintain a pressure/cooldown rate. cooldown rate 100° F/Hr OR RWL exceeding 100 inches change on 2N32-K4001A or B.

ALTERNATE PATH STARTS HERE NOTE: SIMULATOR OPERATOR, WHEN the operator has successfully opened Bypass Valves (BPVs) and reactor pressure is being reduced to <800 psig ENSURE Event Trigger EGN37-1 FULLY CLOSES ALL Bypass Valves AND TRIPS BOTH EHC Pumps.

8. The failure of ALL BPVs is Operator identifies all BPVs recognized. closed on 2N32-K4001A or B.

PROMPT: IF the operator reports the failure of the BPVs and EHC pumps, INFORM the operator that you will get Maintenance to investigate, and to control Reactor pressure between 700 - 800 psig.

PROMPT: IF alarm 650-124, Max Combined Flow Limit Limiting, is received, INFORM the operator that another operator will address the ARP.

PROMPT: IF the operator addresses using other systems to control Reactor pressure, INFORM the operator to control Reactor pressure between 700 - 800 psig.

NOTE: The operator can use any of the following procedures to control reactor pressure:

Placard on 2H11-P602 panel

34SO-B21-001-2, Automatic Depressurization (ADS) And Low-Low Set (LLS) Systems

(** Indicates critical step)

CR-SIM 4 2016-301 Page 10 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

9. Operator identifies applicable Operator has IDENTIFIED the procedures to perform the task. correct procedure as:

Placard on 2H11-P602 panel 34SO-B21-001-2, step 7.4.1.

NOTE: ALL SRVs, EXCEPT LLS SRVs, fail to open with the switch.

10. Attempts to OPEN SRV At Panel 2H11-P602, the operator 2B21-F013M. has PLACED the control switch for 2B21-F013M into the OPEN position, red light ILLUMINATES.

11. The failure of the 2B21-F013M to At 2H11-P602, the operator has open is recognized. RECOGNIZED the failure of the 2B31-F013M to OPEN, amber light remains EXTINGUISHED.

PROMPT: IF the operator reports the failure of the 2B21-F013M to open, INFORM the operator that you will get Maintenance to investigate, and to control Reactor pressure between 700 - 800 psig.

NOTE: Due to failures, LLS will NOT automatically ARM with Reactor pressure >1074 psig.

NOTE: EVENT TRIGGER EGB21-21, 22, 23 & 24 will allow 2B21-F013B, G, F, & D LLS valve to be used to control RPV pressure.

NOTE: Any of the LLS valves (2B21-F013B, D, F, or G) will be used to control RPV pressure and will successfully meet the intent of Critical Step **12. 34SO-B21-001-2 allows opening of any of the LLS valves to control RPV pressure.

- 12. OPEN SRV 2B21-F013B, D, F, or G. At Panel 2H11-P602, the operator has PLACED the control switch for 2B21-F013B, D, F, or G into the OPEN position prior to 1250 psig, red light ILLUMINATED.

PROMPT: IF the operator addresses checking SRV tailpipe temperature on recorder 2B21-R614, at Panel 2H11-P614, INFORM the operator that another operator will check the recorder for proper SRV operation.

(** Indicates critical step)

CR-SIM 4 2016-301 Page 11 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 13. Reactor pressure in band: The operator CONTROLS 700 to 800 psig pressure in band:

700 to 800 psig (+/- 50 psig)

- 14. Before Reactor decreases below 700 At panel 2H11-P602 the operator psig, CLOSE SRV 2B21-F013B, D, F, has PLACED the control switch or G. for 2B21-F013B, D, F, or G into the CLOSE position PRIOR to Reactor pressure lowering below its band (-50 psig), green light ILLUMINATED.

NOTE: AFTER the operator has demonstrated proper control of Reactor pressure, INFORM the operator that another operator will continue maintaining Reactor pressure in band.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when any one of the following is met:

After JPM step #14 is complete.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: Another operator will continue from here.

EVALUATOR - PICK UP the Initiating Cue sheet.

(** Indicates critical step)

CR-SIM 4 2016-301 Page 12 of 13 Summary of JPM Attributes JPM CR-SIM 4 2016-301:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 7 Step 4 Enters ramp rate Entering a ramp rate is required to lower the pressure reference signal.

Step 5 Selects Pressure Selecting the Pressure button allows the operator to reduce the desired pressure value.

Step 6 Enters target Pressure Entering the target pressure allows the operator to start the pressure reduction to this desired pressure value.

Step 7 Adjusts ramp/rate Adjusts as needed to maintain a cooldown rate 100° F/Hr OR RWL exceeding 100 inches.

Step 12 Opens SRV 2B Terminates the pressure increase.

Step 13 Reactor pressure in band Controls pressure in band Step 14 Closes SRV 2B Prior to exceeding pressure band on lower band Time to Perform JPM <45 min 20.0 min Normal / Faulted /

Alternate Path Alternate Path When the Bypass valves fail, the Operator is required to control pressure via an alternate method and use SRVs.

Setting (administered)

Simulator Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 Reactor has been scrammed.

2. Other operators are performing scram actions.

3. A Reactor pressure reduction is required due to an Unisolable steam leak in the Reactor Building.

4. You have the sole responsibility for Reactor Pressure Control.

INITIATING CUES:

LOWER AND THEN MAINTAIN Reactor pressure between 700 and 800 psig using the Bypass Valves.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 5 (ALL)

Title:

Perform a Manual Initiation of Drywell Sprays (Alternate Path)

Author: Media Number: Time:

Anthony Ball CR-SIM 5 2016-301 15.0 Minutes Line Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee (N/A for minor revisions) Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date:

Ed Jones 05/30/16

This page intentionally left blank Page 3 of 14 Course Number Program Name Media Number N/A OPERATIONS TRAINING CR-SIM 5 2016-301 Authors Sups Ver. No. Date Reason for Revisions Initials Initials 00.0 30Nov15 Initial Development for Simulator only. MCK ALS Reviewed JPM against current procedure for use on 2016-301 NRC Exam. Changed Media 0.1 05/30/16 Number to CR-SIM 5 2016-301. After NRC ARB ELJ Exam, Media Number will be changed to LR-JP-00701A (Alt Path).

Page 4 of 14 Line Contributors The following individuals contributed to the development of this lesson plan.

Ver. No. List of Contributors

CR-SIM 5 2016-301 Page 5 of 14 UNIT 1 () UNIT 2 (X)

TASK TITLE: Perform a Manual Initiation of Drywell Sprays (Alternate Path)

JPM NUMBER: CR-SIM 5 2016-301 TASK STANDARD: The task shall be completed when the RHR System has been initiated in the Drywell spray mode, per 34SO-E11-010-2 with total RHR flow > 5000gpm but <17,000gpm. Operator is to take action based on Overload protection alarm for the 2A RHR pump by securing the pump.

TASK NUMBER: 007.001 OBJECTIVE NUMBER: 007.001.O PLANT HATCH JTA IMPORTANCE RATING:

RO 4.71 SRO 4.05 K/A CATALOG NUMBER: 226001A4.03 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.50 SRO 3.50 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 Unit 2 34SO-E11-010-2 Ver. 42.0 N/A 31EO-EOP-012-2 Ver. 6 REQUIRED MATERIALS: Unit 1 Unit 2 N/A 34SO-E11-010-2 Ver. 42.0 APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: Refer to Simulator setup sheet on the following page.

CR-SIM 5 2016-301 Page 6 of 14 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to IC # 113 (100%) or SNAP 615 and leave in FREEZE.

2. ACTIVATE THE FOLLOWING EVENT TRIGGERS:

Trigger # DESCRIPTION CONDITIONS EGE11-31 Inserts 2A RHR Pump Overload Alarm loE11-F021AR2.algToPanel = 1

3. INSERT the following MALFUNCTIONS:

Activator MALF # TITLE FINAL RAMP VALUE RATE ST 0 mfE41_107 HPCI Failure to Start (F001 Stuck)

ST 0 mfE51_110 RCIC Turbine Trip ST 0 mfB21_229B FW Line B Break Inside Containment (Var) 10 100 ST 0 mfR22_183 4KV Buss 2F Fault 1 ST 0 mfR43_167B Diesel Gen Failure to Start 1B 1

4. INSERT the following REMOTE FUNCTIONS:

Activator REM # Description Status ST 0 rfE11_167 2E11-F017A & B Override 5 Min Timer ORIDE

5. INSERT the following OVERRIDES:

Activator TAG # S/M/L DESCRIPTION Final Ramp Delay Value Rate ST-0 diE11-F028B S Torus Spray OR Test Vlv CLOSE 0 ST-0 diE11-F027A S Torus Spray Vlv CLOSE 0

CR-SIM 5 2016-301 Page 7 of 14

6. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A. Perform first five (5) Steps of RC-1.

B. Close 2N21-F006B. Allow the valve to go FULL CLOSE.

C. Perform actions of RC-2 to stabilize RWL around 9 inches.

D. Place RHR pump 2B in OFF.

E. Trip Recirculation Pumps 2A and 2B place in PTL.

F. Secure all Drywell cooling fans.

G. Allow Simulator to run approximately 10 min to stabilize conditions.

H. Acknowledge all Annunciators.

7. PLACE DANGER TAGS on the following equipment:

MPL # COMPONENT TAGGED POSITION NONE

8. PLACE Protected Equipment tags on the following: NONE

9. PLACE the Simulator in FREEZE until the INITIATING CUE is given.

10. ESTIMATED Simulator SETUP TIME: 30 Minutes

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Torus pressure is greater than 11 psig.

31EO-EOP-012-2, PC Primary Containment Control is in progress.

2. 2E11-F027A, Torus Spray Valve, is bound closed and cannot be opened.

3. Drywell pressure and temperature are within the SAFE region of the Drywell Spray Initiation Limit Curve. (GRAPH 8).

4. Pre-Job Brief is NOT required.

INITIATING CUES:

Initiate Drywell sprays using the RHR Loop 2A per 34SO-E11-010-2.

CR-SIM 5 2016-301 Page 9 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

START TIME:_________

NOTE: This JPM is set up for the Operator to use the CONTAINMENT SPRAY INITIATION PLACARD.

1. IF RWL <2/3 core height, (-193 Operator VERIFIES that RWL is inches), PLACE the Cnmt Spray Vlv >-193 and this step is not Cntl 2/3 Core Ht Permis keylock in applicable.

MANUAL OVERRD.

Step 1

- 2. IF required by EOPs AND LOCA At panel 2H11-P601, the signal present, Operator PLACES the PLACE Cnmt Spray Vlv Cntl switch CONTAINMENT SPRAY in the MANUAL position. VALVE CONTROL switch to Step 2 MANUAL, white light illuminated for 2A Loop RHR.

3. Confirm CLOSED 2E11-F015A At panel 2H11-P601, CONFIRM and/or 2E11-F017A, unless required Closed 2E11-F015A and/or for core cooling. 2E11-F017A.

Step 3

(** Indicates critical step)

CR-SIM 5 2016-301 Page 10 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

4. IF power is being provided by EDG, Operator VERIFIES that EDGs CHECK EDG loading prior to start of are not providing power to RHR pump(s). emergency buses.

Step 4

5. START RHR pump(s) in loop A. At panel 2H11-P601, Operator Step 5 VERIFIES the 2A RHR pump is RUNNING, red light illuminated.

6. IF TORUS Spray is desired, Operator DETERMINES that PERFORM the following: Torus Sprays are in service on 2B Step 6 Loop of RHR remainder of step 6 is NOT required.

- 7. IF DRYWELL Spray is desired, At panel 2H11-P601, the PERFORM the following: Operator OPENS 2E11-F021A OPEN Containment Spray Valve CNMT SPRAY INBD VLV.

2E11-F021A.

Step 7.1 ALTERNATE PATH STARTS HERE (When 2E11-F021A goes intermediate (>50% Open),

2A RHR pump indicates an overload condition but the pump fails to trip).

8. Operator identifies annunciator RHR Operator IDENTIFIES Pump A OVLD/LOCKOUT Relay annunciator, RHR Pump A Trip is alarming. OVLD/LOCKOUT Relay Trip (601-212), is alarming.

NOTE: The Operator may refer to the Annunciator Response Procedure (ARP) 34AR-601-212-2 RHR PUMP A OVLD/LOCKOUT RELAY TRIP only step 5.1 is required action.

- 9. IF 2E11-C002A, RHR Pump A has Operator TRIPS 2A RHR pump NOT tripped, TRIP 2E11-C002A, (2E11-C002A) at Panel 2H11-panel 2H11-P601, P601.

ARP - Step 5.1 PROMPT: IF Operator asks, INFORM the Operator that Maintenance will investigate the problem with 2A RHR Pump.

PROMPT: IF Operator asks, INFORM the Operator to Spray the Drywell.

(** Indicates critical step)

CR-SIM 5 2016-301 Page 11 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

10. IF RWL <2/3 core height, (-193 Operator VERIFIES that RWL is inches), PLACE the Cnmt Spray Vlv >-193 and this step is not Cntl 2/3 Core Ht Permis keylock in applicable.

MANUAL OVERRD.

Step 1

- 11. IF required by EOPs AND LOCA At panel 2H11-P601, the signal present, Operator PLACES the PLACE Cnmt Spray Vlv Cntl switch CONTAINMENT SPRAY in the MANUAL position. VALVE CONTROL switch to MANUAL, white light Step 2 illuminated for 2B Loop RHR.

12. Confirm CLOSED 2E11-F015B At panel 2H11-P601, the and/or 2E11-F017B, unless required Operator CONFIRMS Closed for core cooling. 2E11-F015B and/or 2E11-F017B.

Step 3

13. IF power is being provided by EDG, Operator VERIFIES that EDGs CHECK EDG loading prior to start of are not providing power to RHR pump(s). emergency buses.

Step 4

14. START RHR pump(s) in Loop B. At panel 2H11-P601, Operator Step 5 VERIFIES the 2B RHR pump is RUNNING, red light illuminated

15. IF TORUS Spray is desired, Operator DETERMINES that PERFORM the following: Torus Sprays cannot be placed in Step 6 service on 2B Loop of RHR so remainder of Step 6 is not required.

- 16. IF DRYWELL Spray is desired, At panel 2H11-P601, the PERFORM the following: Operator OPENS 2E11-F021B OPEN 2E11-F021B CNMT SPRAY INBD VLV.

Step 7.1 NOTE: To achieve the proper spray pattern from the nozzles, a Minimum Drywell Spray flow of at least 5,000 gpm is required.

- 17. THROTTLE OPEN 2E11-F016B The Operator THROTTLES Step 7.2 OPEN 2E11-F016B, CNMT SPRAY OUTBD VLV.

(** Indicates critical step)

CR-SIM 5 2016-301 Page 12 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 18. Operator establishes RHR Total flow The Operator ESTABLISHES to provide adequate drywell spray Total RHR Flow of >5000 gpm.

flow.

19. Operator verifies proper response. The Operator OBSERVES drop in Drywell pressure.

20. Refer to 34SO-E11-010-2, AND place Operator REFERS to 34SO-E11-RHR Hx into service. 010-2 Step 8 PROMPT: IF Operator proceeds to place RHR HX into service, INFORM the Operator another Operator will perform those actions.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when any of the following conditions are met:

Operator completes step 20 of this JPM.

With no reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

CR-SIM 5 2016-301 Page 13 of 14 Summary of JPM Attributes JPM CR-SIM 5 2016-301:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 5 Step 9 Operator TRIPS 2A RHR pump Action required protecting equipment from potential fire.

Step 11 PLACES switch to MANUAL Action required for opening drywell spray valves Step 16 OPENS 2E11-F021B Required to initiate drywell sprays.

Step 17 THROTTLES OPEN 2E11-F016B Required to establish drywell sprays.

Step 18 ESTABLISHES Total RHR Flow Minimum flow is >5000gpm for drywell sprays.

Number of JPM Steps <30 20 Time to Perform JPM <45 min 10 min Normal / Faulted /

Alternate Path Alternate While drywell sprays are being aligned in the 2A Loop of RHR the 2A RHR pump receives an overload condition but does not trip. This requires the operator to trip the 2A RHR pump and establish drywell sprays in the 2B Loop of RHR.

Setting (administered)

Simulator Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Torus pressure is greater than 11 psig.

31EO-EOP-012-2, PC Primary Containment Control is in progress.

2. 2E11-F027A, Torus Spray Valve, is bound closed and cannot be opened.

3. Drywell pressure and temperature are within the SAFE region of the Drywell Spray Initiation Limit Curve. (GRAPH 8).

4. Pre-Job Brief is NOT required.

INITIATING CUES:

Initiate Drywell sprays using the RHR Loop 2A per 34SO-E11-010-2.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 6 (RO & SRO-I)

Title:

Transfer an Emergency 4160 VAC Bus from the Emergency to the Normal Power Supply Author: Media Number: Time:

Anthony Ball CR-SIM 6 2016-301 20 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee: Date:

N/A N/A Approved By (Training Program Supervisor, Lead Instructor or Line Supervisor) Date:

Ed Jones N/A

This page intentionally left blank Course Number Program Name Media Number N/A OPERATIONS TRAINING CR-SIM 6 2016-301 Authors Sups Rev. No. Date Reason for Revisions Initials Initials 01 06/09/89 General revision and format change WGW RSG 02 08/24/89 Revise questions & add LR lesson plans JEM DHG 03 07/01/92 General revision and format change WMM DHG 04 09/23/93 General revision, word processor change RAB RSG 05 07/18/94 Correct for D/G loading, adjust format RAB SMC Correct simulator setup and prompts to include directions for the simulator 06 02/23/95 Operator to place speed drop and voltage regulator to the correct positions, RAB DHG adjust format, include phonetics in the initiating cue Format change, incorporate student comment about Unit 1 section 07 08/17/95 RAB SMC 08 07/05/96 Format change RAB SMC Revised based on comments from the 1997 annual exam.

09 10/01/97 SCB DHG Revised to make steps for direction of synchscope rotation, step 8 (U1) and 10 03/05/99 Step 9 (U2) noncritical. Revised for new simulator malfunction numbers. SCB DHG Format modification, change time allowance based on running average, 11 02/11/00 update to new simulator operating system RAB DHG TLB comment; change step 10 of U2 for voltage requirement of the diesel 12 03/29/00 RAB SMC Include objective number, TLB comment, correct Step 9 of Unit 1 section to 13 11/02/00 agree with procedure change RAB DHG Incorporate instructor comment on goal for power decrease of Step 12 for 14 03/11/02 Unit 2, include initial Operator statement RAB RAB 15 03/08/05 Documentum revision DNM RAB Revised Initial License statement for successful completion 16 06/13/05 RAB RAB 17 04/18/06 Remove Response Cues RAB RAB Changed note before step 8 from lightly loaded to > 500 KW to 18 09/17/08 JWP RAB correspond to procedure guidance.

Reviewed JPM against current procedure. Added Fundamental question to 18.1 10/17/11 Attachment 1. Added pass / fail criteria. Added 30AC-OPS-003 for resetting MMG ALS LOSP Lockout Relay. Added the following prompt, WHEN the Operator addresses Manual Start Permissive lights, INFORM the Operator that U-1 light is illuminated and U-2 light is extinguished.

Added Summary of JPM Attributes and changed wording to match 18.2 08/24/15 procedure including procedure step numbers. Deleted Unit 1 section, will MMG ALS perform in Simulator for Unit 2. Deleted fundamental question.

Reviewed JPM against current procedure.

Changed Media Number to CR-SIM 6 2016-18.3 05/30/16 ARB ELJ 301. After NRC Exam, Media Number will be changed back to LR-JP-02711.

Line Contributors The following individuals contributed to the development of this lesson plan.

Rev. No. List of Contributors

CR-SIM 6 2016-301 Page 5 of 14 UNIT 1 ( ) UNIT 2 (X)

TASK TITLE: Transfer an Emergency 4160 VAC Bus from the Emergency to the Normal Power Supply JPM NUMBER: CR-SIM 6 2016-301 TASK STANDARD: The task shall be completed when the Operator has transferred the 2F 4160 VAC Emergency Bus power supply from the associated Emergency Diesel to the D Startup Transformer, per 34SO-R43-001, with exception of placing the selected Diesel Generator in Standby.

TASK NUMBER: 027.011 OBJECTIVE NUMBER: 027.011.O PLANT HATCH JTA IMPORTANCE RATING:

RO 3.07 SRO 3.07 K/A CATALOG NUMBER: 262001A404 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.60 SRO 3.60 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 Unit 2 NA 34SO-R43-001-2, Ver 28.2 REQUIRED MATERIALS: Unit 1 Unit 2 NA 34SO-R43-001-2, Ver 28.2 APPROXIMATE COMPLETION TIME: 20 Minutes SIMULATOR SETUP: N/A

CR-SIM 6 2016-301 Page 6 of 14 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to IC # for 100% power or SNAP 616 and leave in FREEZE.

2. INSERT the following REMOTE FUNCTIONS:

Activator REM # Description Status RB 1 rfR43_241 Diesel Gen 1B Engine Control Switch UNIT 2 RB 2 rfR43_295 Diesel Gen 1B Engine Remote Speed Droop (0 to 100) 50 RB-3 rfR43_188 Diesel Gen 1B Unit 1 Voltage Reg Transfer MAN

3. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A. Open the Normal and Alternate supply breakers to Bus 2F.

B. Verify the 1B D/G output breaker closes and match flags on the breaker switch.

C. Place Diesel Generator B Volt Select switch in OFF position.

D. Ensure Diesel Generator load is greater than 500 kW.

E. Start another PSW pump on that bus.

4. PLACE the Simulator in FREEZE until the INITIATING CUE is given.

5. ESTIMATED Simulator SETUP TIME: 15 Minutes

Page 7 of 10 EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. 4160 VAC Emergency Bus 2F is being supplied from Emergency Diesel Generator 1B.

2. The condition that caused Bus 2F to de-energize has been corrected.

3. 4160 VAC Emergency Bus 2F is ready to be transferred to its normal power supply.

4. All procedure requirements have been met for the reset of the 4160V Bus 2F LOSP Lockout Relay.

5. A Systems Operator is stationed in the Emergency Diesel Generator 1B Room.

6. Pre-Job Brief is NOT required.

INITIATING CUES:

Transfer the 4160 VAC Bus 2F to the normal power supply.

CR-SIM 6 2016-301 Page 8 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

START TIME:_________

1. Operator determines the correct The Operator DETERMINES that procedure. procedure 34SO-R43-001-2, section 7.2.2.3 should be used.

2. Confirm power has been restored to At panel 2H11-P651, the Startup Transformers 2C OR 2D. Operator has VERIFIED that (potential lights for Startup Aux Xfmr SUT 2D potential lights are 2C OR 2D ILLUMINATED, panel illuminated.

2H11-P651)

(Step 7.2.2.3.1)

- 3. Reset 4160V Bus 2F LOSP Lockout At panel 2H11-P652, the Relay in accordance with NMP-OS- Operator RESETS BUS 2F 007-001, Conduct of Operations LOSP LOCKOUT RELAY.

Standards and Expectations, and (Switch TURNED clockwise and 31GO-OPS-021-0, Manipulation of HELD until its white light Controls and Equipment, AND illuminates).

(Step 7.2.2.3.2)

(** Indicates critical step)

CR-SIM 6 2016-301 Page 9 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

4. ******************************* At panel 2H11-P652, the

- - - - Operator CONFIRMS

- - - - , annunciator 652-202, LOSS OF AND, OFFSITE POWER, is clear.

confirm annunciator 652-202, LOSS OF OFF SITE POWER, is clear.

(Step 7.2.2.3.2)

- 5. Place Diesel Gen 1B Mode Select At panel 2H11-P652, the Switch in TEST. Operator PLACES Diesel Gen 1B (step 7.2.2.3.3) Mode Select Switch in TEST.

NOTE: SIMULATOR OPERATOR, WHEN the Operator addresses adjusting speed droop, the Simulator Operator will TOGGLE REMOTE FUNCTION rfR43241, (RB 1) Diesel Gen 1B Engine Control Switch to UNIT 2. As the SO, INFORM the Operator that Diesel Gen 1B Engine Control Switch has been placed to UNIT 2, (step 7.2.2.3.4).

6. Confirm Manual Start Permissive At panel 2H11-P652, the light is illuminated on 2H11-P652. Operator CONFIRMS Manual (Step 7.2.2.3.4.1) Start Permissive light is illuminated on 2H11-P652.

NOTE: SIMULATOR OPERATOR, WHEN the Operator addresses the Manual Start Permissive light on Unit 1, as the Unit 1 Operator, INFORMS the Operator that the Unit 1 Manual Start Permissive light is extinguished.

(Step 7.2.2.3.4.2)

NOTE: SIMULATOR OPERATOR, WHEN the Operator addresses adjusting speed droop, the Simulator Operator will TOGGLE REMOTE FUNCTION rfR43295, (RB 2) D/G 1B Engine Remote Speed Droop (0 to 100), to 50. As the SO, INFORM the Operator that speed droop has been adjusted to 50. (Step 7.2.2.3.5)

(** Indicates critical step)

CR-SIM 6 2016-301 Page 10 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

NOTE: SIMULATOR OPERATOR, WHEN the Operator addresses the position of the Unit 1 Voltage Regulator Transfer switch, the Simulator Operator will TOGGLE REMOTE FUNCTION rfR43188, (RB 3) Diesel Gen 1B Unit 1 Voltage Reg Transfer, to MAN. As the Unit 1 Control Room Operator, INFORM the Operator that the Unit 1 Voltage Regulator Transfer switch is in manual. (Step 7.2.2.3.6)

- 7. Place OR confirm Diesel Gen 1B At panel 2H11-P652, the Voltage Reg Transfer switch to Operator PLACES VOLTAGE MANUAL, panel 2H11-P652. REG TRANSFER switch in MANUAL, green light (Step 7.2.2.3.7) illuminated.

- 8. Place Synch Switch (SSW) in ON for: At panel 2H11-P652, the ACB 135574, 4160V Bus 2F Normal Operator PLACES SSW ACB Supply, 135574, in the ON position.

OR ACB 135564, 4160V Bus 2F Alternate Supply.

(Step 7.2.2.3.8)

NOTE: Diesel Generator B Volt Select switch must be turned on to check DG voltage.

9. Adjust the Diesel Gen 1B Voltage At panel 2H11-P652, the Adjust switch UNTIL diesel output Operator ADJUSTS the 1B voltage is equal to 4160V. DIESEL GEN B VOLTAGE ADJUST switch as necessary to (Step 7.2.2.3.9) indicate approximately 4160 volts on VOLTMETER for 4KV BUS 2F.

NOTE: For performance of this JPM, the Diesel Generator is Heavly loaded (> 500 KW).

- 10. Using Diesel Gen 1 B Speed Adjust At panel 2H11-P652, the switch, adjust diesel speed to attain a Operator ADJUSTS the DIESEL slow synchroscope rotation in the GEN B SPEED ADJUST switch desired direction (1 to 3 rpm). as needed until the Synchroscope (Step 7.2.2.3.10) rotation is in the CLOCKWISE direction at 1 to 3 rpm.

(** Indicates critical step)

CR-SIM 6 2016-301 Page 11 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 11. Using Diesel Gen 1B Voltage Adjust, At panel 2H11-P652, the adjust Diesel Gen 1B output voltage Operator ADJUSTS Diesel output to match the highest phase of the voltage using DIESEL GEN B, incoming source (Startup Transformer VOLTAGE ADJUST to match 2D (normal) OR 2C (alternate)). the highest phase of SUT 2D Winding 2. Operator does not (Step 7.2.2.3.11) exceed 4400 volts on any phase.

NOTE: For the purpose of this JPM, +/-100 volts is considered matched.

- 12. WHEN the sychroscope indicates 2 At panel 2H11-P652, the minutes to 12 AND Operator TAKES 4160 2F, WHEN the synchroscope lights NORMAL SUPPLY ACB approach the dimmest point, take: 135574 control switch to CLOSE, ACB 135574, 4160V 2F Normal (when synchroscope is 2 minutes Supply, to 12:00 position and when the OR synchroscope lights approach the dimmest point, then released to ACB 135564, Alternate Suppy, the midposition, red light To CLOSE. illuminated.)

(Step 7.2.2.3.12)

NOTE: If the synchroscope for ACB 135574 was not energized the breaker remains OPEN, green light on.

13. Using the Diesel Gen 1B Speed At panel 2H11-P652, the Adjust switch, decrease the load on Operator ADJUSTS the DIESEL diesel to between 400 AND 500 KW GEN B, VOLT ADJUST and WHILE maintaining diesel reactive SPEED ADJUST switches as load between 400 AND 500 KVAR, necessary to reduce load on using Diesel Gen 1B Voltage Adjust Diesel to 400-500 KW while switch. maintaining 400-500 KVAR.

(Step 7.2.2.3.13)

- 14. Take ACB 135570, Diesel Gen 1B At panel 2H11-P652, the Emergency Supply, control switch to Operator TAKES DIESEL GEN TRIP. B, EMERGENCY SUPPLY ACB (Step 7.2.2.3.14) 135570 control switch to TRIP and released to midposition, green light illuminated.

(** Indicates critical step)

CR-SIM 6 2016-301 Page 12 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

15. Confirm ACB 135570, Diesel Gen 1B At panel 2H11-P652, the Emergency Supply, green (OPEN) Operator IDENTIFIES that the light is ILLUMINATED. DIESEL GEN B, EMERGENCY (Step 7.2.2.3.15) SUPPLY ACB 135570 green light is illuminated.

16. Place Synch Switch (SSW) in OFF At panel 2H11-P652, the for: Operator PLACES SSW ACB 135574 in OFF.

ACB 135574, 4160V Bus Normal Supply OR ACB 135564, Alternate Supply.

(Step 7.2.2.3.16)

PROMPT: WHEN the Operator addresses securing of the Diesel Generator, as the Shift Supervisor, INFORM the Operator that another Operator will shutdown the Diesel Generator.

END TIME: _________

NOTE: The terminating cue shall be given to the operator when any of the following conditions are met:

Operator completes Step 16 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

CR-SIM 6 2016-301 Page 13 of 14 Summary of JPM Attributes JPM CR-SIM 6 2016-301:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 8 Step 3 Reset Lockout Relay Operator must reset Lockout Relay to be able to close the normal supply breaker.

Step 5 EDG in Test Operator must place Mode Select Switch to TEST to be able to parallel sources.

Step 7 Volt Reg to Manual Voltage Reg is transferred to manual to allow voltage to be adjusted.

Step 8 Synch Switch ON Operator must place synch switch for normal breaker to ON to defeat interlock so breaker can be closed.

Step 10 Adjust Speed Operator must adjust speed to obtain proper rotation.

Step 11 Adjust Voltage Operator must adjust voltage to limit the initial VARS Step 12 Close Norm Bkr To supply power from normal supply, the breaker must be closed.

Step 14 Open EDG Bkr To un-parallel electrical sources, must open EDG output breaker.

Number of JPM Steps <30 16 Time to Perform JPM <45 min 20 min Normal / Faulted /

Alternate Path Normal Operator is told to transfer power from the 1B EDG to the normal supply.

Setting (administered)

Simulator Is LOD 1 or 5 NO NO

CR-SIM 6 2016-301 Page 14 of 14 UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. 4160 VAC Emergency Bus 2F is being supplied from Emergency Diesel Generator 1B.

2. The condition that caused Bus 2F to de-energize has been corrected.

3. 4160 VAC Emergency Bus 2F is ready to be transferred to its normal power supply.

4. All procedure requirements have been met for the reset of the 4160V Bus 2F LOSP Lockout Relay.

5. A Systems Operator is stationed in the Emergency Diesel Generator 1B Room.

6. Pre-Job Brief is NOT required.

INITIATING CUES:

Transfer the 4160 VAC Bus 2F to the normal power supply.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 7 (RO Only)

Title:

Conduct a Rod Worth Minimizer (RWM) Functional Test (Failure)

Author: Media Number: Time:

Anthony Ball CR-SIM 7 2016-301 10.0 Minutes Line Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee (N/A for minor revisions) Date:

N/A N/A Approved By (Training Program Supervisor or Lead Instructor) Date:

Ed Jones 05/30/16

Page 2 of 12 Course Number Program Name Media Number N/A OPERATIONS TRAINING CR-SIM 7 2016-301 Authors Sups Ver. No. Date Reason for Revisions Initials Initials 00 11/15/99 Initial development RAB DHG 01 11/06/00 Include objective number RAB DHG 02 03/19/02 Include initial operator statement RAB RAB Deleted S from procedure numbers, changed Revision and Rev. numbers to Current Version.

03 03/17/05 Changed to Nuclear Plant Operator. Updated ARB DHG Simulator IC# and added Prompt for sequence control mode.

Revised Initial License statement for successful 04 06/27/05 completion RAB RAB 05 06/30/05 Remove Response Cues RAB RAB Reviewed JPM against current procedure. Added pass / fail criteria. Added Fundamental question to 05.1 10/17/11 new Attachment 1. Corrected JPM to reflect what MMG ALS a Rod Group 3 and 4 rod is. Added prompt to tell student what Step a Rod Group 3 & 4 is.

Reviewed JPM against current procedure for use on 2016-301 NRC Exam. Changed the Media 05.2 05/30/16 Number to CR-SIM 7 2016-301. Deleted ARB ELJ Attachment 1 (Fundamental Question).

Page 3 of 12 Line Contributors The following individuals contributed to the development of this lesson plan.

Ver. No. List of Contributors 05.1 MMG

CR-SIM 7 2016-301 Page 4 of 12 UNIT 1 () UNIT 2 (X)

TASK TITLE: Conduct a Rod Worth Minimizer (RWM) Functional Test (Failure)

JPM NUMBER: CR-SIM 7 2016-301 TASK STANDARD: The task shall be completed when the operator has successfully conducted the Rod Worth Minimizer Functional Test per 34GO-OPS-001.

TASK NUMBER: 001.014 OBJECTIVE NUMBER: 001.014.A PLANT HATCH JTA IMPORTANCE RATING:

RO 3.40 SRO 2.85 K/A CATALOG NUMBER: 201006A302 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.40 SRO 3.50 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 Unit 2 N/A 34GO-OPS-001-2, Att 5, Ver 47.1 34GO-OPS-065-0, Ver 12.6 34AB-C11-004-2, Ver 4.1 Control Rod Movement Sequence REQUIRED MATERIALS: Unit 1 Unit 2 N/A 34GO-OPS-001-2, Att 5, Ver 47.1 Control Rod Movement Sequence APPROXIMATE COMPLETION TIME: 10.0 Minutes SIMULATOR SETUP: Refer to Simulator Setup sheet on the following page.

CR-SIM 7 2016-301 Page 5 of 12 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to All Rods IN and leave in FREEZE.

2. ACTIVATE the following Event Trigger:

Trigger # DESCRIPTION CONDITIONS EGC91-01 Inserts Override C91-J001 f2 loC51-RS-10-43B1.algToPanel=1 EGC91-02 Inserts Override C91-J001 f2 loC51-RS-42-11B1.algToPanel=1 EGC91-03 Inserts Override C91-J001 f2 loC51-RS-10-11B1.algToPanel=1 EGC91-04 Inserts Override C91-J001 f2 loC51-RS-42-43B1.algToPanel=1

3. INSERT the following REMOTE FUNCTIONS:

REM # DESCRIPTION STATUS rfC51_190 RWM Sequence Control ON

4. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A. RESET all annunciators.

B. SELECT a Control Rod from Step 1 and initialize the RWM by pushing the ETC button on the operator display.

C. VERIFY that all RWM rod blocks are clear D. VERIFY the Rod Sequence Selector Switch is in A12 (B12).

E. VERIFY RWM Sequence Control is in the ON position.

4. PLACE the Simulator in FREEZE until the crew assumes the shift.

5. ESTIMATED Simulator SETUP TIME: 10 Minutes

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. The Reactor is shutdown; the manual scram has been reset.

2. The Unit 2 Refueling Bridge has been confirmed to have power.

3. 34GO-OPS-001-2, Plant Startup, is in progress.

4. The RWM Instrument Console's keylock switch at panel 2H11-P616 is in the OPERATE position.

5. Reactor Engineering has confirmed the following:

Steps 1.3.1, 1.3.2 & 1.3.3 of Attachment 5 are complete

Rod Group 3 Step16

Rod Group 4 Step 34 INITIATING CUES:

Perform the Rod Worth Minimizer Functional Test using Attachment 5 of 34GO-OPS-001-2.

CR-SIM 1 2016-301 Page 7 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

START TIME:_________

1. Confirm RMCS/RWM ROD BLOCK At panel 2H11-P603, the operator OR SYS TROUBLE annunciator is VERIFIES that the annunciator clear. 603-239, RMCS/RWM ROD BLOCK OR SYS TROUBLE, is extinguished.

2. Confirm RWM keylock switches are At panel 2H11-P603, the in OPERATE. Operators Display keylock switch is in OPERATE.

Initial Conditions states that the keylock switch at panel 2H11-P616 is in OPERATE.

(** Indicates critical step)

CR-SIM 1 2016-301 Page 8 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

3. Confirm Step 01 is displayed on At panel 2H11-P603, the operator RWM Operators Display. has VERIFIED that 01 is displayed on the RWM Operators Display.

4. Confirm the Reactor Mode switch is At panel 2H11-P603, the operator in START & HOT STBY. places or CONFIRMS the Reactor Mode switch is in START & HOT STBY.

5. Select a rod from Step 2 of the Rod At panel 2H11-P603, using the .

Worth Minimizer Sequence and verify CONTROL ROD SELECT system response. matrix pushbuttons, a rod is SELECTED from Step 2 of the RWM Sequence AND At the RWM operators display, the operator has CONFIRMED "SE" appears on the RWM Operator's Display and the Message Section confirms a Withdrawal Block exists due to a Select Error.

NOTE: If the operator selects any rod NOT in Step 1 of the RWM Sequence, they will still receive the same indications as a Step 2 rod.

6. Attempt to withdraw the selected rod. At panel 2H11-P603, the operator VERIFIES no rod motion occurred.

PROMPT: WHEN the operator asks the STA/RE for a Rod Group 3 rod, INFORM the operator to refer to the Initial Conditions.

(** Indicates critical step)

CR-SIM 1 2016-301 Page 9 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

7. Select a rod from Rod Group 3 of the At panel 1H11-P603, using the Rod Worth Minimizer Sequence and CONTROL ROD SELECT verify system response. matrix pushbuttons, a rod is SELECTED from Group 3 Step 16 of the RWM Sequence AND At the RWM operators display, the operator has CONFIRMED "SE" appears on the RWM Operator's Display and the Message Section confirms a Withdrawal Block exists due to a Select Error.

8. Attempt to withdraw the selected rod. At panel 2H11-P603, the operator VERIFIES no rod motion occurred.

NOTE: When the operator selects a Step 34 Group 4 rod, an Event Trigger will ACTIVATE OVERRIDE C91_J001DI to BYPASS.

PROMPT: WHEN the operator asks the STA/RE for a Rod Group 4 rod, INFORM the operator to refer to the Initial Conditions.

- 9. Select a rod from Rod Group 4 of the At panel 2H11-P603, using the Rod Worth Minimizer Sequence and CONTROL ROD SELECT verify system response. matrix pushbuttons, a rod is SELECTED from Group 4 Step 34 of the RWM Sequence AND At the RWM operators display, the operator has CONFIRMED "SE" appears on the RWM Operator's Display and the Message Section confirms a Withdrawal Block exists due to a Select Error.

- 10. Attempt to withdraw the selected rod. At panel 2H11-P603, the operator RECOGNIZES that the control rod moved.

(** Indicates critical step)

CR-SIM 1 2016-301 Page 10 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 11. Insert the control rod and notify the At panel 2H11-P603, the operator SS that the RWM failed its operability INSERTS the control rod to the check. full in position; AND, Notifies the SS that the RWM has failed its operability check.

PROMPT: IF addressed by the operator, INFORM the operator that the STA has confirmed the RWM Scram Buffers are clear and ready to accept data.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when any of the following conditions are met:

Operator completes step 11 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: Another operator will continue from here.

(** Indicates critical step)

CR-SIM 7 2016-301 Page 11 of 12 Summary of JPM Attributes JPM CR-SIM 2 2016-301:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 3 Step 9 Selects Group 4 rod Proper rod to confirm RWM operation.

Step 10 Attempts to move Gr 4 Recognizes rod moved.

Step 11 Inserts Gr. 4 rod/notifies SS Proper procedure response for failed RWM.

Number of JPM Steps

<30 25 Time to Perform JPM

<45 min 10 min Normal / Faulted /

Alternate Path Alternate Path RWM has failed the operability test by allowing a control rod to be moved when it should not have.

Setting (administered)

Simulator Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. The Reactor is shutdown; the manual scram has been reset.

2. The Unit 2 Refueling Bridge has been confirmed to have power.

3. 34GO-OPS-001-2, Plant Startup, is in progress.

4. The RWM Instrument Console's keylock switch at panel 2H11-P616 is in the OPERATE position.

5. Reactor Engineering has confirmed the following:

Steps 1.3.1, 1.3.2 & 1.3.3 of Attachment 5 are complete

Rod Group 3 Step16

Rod Group 4 Step 34 INITIATING CUES:

Perform the Rod Worth Minimizer Functional Test using Attachment 5 of 34GO-OPS-001-2.

Page 1 of 14 Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL CR-SIM 8 (ALL)

Title:

Perform 34IT-T45-001-2, Reactor Building Instrument Sumps Isolation Valve Exercise Author: Media Number: Time:

Richard A. Greenhouse CR-SIM 8 2016-301 15 Minutes Line Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee (N/A for minor revisions) Date:

N/A N/A Approved By (Training Program Supervisor or Lead Instructor) Date:

Ed Jones 05/30/16

Page 2 of 14 This page intentionally left blank

Page 3 of 14 Course Number Program Name Media Number N/A OPERATIONS TRAINING CR-SIM 8 2016-301 Authors Sups Ver. No. Date Reason for Revisions Initials Initials Initial development for use on 2016-301 NRC 00 05/30/16 RAG ELJ Exam.

Page 4 of 14 Line Contributors The following individuals contributed to the development of this lesson plan.

Ver. No. List of Contributors

CR-SIM 8 2016-301 Page 5 of 14 UNIT 1 () UNIT 2 (X)

TASK TITLE: Perform 34IT-T45-001-2, Reactor Building Instrument Sumps Isolation Valve Exercise JPM NUMBER: CR-SIM 8 2016-301 TASK STANDARD: This task shall be successfully completed when all of the JPM Critical Steps corresponding to 34IT-T45-001-2, Sections 7.2, 7.3 and 7.4, have been correctly performed to complete the Instrument Sump Isolation Valve exercise.

K/A CATALOG NUMBER: 268000K1.04 K/A CATALOG JTA IMPORTANCE RATING:

RO 2.7 SRO 2.9 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 Unit 2 NA 34IT-T45-001-2, Ver 0.9 REQUIRED MATERIALS: Unit 1 Unit 2 NA 34IT-T45-001-2, Ver 0.9 APPROXIMATE COMPLETION TIME: 15 Minutes SIMULATOR SETUP: Refer to Simulator Setup sheet on the following page.

CR-SIM 8 2016-301 Page 6 of 14 SIMULATOR SETUP Simulator Initial Conditions:

1. RESET the Simulator to IC for 100% RTP and leave in FREEZE.

2. Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:

A. None

3. PLACE the Simulator in FREEZE until the INITIATING CUE is given.

4. ESTIMATED Simulator SETUP TIME: 5 Minutes

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is operating at 100% RTP.

2. 34IT-T45-001-2, Reactor Building Instrument Sumps Isolation Valve Exercise, is in progress. Section 7.1 of 34IT-T45-001-2 is complete.

3. A designated operator is stationed as required to support valve manipulations.

INITIATING CUES:

Perform 34IT-T45-001-2, Reactor Building Instrument Sumps Isolation Valve Exercise, sections 7.2, 7.3 and 7.4.

CR-SIM 8 2016-301 Page 8 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

START TIME:_________

NOTE To Evaluator: Perform the turn-over for this JPM prior to entering the simulator when possible (i.e allow the student to review the procedure in the Virtual Simulator or Simulator Assessment Room, etc.) Doing this will minimize the time the simulator is not being actively used.

PROMPT: WHEN the operator addresses obtaining permission from the Shift Supervisor, INFORM the operator that permission has been granted.

1. Confirm the Sump Isol switch for At panel 2H11-P654, the operator 2T45-F005, 2T45-F003, and 2T45- confirms the control switch for F001 is in CLOSED, panel 2H11- 2T45-F005, 2T45-F003 and P654. 2T45-F001 is in the CLOSE (Step 7.2.1) position.

CR-SIM 8 2016-301 Page 9 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

2. Confirm the following valves are At panel 2H11-P654, the operator CLOSED: confirms the following:

2T45-F005, RHR N-E Inbd Sump 2T45-F005 is CLOSED, green Isol light illuminated.

2T45-F003, Torus N-E & S-E 2T45-F003 is CLOSED, green Inbd Sump Isol light illuminated.

2T45-F001, HPCI Sump Isol 2T45-F001 is CLOSED, green light illuminated.

(Step 7.2.2)

- 3. Place the Sump Isol switch for 2T45- At panel 2H11-P654, the operator F005, 2T45-F003, and 2T45-F001, in places the control switch for AUTO: 2T45-F005, 2T45-F003 and

2T45-F005 2T45-F001 in the AUTO position.

2T45-F003

2T54-F001 (Step 7.2.3)

4. Confirm the following valves OPEN: At panel 2H11-P654, the operator confirms the following:

2T45-F005

2T45-F003 2T45-F005 is OPEN, red light

2T45-F001 illuminated.

2T45-F003 is OPEN, red light illuminated.

2T45-F001 is OPEN, red light (Step 7.2.4) illuminated.

- 5. Place the Sump Isol switch for 2T45- At panel 2H11-P654, the operator F005, 2T45-F003, and 2T45-F001 in places the control switch for CLOSE: 2T45-F005, 2T45-F003 and 2T45-F001 in the CLOSE

2T45-F005, RHR N-E Inbd Sump position.

Isol

2T45-F003, Torus N-E & S-E Inbd Sump Isol

2T45-F001, HPCI Sump Isol (Step 7.2.5)

CR-SIM 8 2016-301 Page 10 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

6. Confirm the following valves CLOSE: At panel 2H11-P654, the operator confirms the following:

2T45-F005, RHR N-E Inbd Sump Isol 2T45-F005 is CLOSED, green

2T45-F003, Torus N-E & S-E light illuminated.

Inbd Sump Isol 2T45-F003 is CLOSED, green

2T45-F001, HPCI Sump Isol light illuminated.

2T45-F001 is CLOSED, green (Step 7.2.6) light illuminated.

7. Confirm the Sump Isol switch for At panel 2H11-P654, the operator 2T45-F007 and 2T45-F006 is in confirms the control switch for CLOSED, panel 2H11-P654. 2T45-F007 and 2T45-F006 is in (Step 7.3.1) the CLOSE position.

8. Confirm the following valves are At panel 2H11-P654, the operator CLOSED: confirms the following:

2T45-F007, Torus N-W & S-W 2T45-F007 is CLOSED, green Inbd Sump Isol light illuminated.

2T45-F006, RCIC Sump Isol 2T45-F006 is CLOSED, green (Step 7.3.2) light illuminated.

- 9. Place the Sump Isol switch for 2T45- At panel 2H11-P654, the operator F007 and 2T45-F006 in AUTO: places the control switch for

2T45-F007 2T45-F007 and 2T45-F006 in the AUTO position.

2T45-F006 (Step 7.3.3)

10. Confirm the following valves OPEN: At panel 2H11-P654, the operator confirms the following:

2T45-F007

2T45-F006 2T45-F007 is OPEN, red light illuminated.

(Step 7.3.4) 2T45-F006 is OPEN, red light illuminated.

- 11. Place the Sump Isol switch for 2T45- At panel 2H11-P654, the operator F007 and 2T45-F006 in CLOSE: places the control switch for 2T45-F007 and 2T45-F006 in the

2T45-F007, Torus N-W & S-W CLOSE position.

Inbd Sump Isol

2T45-F006, RCIC Sump Isol (Step 7.3.5)

CR-SIM 8 2016-301 Page 11 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

12. Confirm the following valves CLOSE: At panel 2H11-P654, the operator confirms the following:

2T45-F007, Torus N-W & S-W Inbd Sump Isol 2T45-F007 is CLOSED, green

2T45-F006, RCIC Sump Isol light illuminated.

(Step 7.3.6) 2T45-F006 is CLOSED, green light illuminated.

13. Confirm the Sump Isol switch for At panel 2H11-P654, the operator 2T45-F004 and 2T45-F002 is in observes the control switch for CLOSED, panel 2H11-P654. 2T45-F004 and 2T45-F002 is in the CLOSE position.

(Step 7.4.1)

14. Confirm the following valves are At panel 2H11-P654, the operator CLOSED: confirms the following:

2T45-F004, RHR N-E Outbd 2T45-F004 is CLOSED, green Sump Isol light illuminated.

2T45-F002, Torus N-E & S-E 2T45-F002 is CLOSED, green Outbd Sump Isol light illuminated.

(Step 7.4.2)

- 15. Place the Sump Isol switch for 2T45- At panel 2H11-P654, the operator F004 and 2T45-F002 in AUTO: places the control switch for

2T45-F004 2T45-F004 and 2T45-F002 in the AUTO position.

2T45-F002 (Step 7.4.3)

16. Confirm the following valves OPEN: At panel 2H11-P654, the operator confirms the following:

2T45-F004

2T45-F002 2T45-F004 is OPEN, red light illuminated.

(Step 7.4.4) 2T45-F002 is OPEN, red light illuminated.

- 17. Place the Sump Isol switch for 2T45- At panel 2H11-P654, the operator F004 and 2T45-F002 in CLOSE: places the control switch for 2T45-F004 and 2T45-F002 in the

2T45-F004, RHR N-E Outbd CLOSE position.

Sump Isol

2T45-F002, Torus N-E & S-E Sump Isol (Step 7.4.5)

CR-SIM 8 2016-301 Page 12 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

18. Confirm the following valves CLOSE: At panel 2H11-P654, the operator confirms the following:

2T45-F004, RHR N-E Outbd Sump Isol 2T45-F004 is CLOSED, green

2T45-F002, Torus N-E & S-E light illuminated.

Sump Isol 2T45-F002 is CLOSED, green (Step 7.4.6) light illuminated.

PROMPT: ONCE the operator has completed Step 7.4.6, INFORM the operator that another operator will complete the restoration section of the procedure.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when any of the following conditions are met:

Operator completes step 18 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

CR-SIM 8 2016-301 Page 13 of 14 Summary of JPM Attributes JPM CR-SIM 8 2016-301:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 6 Step 3 Place the switch for 2T45-F005, Confirm operability of isolation valves in F003 and F001 in AUTO the OPEN position Step 5 Place the switch for 2T45-F005, Confirm operability of isolation valves in F003 and F001 in CLOSE the CLOSE position Step 9 Place the switch for 2T45-F006 Confirm operability of isolation valves in and F007 in AUTO the OPEN position Step 11 Place the switch for 2T45-F006 Confirm operability of isolation valves in and F007 in CLOSE the CLOSE position Step 15 Place the switch for 2T45-F002 Confirm operability of isolation valves in and F004 in AUTO the OPEN position Step 17 Place the switch for 2T45-F002 Confirm operability of isolation valves in and F004 in CLOSE the CLOSE position Number of JPM Steps <30 18 Time to Perform JPM <45 min 15 min Normal / Faulted /

Alternate Path Normal Complete sections 7.2, 7.3 and 7.4 of 34IT-T45-001-2.

Setting (administered)

Simulator Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is operating at 100% RTP

2. 34IT-T45-001-2, Reactor Building Instrument Sumps Isolation Valve Exercise, is in progress. Section 7.1 of 34IT-T45-001-2 is complete.

INITIATING CUES:

Perform 34IT-T45-001-2, Reactor Building Instrument Sumps Isolation Valve Exercise, sections 7.2, 7.3 and 7.4.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL PLANT 1 (ALL)

Title:

From Outside the MCR, Insert a Manual Reactor Scram (Alternate Path)

Author: Media Number: Time:

Anthony Ball PLANT 1 2016-301 14 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A Reviewed by Instructional Technologist or designee: Date:

N/A Approved By (Training Program Supervisor, Lead Instructor or Line Supervisor) Date:

Ed Jones 05/30/16

This page intentionally left blank Course Number Program Name Media Number N/A OPERATIONS TRAINING PLANT 1 2016-301 Authors Sups Rev. No. Date Reason for Revisions Initials Initials Initial development. A manual scram by opening RPS breakers will not work forcing the Operator to use the SDV Level Switches in the Reactor 0.0 08/06/15 MMG ALS Building. Added Summary of JPM Attributes and changed wording to match procedure including procedure step numbers.

Reviewed JPM against current procedure for use on 2016-301 NRC Exam. Changed Media number 0.1 05/30/16 ARB ELJ to PLANT 1 2016-301 and will be returned to LR-JP-01018A after 2016-301 NRC Exam.

Line Contributors The following individuals contributed to the development of this lesson plan.

Rev. No. List of Contributors

UNIT 1 (X) UNIT 2 (X)

TASK TITLE: From Outside the MCR, Insert a Manual Reactor Scram (Alternate Path)

JPM NUMBER: PLANT 1 2016-301 TASK STANDARD: The task shall be completed when the operator has successfully inserted a reactor scram using the SDV Level Switches per 31RS-OPS-001 by tripping magnetrol switches 1C11-N013A & B OR 1C11-N013C & D.

TASK NUMBER: 010.018 OBJECTIVE NUMBER: 010.018.A PLANT HATCH JTA IMPORTANCE RATING:

RO 4.20 SRO 4.67 K/A CATALOG NUMBER: 201001A221 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.6 SRO 3.9 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 Unit 2 31RS-OPS-001-1, Ver 5.24 31RS-OPS-001-2, Ver 6.23 REQUIRED MATERIALS: Unit 1 Unit 2 31RS-OPS-001-1, Ver 5.24 31RS-OPS-001-2, Ver 6.23 APPROXIMATE COMPLETION TIME: 14 Minutes SIMULATOR SETUP: N/A

EVALUATOR COPY UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. A condition has occurred which required the Control Room to be evacuated.

2. The Reactor is NOT shutdown.

3. 31RS-OPS-001-1, Shutdown From Outside the Control Room, is in progress.

4. Pre-Job Brief is NOT required.

INITIATING CUES:

Insert a Manual Scram by de-energizing RPS per 31RS-OPS-001-1.

PLANT 1 2016-301 Page 7 of 21 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

START TIME:__________

1. Operator identifies the procedure The Operator has IDENTIFIED needed to perform the task. the correct procedure as 31RS-OPS-001-1, step 4.4.

2. De-energize RPS. At panel 1C71-P001, the OPEN the following breakers at RPS Operator OPENS breaker distribution panel 1C71-P001: 1C71-CB3A.

1C71-CB3A (Step 4.4.1.1)

3. De-energize RPS. At panel 1C71-P001, the Operator ATTEMPTS to open OPEN the following breakers at RPS breaker 1C71-CB3B. The distribution panel 1C71-P001:

Operator RECOGNIZES that the

********** breaker will not reposition.

1C71-CB3B (Step 4.4.1.1)

(** Indicates critical step)

PLANT 1 2016-301 Page 8 of 21 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

PROMPT: WHEN the Operator attempts to open breaker 1C71-CB3B, INFORM the Operator that the breaker did NOT reposition and can not be moved.

PROMPT: IF the Operator requests direction from the Shift Supervisor, INFORM the Operator to Insert a Manual Scram per 31RS-OPS-001-1.

NOTE: The Operator may elect to reclose breaker 1C71-CB3A prior to addressing the SDV Level Switches.

ALTERNATE PATH STARTS HERE (Step 4)

NOTE: The critical steps will be either steps 4, 5, 8, and 9 OR steps 6, 7, 10, and 11. Both switches on one side of the Reactor Building will insert a Full Reactor Scram. To receive credit, the Operator ONLY has to trip both magnetrol switches on one side of the Reactor Building.

- 4. Scram Discharge Volume Level At location 139RER11, the Switches. Operator REMOVES the cover At the Scram Discharge Volume, remove from magnetrol switch the covers to one of the following sets of 1C11-N013A.

level switches:

1C11-N013A and *********

OR (Step 4.4.2.1)

- 5. Scram Discharge Volume Level Switches. At location 139RER11, the At the Scram Discharge Volume, remove Operator REMOVES the cover the covers to one of the following sets of from magnetrol switch level switches: 1C11-N013B.

- - - - and 1C11-N013B, OR (Step 4.4.2.1)

NOTE: The Operator may remove the covers for 1C11-N013A and B, then trip their magnetrol switches and replace their covers. The Operator may stop there or proceed to performing the same actions for 1C11-N013C and D.

(** Indicates critical step)

PLANT 1 2016-301 Page 9 of 21 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 6. Scram Discharge Volume Level Switches. At location 139RER03, the At the Scram Discharge Volume, remove Operator REMOVES the cover the covers to one of the following sets of from magnetrol switch level switches: 1C11-N013C.

OR 1C11-N013C and ************

(Step 4.4.2.1)

- 7. Scram Discharge Volume Level Switches. At location 139RER03, the At the Scram Discharge Volume, remove Operator REMOVES the cover the covers to one of the following sets of from magnetrol switch level switches: 1C11-N013D.

OR

- - - - and 1C11-N013D (Step 4.4.2.1)

- 8. Trip magnetrol switches for the At location 139RER11, the switches with removed covers: Operator TRIPS magnetrol switch 1C11-N013A and ***********, 1C11-N013A.

OR (Step 4.4.2.2)

- 9. Trip magnetrol switches for the At location 139RER11, the switches with removed covers: Operator TRIPS magnetrol

- - - - and 1C11-N013B, switche 1C11-N013B.

OR (Step 4.4.2.2)

- 10. Trip magnetrol switches for the At location 139RER03, the switches with removed covers: Operator TRIPS magnetrol

- - - - , switche 1C11-N013C.

OR 1C11-N013C and **********

(Step 4.4.2.2)

(** Indicates critical step)

PLANT 1 2016-301 Page 10 of 21 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 11. Trip magnetrol switches for the At location 139RER03, the switches with removed covers: Operator TRIPS magnetrol

- - - - , switche 1C11-N013D.

OR

- - - - AND 1C11-N013D (Step 4.4.2.2)

12. Replace the covers to the magnetrol Operator REPLACES all switches. removed magnetrol switch (Step 4.4.2.3) covers.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when any of the following conditions are met:

Operator completes step 12 of this JPM.

With no reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: Another operator will continue from here.

(** Indicates critical step)

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. A condition has occurred which required the Control Room to be evacuated.

2. The Reactor is NOT shutdown.

3. 31RS-OPS-001-2, Shutdown From Outside the Control Room, is in progress.

4. Pre-Job Brief is NOT required.

INITIATING CUES:

Insert a Manual Scram by de-energizing RPS per 31RS-OPS-001-2.

PLANT 1 2016-301 Page 12 of 21 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Start Time:_________

1. Operator identifies the procedure Operator has IDENTIFIED the needed to perform the task. correct procedure as 31RS-OPS-001-2 step 4.4

2. De-energize RPS. At panel 2C71-P001, the OPEN the following breakers at RPS Operator OPENS breaker distribution panel 2C71-P001, 2C71-CB3A.

at 130TGT12.

2C71-CB3A (Step 4.4.1.1)

(** Indicates critical step)

PLANT 1 2016-301 Page 13 of 21 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

3. De-energize RPS. At panel 2C71-P001, the Operator ATTEMPTS to open OPEN the following breakers at RPS distribution panel 2C71-P001, breaker 2C71-CB3B. The Operator RECOGNIZES that the at 130TGT12.

breaker will not reposition.

2C71-CB3B (Step 4.4.1.1)

PROMPT: WHEN the Operator attempts to open breaker 2C71-CB3B, INFORM the Operator that the breaker did NOT reposition and can not be moved.

PROMPT: IF the Operator requests direction from the Shift Supervisor, INFORM the Operator to Insert a Manual Scram per 31RS-OPS-001-2.

NOTE: The Operator may elect to reclose breaker 2C71-CB3A prior to addressing the SDV Level Switches.

ALTERNATE PATH STARTS HERE (Step 4)

NOTE: The critical steps will be either steps 4, 5, 8, and 9 OR steps 6, 7, 10, and 11. Both switches on one side of the Reactor Building will insert a Full Reactor Scram. To receive credit, the Operator ONLY has to trip both magnetrol switches on one side of the Reactor Building.

- 4. Scram Discharge Volume Level Switches. At location 130RBR15, the Remove the covers to 2C11-N013A & Operator REMOVES the cover

- - - - , Magnetrol Switches, from magnetrol switch at 130RBR15 ******************* 2C11-N013A.

(Step 4.4.2.1)

- 5. Scram Discharge Volume Level Switches. At location 130RBR15, the Remove the covers to ********* & Operator REMOVES the cover 2C11-N013B, Magnetrol Switches, from magnetrol switch at 130RBR15 ******************* 2C11-N013B.

(Step 4.4.2.1)

(** Indicates critical step)

PLANT 1 2016-301 Page 14 of 21 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

NOTE: The Operator may remove the covers for 2C11-N013A and B, then trip their magnetrol switches and replace their covers. The Operator may stop there or proceed to performing the same actions for 2C11-N013C and D.

- 6. Scram Discharge Volume Level Switches. At location 130RBR23, the Remove the covers ************* Operator REMOVES the cover

- - - - from magnetrol switch

- - - - OR 2C11-N013C & 2C11-N013C.

- - - - , Magnetrol Switches, at 130RBR23. (Step 4.4.2.1)

- 7. Scram Discharge Volume Level Switches. At location 130RBR23, the Remove the covers ************* Operator REMOVES the cover

- - - - from magnetrol switch

- - - - OR ************ & 2C11-N013D.

2C11-N013D, Magnetrol Switches, at 130RBR23. (Step 4.4.2.1)

- 8. Trip the magnetrol switches. At location 130RBR15, the (Step 4.4.2.2) Operator TRIPS magnetrol switche 2C11-N013A.

- 9. Trip the magnetrol switches. At location 130RBR15, the Operator TRIPS magnetrol (Step 4.4.2.2) switche 2C11-N013B.

- 10. Trip the magnetrol switches. At location 130RBR23, the Operator TRIPS magnetrol (Step 4.4.2.2) switche 2C11-N013C.

- 11. Trip the magnetrol switches. At location 130RBR23, the Operator TRIPS magnetrol (Step 4.4.2.2) switche 2C11-N013D.

(** Indicates critical step)

PLANT 1 2016-301 Page 15 of 21 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

12. Replace the covers to the magnetrol Operator REPLACES all switches. removed magnetrol switch covers.

(Step 4.4.2.3)

END TIME:__________

NOTE: The terminating cue shall be given to the operator when any of the following conditions are met:

Operator completes step 12 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: Another operator will continue from here.

(** Indicates critical step)

Page 16 of 21 Page 17 of 21 Page 18 of 21 Page 19 of 21 PLANT 1 2016-301 Page 20 of 21 Summary of JPM Attributes JPM PLANT 1 2016-301:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 4 Step 4/6 Remove SDV Level Switch Cover Operator removes 1/2C11-N013A(C) magnetrol switch cover to gain access to switch.

Step 5/7 Remove SDV Level Switch Cover Operator removes 1/2C11-N013B(D) magnetrol switch cover to gain access to switch.

Step 8/10 Trip SDV Level Switch Operator Trips 1/2C11-N013A(C) magnetrol switch to de-energize RPS A.

Step 9/11 Trip SDV Level Switch Operator Trips 1/2C11-N013B(D) magnetrol switch to de-energize RPS B.

Number of JPM Steps <30 12 Time to Perform JPM <45 min 14 min Normal / Faulted /

Alternate Path Alternate Path When the Operator attempts to insert a Reactor Scram by de-energizing RPS, one of the breakers will not open. The Operator must decide to continue with the procedure and insert a Reactor Scram with the SDV Level Switches in the Reactor Building.

Setting (administered)

Plant Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. A condition has occurred which required the Control Room to be evacuated.

2. The Reactor is NOT shutdown.

3. 31RS-OPS-001-2, Shutdown From Outside the Control Room, is in progress.

4. Pre-Job Brief is NOT required.

INITIATING CUES:

Insert a Manual Scram by de-energizing RPS per 31RS-OPS-001-2.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL PLANT 2 (RO & SRO-I)

Title:

From the Remote Shutdown Panel, Start RHR and Inject into the Reactor Author: Media Number: Time Richard A. Greenhouse PLANT 2 2016-301 13 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee: Date N/A N/A Approved By (Training Program Supervisor, Lead Instructor or Line Supervisor) Date:

Ed Jones 05/30/16

Course Number Program Name Media Number N/A OPERATIONS TRAINING PLANT 2 2016-301 Authors Sups Ver. No. Date Reason for Revisions Initials Initials 11 02/04/00 Format modification, modify title, upgrade to the new RAB DHG simulator operating system 12 10/31/00 Include objective number RAB DHG 13 02/26/02 Include initial operaotr statement RAB RAB 14 03/17/05 Deleted S from procedure numbers, changed BEB DHG Revision and Rev. numbers to Current Version, changed Reactor Operator to Nuclear Plant Operator, and changed IC #104 for Simulator Setup.

15 05/31/05 Revised Initial License statement for successful RAB RAB completion 16 04/06/06 Remove Response Cues RAB RAB 17 09/21/09 Added HU steps. CLN ALD 17.1 8/11/11 Reviewed JPM against current procedure. Added pass / MMG DNM fail criteria. Added to ensure Reactor pressure is < 200 psig and RWL is -120 in the simulator setup. Added Confirms Reactor pressure is less than 449 (500) psig prior to opening injection valves.

17.2 5/30/16 Reviewed JPM against current procedure. Changed RAG ELJ media number to PLANT 2 2016-301. Removed U1 material and will be replaced once NRC exam is complete.

Line Contributors The following individuals contributed to the development of this lesson plan.

Ver. No. List of Contributors

PLANT 2 2016-301 Page 4 of 12 UNIT 1 ( ) UNIT 2 (X)

TASK TITLE: From the Remote Shutdown Panel, Start RHR and Inject into the Reactor JPM NUMBER: PLANT 2 2016-301 TASK STANDARD: The task shall be completed when the operator has successfully started RHR Loop B in the LPCI mode and injected into the Reactor from the Remote Shutdown Panel per 31RS-OPS-001.

TASK NUMBER: 007.019 OBJECTIVE NUMBER: 007.019.O PLANT HATCH JTA IMPORTANCE RATING:

RO 4.20 SRO 3.60 K/A CATALOG NUMBER: 203000A1.01 K/A CATALOG JTA IMPORTANCE RATING:

RO 4.20 SRO 4.30 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 Unit 2 N/A 31RS-OPS-001-2, Ver. 6.24 REQUIRED MATERIALS: Unit 1 Unit 2 N/A 31RS-OPS-001-2, Ver. 6.24 Key for Remote Shutdown Panel (if performed in plant)

APPROXIMATE COMPLETION TIME: 13.0 Minutes SIMULATOR SETUP: REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. An event has occurred which resulted in the evacuation of the Control Room.

2. Normal power supplies are available.

3. A failure of the RHR LOCA logic has occurred.

4. RHR Loop B is in Standby.

5. RWL is -120 inches.

6. RPV Pressure is <200 psig.

7. 31RS-OPS-001-2 is in progress.

8. All RHRSW Pumps are tripped

9. Both Recirc Pumps are tripped INITIATING CUES:

From the Remote Shutdown Panel, place LPCI in operation using RHR Loop B in accordance with 31RS-OPS-001-2, Attachment 5.

PLANT 2 2016-301 Page 6 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

Start Time:_________

1. Operator identifies the procedure The Operator has IDENTIFIED needed to perform the task. the correct procedure as 31RS-OPS-001-2, Attachment 5.

NOTE: **Indicates Transfer Switches that MUST be positioned to satisfactorily complete the critical step.

2. Place the following Transfer Switches At Panel 2C82-P001, the in EMERG position: Operator has placed 2C82-S53 2C82-S53 Transfer Switch in the EMERG position.

Step1.0

3. Place the following Transfer Switches At Panel 2C82-P001, the in EMERG position: Operator has placed 2C82-S52 2C82-S52 Transfer Switch in the EMERG position.

Step 1.0

4. Place the following Transfer Switches At Panel 2C82-P001, the in EMERG position: Operator has placed 2C82-S5 2C82-S5 Transfer Switch in the EMERG position.

Step 1.0

(** Indicates critical step)

PLANT 2 2016-301 Page 7 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

5. Place the following Transfer Switches At Panel 2C82-P001, the in EMERG position: Operator has placed 2C82-S18 2C82-S18 Transfer Switch in the Step 1.0 EMERG position.

6. Place the following Transfer Switches At Panel 2C82-P001, the in EMERG position: Operator has placed 2C82-S8 2C82-S8 Transfer Switch in the Step 1.0 EMERG position.

- 7. Place the following Transfer Switch in At Panel 2C82-P001, the EMERG position: Operator has placed 2C82-S80 2C82-S80 Transfer Switch in the EMERG position.

Step 1.0

- 8. Place the following Transfer Switch in At Panel 2C82-P001, the EMERG position: Operator has placed 2C82-S9 2C82-S9 Transfer Switch in the Step 1.0 EMERG position.

- 9. Place the following Transfer Switch in At Panel 2C82-P001, the EMERG position: Operator has placed 2C82-S13 2C82-S13 Transfer Switch in the EMERG position.

Step 1.0

10. Place the following Transfer Switches At Panel 2C82-P001, the in EMERG position: Operator has placed 2C82-S10 2C82-S10 Transfer Switch in the EMERG position.

Step 1.0

11. Place the following Transfer Switches At Panel 2C82-P001, the in EMERG position: Operator has placed 2C82-S1 2C82-S1 Transfer Switch in the EMERG position.

Step 1.0

12. Place the following Transfer Switches At Panel 2C82-P001, the in EMERG position: Operator has placed 2C82-S12 2C82-S12 Transfer Switch in the EMERG position.

Step 1.0

13. Place the following Transfer Switches At Panel 2C82-P001, the in EMERG position: Operator has placed 2C82-S17 2C82-S17 Transfer Switch in the EMERG position.

Step 1.0

(** Indicates critical step)

PLANT 2 2016-301 Page 8 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

14. Place the following Transfer Switches At Panel 2C82-P001, the in EMERG position: Operator has placed 2C82-S14 2C82-S14 Transfer Switch in the Step 1.0 EMERG position.

15. Place the following Transfer Switches At Panel 2C82-P001, the in EMERG position: Operator has placed 2C82-S11 2C82-S11 Transfer Switch in the Step 1.0 EMERG position.

- 16. Place the following Transfer Switches At Panel 2C82-P001, the in EMERG position: Operator has placed 2C82-S16 2C82-S16 Transfer Switch in the EMERG position.

Step 1.0

17. Confirm Minimum Flow Bypass At panel 2C82-P001 the operator Valve, 2E11-F007B is open. VERIFIES that the MIN FLOW Step 4.0 BYP VLV, 2E11-F007B, is OPEN, red light is illuminated.

- 18. Start RHR Pump 2E11-C002B. At panel 2C82-P001, RHR Step 5.0 PUMP, 2E11-C002B, is RUNNING, red light illuminated.

PROMPT: WHEN the operator addresses starting RHR Pump 2D, INFORM the operator a System Operator has started it locally.

19. Confirm or open Heat Exchanger At panel 2C82-P001, BYPASS Shell Side Bypass Valve, VLV, 2E11-F048B, is OPEN, red 2E11-F048B. light illuminated.

Step 7.0

20. Confirm or close the following valve: At panel 2C82-P001, the 2E11-F028B Operator has confirmed Step 8.0 2E11-F028B is CLOSED, green light illuminated.

- 21. Confirm or close the following valve: At panel 2C82-P001, the 2B31-F023B Operator has CLOSED Step 8.0 2EB31-F023B, green light illuminated.

(** Indicates critical step)

PLANT 2 2016-301 Page 9 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

22. Confirm or close the following valve: At panel 2C82-P001, the 2E11-F011B Operator has confirmed 2E11-F011B is CLOSED, Step 8.0 green light illuminated.

23. Confirm or close the following valve: At panel 2C82-P001, the 2E11-F016B Operator has confirmed 2E11-F016B is CLOSED, Step 8.0 green light illuminated.

24. Confirm or close the following valve: At panel 2C82-P001, the 2E11-F006A Operator has confirmed Step 8.0 2E11-F006A is CLOSED, green light illuminated.

25. Confirm or close the following valve: At panel 2C82-P001, the 2E11-F006B Operator has confirmed Step 8.0 2E11-F006B is CLOSED, green light illuminated.

26. Confirm or close the following valve: At panel 2C82-P001, the 2E11-F006C Operator has confirmed Step 8.0 2E11-F006C is CLOSED, green light illuminated.

27. Confirm or close the following valve: At panel 2C82-P001, the 2E11-F006D Operator has confirmed 2E11-F006D is CLOSED, Step 8.0 green light illuminated.

28. Confirm or close the following valve: At panel 2C82-P001, the 2E11-F073B Operator has confirmed Step 8.0 2E11-F073B is CLOSED, green light illuminated.

29. Confirms Reactor pressure is less than Confirms Reactor pressure is less 500 psig than 500 psig Step 9.0 PROMPT: IF addressed, INFORM the operator Reactor pressure is less than 500 psig.

- 30. Open the RHR Inboard Injection At panel 2C82-P001, RHR INBD Valve, 2E11-F015B. INJ VLV, 2E11-F015B, OPEN, Step 9.0 red light illuminated.

(** Indicates critical step)

PLANT 2 2016-301 Page 10 of 12 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

31. Confirm or open the RHR Outboard At panel 2C82-P001 operator Injection Valve, 2E11-F017B. VERIFIES RHR OUTBD INJ Step 9.0 VLV, 2E11-F017B, is OPEN, red light illuminated.

PROMPT: Another operator will continue from here.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when:

Operator completes step 31 of this JPM.

With no reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

PLANT 2 2016-301 Page 11 of 12 Summary of JPM Attributes JPM PLANT 2 2016-301:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 6 Step 7 PLACES switch 2C82-S80 to EMERG Allows control of 2E11-F007B.

Step 8 PLACES switch 2C82-S9 to EMERG Allows control of 2E11-C002B.

Step 9 PLACES switch 2C82-S13 to EMERG Allows control of 2E11-F017B, F015B & C001B.

Step 16 PLACES switch 2C82-S16to EMERG Allows control of 2B31-F023B.

Step 18 STARTS RHR pump 2B Required to initiate LPCI injection.

Step 30 OPENS 2E11-F015B Required to initiate LPCI injection.

Number of JPM Steps <30 31 Time to Perform JPM <45 min 13 min Normal / Faulted /

Alternate Path Normal Setting (administered)

Plant or Simulator Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. An event has occurred which resulted in the evacuation of the Control Room.

2. Normal power supplies are available.

3. A failure of the RHR LOCA logic has occurred.

4. RHR Loop B is in Standby.

5. RWL is -120 inches.

6. RPV Pressure is <200 psig.

7. 31RS-OPS-001-2 is in progress.

8. All RHRSW Pumps are tripped

9. Both Recirc Pumps are tripped INITIATING CUES:

From the Remote Shutdown Panel, place LPCI in operation using RHR Loop B in accordance with 31RS-OPS-001-2, Attachment 5.

Sheet 5 Sheet 1 Sheet 6 Sheet 2 Sheet 3 Sheet 7 U2 RSDP Sheet 4 Sheet 8

Sheet 1 2C82-S7 2C82-S18

Sheet 2 2C82-S53 2C82-S4 2C82-S15

Sheet 3 2C82-S52 2C82-S5 2C82-S2

Sheet 4 2C82-S6 2C82-S3

Sheet 5 2C82-S8 2C82-S80

Sheet 6 2C82-S9 2C82-S13 2C82-S10

Sheet 7 2C82-S1 2C82-S12 2C82-S17

Sheet 8 2C82-S16 2C82-S14 2C82-S11

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL PLANT 3 (ALL)

Title:

Transfer the Vital AC System from Alternate Power to the Inverter Author: Media Number: Time:

Anthony Ball PLANT 3 2016-301 15 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee: Date:

N/A N/A Approved By (Training Program Supervisor, Lead Instructor or Line Supervisor) Date:

Ed Jones 05/30/16

This page intentionally left blank Course Number Program Name Media Number N/A OPERATIONS TRAINING PLANT 3 2016-301 Authors Sups Rev. No. Date Reason for Revisions Initials Initials 01 07/01/92 General revision and format change WMM RSG General revision, incorporate instructor comments, 02 08/13/93 RAB RSG word processor change 03 11/15/93 Correct standard in step 10, both units RAB SMC Format change, modify time allowance, made steps 5, 04 07/05/96 RAB SMC 7, and 9 critical 05 09/14/98 Revised based on annual exam comments. SCB DHG Format modification, change title to better reflect task, 06 02/21/00 RAB DHG update K/As Include objective number, change operator applicability 07 11/02/00 RAB DHG to System Operator 08 03/11/02 Include initial operator statement RAB RAB 09 03/08/05 Documentum Revision DNM RAB Revised Initial License statement for successful 10 06/13/05 RAB RAB completion 11 04/11/06 Removed Response Cues RAB RAB 12 09/25/09 Added HU tools ADY ALD Reviewed JPM against current procedure. Added 12.1 10/17/11 MMG ALS Fundamental question to new Attachment 1.

Removed fundamental questions and added JPM 12.2 01/22/14 attribute page. Added procedure step numbers to JPM JSC ELJ staps.

Updated Summary of JPM Attributes and changed 13 08/06/15 wording to match procedure including procedure step MMG ALS numbers.

Reviewed JPM against current procedure to be used on ILT-10 NRC Exam. Changed Media Number to Plant 13.1 05/30/16 3 2016-301. Removed U1 information and once exam ARB ELJ is complete will be added back and update the JPM Database.

Line Contributors The following individuals contributed to the development of this lesson plan.

Rev. No. List of Contributors

PLANT 3 2016-301 Page 5 of 13 UNIT 1 () UNIT 2 (X)

TASK TITLE: Transfer the Vital AC System from Alternate Power to the Inverter JPM NUMBER: PLANT 3 2016-301 TASK STANDARD: The task shall be completed when Vital AC Power has been transferred from the alternate source to the inverter per 34SO-R25-002.

TASK NUMBER: 027.031 OBJECTIVE NUMBER: 027.031.O PLANT HATCH JTA IMPORTANCE RATING:

RO 2.86 SRO 2.96 K/A CATALOG NUMBER: 2620012130 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.90 SRO 3.40 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 Unit 2 N/A 34SO-R25-002-2, Ver. 5.3 REQUIRED MATERIALS: Unit 1 Unit 2 N/A 34SO-R25-002-2, Ver. 5.3 APPROXIMATE COMPLETION TIME: 15 Minutes SIMULATOR SETUP: N/A

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Vital AC room cooler is in operation.

2. The Vital AC rectifier and inverter have been started.

3. Pre-Job Brief is NOT required.

INITIATING CUES:

Transfer Unit 2 Vital AC from the Alternate Source to the Inverter in accordance with 34SO-R25-002-2, Section 7.1.4.

PLANT 3 2016-301 Page 7 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Start Time:_________

1. Confirm SYNC-MONITOR light is At the Vital AC Panel, location ILLUMINATED. 112TET12, the Operator (Step 7.1.4.1) CONFIRMS the SYNC -

MONITOR clear light is illuminated.

2. Confirm in OR place RETURN At Vital AC Panel, 112TET12, MODE Switch in AUTO position. the Operator CONFIRMS the RETURN MODE switch is in (Step 7.1.4.2) AUTO.

- 3. Place MANUAL BYPASS switch in At Vital AC Panel, 112TET12, BYP-SYNC position. the Operator PLACES the (Step 7.1.4.3) MANUAL BYPASS switch from BYPASS to the BYP-SYNC position.

4. Confirm SYNC-MONITOR light is At Vital AC Panel, 112TET12, EXTINGUISHED. the Operator CONFIRMS the (Step 7.1.4.4) clear SYNC-MONITOR light is extinguished.

(** Indicates critical step)

PLANT 3 2016-301 Page 8 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 5. Place MANUAL BYPASS switch in At Vital AC Panel, 112TET12, BYP-TEST position. the Operator PLACES the (Step 7.1.4.5) MANUAL BYPASS switch in BYP-TEST.

PROMPT: IF the operator asked for the status of the red INVERTER static switch position light, INFORM the operator that light is ILLUMINATED (Step 7.1.4.6).

6. Confirm the following: At Vital AC Panel, 112TET12, red INVERTER static switch position the Operator has IDENTIFIED light is ILLUMINATED; AND the following indications:

- - - - INVERTER red light illuminated.

(Step 7.1.4.7) *****************

7. Confirm the following: At Vital AC Panel, 112TET12,

- - - - the Operator has IDENTIFIED the white ALT LINE static switch the following indications:

position light is EXTINGUISHED; **********************.

ALT LINE white light extinguished.

(Step 7.1.4.7)

8. Confirm the following: At Vital AC Panel, 112TET12,

- - - - the Operator has IDENTIFIED the following indications:

SYNC MONITOR light is *********************.

EXTINGUISHED. (Step 7.1.4.7)

SYNC MONITOR clear light extinguished.

NOTE: Step 7.1.4.8 is not applicable.

(** Indicates critical step)

PLANT 3 2016-301 Page 9 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 9. Place TEST toggle switch in ALT At Vital AC Panel, 112TET12, LINE position. the Operator PLACES the TEST (Step 7.1.4.9) toggle switch from CENTER to the ALT LINE (down) position.

10. Confirm the following: At Vital AC Panel, 112TET12, the Operator has IDENTIFIED white ALT LINE static switch the following indications:

position light is ILLUMINATED; AND ALT LINE white light illuminated.

(Step 7.1.4.10) *****************

11. Confirm the following: At Vital AC Panel, 112TET12, the Operator has IDENTIFIED the following indications:

red INVERTER static switch position light is EXTINGUISHED; AND ********************

INVERTER red light extinguished.

(Step 7.1.4.10)

12. Confirm the following: At Vital AC Panel, 112TET12, the Operator has IDENTIFIED the following indications:

SYNC MONITOR light is EXTINGUISHED (Step 7.1.4.10) SYNC MONITOR clear light extinguished.

- 13. Place MANUAL BYPASS switch in At Vital AC Panel, 112TET12, NORMAL position. the Operator PLACES the (Step 7.1.4.11) MANUAL BYPASS Switch in NORMAL.

- 14. Place TEST toggle switch in At Vital AC Panel, 112TET12, CENTER position. the Operator PLACES the TEST (Step 7.1.4.12) toggle switch in CENTER position.

(** Indicates critical step)

PLANT 3 2016-301 Page 10 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

PROMPT: IF the operator asked for the status of the red INVERTER static switch position light, INFORM the operator that light is ILLUMINATED (Step 7.1.4.13).

15. Confirm the following: At Vital AC Panel, 112TET12, the red INVERTER static switch position Operator has IDENTIFIED the light is ILLUMINATED; AND following indications:

- - - - INVERTER red light illuminated.

(Step 7.1.4.14) ****************

16. Confirm the following: At Vital AC Panel, 112TET12, the

- - - - Operator has IDENTIFIED the following indications:

white ALT LINE static switch position light is EXTINGUISHED; *********************

AND ALT LINE White light extinguished.

(Step 7.1.4.14)

17. Confirm the following: At Vital AC Panel, 112TET12, the

- - - - Operator has IDENTIFIED the

- - - - following indications:

SYNC MONITOR light is *********************

EXTINGUISHED. *********************

(Step 7.1.4.14) SYNC MONITOR clear light extinguished.

NOTE: Step 7.1.4.15 is not applicable.

PROMPT: WHEN addressed by the operator, as the Shift Supervisor, INFORM the operator that it is desired to place the Return Mode Switch to MANUAL.

(** Indicates critical step)

PLANT 3 2016-301 Page 11 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

18. IF desired, At Vital AC Panel, 112TET12, place RETURN MODE SWITCH in the Operator PLACES the MANUAL position. RETURN MODE switch in (Step 7.1.4.16) MAN.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when any of the following conditions are met:

Operator completes step 18 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

(** Indicates critical step)

PLANT 3 2016-301 Page 12 of 13 Summary of JPM Attributes JPM JP02731-13:

SUMMARY

OF JPM QUANTITATIVE ATTRIBUTES CATEGORY Minimum NRC JPM CONTENT Attributes Total Critical Steps At least 2 5 Step 3 BYP-SYNC position Energizes synch circuit to compare inverter output voltage to bypass voltage (checks for out of phase between sources).

Step 5 BYP-TEST position Aligns Alternate power to Static Switch.

Step 9 Toggle Switch to Alt Line Allows Static Switch to supply Alternate power to bus.

Step 13 BYP-Switch to Normal Opens B1 contact so Alternate Power and Inverter power are controlled by the Static Switch (needed for Static Switch to have automatic control).

Step 14 Toggle Switch to Center Places Static Switch in control with power being supplied by the Inverter as long as sufficient voltage is present.

Number of JPM Steps <30 18 Time to Perform JPM <45 min 15 min Normal / Faulted /

Alternate Path Normal Operator is told to transfer power from Alternate to the Inverter.

Setting (administered)

Plant Is LOD 1 or 5 NO NO

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Vital AC room cooler is in operation.

2. The Vital AC rectifier and inverter have been started.

3. Pre-Job Brief is NOT required.

INITIATING CUES:

Transfer Unit 2 Vital AC from the Alternate Source to the Inverter in accordance with 34SO-R25-002-2, Section 7.1.4.

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL ADMIN 1 (ALL)

Title:

Determine if plant conditions allow a "Quick Restart" of a Recirc Pump Author: Media Number: Time:

Richard A. Greenhouse 2016-301 ADMIN 1 15.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee (N/A for minor revisions) Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date:

Ed Jones 05/30/16

Course Number Program Name Media Number N/A OPERATIONS TRAINING 2016-301 ADMIN 1 Authors Sups Ver. No. Date Reason for Revisions Initials Initials Modified from LR-JP-25050 & will become new 0.0 06/07/12 LR-JP-25053 after NRC Exam. ARB CME Minor revision to match procedure and use on ILT-10 NRC Exam. Reviewed JPM against current procedure.

1.0 05/30/16 Changed Media Number to 2016-301 ADMIN 6. This RAG ELJ JPM will become LR-JP-25061 after NRC Exam.

Line Contributors The following individuals contributed to the development of this lesson plan.

Rev. No. List of Contributors

2016-301 ADMIN 1 Page 4 of 14 UNIT 1 (X) UNIT 2 ( )

TASK TITLE: Determine if plant conditions allow a "Quick Restart" of a Recirc Pump JPM NUMBER: 2016-301 ADMIN 1 TASK STANDARD: The task shall be complete when Attachment 6 of 34SO-B31-001-1, Reactor Recirculation System, has been performed through Step 5.2, and it has been determined that the requirements have NOT been met to start Recirc pump 1B.

TASK NUMBER: 004.002 OBJECTIVE NUMBER: 004.002.C K/A CATALOG NUMBER: Generic 2.1.20 K/A CATALOG JTA IMPORTANCE RATING:

RO 4.6 SRO 4.6 OPERATOR APPLICABILITY: NPO and SRO GENERAL

REFERENCES:

Unit 1 34SO-B31-001-1, Ver 46.2 REQUIRED MATERIALS: Unit 1 34SO-B31-001-1, Ver 46.2 APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: N/A

2016-301 ADMIN 1 Page 5 of 14 EVALUATOR COPY UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. 10 minutes ago, the Unit 1 reactor scrammed from 100% power.

2. Both Recirc Pumps tripped during the scram transient.

3. RWL went as low as -10 inches, and has been restored to +37 inches using Reactor Feedwater Pumps.

4. An operator has entered 34SO-B31-001-1, Reactor Recirculation System, and completed steps 7.1.4.2.1 through 7.1.4.2.5 (Recirc Pump B Quick Re-Start).

5. Data has been collected for use on step 7.1.4.2.6 of 34SO-B31-001-1.

6. Per the STA, the Power/flow condition is acceptable for restart of Recirc Pump 1B.

INITIATING CUES:

Perform step 7.1.4.2.6 of 34SO-B31-001-1, Reactor Recirculation System, AND, Determine if plant conditions meet the procedural requirements for the Quick Re-Start of Recirc Pump 1B.

2016-301 ADMIN 1 Page 6 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-111, On-The-Job Training and Task Performance Evaluation.

START TIME:__________

NOTE: 34SO-B31-001-1, Attachment 6 serves as an answer key for this JPM. It is NOT to be provided to the student.

NOTE: At this time, PROVIDE the operator with Attachment 1 (Plant Data page) and a copy of 34SO-B31-001-1.

1. Operator refers to step 7.1.4.2.6 and is The operator enters Attachment 6 directed to Attachment 6 of 34SO- of 34SO-B31-001-1.

B31-001-1.

2. Recirc Loop and RPV Limit Checks: The operator places a check mark (Step 1.0 of Attachment 6) next to B Recirc.

(** Indicates critical step)

2016-301 ADMIN 1 Page 7 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

3. Confirm the reactor is at least 13% The operator determines the below the 78% load line of reactor is SHUTDOWN and Attachment 1 of 34GO-OPS-005-1, Initials Step 2.0 (1) and marks AND Step 2.0 (2) as N/A.

The Power/flow condition is acceptable for restart per the STA/Rx Engineering OR If the OPRM System is inoperable, the reactor is at least 10% below the 61%

load line of Attachment 1 of 34AB-C51-001-1.

(Step 2.0 of Attachment 6)

4. Record the following data: Time The operator records the CURRENT TIME.

The operator initials the step.

(Step 3.0 of Attachment 6)

NOTE: Data is NOT required to be entered for Recirc Pump 1A in the following step.

- 5. Record the following data: RPV The operator determines the RPV Saturation Temp. Saturation Temp for 820 psia (805 psig + 15 psi) is 521°°F, by using Attachment 1 of 34SO-(Step 3.0 (A) of Attachment 6) B31-001-1

6. Record the following data: A The operator records A Recirc Recirc Suction Temp Suction Temp as 470°°F (Plant Data Sheet)

(Step 3.0 (B) of Attachment 6)

7. Record the following data: B The operator records B Recirc Recirc Suction Temp Suction Temp as 475°°F (Plant (Step 3.0 (C) of Attachment 6) Data Sheet)

8. Record the following data: Vessel The operator records Vessel Bottom Head Drain Bottom Head Drain temperature (Step 3.0 (D) of Attachment 6) as N/A or Not Available

(** Indicates critical step)

2016-301 ADMIN 1 Page 8 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 9. Confirm the T between reactor The operator records Loop B coolant temp in the loop AND the T as 46°°F (+ 2°°F)

RPV coolant temp is < 50° F:

Loop B T = l(A)-(C)l The operator initials the step.

(Step 4.1 of Attachment 6)

- 10. Confirm the T between the bottom The operator determines the step head coolant temp AND the RPV 5.2 must be used because Vessel coolant temp by performing step 5.1 Bottom Head Drain temp is NOT OR 5.2. available.

The operator records Step 5.1 as N/A (Step 5.0 of Attachment 6)

- 11. Confirm ALL of the following: The operator determines loop One OR more loop drive flows were drive flows were > 40% prior to

>40% of rated flow prior to the RPT the RPT (Unit 1 was at 100%

RTP prior to the scram and RPT).

(Step 5.2 (a) of Attachment 6)

The operator initials the step.

- 12. Confirm ALL of the following: The operator determines HPCI HPCI and RCIC have not injected and RCIC have not injected since since the RPT the RPT (RWL decreased to -10 and was restored using RFPTs).

(Step 5.2 (b) of Attachment 6)

The operator initials the step.

- 13. Confirm ALL of the following: The operator determines Feedwater temp has NOT Feedwater temp has remained > 300°F remained > 300°F since the RPT since the RPT.

(Plant Data sheet lists current Feedwater temp as 295°°F).

(Step 5.2 (c) of Attachment 6)

14. Confirm ALL of the following: The operator records the RPT time (T1) and time Recirc start is Time between the RPT and restart is

< 30 minutes. required.

(Step 5.2 (d) of Attachment 6)

(** Indicates critical step)

2016-301 ADMIN 1 Page 9 of 14 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

15. IF only ONE Recirc pump is idle, The operator determines BOTH THEN confirm the operating pump Recirc pumps are tripped and loop flow is < 22,500 gpm. marks Step 6.0 as N/A.

(Step 6.0 of Attachment 6)

16. Verify the operating pump loop flow The operator determines BOTH is < 22,500 gpm. Recirc pumps are tripped and marks Step 6.3 as N/A.

(Step 6.3 of Attachment 6)

17. Independently verify the data recorded above is ACCEPTABLE prior to proceeding with the recirc pump start.

(Step 7.0 of Attachment 6)

- 18. The operator reports to the Shift The operator reports that plant Supervisor. conditions do NOT meet the procedural requirements for the Quick Re-Start of Recirc Pump 1B.

PROMPT: IF addressed by the operator, as the Shift Supervisor, INFORM the operator that another operator will perform Step 7.0 of Attachment 6.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when:

After JPM step #18 is complete.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR - PICK UP the Initiating Cue sheet.

(** Indicates critical step)

ANSWER KEY SNC PLANT E. I. HATCH Pg 182 of 203 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION No:

REACTOR RECIRCULATION SYSTEM 34SO-B31-001-1 46.2 ATTACHMENT 6 Attachment Page TITLE: RECIRC PUMP QUICK RE-START LIMIT CHECKS 2 of 4 CONTINUOUS NOTE: This attachment may be performed in Modes 1, 2, AND 3.

1.0 Recirc Loop and RPV Limit Checks:

Pre-startup checks for (): __________ A recirc

_________ B recirc LOAD LINE INCREASES OF UP TO 10% HAVE BEEN OBSERVED WHEN A CAUTION:

RECIRC PUMP IS STARTED.

Critical 2.0 Confirm the:

(1) The reactor is at least 13% below the 78% load line of Attachment 1, Power vs. flow map in 34GO-OPS-005-1, INITIALS AND The Power/flow condition is acceptable for restart per the STA/Rx Engineering. INITIALS OR (2) IF the OPRM System is inoperable, the reactor is at least 10% below the 61% Load Line of Attachment 1, OPRM System INOP Power vs. Flow map in 34AB-C51-001-1, in order to avoid inadvertent entry into the RPI. N/A 3.0 Record the following data: Time CURRENT TIME INITIALS Parameter Location Value SPDS MISC RPV Heatup/

(A) RPV Saturation Temp. (A)

Cooldown OR Steam Tables 521°F (+/-2°F) 1B31-R650 OR Equivalent, (B) A Recirc Suction Temp average of process computer (B) 470°F points B034, B035 1B31-R650 OR Equivalent, (C) B Recirc Suction Temp average of process computer (C) 475°F points B036, B037

1B21-R606 Pt 3 OR (D) *Vessel Bottom Head Drain (D) 1G31-N601 Pt 5 Not Available OPS-1321 Ver. N/A G16.030

ANSWER KEY SNC PLANT E. I. HATCH Pg 183 of 203 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION No:

REACTOR RECIRCULATION SYSTEM 34SO-B31-001-1 46.2 ATTACHMENT 6 Attachment Page TITLE: RECIRC PUMP QUICK RE-START LIMIT CHECKS 3 of 4

The Bottom Head Drain temperature (D) may still be used even IF RWCU is NOT in service.

(See Limitation 5.2.14). IF Bottom Head Drain temperature is NOT available, (i.e., inoperable),

THEN use the alternate method of confirming the Bottom Head to Coolant T in step 5.0.

Critical 4.0 FOR the Recirc loop to be started, confirm the T between the reactor coolant temperature in the loop AND the RPV coolant temperature is 50°F by performing step3.1 OR 3.2 below:

4.1 IF both recirc loops are idle; Loop A T = (A) - (B) = ____________ (acceptable 50°F) N/A OR Loop B T = (A) - (C) = 46°F (+/-2°F) (acceptable 50°F) INITIALS

- - - - OR ******************************************

4.2 IF only one recirc loop is idle, THEN loop T = (B) - (C) = ________________ (acceptable 50°F) N/A IF a direct indication is NOT available for Vessel Bottom Head Drain temp (D),

NOTE: THEN within 30 minutes of an RPT, the bottom head to coolant T ( 145°F) may be confirmed per the alternate method in step 5.2.

Critical 5.0 Confirm the T between the bottom head coolant temperature AND the reactor pressure vessel (RPV) coolant temperature is 145°F by performing step 4.1 OR 4.2 below:

5.1 T = (A) - (D) = __________ (acceptable 145°F) N/A

- - - - OR ******************************************

5.2 Per Tech Spec BASES B.3.4.9, confirm ALL of the following:

(a) One OR more loop drive flows were > 40% (18,000 gpm) of rated flow prior to the RPT, AND INITIALS (b) HPCI and RCIC Systems have NOT injected since the RPT, AND INITIALS (c) Feedwater temperature has remained > 300°F since the RPT, AND NOT MET (d) Time between the RPT AND restart is < 30 minutes.

Record Recirc RPT trip time: RPT time (T1)

Recirc start is required prior to:

(T1) + 30 minutes = RPT time + 30 min INITIALS OPS-1321 Ver. N/A G16.030

ANSWER KEY SNC PLANT E. I. HATCH Pg 184 of 203 DOCUMENT TITLE: DOCUMENT NUMBER: VERSION No:

REACTOR RECIRCULATION SYSTEM 34SO-B31-001-1 46.2 ATTACHMENT 6 Attachment Page TITLE: RECIRC PUMP QUICK RE-START LIMIT CHECKS 4 of 4 Critical 6.0 IF only ONE Recirc pump is idle, THEN confirm the operating pump loop flow is < 22,500 gpm. N/A 6.3 Verify the operating pump loop flow is < 22,500 gpm. ________ N/A 7.0 Independently verify the data recorded above is ACCEPTABLE prior to proceeding with the recirc pump start. (VERIFIED) _____

Critical 8.0 Confirm the steps 1.0 thru 7.0 above, was performed within the last 15 minutes. _____

9.0 Record Recirc pump start time: _______________ _____

OPS-1321 Ver. N/A G16.030

UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:

1. 10 minutes ago, the Unit 1 reactor scrammed from 100% power.

2. Both Recirc Pumps tripped during the scram transient.

3. RWL went as low as -10 inches, and has been restored to +37 inches using Reactor Feedwater Pumps.

4. An operator has entered 34SO-B31-001-1, Reactor Recirculation System, and completed steps 7.1.4.2.1 through 7.1.4.2.5 (Recirc Pump B Quick Re-Start).

5. Data has been collected for use on step 7.1.4.2.6 of 34SO-B31-001-1.

6. Per the STA, the Power/flow condition is acceptable for restart of Recirc Pump 1B.

INITIATING CUES:

Perform step 7.1.4.2.6 of 34SO-B31-001-1, Reactor Recirculation System, AND, Determine if plant conditions meet the procedural requirements for the Quick Re-Start of Recirc Pump 1B.

PROVIDE TO APPLICANT Plant Data

Reactor pressure: 805 psig

A Recirc Suction Temp (1B31-R650): 470° F

B Recirc Suction Temp (1B31-R650): 475° F

Vessel Bottom Head Drain: NOT AVAILABLE

Reactor Feedwater temperature: 295° F

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL ADMIN 2 - (ALL)

Title:

USE A SYSTEM LOGIC DIAGRAM Author: Media Number: Time:

A. B. Genereux 2016-301 ADMIN 2 20.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee: Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Ed Jones 05/30/16

This page intentionally left blank Course Number Program Name Media Number N/A OPERATIONS TRAINING 2016-301 ADMIN 2 Authors Sups Rev. No. Date Reason for Revisions Initials Initials 0.0 05/30/16 Initial Development. ABG ELJ

Line Contributors The following individuals contributed to the development of this lesson plan.

Rev. No. List of Contributors

UNIT 1 () UNIT 2 (X)

TASK TITLE: USE A SYSTEM LOGIC DIAGRAM JPM NUMBER: 2016-301 ADMIN 2 TASK STANDARD: The task shall be complete when the operator has determined the failure condition of a relay using Plant Hatch logic drawings.

PLANT HATCH JTA IMPORTANCE RATING:

RO 3.08 SRO 2.67 K/A CATALOG NUMBER: G2.2.41 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.5 SRO 3.9 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 Unit 2 H-27664, H-27671, H-27667, H-27665, H-51689 REQUIRED MATERIALS: Unit 1 Unit 2 H-27664, H-27671, H-27667, H-27665, H-51689 APPROXIMATE COMPLETION TIME: 20.0 Minutes SETUP: This JPM may be performed in the Simulator Library, Control Room, Simulator, or Document Control.

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is at operating at 100% rated power.

2. HPCI is operating at rated flow per 34SV-E41-002-2, HPCI Pump Operability.

3. Relay 2E41-K20 fails in the ENERGIZED condition.

INITIATING CUES:

5 minutes after the initial conditions above and using the applicable plant logic drawings, circle the position of the following HPCI valves:

2E41-F004, OPEN CLOSED CST Suction 2E41-F011, OPEN CLOSED Test To CST Valve 2E41-F008, OPEN CLOSED Test To CST Valve

2016-301 ADMIN 2 Page 7 of 10 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

START TIME:__________

Provide the Applicant with drawings H-27664, H-27671, H-27667, H-27665 and H-51689

1. Operator locates relay 2E41-K20. Using the relay tabulation table on H-27664 the operator locates 2E41-K20 on drawing H-27667, coordinate F-10.

- 2. Operator determines that 2E41-F004, Using the relay tabulation table HPCI CST Suction valve, DOES NOT on H-27664 the operator locates receive a close signal. 2E41-F004 on drawing H-27671, coordinates E-1 and E-2. The operator DETERMINES that 2E41-F004 DOES NOT receive a close signal (remains OPEN).

2016-301 ADMIN 2 Page 8 of 10 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 3. Operator determines that 2E41-F011, Using the relay tabulation table HPCI Test to CST valve DOES on H-27664 the operator locates receive a close signal. 2E41-F011 on drawing H-27671, coordinate J-2, the operator DETERMINES that 2E41-F011 DOES receive a close signal.

(travels CLOSE)

- 4. Operator determines that 2E41-F008, Using the relay tabulation table HPCI Test to CST valve DOES on H-27664 the operator locates receive a close signal. 2E41-F008 on drawing H-51689, coordinate D-6, the operator DETERMINES that 2E41-F008 DOES receive a close signal.

(travels CLOSE)

END TIME:__________

NOTE: The terminating cue shall be given to the Operator when:

After JPM step #4 is complete.

With NO reasonable progress, the Operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR - PICK UP the Initiating Cue sheet AND DRAWINGS H-27664, H-27671, H-27667, H-27665 and H-51689.

2016-301 ADMIN 2 Page 9 of 10 ANSWER KEY 2E41-F004, OPEN CLOSED CST Suction 2E41-F011, OPEN CLOSED Test To CST Valve 2E41-F008, OPEN CLOSED Test To CST Valve

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is at operating at 100% rated power.

2. HPCI is operating at rated flow per 34SV-E41-002-2, HPCI Pump Operability.

3. Relay 2E41-K20 fails in the ENERGIZED condition.

INITIATING CUES:

5 minutes after the initial conditions above and using the applicable plant logic drawings, circle the position of the following HPCI valves:

2E41-F004, OPEN CLOSED CST Suction 2E41-F011, OPEN CLOSED Test To CST Valve 2E41-F008, OPEN CLOSED Test To CST Valve

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL ADMIN 3 - SRO ONLY

Title:

VERIFY FUEL MOVEMENT SHEET Author: Media Number: Time:

Anthony Ball 2016-301 ADMIN 3 30.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee: Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Ed Jones 05/30/16

This page intentionally left blank SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 3 of 10 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code: OPERATIONS TRAINING Media Number: 2016-301 ADMIN 3 Rev. Authors Supvs Date Reason for Revision No. Initials Initials 00 03/17/09 Initial development FNF CME Revision for use on 2012-301 NRC Exam. After NRC Exam, Media 01 06/07/12 ARB CME Number will be changed to LR-JP-45.33A.

Minor revision for use on 2016-301 NRC Exam. Reviewed JPM against current procedure. Changed Media Number 1.1 05/30/16 to 2016-301 ADMIN 3. Incorporated JPM into a Fuel ARB ELJ Movement Sheet Verification. After NRC Exam, Media Number will be changed to LR-JP-45.33B.

2016-301 ADMIN 3 Page 4 of 10 UNIT 1 (X) UNIT 2 (X)

TASK TITLE: VERIFY FUEL MOVEMENT SHEET JPM NUMBER: 2016-301 ADMIN 3 TASK STANDARD: The task will be complete when the operator has identified all in-core placement errors of all components listed on Page 1 of the attached Fuel Movement Sheet.

TASK NUMBER: 045.033 OBJECTIVE NUMBER: 045.033.O PLANT HATCH JTA IMPORTANCE RATING:

RO Not Available SRO Not Available K/A CATALOG NUMBER: G2.1.35 K/A CATALOG JTA IMPORTANCE RATING:

RO 2.2 SRO 3.9 OPERATOR APPLICABILITY: Senior Reactor Operator GENERAL

REFERENCES:

Refuel Floor 34FH-OPS-001-0 (current version) 42FH-ERP-014-0 (current version)

REQUIRED MATERIALS: Refuel Floor Fuel Movement Sheets 34FH-OPS-001-0 (current version) 42FH-ERP-014-0 (current version)

APPROXIMATE COMPLETION TIME: 30 Minutes SIMULATOR SETUP: N/A

EVALUATOR COPY UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is in a refueling outage.

2. You are the oncoming Refuel Floor SRO.

3. You are performing a turnover with the off-going Refuel Floor SRO.

4. You are asked to verify the attached Fuel Movement Sheet which was completed last shift.

5. The fuel movement sheet, Core Map and pictures of the associated core cells are available.

INITIATING CUES:

IAW 34FH-OPS-001-0, Fuel Movement Operation,

1. VERIFY fuel movement on the attached Fuel Movement Sheet.

2. If verification results in any discovered errors, identify the error(s) and corrective action(s) required.

2016-301 ADMIN 3 Page 6 of 10 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences.

Reference:

NMP-TR-111, On-The-Job Training and Task Performance Evaluation.

START TIME: __________

PROMPT: Hand the operator the fuel movement sheets, pictures of the core cells and 34FH-OPS-001-2 & 42FH-ERP-014-0.

PROMPT: IF the operator has problems reading the bundle serial numbers, THEN provide the serial numbers to the operator.

PROMPT: IF the operator asks about Spent Fuel Pool verification, THEN tell the operator he is only responsible for in-core verifications.

1. Obtains the correct procedures. Obtains and reviews 42FH-ERP-014-0, Fuel Movement and 34FH-OPS-001-0, Fuel Movement Operation.

2. Verify Step #1 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLV675) has been loaded in its proper location and Step #1 of Fuel Movement Sheet is correct.

3. Verify Step #2 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLV682) has been loaded in its proper location and Step #2 of Fuel Movement Sheet is correct.

(** Indicates critical step)

2016-301 ADMIN 3 Page 7 of 10 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

NOTE: Step #3 of Fuel Movement Sheet is a Double Blade Guide and is located in the Fuel Pool.

4. Verify Step #4 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLK804) has been loaded in its proper location and Step #4 of Fuel Movement Sheet is correct.

5. Verify Step #5 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLK817) has been loaded in its proper location and Step #5 of Fuel Movement Sheet is correct.

NOTE: Control Cell 38-37 is correct.

- 6. Verify Step #6 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLV698) has NOT been loaded in its proper location and Step #6 of Fuel Movement Sheet is INCORRECT. (JLV678 should be loaded in this location)

NOTE: The applicant may report the findings to the Shift Supervisor at this time or wait until all of the Fuel Movement Sheet has been verified, either is acceptable.

7. Verify Step #7 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLV670) has been loaded in its proper location and Step #7 of Fuel Movement Sheet is correct.

NOTE: Step #8 of Fuel Movement Sheet is a Double Blade Guide and is located in the Fuel Pool.

8. Verify Step #9 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLK805) has been loaded in its proper location and Step #9 of Fuel Movement Sheet is correct.

9. Verify Step #10 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLK812) has been loaded in its proper location and Step #10 of Fuel Movement Sheet is correct.

(** Indicates critical step)

2016-301 ADMIN 3 Page 8 of 10 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

NOTE: Control Cell 14-37 is NOT correct.

- 10. Verify Step #11 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLV968) has NOT been loaded in its proper location and Step

11 of Fuel Movement Sheet is INCORRECT. (JLV698 should be loaded in this location)

NOTE: The applicant may report the findings to the Shift Supervisor at this time or wait until all of the Fuel Movement Sheet has been verified, either is acceptable.

11. Verify Step #12 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLV708) has been loaded in its proper location and Step #12 of Fuel Movement Sheet is correct.

NOTE: Step #13 of Fuel Movement Sheet is a Double Blade Guide and is located in the Fuel Pool.

12. Verify Step #14 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLK802) has been loaded in its proper location and Step #14 of Fuel Movement Sheet is correct.

- 13. Verify Step #15 of Fuel Movement Operator determines Fuel Bundle Sheet is correct. (JLK802) has NOT been loaded in its proper location and Step

15 of Fuel Movement Sheet is INCORRECT. (JLK820 should be loaded in this location)

NOTE: Control Cell 38-17 is NOT correct.

NOTE: The applicant may report the findings to the Shift Supervisor at this time or wait until all of the Fuel Movement Sheet has been verified, either is acceptable.

(** Indicates critical step)

2016-301 ADMIN 3 Page 9 of 10 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 14. Perform 34FH-OPS-001-0 Section 7.1 Operator reports to Shift FUEL MOVEMENT ERRORS. Supervisor the following Steps are INCORRECT:

Step#6 Step#11 Step#15

- 15. Perform 34FH-OPS-001-0, Step Operator reports to Shift 7.1.1.4. Supervisor to NOTIFY Reactor Engineering of the fuel movement errors.

- 16. Perform 34FH-OPS-001-0, Step Operator reports to Shift 7.1.1.5. Supervisor to INITIATE a CR documenting the fuel movement error

- 17. Perform 34FH-OPS-001-0, Step Operator reports to Shift 7.1.1.6. Supervisor to NOT make any further fuel movements, until directed by Plant Management AND Reactor Engineering has provided a Reactivity Plan for recovery from the fuel movement error.

END TIME:__________

NOTE: The terminating cue shall be given to the Operator when:

After JPM step #17 is complete.

With NO reasonable progress, the Operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

EVALUATOR - PICK UP the Initiating Cue sheet.

(** Indicates critical step)

UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. Unit 2 is in a refueling outage.

2. You are the oncoming Refuel Floor SRO.

3. You are performing a turnover with the off-going Refuel Floor SRO.

4. You are asked to verify the attached Fuel Movement Sheet which was completed last shift.

5. The fuel movement sheet, Core Map and pictures of the associated core cells are available.

INITIATING CUES:

IAW 34FH-OPS-001-0, Fuel Movement Operation,

3. VERIFY fuel movement on the attached Fuel Movement Sheet.

4. If verification results in any discovered errors, identify the error(s) and corrective action(s) required.

SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 1 OF 3 FORM TITLE:

FUEL MOVEMENT SHEETS TYPE OF FUEL MOVEMENT:

(check the type of fuel sheets)

Core Off-Load: ____ Partial Offload: _____

Core Reload: _X _ Upfront Shuffle: _____

Shuffle: ____ Backend Shuffle: _____

General Moves: ____ Other (Specify): ______________________

Special Activity: ____

Brief description of moves: ____Control Cells 38-37, 14-37 and 38-17 to be loaded with fuel and blade guides removed. Control Cell 14-17 to have blade guide installed for insertion of control rod. ______

Verify the following for all core reload move sheets:

The first 4 steps in the movement sequence will place bundles around the SRM which will first be in the fueled region.

N/A /

Date N/A /

Date Verify the following for all core shuffle move sheets:

At least 2 irradiated fuel assemblies will remain around each SRM unless approved by the Reactor Engineering Supervisor or designated alternate.

Samuel Johnson / 06/18/16 Date

Michael Best / 06/18/16 Date Prepared by: Ben Williams / 06/18/16 Reactor Engineering Date Verified by: Mike Watson / 06/18/16 Reactor Engineering Date

Verified by: Kenneth Fairson / 06/18/16 Reactor Engineering Date

- Approved by: William Jefferson / 06/18/16 Reactor Engineering Supervisor Date

Additional verification IF required by the Reactor Engineering Supervisor for certain evolutions or marked N/A, initialed and dated by the RE Supervisor.

- The Approved space on the actual sheets is to be signed by the Reactor Engineering Supervisor or designated alternate.

Spent Fuel Pool Inventory Database Updated By: Kenneth Fairson / 06/18/16 Date Verified By: William Jefferson / 06/18/16 Dat ENG-0190 V8.0 PP1.015 42FH-ERP-014-0

SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 2 OF 3 FORM TITLE:

FUEL MOVEMENT SHEETS UNIT _2_ X Performs these These may be Approved Date moves in sequence performed non-sequentially William Jefferson 6/18/16 Step Move From: Comments: Move To: Double Verif.

Location Init OR Init Serial Number Location Init OR Init Init Date 1 23K11 JH SW JH JLV675 37-36 JH SE JH AC 06/18/16 2 23K10 JH SW JH JLV682 39-38 JH NW JH AC 06/18/16 3 37-38 / 39-36 JH N/A JH DBL B/G 17F11 / 17G10 JH N/A JH AC 06/18/16 4 23H12 JH SW JH JLK804 37-38 JH SW JH AC 06/18/16 5 23H11 JH SW JH JLK817 39-36 JH NE JH AC 06/18/16 6 23H10 JH SW JH JLV678 13-36 JH SE JH AC 06/18/16 7 23H09 JH SW JH JLV670 15-38 JH NW JH AC 06/18/16 8 13-38 / 15-36 JH N/A JH DBL B/G 17F10 / 17G09 JH N/A JH AC 06/18/16 9 23K09 JH SW JH JLK805 13-38 JH SW JH AC 06/18/16 10 23K08 JH SW JH JLK812 15-36 JH NE JH AC 06/18/16 11 23G11 JH SW JH JLV698 37-16 JH SE JH AC 06/18/16 12 23G10 JH SW JH JLV708 39-18 JH NW JH AC 06/18/16 13 37-18 / 39-16 JH N/A JH DBL B/G 17F09 / 17G08 JH N/A JH AC 06/18/16 14 23F10 JH SW JH JLK807 37-18 JH SW JH AC 06/18/16 15 23F09 JH SW JH JLK820 39-16 JH NE JH AC 06/18/16 16 17J13 / 17J12 JH N/A JH DBL B/G 13-18 / 15-16 JH N/A JH AC 06/18/16 ENG-0190 V8.0 PP1.015 42FH-ERP-014-0

SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 3 OF 3 FORM TITLE:

FUEL MOVEMENT SHEETS Movements Performed/Verified By:

John Hart / JH / 6/18/16 / /

Print Init Date Print Init Date Alan Carter / AC / 6/18/16 / /

Print Init Date Print Init Date

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Print Init Date Print Init Date ENG-0190 V8.0 PP1.015 42FH-ERP-014-0

EAST N S O O R U T T H H WEST Control Cell 38-37

EAST N S O O R U T T H H WEST Control Cell 14-37

EAST N S O O R U T T H H WEST Control Cell 38-17

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL ADMIN 4 (RO ONLY)

Title:

CONDUCT OF OPERATIONS, 34SV-SUV-019-1 SURVEILLANCE Author: Media Number: Time:

Anthony Ball 2016-301 ADMIN 4 15.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee: Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Ed Jones 05/30/16

This page intentionally left blank SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 3 of 11 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code: OPERATIONS TRAINING Media Number: 2016-301 ADMIN-4 Authors Supvs Rev. No. Date Reason for Revision Initials Initials Made editorial changes from LR-JP-10022 to use on 1 5/26/11 2011-301 NRC Exam. Changed K/A to G2.1.7. ELJ CME Minor revision to match procedure and use on ILT-10 NRC Exam. Reviewed JPM against current 1.1 05/30/16 procedure. Changed Media Number to 2016-301 ARB ELJ ADMIN 4. This JPM will become LR-JP-10022 after NRC Exam.

2016-301 ADMIN 4 Page 4 of 11 UNIT 1 (X) UNIT 2 ()

TASK TITLE: CONDUCT OF OPERATIONS, 34SV-SUV-019-1 SURVEILLANCE JPM NUMBER: 2016-301 ADMIN 4 TASK STANDARD: This task will be satisfactorily met when the student has completeted section 7.5 of 34SV-SUV-019-1, SURVEILLANCE CHECKS, and informed the evaluator that Unit 1 drywell cooling system should be placed in Additional Cooling Operating Mode.

TASK NUMBER:

OBJECTIVE NUMBER:

JTA IMPORTANCE RATING:

K/A CATALOG NUMBER: G2.1.7 RO 4.40 SRO 4.70 OPERATOR APPLICABILITY: Reactor Operator (RO)

GENERAL

REFERENCES:

Unit 1 34SV-SUV-019-1 REQUIRED MATERIALS: Unit 1 34SV-SUV-019-1.

Complete previous shift data in step 7.5.4 (149 and 148)

Calculators APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: NOT applicable

EVALUATOR COPY UNIT 1 READ TO THE CANDIDATE INITIAL CONDITIONS:

1. Unit 1 is operating at 100 % power.

2. 1T47-R611 is out of service.

3. 1T47-R612 is out of service.

4. The SS has directed this surveillance be completed as a paper version.

5. 1T47-R611 PT 14 and 1T47-R612 PT 10 Previous readings:

1T47-R611 PT 14 (1T47-N009) was 149ºF

1T47-R612 PT 10 (1T47-N003) was 148ºF INITIATING CUES:

Complete section 7.5 of 34SV-SUV-019-1, SURVEILLANCE CHECKS, which evaluates drywell temperatures, AND Inform the evaluator of any actions (if any) that need to be taken as a result of the readings or results obtained from this surveillance.

SHOW ALL WORK.

2016-301 ADMIN 4 Page 6 of 11 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

PROMPT: GIVE the operator an entire copy of 34SV-SUV-019-1.

START TIME:__________

NOTE: When the candidate addresses the need for SPDS readings provide Attachment 1.

1. Determine method for obtaining Per NOTE S of 34SV-SUV-temperature readings. 019-1, the candidate determines temperature readings can be obtained from SPDS.

- 2. Performs step 7.5.1 of From the SPDS screen shot, the 34SV-SUV-019-1. candidate has listed the following temperature readings on the surveillance sheet for; 1T47-N001L 120 N004 109 N008, 114 N001M, 114 N005 114

3. Performs step 7.5.2 of The candidate evaluates the 34SV-SUV-019-1. temperatures from step 7.5.1 and determines the maximum temperatute minus the minimum temperature is less than 40ºF.

4. Performs step 7.5.3 of The candidate evaluates the 34SV-SUV-019-1. readings in step 7.5.1. and concludes the highest is less than 275ºF and the lowest temperature is greater than 50ºF.

2016-301 ADMIN 4 Page 7 of 11 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 5. Performs step 7.5.4 of From the SPDS screen shot, the 34SV-SUV-019-1. candidate has listed the following temperature readings on the surveillance sheet for; 1T47-N009 176 1T47-N003 175 AND Has listed the temperatures from the previous readings provided in the Initial Conditions.

- 6. Performs step 7.5.5 of The candidate compares the 34SV-SUV-019-1. current temperature readings in step 7.5.4 to those from the previous reading and concludes the temperatures DO differ by more than 10ºF AND that a CR must be written

7. Performs step 7.5.6 of The candidate confirms the 34SV-SUV-019-1. maximum reading in step 7.5.4 is less than 275ºF and the minimum is greater than 50ºF AND the maximum temperature minus the minimum temperature of step 7.5.4 is less than 50ºF.

- 8. Performs step 7.5.7 of From the SPDS screen shot, the 34SV-SUV-019-1. candidate has listed the following temperature readings on the surveillance sheet for; 1T47-N001J, 199 N001K, 164 N002, 157 N001A, 182 N001B, 187 N010. 154

2016-301 ADMIN 4 Page 8 of 11 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

9. Performs step 7.5.8 of The candidate determines the 34SV-SUV-019-1. maximum temperature from step 7.5.7 minus the lowest temperature from step 7.5.7 is less than 100ºF.

10. Performs step 7.5.9 of The candidate confirms the 34SV-SUV-019-1. maximum reading in step 7.5.7 is less than 275ºF and the minimum is greater than 50ºF.

- 11. Performs step 7.5.10 of Using the formula at the bottom 34SV-SUV-019-1. of the surveillance page, the candidate calculates the average drywell temperature to be 136.7ºF. (Accept +/-1°F due to rounding errors)

- 12. Addresses any additional actions that The candidate informs the are required as a result of the average evaluator that since average drywell temperature reading. drywell temperature exceeds 135ºF, per note L of the surveillance the shift is to place the Drywell Cooling System in Additional Cooling Operating mode per 34SO-T47-001-1.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when:

Operator completes step 12 of this JPM With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: That completes this JPM.

Answer Key REAC T/S OR OPER 7.5 PANEL - INSTRUMENT / TECH SPEC. NOTE FREQ N D MODE LIM 1H11-P657: - 1T47-R611, Pt 9 (1T47-N001L) 120 Pt 11 (1T47-N004) R,S,C 109 7.5.1 Pt 13 (1T47-N008) (spec 1,2,3 c NA 114 1H11-P654: - 1T47-R612, Pt 9 (1T47-N001M) only) 114 Pt 11 (1T47-N005) 114 7.5.2 Confirm max minus min in 7.5.1 < 40°F B 1,2,3 c SAT 7.5.3 Confirm max < 275°F and min > 50°F in 7.5.1 B,C 1,2,3 c NA SAT 1H11-P657: - 1T47-R611, PT 14 (1T47-N009)

Previous shift reading 149 Present reading 176 7.5.4 R,S 1,2,3 c NA 1H11-P654: - 1T47-R612, PT 10 (1T47-N003)

Previous shift reading 148 Present reading 175 IF the previous reading differs from the present reading by YES IF CR greater than 10°F OR IF erratic instrument behavior is submitted. YES 7.5.5 observed THEN submit a CR to evaluate the Operability of N/A 1,2,3 c the instruments in step 7.5.4. NR IF NOT (SR 3.3.3.1.1 for 3.3.3.1-1(10)) required Confirm max < 275°F and min > 50°F AND max minus min <

7.5.6 50°F in 7.5.4 B 1,2,3 c NA (SR 3.3.3.1.1 for 3.3.3.1-1(10)) SAT 1H11-P657: - 1T47-R611, Pt 7, (1T47-N001J) 199 Pt 8, (1T47-N001K) 164 Pt 10, (1T47-N002) 157 7.5.7 R,S 1,2,3 c NA 1H11-P654: - 1T47-R612, Pt 7, (1T47-N001A) 182 Pt 8, (1T47-N001B) 187 Pt 13, (1T47-N010) 154 Confirm max minus min in 7.5.7 < 100°F 7.5.8 B 1,2,3 c (SR 3.3.3.1.1 for 3.3.3.1.1(10)) SAT 7.5.9 Confirm max < 275°F and min > 50°F in 7.5.7 B,C 1,2,3 c NA SAT Average Drywell Temperature 7.5.10 (SR 3.6.1.5.1)

L 1,2,3 c < 150°F 136.7 INITIALS Calculations verified DATE TIME DW Temp = (7.5.1 TE's ) (0.63) + (7.5.4 TEs) (0.22) + (7.5.7 TE's ) (0.15) 1 5 2 6 Page 9 of 11

UNIT 1 READ TO THE CANDIDATE INITIAL CONDITIONS:

1. Unit 1 is operating at 100 % power.

2. 1T47-R611 is out of service.

3. 1T47-R612 is out of service.

4. The SS has directed this surveillance be completed as a paper version.

5. 1T47-R611 PT 14 and 1T47-R612 PT 10 Previous readings:

1T47-R611 PT 14 (1T47-N009) was 149ºF

1T47-R612 PT 10 (1T47-N003) was 148ºF INITIATING CUES:

Complete section 7.5 of 34SV-SUV-019-1, SURVEILLANCE CHECKS, which evaluates drywell temperatures, AND Inform the evaluator of any actions (if any) that need to be taken as a result of the readings or results obtained from this surveillance.

SHOW ALL WORK.

Page 10 of 11 Page 11 of 11

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL ADMIN 5 (ALL)

Title:

EVALUATE AN RWP AND SURVEY MAP Author: Media Number: Time:

Art Genereux 2016-301 ADMIN 5 10.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee: Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Ed Jones 05/30/16

This page intentionally left blank SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH Page 3 of 8 FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code: OPERATIONS TRAINING Media Number: 2016-301 ADMIN 5 Authors Supvs Rev. No. Date Reason for Revision Initials Initials 00 08/16/13 Modified 2009-302 NRC Exam & renumbered for ARB CME ILT-8 NRC Exam. After exam will be renumbered and placed into the LOCT & ILT bank.

0.1 05/30/16 Modified 2013-301 NRC Exam to select RWP and ABG ELJ determine if task can completed without exceeding any limits. After exam will be renumbered and placed into the LOCT & ILT bank as a New JPM.

2016-301 ADMIN 5 Page 4 of 8 UNIT 1 (x) UNIT 2 ()

TASK TITLE: Comply with radiation work permit requirements during normal or abnormal conditions.

JPM NUMBER: 2016-301 ADMIN 5 TASK STANDARD: The task shall be completed when the operator has determined:

the correct RWP, Estimated Dose, and whether or not the predicted task could be completed without exceeding any limits and why.

TASK NUMBER: N/A OBJECTIVE NUMBER: N/A TYPE N/A PLANT HATCH JTA IMPORTANCE RATING:

RO N/A SRO N/A K/A CATALOG NUMBER: G2.3.7 K/A CATALOG JTA IMPORTANCE RATING:

RO 3.5 SRO 3.6 OPERATOR APPLICABILITY: Nuclear Plant Operator (NPO)

GENERAL

REFERENCES:

Unit 1 RWP 16-0004 RWP 16-0164 RP surveys Condenser Bay NMP-HP-001, Radiation Protection Standards 60AC-HPX-004-0, Radiation & Contamination Control REQUIRED MATERIALS: Unit 1 RWP 16-0004 RWP 16-0164 RP surveys Condenser Bay APPROXIMATE COMPLETION TIME: 10 Minutes SIMULATOR SETUP: N/A

EVALUATOR COPY UNIT 1 READ AND GIVE A COPY TO THE OPERATOR INITIAL CONDITIONS:

1 Unit 1 is operating at 20% RTP.

2. You will be performing clearance activities in the vicinity of the Main Turbine Control valves.

3. The clearance activities will be performed on the 147 ft elevation in the Condenser Bay.

4. Total estimated round-trip TRANSIT dose is 5 mrem

5. Total estimated time at the job site is 80 minutes INITIATING CUES:

Use the above conditions and the provided survey map to determine the following:

The correct RWP for the task

The projected dose

If the clearance activity can or cannot be performed. If applicable, identify any limits that are exceeded.

2016-301 ADMIN 5 Page 6 of 8 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For Initial Operator Programs:

For OJT/OJE; All procedure steps must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

START TIME: _________

PROMPT: AT this time, give the operator the RWPs and RP Survey Map.

- 1. Determine the appropriate RWP. Operator determines that RWP 16-0164 is the correct RWP.

NOTE: RWP 16-004 can be used to enter High Rad Areas but not Locked High Rad or Very High Rad areas.

- 2. Determines the estimated dose. Operator determines the estimated dose, using at location dose rate of 105 mR/hr, for the task is: 80 minutes

105 mrem

/60 min = 140 mrem. Add transit dose of 5 mrem combine dose =

145 mrem (+ 1.0 mrem).

NOTE: The student may say that current plant policy is to leave the area at 80% of the allowable dose (80 mrem).

2016-301 ADMIN 5 Page 7 of 8 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 3. Determine the task can be completed Operator determines that the task without exceeding limits. cannot be completed without exceeding the task dose alarm of 100 mrem.

END TIME:__________

NOTE: The terminating cue shall be given to the Applicant when:

After JPM step #3 is complete.

With NO reasonable progress, the Applicant exceeds double the allotted time.

Applicant states the task is complete.

TERMINATING CUE: That completes this JPM.

UNIT 1 READ AND GIVE A COPY TO THE OPERATOR INITIAL CONDITIONS:

1 Unit 1 is operating at 20% RTP.

2. You will be performing clearance activities in the vicinity of the Main Turbine Control valves.

3. The clearance activities will be performed on the 147 ft elevation in the Condenser Bay.

4. Total estimated round-trip TRANSIT dose is 5 mrem

5. Total estimated time at the job site is 80 minutes INITIATING CUES:

Use the above conditions and the provided survey map to determine the following:

The correct RWP for the task

The projected dose

If the clearance activity can or cannot be performed.

If applicable, identify any limits that are exceeded.

20 80 105 mrem/hr 105

Southern Nuclear Company Operations Training Job Performance Measure (JPM)

FINAL ADMIN 6 SRO ONLY

Title:

Emergency Classification - Complete NMP-EP-110 Checklist 1 Author: Media Number: Time Critical:

Anthony Ball 2016-301 ADMIN 6 15.0 Minutes Line Technical Review By (N/A for minor revisions) Date:

N/A N/A Reviewed by Instructional Technologist or designee (N/A for minor revisions) Date:

N/A N/A Approved By (Training Program Manager or Lead Instructor) Date Ed Jones 05/30/16

This page intentionally left blank Page 3 of 13 Course Number Program Name Media Number N/A OPERATIONS TRAINING 2016-301 ADMIN 6 Authors Sups Ver. No. Date Reason for Revisions Initials Initials 0.0 04/30/07 Initial development CME RAB Added Task and HU Pass/Fail criteria. Updated 1.0 11/04/10 Southern Company logo. ELJ CME Updated references to NMP-EP-110 and 2.0 01/12/11 NMP-EP-111 MCK DNM General revision for use on NRC Exam 2012-301. After 3.0 06/07/12 NRC Exam, Media Number will be changed to LR-JP- ARB CME 25061-03.

Minor revision to match procedure and use on ILT-10 NRC Exam. Reviewed JPM against current procedure.

3.1 03/30/16 ARB ELJ Changed Media Number to 2016-301 ADMIN 6. This JPM will become LR-JP-25061 after NRC Exam.

Line Contributors The following individuals contributed to the development of this lesson plan.

Ver. No. List of Contributors

2016-301 ADMIN 6 Page 5 of 13 UNIT 1 (X) UNIT 2 (X)

TASK TITLE: Emergency Classification - Complete NMP-EP-110 Checklist 1 JPM NUMBER: 2016-301 ADMIN 6 TASK STANDARD: This task shall be successfully completed when the event has been classified and NMP-EP-110 Checklist 1, step 1 through step 6, has been correctly completed.

TASK NUMBER: 200.052 OBJECTIVE NUMBER: 200.052.A PLANT HATCH JTA IMPORTANCE RATING:

RO 4.67 SRO 4.04 K/A CATALOG NUMBER: Generic 2.4.41 K/A CATALOG JTA IMPORTANCE RATING:

RO 2.30 SRO 4.1 OPERATOR APPLICABILITY: Senior Reactor Operator GENERAL

REFERENCES:

Unit 1 & 2 NMP-EP-110, Ver 8.1 NMP-EP-111, Ver 11.0 REQUIRED MATERIALS: Unit 1 & 2 NMP-EP-110, Ver 8.1 NMP-EP-111, Ver 11.0 APPROXIMATE COMPLETION TIME: 15.0 Minutes SIMULATOR SETUP: NA

EVALUATOR COPY UNIT 1 & 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. You are the On-Shift Shift Manager.

2. Both Units were operating a 100% RTP when they both experienced a Loss of Station Power (LOSP).

3. The following Unit 1 conditions exist:

EDG 1A, 1B, and 1C start attempts have been unsuccessful from the Main Control Room

Other plant systems operated as expected

4. The following Unit 2 conditions exist:

EDG 2A successfully started and operated as expected

EDG 2C start attempts have been unsuccessful

Other plant systems operated as expected

5. Maintenance and System Operators have been dispatched to locally start the remaining EDGs.

Maintenance informs the Main Control Room that EDG 1A will be ready to be started in 30 minutes.

Maintenance informs the Main Control Room that EDG 1B & EDG 1C will be ready to be started in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

INITIATING CUES:

DECLARE the event using NMP-EP-110, Checklist 1.

THIS IS TIME CRITICAL.

2016-301 ADMIN 6 Page 7 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

For INITIAL Operator Programs:

For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.

For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.

IF THEN Human performance tools, safety, PPE met (1), AND Mark the JPM as a PASS For initial trg all steps completed correctly OR PASS For continuing trg, critical steps (if used) completed correctly Mark the JPM as a FAIL FAIL Above standards not met (1) The standard for human performance tools, safety, PPE, and other pertinent expectations is considered met provided any deviations are minor and have little or no actual or potential consequence. Errors may be self-corrected provided the action would not have resulted in significant actual or potential consequences. (AG-TRN-01-0685 Section 6.5.3 provides examples)

NOTE: The CLASSIFICATION must be made within 15 minutes of the initial prompt and the Student states they understand the initial conditions.

NOTE: Provide a copy of Checklist 1of NMP-EP-110 and Attachment 1 of JPM.

START TIME:_________

1. Operator identifies the procedure The operator has OBTAINED needed to perform the task. Check List 1, which is contained in NMP-EP-110.

2. Determine the appropriate Initiating On Checklist 1, Step 1, Condition Matrix for classification of The operator has selected HOT the event based on the current IC/EAL Matrix Evaluation Chart operating mode:

HOT IC/EAL Matrix Eval Chart COLD IC/EAL Matrix Eval Chart Both HOT & COLD IC/EAL Matrix (Checklist 1, Step 1)

- Indicates critical step)

2016-301 ADMIN 6 Page 8 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

3. Evaluate the status of the fission On Checklist 1, Step 2.a, product barrier using Figure 1, Fission The operator has selected Product Barrier Evaluation. INTACT for Fuel Cladding Select the condition of each fission Integrity.

product barrier:

Fuel Cladding Integrity (Checklist 1, Step 2)

4. Evaluate the status of the fission On Checklist 1, Step 2.a, product barrier using Figure 1, Fission The operator has selected Product Barrier Evaluation. INTACT for Reactor Cooling Select the condition of each fission System.

product barrier:

Reactor Coolant System (Checklist 1, Step 2)

5. Evaluate the status of the fission On Checklist 1, Step 2.a, product barrier using Figure 1, Fission The operator has selected Product Barrier Evaluation. INTACT for Containment Select the condition of each fission Integrity.

product barrier:

Containment Integrity (Checklist 1, Step 2)

6. Determine the highest applicable On Checklist 1, Step 2.b, fission product barrier Initiating The operator has selected NONE Condition (IC).

(Checklist 1, Step 2.b.)

- Indicates critical step)

2016-301 ADMIN 6 Page 9 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

7. Evaluate AND determine the highest On Checklist 1, Step 3.

applicable IC/EAL using the Matrix The operator has identified SS1 Evaluation Chart(s) identified in step 1 THEN Go To step 4.

(Checklist 1, Step 3)

8. Check the highest emergency On Checklist 1, Step 4.

classification level identified from The operator has selected either step 2b or 3:

Site-Area as the Classification.

Classification (Checklist 1, Step 4)

- 9. Check the highest emergency On Checklist 1, Step 4.

classification level identified from The operator has selected SS1 for either step 2b or 3: the Based on IC#. SS1 is highest

- - - - and current EAL for Unit 1.

Based on IC # Current EAL for Unit 2 is SA5 (Checklist 1, Step 4)

NOTE: It is expected that the IC# be filled in on Checklist 1 (in the above step).

10. Remarks (Identify the specific EAL, On Checklist 1, Step 4.

as needed). The operator has written Loss of both SATs and failure of EDGs (Checklist 1, Step 4) to power Emerg Buses and at least 1 Emerg Bus not restored within 15 minutes in the space provided.

NOTE: If follow-up questioning reveals that a classification was declared and based on another IC #, the classification should be evaluated for validity.

- Indicates critical step)

2016-301 ADMIN 6 Page 10 of 13 STEP PERFORMANCE STEP STANDARD SAT/UNSAT

(COMMENTS)

- 11. Declare the event by approving the On Checklist 1, Step 5.

Emergency Classification. The operator has signed their name as the Emergency Director (Checklist 1, Step 5) in the space provided.

- 12. Fill in the Date in the space provided. On Checklist 1, Step 5.

The operator has entered the (Checklist 1, Step 5) current Date in the space provided.

- 13. Fill in the Time in the space provided. On Checklist 1, Step 5.

The operator has entered the (Checklist 1, Step 5) current Time in the space provided.

Time Critical Stop Time: .

NOTE: For this step to be completed considered SAT, the time entered must be within 15 minutes of the time recorded on the Initial Conditions sheet provided to the operator.

END TIME:__________

NOTE: The terminating cue shall be given to the operator when:

Operator completes step 13 of this JPM.

With NO reasonable progress, the operator exceeds double the allotted time.

Operator states the task is complete.

TERMINATING CUE: We will stop here.

- Indicates critical step)

- - INSTRUCTOR ANSWER KEY ***

Checklist 1 - Classification Determination NOTE Key Parameters should be allowed to stabilize to accurately represent plant conditions prior to classifying an event Initial Actions Completed by

1. Determine the appropriate Initiating Condition Matrix for classification of the event based on the current operating mode:

Student HOT IC/EAL Matrix Evaluation Chart (Go To Step 2) to evaluate the Barriers)

COLD IC/EAL Matrix Evaluation Chart (Go To Step 3)

Both HOT & COLD IC/EAL Matrix Evaluation Chart apply (Go To Step 2)

2. Evaluate the status of the fission product barrier using Figure 1, Fission Product Barrier Evaluation.

a. Select the condition of each fission product barrier: Student LOSS POTENTIAL LOSS INTACT Fuel Cladding Integrity Reactor Coolant System Containment Integrity

b. Determine the highest applicable fission product barrier Initiating Condition (IC): Student (select one) FG1 FS1 FA1 FU1 None

3. Evaluate AND determine the highest applicable IC/EAL using the Matrix Evaluation Chart(s) identified in step 1 THEN Go To step 4.

Student Hot IC# SS1 Unit 1 and/or Cold IC# __________ Unit___ or None

4. Check the highest emergency classification level identified from either step 2b or 3:

Student Classification Based on IC# Classification Based on IC#

General Alert Site-Area SS1 NOUE None N/A Remarks (Identify the specific EAL, as needed): A loss of both SATs and failure of EDGs to power Emerg Buses and at least 1 Emerg Bus not restored within 15 minutes.

5. Declare the event by approving the Emergency Classification.

Student Date: ***** / ***** / **** Time: ****** Student Emergency Director

6. Obtain Meteorological Data (not required prior to event declaration):

Wind Direction (from) 130 Wind Speed 5 Stability Class D Precipitation 0 Student

7. Initiate Attachment 2, Checklist 2 - Emergency Plan Initiation. ____________

Page 11 of 13

UNIT 1 & 2 READ TO THE OPERATOR INITIAL CONDITIONS:

1. You are the On-Shift Shift Manager.

2. Both Units were operating a 100% RTP when they both experienced a Loss of Station Power (LOSP).

3. The following Unit 1 conditions exist:

EDG 1A, 1B, and 1C start attempts have been unsuccessful from the Main Control Room

Other plant systems operated as expected

4. The following Unit 2 conditions exist:

EDG 2A successfully started and operated as expected

EDG 2C start attempts have been unsuccessful

Other plant systems operated as expected

5. Maintenance and System Operators have been dispatched to locally start the remaining EDGs.

Maintenance informs the Main Control Room that EDG 1A will be ready to be started in 30 minutes.

Maintenance informs the Main Control Room that EDG 1B & EDG 1C will be ready to be started in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

INITIATING CUES:

DECLARE the event using NMP-EP-110, Checklist 1.

THIS IS TIME CRITICAL.

ATTACHMENT 1 METEOROLOGICAL DATA Wind Direction (from) 130 Wind Speed 5 Stability Class D Precipitation 0

ML17187A227

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