ML17096A738

2017 Perry Nuclear Power Plant Initial Licensed Operator Examination Administered Simulator Scenarios

ML17096A738
Person / Time
Site:	Perry
Issue date:	04/05/2017
From:	David Reeser NRC/RGN-III/DRS/OLB
To:	NRC/RGN-III/DRS/OLB, FirstEnergy Nuclear Operating Co
Shared Package
ML16242A242	List: ML17096A729 ML17096A732 ML17096A737 ML17096A738 ML17096A744
References
Download: ML17096A738 (79)

Text

Appendix D Scenario Outline Form ES-D-1 NUREG 1021, Rev. 10 Page 1 of 1 FENOC Facsimile Facility: Perry Scenario No.: 1 - 100%

Op-Test No.: 2017-1 Examiners:

Operators:

(SRO)

(ATC)

(BOP)

Initial Conditions: Plant is at 100% power. Motor Feed Pump and CRD B pump are tagged out due to oil leaks. HPCS/RCIC are Protected. eSOMS Narrative Log is down. Risk is Green and the Grid is Normal.

Turnover: Planned activities; Start HPCS ESW pump for vibration testing. Page Jeff Reeves when HPCS ESW is running. Shift Manager has evaluated risk and directs crew to start HPCS ESW. NLO has been briefed and is on station to support pump start. When contacted by SCC lower Rx power to 93% per the Reactivity Plan and IOI-3 Power Maneuvering, for upcoming surveillances. Make any Narrative Log entries on your note pads.

Event No.

Malf.

No.

Event Type*

Event Description 1

N-(BOP)

N-(SRO)

Start HPCS ESW for vibration testing.

2 av02_1n25f 0280a &

av021n25f0 290a R-(ATC)

R-(SRO) 6A Feedwater Heater isolation.

Lower Rx power 96%

3 NM04A I-(ATC)

I-(SRO)

APRM A fails upscale - lockup FCVs TS 3.3.1.1 & ORM 6.2.1 4

cp02_1p45 c0002 C-(BOP)

C-(SRO)

HPCS ESW pump trips.

TS 3.5.1 and/or 3.8.1 5

>OBE_file ZA1N27R0 401_7 &

FW66 &

cp03_1n27 c0002b M-(Crew)

Earthquake <OBE &Trip RFPT A on high vibrations Scram Rx on lowering RPV level. Enter EOP-1 6

C-(BOP)

Post SCRAM RCIC fails to auto start at L2 7

>OBE_file loss_level_f ile M(Crew)

C-(BOP)

Earthquake aftershock >OBE Loss of RPV level - enter E0P-4-4 ADS SRV B21-F041E fails to open on ED (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Narrative Summary - Initial Scenario 1 100%

Event

1.

The BOP starts the HPCS ESW Pump (P45-C002).

2.

Feedwater heater 6A drain valves fail causing a high heater water level resulting in isolation of extraction steam to the FW heater. The SRO will enter ONI-N36. The ATC will immediately lower Rx power to 96% with Recirc Flow and maintain Rx power 96% as FW temperature decreases causing Rx power to increase. The SRO will also enter ONI-C51 for the unexpected Rx power change.

3.

APRM A fails upscale requiring the ATC to lockup Recirc Flow Control Valves. APRM A will then be bypassed. SRO evaluates T.S 3.3.1.1 & ORM 6.2.1

4.

The HPCS ESW pump will trip due to a heat damaged control power transformer in the MCC bucket. The SRO enters T.S. 3.7.1 & 3.8.1. The SRO will direct the BOP to place Div. 3 diesel generator and HPCS system in secured status.

5.

An earthquake (<OBE) causes lowering flow on RFPT B and high vibrations on RFPT A. The vibration level exceeds the ARI setpoint for the operator to trip the pump. If the operator fails to trip the RFPT, it will trip after several minutes resulting in a Recirc FCV runback and a slow downward trend on RPV water level as flow continues to degrade on RFPT B. As RPV water level approaches L3, the ATC will scram the Rx. If the crew allows RPV water level to go <L3, RPS will not automatically scram the Rx. However, if the crew allows RPV water level to lower to L2, ARI will insert rods.

6.

If RCIC has not been manually initiated before RPV level lowers to L2, RCIC will not auto start.

The operator must manually initiate RCIC to recover RPV level.

7.

After RCIC has been started and is recovering RPV level, a second and larger earthquake (>OBE) will occur. This will result in a sequential loss of all RPV level indication. This will require the crew to Emergency Depressurize the Rx and flood the RPV up to the Main Steam Lines. While performing ED, SRV B21-F041E will fail to open, requiring operator to open additional SRV.

EOPs:

EOP-1 & EOP-04-4 ABNORMALs:

ONI-N36 ONI-C51 ONI-C34 ONI-D51 Critical tasks:

1. Manually initiate RCIC prior to reaching L1 causing an MSIV isolation.

2. ED when RPV level indication is lost.

3. Use low pressure systems to raise RPV water level above the MSLs

Appendix D, Rev. 10 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 1 of 21 Event

Description:

N/A - Driver Instructions Cue:

Time Position Applicants Actions or Behavior Driver Driver Simulator Setup:

Reset Simulator to IC 131 Load Schedule File: NRC2017-S1.sch Verify Schedule File: NRC2017-S1-seismic1.sch, NRC2017-S1-seismic2.sch, &

NRC2017-S1-level.sch are in the Exam folder in SCHEDULES Verify Event File: NRC2017-S1.evt loads Verify Unit 2 Electrical Line-up Board is posted outside Instructor Station.

Adjust white o-rings Place Protected Train sign in front of HPCS /RCIC Adjust N21-F220 to maintain N21-R475 75% to 85%.

Remove Requal IOI-3 and Rod Book from horseshoe.

Verify correct set of EOP charts.

Driver Driver Verify Initial Conditions:

Reactor Power 100%. Rod Book B1151221.SEQ, Rods @ Step 67.

IOI-3 Step 4.6 is complete.

Tech Spec Rounds Book is in Simulator MFP and CRD B shutdown to secured status.

Place YELLOW switch caps on MFP, suction & discharge valves and AC & DC Oil Pumps and CRD B & Aux Oil Pump.

Traffic Light - Green Risk.

Driver Driver Initial Conditions:

Plant is at 100% power. Motor Feed Pump and CRD B Pump are tagged out due to oil leaks. HPCS/RCIC are Protected. eSOMS Narrative Log is down. Risk is Green and the Grid is Normal Turnover: Planned activities; Start HPCS ESW for vibration testing. Page Jeff Reeves when HPCS ESW is running. Shift Manager has evaluated risk and directs crew to start HPCS ESW.

NLO has been briefed and is on station to support pump start. When contacted by SCC lower, power to 93% per the Reactivity Plan and IOI-3 Power Maneuvering, for upcoming surveillances. Make any Narrative Log entries on your note pads.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 2 of 21 Event

Description:

1 - Start HPCS ESW for vibration testing Cue: From Turnover Time Position Applicants Actions or Behavior Driver Role play as an NLO/Chemistry as directed.

Evaluator Should discuss expected alarm for ESW Pump start.

SRO Direct BOP to start HPCS ESW IAW SOI-P45/49.

BOP Perform SOI-P45/49 Section 4.5 to startup HPCS ESW pump.

4.5.1 TAKE the HPCS ESW PUMP control switch to START.

1P45-C002 4.5.2 VERIFY the following:

• HPCS ESW PUMP DISCH VALVE starts opening.

1P45-F140

• WHEN the discharge valve reaches approximately 10% open, THEN the HPCS ESW PUMP starts.

1P45-C002

• HPCS ESW PUMP DISCH VALVE opens fully.

1P45-F140 4.5.3 DIRECT Chemistry to perform the following:

• OBTAIN required samples per REC-0104.

• CHLORINATE HPCS ESW as required.

4.5.4 PERFORM a Channel Check of ESW Effluent flow indication per the Technical Specification Rounds, and record the channel check in the Narrative Log.

BOP Report to SRO that pump start is complete and contact Jeff Reeves.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 3 of 21 Event

Description:

2 - 6A Feedwater Heater isolation Cue: ARI-H13-P870-05-E1 Time Position Applicants Actions or Behavior Driver When directed initiate Event 2. Role play as needed ATC Announce unexpected alarms and give stability report.

BOP Announce HTR 6A EXST & INLET DRAINS ISOL LEVEL HIGH alarm.

Walkdown H13-P870 and determine and announce 6A FW Heater is isolating/has isolated.

Report ONI-N36 entry condition.

SRO Announce entry into ONI-N36, Loss of Feedwater Heating ATC Perform ONI-N36 Immediate Action - Lower Rx power 96% using Recirc Flow.

Evaluator Power reduction should be immediate and performed without direction from the SRO. If ATC slow to lower Rx power, may get Turbine Bypass Valve open.

SRO Announce entry into ONI-C51, Unplanned Change in Rx Power or Reactivity and obtain ONI-C51 Flow Chart BOP Monitor the remaining FW heaters for proper operation.

SRO Direct ATC and BOP to perform Supplemental Actions in ONI-N36 and Subsequent Operator Actions for ARI H13-P870-05A-E1 BOP Verify that the valves identified in ARI H13-P870-5A-E1 have automatically repositioned. Perform ARI Subsequent Operator Actions when directed by the SRO SRO Direct ONI-C51 flow chart Actions:

Direct ATC to monitor nuclear instrumentation for oscillations and Scram the Rx if any occur (Step C51-4)

ATC Monitor nuclear instrumentation for oscillations and Scram the Rx if any occur SRO Direct BOP to perform ONI-SPI-G4 Power Verification. (ONI-C51-flow chart Step C51-5)

BOP Perform ONI-SPI G4, Power Verification.

• Inform Reactor Engineer of current plant conditions.

• Declare a TRA Event on 3DMonitor computer

• Review Power/Flow Map to determine if licensed power limits were exceeded.

• Print a Periodic Log to determine if Thermal Limits were exceeded

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 4 of 21 Event

Description:

2 - 6A Feedwater Heater isolation Cue: ARI-H13-P870-05-E1 Time Position Applicants Actions or Behavior SRO Direct ATC to confirm jet pump operation within established limits. (ONI-C51 flow chart Step C51-15)

ATC Confirm jet pump operation within established limits by observing ICS Jet Pump Screen and From SPDS Operator Aid Menu:

• Selects NORM JET PUMP DPS and observes Jet Pump DPS is NORMAL (green) with no red or yellow individual jet pump readings.

• Selects NORM JET PUMP FLOW and observes Jet Pump FLOWS is NORMAL (green) with no red or yellow individual jet pump readings.

Report to SRO that jet pump operation within established limits.

Driver If directed to manually open Heater 6A Drain to Cndr 1N25F280A, then in 1/2 hour report the valve has been manually opened Driver If asked to look at 1N25-F290A locally, after appropriate time, respond that it looks like it is sticking.

Driver If directed (as I&C) to pull trip units C71-N652AD, IAW ONI-N36 Attachment 3 Step 2.0, wait 4 minutes them report trip units pulled.

Evaluator NOTE: Actions to pull trip units not required for scenario. If not directed, Evaluator discuss with SRO post scenario.

SRO Evaluate FW temperature reduction effects on Tech Specs (referenced in ONI-SPI-G4) 3.3.1.1-1.9 Turbine stop valve closure 3.3.1.1-1.10 Turbine control valve closure 3.3.2.1-1.1 Rod Pattern Control System 3.3.4.1 EOC RPT

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 5 of 21 Event

Description:

3 - APRM A fails upscale Cue: ARI-H13-P680-06-B5 & C4 and APRM Instrumentation Time Position Applicants Actions or Behavior Driver When directed initiate Event 3. Role play as needed ATC Announce unexpected alarms and give stability report.

Determine that APRM A is failing (or has failed) upscale causing a 1/2 scram and that AFDL is in control.

Perform immediate actions of ARI-H13-P680-04-E9:

3.1 IF the alarm is due to APRM A or E failed upscale, THEN PERFORM the following:

• 3.1.1 VERIFY reactor power has NOT increased.

• 3.1.2 ARM and DEPRESS HPU A SHUTDOWN pushbutton.

• 3.1.3 ARM and DEPRESS HPU B SHUTDOWN pushbutton.

Notify SRO that Recirculation HPUs have been locked-up.

SRO Enter ONI-C51, Unplanned Changes in Reactor Power or Reactivity if power changed.

Evaluator If ATC locks-up FCVs before they move, no power change will occur.

If the Crew enters ONI-C51, there are no pertinent actions in the ONI for this event.

Driver If BOP looks for indications on APRM A, inform him the meter is reading upscale and the UPSCALE Trip light is illuminated.

Crew Determine that APRM A should be bypassed and that 1/2 scram should be reset per SOI-C51(APRM) and SOI-C71.

SRO Direct ATC/BOP to bypass the APRM A channel per SOI-C51(APRM).

ATC Bypasses APRM A IAW SOI-C51(APRM) Section 7.4:

7.4.1 REFER TO Technical Specification Table 3.3.1.1-1 Item 2 for applicability.

7.4.2 IF APRM Channel A is to be bypassed, THEN VERIFY that all conditions of either 7.4.2.a OR 7.4.2.b exist:

NOTE When bypassing APRM A, the following step must be performed to ensure a Rcirc Flow change does not occur.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 6 of 21 Event

Description:

3 - APRM A fails upscale Cue: ARI-H13-P680-06-B5 & C4 and APRM Instrumentation Time Position Applicants Actions or Behavior ATC 7.4.2.a Both of the following conditions exist:

• FCV A MOTION INHIBITED annunciator, H13-P680-4-A5, is alarmed.

• FCV B MOTION INHIBITED annunciator H13-P680-4-A14, is alarmed.

7.4.2.b All of the following conditions exist:

• RCIRC AUTOMATIC FLOW DEMAND LIMITER indicates zero output. (1B33-K650)

• The AFDL IN CONTROL annunciator is NOT alarmed.

• RCIRC FLUX CONTROL is in MAN. (1B33-K602)

• The AFDL Setpoint on RCIRC AUTOMATIC FLOW DEMAND LIMITER tapeset is higher than the APRM CH E reading. (1B33-K650) 7.4.3 PLACE the NEUTRON MONITOR BYPASS, APRM joystick on 1H13-680, in the BYPASS position for the APRM Channel being bypassed.

1C51B-S3 CH A Directs BOP to perform Steps 7.4.4 & 7.4.9.

Evaluator If asked, APRM A Back Panel Bypass light is lit BOP 7.4.4 CONFIRM that the APRM BYPASS status light comes on at the selected APRM's Power Range Neutron Mon Panel.

1H13-P669 7.4.9 If the bypassed APRM channel caused any trips any alarms, then reset those trips or alarms ATC Inform Crew that APRM A has been bypassed and informs SRO that Technical Specification 3.3.1 Table 3.3.1.1-1 Item 2 should be referenced.

SRO Direct ATC/BOP to reset 1/2 scram IAW SOI-C71 and ARI-P680-06A-B5.

ATC/BOP Reset 1/2 scram by performing SOI-C71, section 7.4:

7.4.1 VERIFY the following:

• The conditions which caused the full or half scram have cleared.

• There is reasonable assurance that another scram signal will NOT be generated.

7.4.2 IF the RPS INST VOL HI annunciator is in alarm on 1H13-P680-5A-A7, THEN PLACE the appropriate RPS division keylock switches in BYPASS.

• INST VOL LEVEL HI SCRAM BYPASS CH A. (1C71-S4A)

• INST VOL LEVEL HI SCRAM BYPASS CH C. (1C71-S4C)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 7 of 21 Event

Description:

3 - APRM A fails upscale Cue: ARI-H13-P680-06-B5 & C4 and APRM Instrumentation Time Position Applicants Actions or Behavior ATC/BOP 7.4.3 VERIFY the following Manual Scram pushbuttons are NOT armed:

• Manual Scram Pushbutton 1C71-S3A

• Manual Scram Pushbutton 1C71-S3B

• Manual Scram Pushbutton 1C71-S3C

• Manual Scram Pushbutton 1C71-S3D 7.4.4 MOMENTARILY DEPRESS the appropriate RPS division pushbuttons on P680:

• SCRAM RESET CH A. 1C71A-S5A

• SCRAM RESET CH C. 1C71A-S5C Evaluator The remaining portion of SOI-C71 Section 7.4 is N/A.

ATC/BOP Inform Crew that 1/2 scram has been reset.

SRO Evaluate Technical Specifications TS 3.3.1.1 RPS Instrumentation Cond H & Cond G (Potential LCOs)

ORM 6.2.1 APRM Control Rod Block Instrumentation (Potential LCO).

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 8 of 21 Event

Description:

4 - HPCS ESW pump trips S/D Div 3 EDG to Sec. Stat and S/D HPCS pump to Sec Stat.

Cue: ARI-H13-P601-16-D4 Time Position Applicants Actions or Behavior Driver When directed initiate Event 4. Role play as needed ATC Announce unexpected alarms and give stability report.

BOP Walkdown H13-P601 and determine and announce HPCS ESW Pump has lost power.

BOP Dispatch NLO to investigate HPCS ESW loss of power.

Driver If directed to investigate MCC EF1E2-H, after appropriate amount of time, report the control power transformer shows signs of over-heating and control power fuse is blown.

If directed to investigate HPCS ESW Pump, report no visible problems.

SRO Direct BOP to place Div. 3 DG and HPCS Pump in secured status.

BOP Place Div. 3 DG in Secured Status IAW SOI-E22B Section 6.3 6.3.1 VERIFY Diesel Generator is Shutdown to Standby Readiness.

6.3.2 PLACE the DIESEL GENERATOR in PULL-TO-LOCK at 1H13-P601.

BOP Direct NLO to perform the following:

6.3.3 PLACE the DIESEL GENERATOR MODE in MAINT at 1E22-P001.

6.3.4 PERFORM Independent Verification of required components.

Evaluator If Div 3 DG not placed in secured status now, will need to do Emergency Shutdown when RPV level goes below L2 later in the scenario.

Driver When directed to Place the Diesel Generator Mode in MAINT at 1E22-P001, after appropriate amount of time report completion. (no computer input necessary)

BOP Place HPCS in Secured Status IAW SOI-E22A Section 6.2 6.2.1 RECORD the following in the Plant Narrative Log in accordance with PAP-1125:

• Availability management time entries

• Unavailable time entries Driver When directed to perform SOI-E22A Step 6.2.2, wait 4 minutes then initiate Event 24 and report completion.

When directed to perform SOI-E22A Step 6.2.3, wait 2 minutes then initiate Event 25 and report completion.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 9 of 21 Event

Description:

4 - HPCS ESW pump trips S/D Div 3 EDG to Sec. Stat and S/D HPCS pump to Sec Stat.

Cue: ARI-H13-P601-16-D4 Time Position Applicants Actions or Behavior BOP Direct NLO to perform the following:

6.2.2 PERFORM one of the following, as directed by Unit Supervisor for the HPCS PUMP Breaker:

EH1304

• REMOVE the control power fuses

• REFER TO SOI-R22 and RACK OUT the HPCS PUMP Breaker 6.2.3 OPEN the HPCS INJECTION VALVE Disconnect.

1E22-F004 EF1E-1-F 6.2.4 IF the HPCS Water Leg Pump is required to be off, THEN PERFORM the following:

1E22-C003 6.2.5 PERFORM independent verification of the required components Evaluator Step 6.2.4 is not required.

SRO Evaluate Tech Specs T.S. 3.8.1 Action B.1 - Perform SR 3.8.1.1 for operable required off site circuits. - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B.2 - Declare required features supported by the inop DG inop when the redundant required features are inop. - 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B.3.1 Determine operable DGs are not inop due to common cause failure. - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B.4 Restore required DG to operable status. - 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for Div. 3 T.S. 3.5.1 Action B.1 - Verify by administrative means RCIC System is operable when RCIC is required to be operable. - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B.2 - Restore HPCS System to operable status. - 14 days Evaluator If TS 3.5.1 Entered then HPCS DG not required and TS 3.8.1 need not be entered.

Evaluator Completion of SVI-R10-T5227 not necessary for scenario.

SRO May direct BOP to perform SVI-R10-T5227 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

BOP Commences SVI-R10-T5227 to be complete within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> as directed.

Driver Provide BOP with Unit 2 Control Room lineup poster.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 10 of 21 Event

Description:

5 - Earthquake <OBE Trip RFPT A on high vibrations Scram Rx on lowering RPV level Cue: ARI-H13-P680-08-B3/C3 & ARI-H13-P680-03-C6 Time Position Applicants Actions or Behavior Driver When directed initiate Event 5. Then immediately call the control room as SAS Operator and report multiple Security Officers have reported a seismic event. Role play as needed ATC Announce unexpected seismic and vibration alarms and give stability report.

Evaluator Feed pump turbine, and Recirc pump vibration annunciators will momentarily alarm, but will return to normal.

BOP Walkdown H13-P969 and determine and announce multiple AMBER seismic alarm lights.

Report ONI-D51 entry condition.

SRO Announce entry into ONI-D51, Earthquake.

SRO Direct ATC and BOP to perform Supplemental Actions in ONI-D51 and Subsequent Operator Actions of ARI H13-P870-08-B3 & C3 Notify Shift Manager to check E-plan BOP Direct NLO to investigate Seismic Panel H51-P021.

Driver If sent to H51-P021, report Event Indicator Flag is WHITE and Seismic Switch Yellow light is NOT illuminated.

BOP Direct NLO to perform ONI-D51 Attachment 1.

SRO Declare seismic instruments INOP until reset by RSE (ORM 6.2.7) per ONI-D51 Step 4.3 Evaluator 5 minutes after earthquake RFPT B will experience an increasing head loss concurrent with RFPT A vibration problem.

ATC Announce unexpected RFPT A vibration alarm and give stability report.

ATC Recognize and announce RFPT A vibration is increasing.

ATC Direct NLO to investigate RFPT A.

Driver If directed to investigate RFPT A vibration, wait until after RFPT A trips and report turbine is coasting down.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 11 of 21 Event

Description:

5 - Earthquake <OBE Trip RFPT A on high vibrations Scram Rx on lowering RPV level Cue: ARI-H13-P680-08-B3/C3 & ARI-H13-P680-03-C6 Time Position Applicants Actions or Behavior SRO Direct ATC to trip RFPT A if vibration >4 mils for 3 minutes.

Driver If crew does not trip RFPT A, when directed, initiate EVENT 15 to trip RFPT A.

ATC Trips RFPT A when vibration >4 mils for 3 minutes.

SRO Announce entry into ONI-C34, Feedwater Flow Malfunction Evaluator RFPT trip will cause a Flow Control Valve runback signal, but FCVs will not runback due to being locked up in Event3.

Evaluator Using the Margins and Limits Hardcard as guidance, SRO may direct scram at RPV level of 185 lowering.

ATC Recognize and announce problem with RFPT B and lowering RPV level.

Scram Rx on lowering RPV level.

Evaluator RPS will fail to automatically insert a scram at L3, but placing Mode Switch to Shutdown will work. Also, if RPV level is allowed to lower to L2, ARI will insert rods.

BOP Make Plant announcement for the Scram and evacuate containment ATC Place the mode switch in Shutdown

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 12 of 21 Event

Description:

6 - Post SCRAM response with RCIC auto start failure Cue: ARI-H13-P680-08-B3/C3 & ARI-H13-P680-03-C6 Time Position Applicants Actions or Behavior ATC Performs Scram Hardcard actions (OAI-1703 att. 10)

1.

VERIFY the following actions completed:

• Mode Switch Locked in Shutdown

• RPS Initiated (if all control rods are not fully inserted)

• ARI Initiated (if RPS failed to Scram the reactor)

2.

IF Reactor Recirc Pumps are running in fast speed, THEN SIMULTANEOUSLY TAKE RCIRC PUMP BRKRs 5A and 5B to XFER.

4.

STABILIZE Reactor level using Feedwater / RCIC / HPCS

5.

STABILIZE Reactor pressure using Turbine / Turbine Bypass valves /

SRVs

6.

PERFORM crew update...

ATC Updates crew on scram status and EOP Entry conditions.

SRO Announce entry into EOP-1, RPV Control SRO Direct ATC to stabilize Rx water level using the Feedwater Hardcard and stabilize Rx pressure using Pressure Control Hardcard ATC Continue Scram Hardcard actions.

7.

RECORD the TIME: _____________

8.

STABLIZE reactor water level:

a) Feedwater REFER TO the FEEDWATER HARDCARD b) RCIC c) HPCS

9.

STABLIZE reactor pressure:

a) Turbine / Turbine Bypass valves:

• REFER TO the PRESSURE CONTROL HARDCARD b) SRVs:

• EVACUATE Containment

• REFER TO the PRESSURE CONTROL HARDCARD

• EVALUATE placing RCIC in pressure CONTROL MODE

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 13 of 21 Event

Description:

6 - Post SCRAM response with RCIC auto start failure Cue: ARI-H13-P680-08-B3/C3 & ARI-H13-P680-03-C6 Time Position Applicants Actions or Behavior

10.

INSERT Nuclear Instruments:

• SRMs

• IRMs

• PLACE recorders in IRM (Leave A or E in APRM for digital display)

11.

IF the generator was synchronized at the time of the reactor scram, THEN WHEN generator load is reduced to less than 90 MWe, Then perform the following a) TRIP the main turbine by depressing the TURBINE TRIP push-button.

b) VERIFY the following have occurred:

• Main Stop Valves are shut (Four Valves)

• Turbine Control Valves are shut (Four Valves)

• Turbine Combined Intermediate Valves are shut (Six Valves)

• GEN BRKR S-610-PY-TIE is open

• GEN BRKR S-611-PY-TIE is open

• GEN FIELD BREAKER is open

12.

VERIFY HST LVL CV MANUAL CONTROL, N21-S19, IN OFF.

ATC Perform Feedwater hard card (OAI-1703 Att. 11) (FW Hardcard will not be useful) and Pressure Control hard card (OAI-1703 att. 14)

BOP Recognize that RCIC failed to Auto start at L2 and manually initiate RCIC and inform the SRO. (Critical Task 1)

Evaluator Event 7 will automatically initiate one minute after RCIC is started.

SRO Direct BOP to verify Isolations and Actuations for Level 3 and Level 2 BOP Verify Isolation and Actuations per Hardcards

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 14 of 21 Event

Description:

7 - Earthquake aftershock >OBE Loss of RPV level - enter E0P-4-4 Cue: SRO Direction / RO response to RPV level trend Time Position Applicants Actions or Behavior Driver Event 7 will automatically initiate 1 minute after RCIC is initiated.

Driver After 2nd earthquake, immediately call the control room again as SAS Operator and report multiple Security Officers have again reported a seismic event.

BOP Walkdown H13-P969 and determine and announce multiple RED and AMBER seismic alarm lights.

Report ONI-D51 entry condition.

SRO Announce re-entry into ONI-D51, Earthquake.

SRO Direct BOP to perform Supplemental Actions in ONI-D51 BOP Direct NLO to perform ONI-D51 Attachments 1, 2, & 3.

Evaluator Note: All level indications are lost over several minutes.

Crew Recognize and report that there is no valid level indication.

SRO Enters EOP-04-4, RPV Flooding Directs BOP to open 8 ADS Valves (Critical Task 2)

BOP/ATC Attempts to opens 8 ADS Valves. One ADS valve B21-F041E fails to open. Report 7 SRVs are open (Critical Task 2)

SRO Direct BOP to open additional SRVs until 8 SRVs are open. (Critical Task 2)

BOP Open additional SRVs to get 8 SRVs open. (Critical Task 2)

SRO Directs BOP to start:

• Hydrogen igniters

• Hydrogen analyzers BOP Performs the following:

• Verifies ESW pump running

• Verifies ECC pump running

• Verifies Comb Bas H2 Anal Outlet Clg Valve open

• Verifies Comb Bas H2 Anal Inlet Clg Valve open

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 15 of 21 Event

Description:

7 - Earthquake aftershock >OBE Loss of RPV level - enter E0P-4-4 Cue: SRO Direction / RO response to RPV level trend Time Position Applicants Actions or Behavior

• Takes Comb Gas H2 Anal Sample Valve keylock switch to open

• Verifies Mode & Function Selector is in Sample

• Places the System Function SW in On

• Directs field operator to complete H2 Analyzer startup

• Takes Div 1 H2 Igniter control switch to On

• Takes Div 2 H2 Igniter control switch to On SRO Directs ATC to inject with RFBPs (Critical Task 3)

ATC Opens Feedwater Pump Bypass Valve, N27-F200 valve. (Critical Task 3)

SRO Directs BOP/ATC to:

• Inject with LPCS IAW EOP-SPI-6.5(Critical Task 3)

• Inject with RHR IAW EOP-SPI-6.1, 6.2, 6.3 (Critical Task 3)

BOP/ATC Performs the following for LPCS:

• Verify LPCS Injection Valve is closed.

• Verify ESW pump A is running.

• Verify ECC pump A is running.

• Verify LPCS pump is running.

• Operate LPCS injection Vlv to full open (Critical Task 3)

BOP/ATC Performs the following for RHR A (B) (C):

• Verify LPCI Injection Valve A (B) (C) is closed

• Verify ESW Pump A (B) is running

• Verify ECC Pump A (B) is running

• Verify LPCI Pump A (B) (C) is running

• Opens LPCI Injection Valve A (B) (C) or opens E12-F053A/B with Bypass Keylock Switch in Bypass. (Critical Task 3)

SRO Directs BOP to isolate:

• MSIVs

• MS Line Drains

• RCIC Steam Isolations BOP Isolates:

• MSIVs

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 16 of 21 Event

Description:

7 - Earthquake aftershock >OBE Loss of RPV level - enter E0P-4-4 Cue: SRO Direction / RO response to RPV level trend Time Position Applicants Actions or Behavior

• MS Line Drains

• RCIC Steam Isolations Evaluator If crew fails to shut MSIVs, they will auto close on high flow when water starts flowing down steam lines.

All At least one injection system is injecting to recover level to above the MSL (Critical Task 3)

SRO

• Enters EOP-2, Primary Containment Control on Suppression Pool Level or Suppression Pool Temperature

• Directs BOP to monitor for level above the MSL.

Evaluator There are no substantive actions for EOP-2.

SRO Direct crew to depressurize RPV to < 45 psig and reduce injection to maintain RPV level above main steam lines.

BOP Monitors for Suppression Pool level, with constant or rising RPV pressure:

• Without injection from outside Suppression Pool level stabilizes

• With injection from sources outside Suppression Pool Level slowly increases.

Notifies SRO when indications of water level above is above Main Steam Lines.

Crew Reduces injection into RPV to lower RPV pressure to < 45 psig while maintaining RPV level above main steam lines.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 17 of 21 Event

Description:

Scenario Termination Criteria Time Position Applicants Actions or Behavior

1.

Reactor shutdown.

2.

Reactor depressurized to less than or equal to 45 psig.

3.

Injects to maintain level above the main steam lines

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 18 of 21 Event

Description:

Critical Task #1 Time Position Applicants Actions or Behavior Prior to Reactor Level lowering to MSIV isolation setpoint (RPV Level 1), crew restores RCIC to control Reactor Level.

1.

Safety Significance:

With MSIVs isolated the Main Condenser is not available as a heat sink for depressurization of the Reactor, thus increasing the energy released to the primary containment.

2.

Cues:

Procedural compliance.

Reactor Level trend.

3.

Measured by:

Observation - Reactor Level maintained greater than 16.5".

Observation - MSIVs do not isolate on low reactor level.

4.

Feedback:

Reactor level trend RCIC Injection Valve position indication

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 19 of 21 Event

Description:

Critical Task #2 Time Position Applicants Actions or Behavior When RPV Level cannot be determined, initiate Emergency Depressurization.

1.

Safety Significance:

Precludes fuel damage by establishing adequate core cooling.

2.

Cues:

Procedural compliance.

Loss of all level indication.

3.

Measured by:

Observation - At least two SRVs opened when RPV level cannot be determined.

4.

Feedback:

RPV pressure trend.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 20 of 21 Event

Description:

Critical Task #3 Time Position Applicants Actions or Behavior With reactor water level unknown, inject into RPV with one or more low pressure ECCS pumps to establish RPV level above the Main steam Lines.

1.

Safety Significance:

Prevent fuel damage by establishing and maintaining adequate core cooling.

2.

Cues:

RPV water level unknown.

Procedural compliance.

3.

Measured by:

Observation - RPV level established and controlled above the MSLs.

(10 psig increase in RPV pressure with ADS SRV tailpipe temperatures decreasing).

4.

Feedback:

RPV pressure indication.

SRV tail pipe temperature indication.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 1 - 100%

Page 21 of 21 Procedures to verify clean Procedure Number Check IV Procedure Number Check IV ARI H13-P870-05-B1, B2, C1, C2, & E1 ORM 6.2.1 ARI-H13-P601-16-D4 ORM 6.2.7 ARI-H13-P680-03-C6 SOI-C51(APRM) Section 7.4 ARI-H13-P680-06-B5 & C4 SOI-C71 Section 7.4 ARI-H13-P680-08-B3/C3 SOI-E22A Section 6.2 EOP-04-4 Chart SOI-E22B Section 6.3 EOP-1 Chart SOI-P45/49 Section 4.5 & 6.4 EOP-SPI 2.3 SRO oversight flip packs EOP-SPI-6.1 SVI-R10-T5227 EOP-SPI-6.2 T.S. 3.5.1 EOP-SPI-6.3 T.S. 3.8.1 EOP-SPI-6.5 TS 3.3.1.1 EOP-SPI 6.6 TS 3.3.1.1-1.10 Scram Hardcard TS 3.3.1.1-1.9 Pressure Control Hardcard TS 3.3.2.1-1.1 Feedwater Hardcard TS 3.3.4.1 Hydrogen Analyzer Startup Hardcard SOI-C51(APRM) Section 7.4 Hydrogen Igniter Startup Hardcard SOI-C71 Section 7.4 Isolation and Actuations Hardcards Margins and Limits Hardcard ONI-C51 ONI-C51 Flow Chart ONI-D51 ONI-N36 ONI-SPI-G4

Appendix D Scenario Outline Form ES-D-1 NUREG 1021, Rev. 10 Page 1 of 1 FENOC Facsimile Facility: Perry Scenario No.: 2 - 90%

Op-Test No.: 2017-1 Examiners:

Operators:

(SRO)

(ATC)

(BOP)

Initial Conditions: Last shift, power was reduced to 90% IAW IOI-3, Attachment 3 per SCC request. Service Water Pump A is out of service for planned maintenance. HPCS pump tagged out for motor replacement - 2 days into LCO. eSOMS Narrative Log is down.

Turnover: Planned activities; raise reactor power to 100% when requested by SCC; shift Service Water Pumps from C to D, an NLO has been briefed and is on station. Make any Narrative Log entries on your note pads. Risk is Green and the Grid is Normal.

Event No.

Malf.

No.

Event Type*

Event Description 1

N-(BOP)

N-(SRO)

Shift Service Water Pumps from C to D running 2

R-(ATC)

R-(SRO)

Raise Rx power using Rx Recirc flow 3

C-(SRO)

SLC B Pump Suction Valve blown fuse, TS 3.1.7 4

I-(BOP)

I-(SRO)

RCIS lock-up ORM 6.1.2 5

C-(ATC)

C-(SRO)

RFBP C pressure degrades 6

M-(Crew)

Loss of IA in DW, Scram on Inboard MSIVs closure, EOP-1 7

M-(crew)

ATWS >4% EOP-01A & EOP-02 8

C-(BOP)

ESW A fails auto start, manually start ESW A 9

C-(BOP)

E12-F042B will not override shut, trip RHR B pump (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Narrative Summary - Initial Scenario 2 90%

Event

1.

The BOP shifts Service Water Pumps from C to D running.

2.

The ATC will raise Rx power to 100% IAW the reactivity plan and IOI-3. The SRO will provide reactivity oversight.

3.

Standby Liquid Control B pump suction valve will lose power due blown main-line fuses in the MCC bucket. The SRO enters T.S. 3.1.7.

4.

RC&IS will become inoperable by locking up on a control rod. The crew will enter ONI-C11-1, Inability to Move Control Rods and will need to reset RC&IS IAW SOI-C11(RC&IS). The SRO will evaluate Tech Specs and ORM and enter ORM 6.1.2.

5.

The Reactor Feed Booster Pump C discharge pressure will begin to degrade but the standby RFBP will not auto start. The operator must manually start the standby RFBP.

6.

A loss of Instrument Air to the Drywell will result in the inboard MSIVs shutting. This will result in an automatic Rx scram and an ATWS >4%. This will challenge HCL. The US will enter EOP-1 and transition to EOP-1A. Also enter EOP-2. The crew will need to inhibit ADS, Terminate injection into the RPV, manually insert control rods, and maintain margin to HCL.

7.

Emergency Service Water pump A will not auto start on T&P and must be manually started.

8.

LPCI A Injection Valve E12-F042B will not override shut for T&P. The RO trips the RHR B pump to T&P EOPs:

EOP-1, EOP-1A & EOP-2 ABNORMALs:

ARI for RC&IS.

ARI for RFBP ONI-C11-1 Critical tasks:

1. Inhibit ADS.

2. Insert Control Rods

3. Terminate and prevent Feedwater and ECCS injection for level control

4. Maintain RPV pressure/Suppression Pool temperature below HCL

5. Terminate and prevent Feedwater and ECCS injection for Emergency Depressurization (Contingency)

6. Emergency Depressurize if cannot Maintain RPV pressure/Suppression Pool temperature below HCL

7. When <MSCP, restore and maintain RPV level above MSCRWL (-25") (Contingency)

Appendix D, Rev. 10 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 2 - 90%

Page 1 of 26 Event

Description:

N/A - Driver Instructions Time Position Applicants Actions or Behavior Driver Driver Simulator Setup:

Reset Simulator to IC 132 Load Schedule File: NRC2017-S2.sch Verify Event File Loads: NRC2017-S2.evt Load patch file RD15 5% power.dat from PSIMA Check APRM gains.

Place Protected Train Sign in front of RCIC.

Adjust white o-rings Adjust N21-F220 to maintain N21-R475 75% to 85%.

Reset NUMACS and acknowledge alarms on Yokagawas (P632/P642 & P614)

Remove Requal IOI-3 and Rod Book from horseshoe.

Place STAR magnet on Load Set Driver Driver Verify Initial Conditions:

Reactor Power 90%

Pull Sheets, Book B1151221 Rods @ Step 67.

IOI-3 Attachment 3 marked-up to Step 1.6. Service Water Pump A is out of service for planned maintenance.

Place yellow switch caps on HPCS Pump & Inj. Valve, SW Pump A & SWP A discharge valve.

Verify SPDS screens are scaled properly.

Traffic Light - Green Risk.

Driver Driver Initial Conditions: Last shift, power was reduced to 90% IAW IOI-3, Attachment 3 per SCC request. Service Water Pump A is out of service for planned maintenance. HPCS pump tagged out for motor replacement - 2 days into LCO.

eSOMS Narrative Log is down.

Turnover: Planned activities; raise reactor power to 100% when requested by SCC; shift Service Water Pumps from C to D, an NLO has been briefed and is on station. Make any Narrative Log entries on your note pads. Risk is Green and the Grid is Normal.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 2 - 90%

Page 2 of 26 Event

Description:

1 - Shift Service Water Pumps from C to D running Cue: From Turnover Time Position Applicants Actions or Behavior Driver Role play as NLO/Chemistry as directed BOP Direct BOP to shift Service Water Pumps Driver IF asked, Seal Water flows for B & C pumps is 3.2 gpm BOP Perform SOI-P40/41 Section 7.1 to shift Service Water Pumps 7.1.1 START the oncoming Service Water Pump as follows:

7.1.1.a IF the oncoming pump is A OR D, THEN THROTTLE, as necessary, the SW Pump Lube Water Supply valve to maintain the oncoming Service Water Pump seal flow between 3 and 5 gpm.

0P41-F546D BOP Direct NLO to verify seal flow is between 3 - 5 gpm for SWP D Driver As NLO, report that SWP D seal water flow is 3.4 gpm.

BOP 7.1.1.c TAKE the SW PUMP DISCH VLV to OPEN.

P41-F040D 7.1.1.d WHEN the blue light comes on, THEN PRESS the STOP button.

7.1.1.e TAKE the SW PUMP to START.

P41-C001D 7.1.1.f WHEN the oncoming SW PUMP AMPS stabilize, THEN TAKE the oncoming SW PUMP DISCH VLV to OPEN.

P41-F040D 7.1.2 SHUTDOWN the Offgoing Service Water Pumps as follows:

7.1.2.a PERFORM the following steps concurrently:

7.1.2.a.1 TAKE the SW PUMP DISCH VLV to CLOSE.

P41-F040C 7.1.2.a.2 WHEN either of the following occur,

• The applicable blue light comes on P41F040C

• SW Pump Discharge valve indicates full closed THEN TAKE the SW PUMP to STOP.

P41-C001C 7.1.2.b THROTTLE the NCC HX SW BYPASS VLV to achieve the desired operating pump discharge pressures.

P41-F400 7.1.2.c VERIFY the applicable SW PUMP DISCH VLV indicates CLOSED.

P41-F040C 7.1.3 Direct Chemistry to place the Service Water Chlorination and dechlorination System in operation per SOI-P48/84B.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 2 - 90%

Page 3 of 26 Event

Description:

2 - Raise Rx power using Rx Recirc flow.

Cue: SCC call to Control Room Time Position Applicants Actions or Behavior Driver Call in as SCC & request Perry to raise power to 100%. Role play as RP, Chemistry, and Unit Dispatch / ACC for the power change SRO Direct ATC to raise Reactor Power to 100% in accordance with the Reactivity Plan with Flow. Provide Oversight.

IOI-3, Power Changes - Power Maneuvering 2.4 Continue to increase reactor power along the desired loadline by increasing Reactor Recirculation System flow UNTIL the desired power level has been obtained.

2.5 Adjust PRESS ST PT as necessary to maintain reactor steam dome pressure less than 1025 psig.

2.6 Maintain the turbine LOAD SET approximately 120 MWe above generator output to a maximum of 1450 MWe.

ATC Notify RP, Chemistry, and Unit Dispatch / ACC of the intended power change.

ATC Raise Rx power in accordance with the Reactivity Plan to 100% using Reactor Recirc flow. Keep A and B loop flows matched.

ATC Keep the Main Turbine load set 120 MWe above turbine load to a max of 1450 MWe ATC Maintain Reactor Feedwater Pump Turbine deviations nulled.

ATC Maintain N21-F230 between 75%-85% open by adjustment of N21-F220 manual control ATC Monitor Main turbine control valve positions for proper response to the power change ATC Monitor Average Power Range Monitors for proper response to the power change ATC Notify the SRO when the power change is complete. Notify RP, Chemistry, and Unit Dispatch / ACC

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 2 - 90%

Page 4 of 26 Event

Description:

3 - SLC B Pump Suction Valve blown fuse, TS 3.1.7 Cue: ARI-H13-P601-18-A4 & SLC B OOS Window Time Position Applicants Actions or Behavior Driver When directed initiate Event 3. Role play as needed ATC Announce unexpected P601 alarm and give stability report.

BOP Announce SLC B OUT OF SERVICE alarm and review the ARI.

SRO Direct BOP to perform Subsequent Operator Actions in ARI H13-P601-18-A4 BOP Perform ARI-H13-P601-18-A4 Subsequent Operator Actions:

4.1 Determine the cause of alarm by checking the following panel indications at 1H13-P601:

• Power available to SLC PUMP SUCT VALVE B C41-F001B BOP Notify the SRO that the cause of the alarm is SLC PUMP SUCT VALVE B, 1C41-F001B, power loss.

BOP 4.2 IF panel indication shows power is NOT available to a component, THEN VERIFY the applicable breaker is closed:

• SLC PUMP SUCT VALVE B EF1C07-C BOP Direct NLO to verify breaker EF1C07-C closed.

Driver After 3 minutes, acting as the NLO, report that the breaker EF1C07-C is closed.

BOP 4.3 The applicable breaker was closed and Power is NOT available, THEN VERIFY fuses associated with the de-energized component are intact:

• SLC PUMP SUCT VALVE B EF1C07-C BOP Direct NLO to verify fuses within EF1C07-C intact.

Driver After 2 minutes, report that two main line fuses in EF1C07-C are blown.

If asked to check penetration fuses, wait 2 minutes and report fuses are good.

BOP Report to SRO the blown fuses found in EF1C07-C.

SRO Evaluate Tech Spec T.S. 3.1.7 Action A.1 Restore SLC subsystem to Operable status. - 7 days

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 2 - 90%

Page 5 of 26 Event

Description:

4 - RCIS Lock-up, ONI-C11-1, Inability to move Control Rods, ORM 6.1.2 Cue: ARI-H13-P680-05-D8 Time Position Applicants Actions or Behavior Driver When directed initiate Event 4. Role play as needed ATC Announce INHIBIT ROD MOTION RCIS OOS alarm and give stability report.

ATC Review ARI H13-P680-05-D8 Subsequent Operator Actions:

4.1 DIRECT I&C to initiate trouble-shooting of RCIS.

4.2 REFER TO ONI-C11-1, Inability to Move Control Rods.

ATC

/BOP Direct I&C to trouble shoot cause of alarm Driver After 10 minutes report as I&C, that youre still investigating the cause of the RCIS OOS alarm.

ATC Inform crew of ONI-C11-1 entry condition SRO Announce entry into ONI-C11-1, Inability to Move Control Rods ATC Perform Immediate Actions of ONI-C11-1 3.0 IMMEDIATE ACTIONS 3.1 MAINTAIN plant parameters as steady as possible.

SRO Direct BOP to perform Supplemental Actions of ONI-C11-1 BOP Perform supplemental actions of ONI-C11-1 4.9 DETERMINE if the problem is in RCIS:

4.9.3 IF necessary, THEN REFER TO SOI-C11 (RCIS), Analyzer Shutdown Recovery to temporarily operate the RGDS Analyzer with a fault.

SRO Direct BOP to perform SOI-C11(RCIS), Section 7.19 RGDS Analyzer Shutdown Recovery

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 2 - 90%

Page 6 of 26 Event

Description:

4 - RCIS Lock-up, ONI-C11-1, Inability to move Control Rods, ORM 6.1.2 Cue: ARI-H13-P680-05-D8 Time Position Applicants Actions or Behavior BOP Perform RGDS Analyzer Shutdown Recovery as directed.

SOI-C11(RCIS) 7.19, RGDS Analyzer Shutdown Recovery NOTES Analyzer shutdown results in:

o All accumulator pressure and level information is blocked. (T.S. 3.1.5 and ORM 6.1.2) 7.19.1 NOTE the coordinates of the failed address.

7.19.2 ATTEMPT to reset the analyzer as follows:

7.19.2.a VERIFY the Test Address switch is in AUTO.

7.19.2.b VERIFY the Drive Bypassed backlit pushbutton is NOT lit.

7.19.2.c RESET the system by DEPRESSING AND HOLDING the RGDS Status RESET (left most pushbutton) on the Analyzer II card in the RGDC for at least 3 seconds.

7.19.2.d IF the analyzer is reset, THEN:

7.19.2.d.1 LOG the coordinates of the failed address.

7.19.2.d.2 NOTIFY the system engineer of the system reset.

7.19.2.d.3 EXIT this section.

Evaluator The analyzer failed on control rod 14-23.

SRO Evaluate Tech Specs T.S. 3.1.3, Control Rod Operability - no actions required T.S. 3.1.5, Control Rod Scram Accumulators - no actions required ORM 6.1.2, Control Rod Scram Accumulators Action a. With one or more accumulator pressure detectors or alarm inoperable,

1.

Locally check the affected accumulator(s) pressure at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or

2.

Declare the associated control rod scram accumulators INOPERABLE.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 2 - 90%

Page 7 of 26 Event

Description:

5 - RFBP C pressure degrades Cue: ARI-H13-P680-03-B9, -C2, & -E3 Time Position Applicants Actions or Behavior Driver When directed initiate Event 5. Role play as needed ATC Announce unexpected RFBP START RFP A/B NPSH LO & RFBP B FAIL TO START & RFBP C DISCH PRESS LO alarms and give stability report.

Driver If directed to investigate RFBP locally, respond that RFBP C is making abnormal noise.

SRO Provide oversight for ARI actions.

ATC Review ARI and RFB pump parameters:

ARI-H13-P680-03-B9 Automatic Action Standby RFBP A (B, C, D), 1N27-C001A, (B, C, D) starts ARI-H13-P680-03-E3 Subsequent Operator Action 4.1 MONITOR Suction and Discharge pressures for all operating RFBPs.

The RFBP C pressures are low The other RFBPs are NOT affected THEN REFER TO SOI-N27 and SHIFT RFBPs in operation Determines RFBP C, 1N27-C001C, discharge pressure is slowly degrading (<250 psig) and RFBP B has not started.

ATC Inform SRO that RFBP C is degrading, RFBP B did not auto start, and starts RFBP B.

Evaluator NOP-OP-1002 4.10.3 step 5 states If automatic actions fail to occur when required, it is the responsibility of the operator to take manual actions to perform the system or component function. Pump or component auto start failures are examples where operators are expected to take manual action.

Crew Follow-up SOI-N27 RFBP shift actions Evaluator Crew may enter ONI-C51 if they see a power change.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 2 - 90%

Page 8 of 26 Event

Description:

6 - Loss of IA in DW, Scram on Inboard MSIVs closure, EOP-1 Cue: ARI-H13-P601-19-C3 Time Position Applicants Actions or Behavior Driver When directed initiate Event 6.

ATC Announce unexpected P601 alarm and give stability report.

BOP Announce unexpected NS4 OUTBD ISOLATION OUT OF SERVICE alarm, observes valve matrix and reviews ARI.

BOP ARI-H13-P601-19-C3 Subsequent Operator Actions 4.1 CHECK the valve matrix (H13-P601), 1H31-P691 AND 1H31-P694 for gross failure.

Evaluator Inboard MSIVs will isolate in a short time as Instrument Air is lost to the Drywell due to P52-F646 closing.

ATC Announce RPS MSIV CLOSURE and FULL SCRAM alarms ATC Perform Scram Hardcard actions (OAI-1703 att. 10)

1.

VERIFY the following actions completed:

• Mode Switch Locked in Shutdown

• RPS Initiated (if all control rods are not fully inserted)

• ARI Initiated (if RPS failed to Scram the reactor)

2.

IF Reactor Recirc Pumps are running in fast speed, THEN SIMULTANEOUSLY TAKE RCIRC PUMP BRKRs 5A and 5B to XFER.

3.

IF Reactor power is above 4%: THEN PERFORM THE FOLLOWING:

• INHIBIT ADS (with US concurrence)

• INITIATE SLC ATC Direct BOP to inhibit ADS (Critical Task 1) with US concurrence and initiate SLC BOP Inhibit ADS (Critical Task 1) with US concurrence and initiate SLC A. -

Recognize SLC A Suction valve failure to open and informs SRO.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 2 - 90%

Page 9 of 26 Event

Description:

6 - Loss of IA in DW, Scram on Inboard MSIVs closure, EOP-1 Cue: ARI-H13-P601-19-C3 Time Position Applicants Actions or Behavior ATC Continue Scram Hardcard actions

4.

STABILIZE Reactor level using Feedwater / RCIC / HPCS ATC verifies Motor Feed Pump is started and manually controls Feedwater.

Continue Scram Hardcard actions

5.

STABILIZE Reactor pressure using Turbine / Turbine Bypass valves /

SRVs

6.

PERFORM crew update.

ATC Updates crew on scram status and EOP 1 Entry conditions.

SRO Announce entry into EOP-1, RPV Control Announce transition to EOP-1A, level Power since Rx power is > 4%

SRO Direct ATC to Monitor and Control Rx Power, Stabilize Rx water level using the Feedwater Hardcard and Stabilize Rx pressure using Pressure Control Hardcard ATC Continue Scram Hardcard actions.

7.

RECORD the TIME: _____________

8.

STABLIZE reactor water level:

9.

STABLIZE reactor pressure:

10.

INSERT Nuclear Instruments:

11.

IF the generator was synchronized at the time of the reactor scram, THEN WHEN generator load is reduced to less than 90 MWe, Then perform the following a) TRIP the main turbine by depressing the TURBINE TRIP push-button.

b) VERIFY the following have occurred:

• Main Stop Valves are shut (Four Valves)

• Turbine Control Valves are shut (Four Valves)

• Turbine Combined Intermediate Valves are shut (Six Valves)

• GEN BRKR S-610-PY-TIE is open

• GEN BRKR S-611-PY-TIE is open

• GEN FIELD BREAKER is open

12.

VERIFY HST LVL CV MANUAL CONTROL, N21-S19, IN OFF.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 2 - 90%

Page 10 of 26 Event

Description:

7 - ATWS >4% EOP-01A & EOP-02 Cue: APRM Down-scale lights are not illuminated Time Position Applicants Actions or Behavior SRO Announce transition to EOP-1A, level Power since Rx power is > 4%

SRO Direct EOP-01A actions Reactor Power Control leg

• Monitor and Control Rx Power

• Insert Control Rods EOP-SPI 1.1-1.7 if APRMs are not downscale (Critical Task 2)

• Initiate SLC

• Inhibit ADS (Critical Task 1)

• Initiate Alternate Boron Injection EOP-SPI 1.8 Reactor Level Control leg Stabilize Rx water level Verify Isolations and Actuations Inhibit ADS (Critical Task 1)

Maintain MSIVs open and override ECCS interlocks EOP-SPI 2.3 Terminate and Prevent (T&P) ECCS Injection (Critical Task 3)

Terminate and Prevent (T&P) Feedwater Injection (Critical Task 3)

When APRMs are downscale give a level band -25 to no more than 100 Start Hydrogen Igniters and Analyzers Reactor Pressure Control Leg Stabilize Reactor Pressure Direct pressure band of 5°F to 10°F below HCL (Critical Task 4)

Start Suppression Pool Cooling BOP Verify Isolations and Actuations hardcards

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 11 of 26 Event

Description:

7 - ATWS >4% EOP-01A & EOP-02 Cue: APRM Down-scale lights are not illuminated Time Position Applicants Actions or Behavior ATC Insert control rods using EOP-SPI 1.1-1.7 (Critical Task 2)

EOP-SPI 1.3 1.0 WHEN any CRD Pump is running, THEN PERFORM the following concurrently with the remainder of this procedure:

1.1 AT H13 P680, PERFORM the following to Insert all control rods to position 00:

DEPRESS AND HOLD the IN TIMER SKIP pushbutton.

SELECT Control Rods as required.

2.0 Isolation valve INST AIR CNTMT ISOL is CLOSED P52 F200 NO known air leak is present in Containment THEN AT H13 P870, THEN OPEN INST AIR CNTMT ISOL.

P52 F200 3.0 AT H13-P601, PERFORM the following:

3.1 VERIFY CRD HYDRAULICS FLOW CONTROL is in MANUAL.

C11-R600 3.2 ADJUST CRD HYDRAULICS FLOW CONTROL output to 100.

C11-R600 3.3 CLOSE CRD DRIVE PRESS CONTROL VALVE.

C11-F003 4.0 VERIFY the following keylock switches in BYPASS:

AT H13 P629, LO POWER SET PT DIV 1 BYPASS C11A-S4 AT H13 P618,LO POWER SET PT DIV 2 BYPASS C11A-S3 BOP When directed Terminate and Prevent ECCS Injection - hardcard (Critical Task 3)

ECCS TERMINATE AND PREVENT HARDCARD 1 PERFORM the following actions for ECCS systems that are in Standby or Operating conditions.

4. PERFORM Step 5 and Step 6 in any logical order.

5. TERMINATE AND PREVENT Division 1 as follows: (@ P601-15 & 17)

A. HOLD the following switches in CLOSE:

LPCS INJECTION VLV. 1E21-F005 LPCI A INJECTION VALVE. 1E12-F042A B. IF LPCS and LPCI A initiation signal is NOT present, THEN ARM AND

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 12 of 26 Event

Description:

7 - ATWS >4% EOP-01A & EOP-02 Cue: APRM Down-scale lights are not illuminated Time Position Applicants Actions or Behavior DEPRESS LPCS & LPCI A MANUAL INITIATION pushbutton to obtain the white LPCS & LPCI A SEAL IN RESET light.

C. PERFORM one of the following,

1) VERIFY LPCS INJECTION VALVE is CLOSED. 1E21-F005

2) TAKE LPCS PUMP to STOP. 1E21-C001 D. PERFORM one of the following,

1) VERIFY the following valves are CLOSED:

• LPCI A INJECTION VALVE. 1E12-F042A

• SHUTDOWN COOLING A TO FDW SHUTOFF valve. 1E12-F053A

• RHR A HEAD SPRAY ISOL valve. 1E12-F023

2) TAKE RHR A PUMP to STOP. 1E12-C002A

6. TERMINATE AND PREVENT Division 2 as follows: (@ P601-14)

A. HOLD the following switches in CLOSE:

• LPCI B INJECTION VALVE. 1E12-F042B

• LPCI C INJECTION VALVE. 1E12-F042C B. IF LPCI B and LPCI C initiation signal is NOT present, THEN ARM AND DEPRESS LPCI B & C MANUAL INITIATION pushbutton to obtain the white LPCI B & C SEAL IN RESET light.

C. PERFORM one of the following,

1) VERIFY RHR C INJECTION VALVE is CLOSED. 1E12-F042C

2) TAKE RHR C PUMP to STOP. 1E12-C002C D. PERFORM one of the following,

1) VERIFY the following valves are CLOSED:

• LPCI B INJECTION VALVE. 1E12-F042B

• SHUTDOWN COOLING B TO FDW

• SHUTOFF valve. 1E12-F053B

2)

TAKE the RHR B PUMP to STOP. 1E12-C002B ATC Terminate Feedwater Injection hardcard (Critical Task 3)

FEEDWATER TERMINATE AND PREVENT HARDCARD (@ P680-3 &

DFWLC Screens)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 13 of 26 Event

Description:

7 - ATWS >4% EOP-01A & EOP-02 Cue: APRM Down-scale lights are not illuminated Time Position Applicants Actions or Behavior

• VERIFY the following (preferred for Level Control):

• RFPT A is Tripped.

1N27-S24

• RFPT B is Tripped.

1N27-S28

• MFP FCV MANUAL/AUTO station in MANUAL with the output set to 0%.

C34-R601C

• MFP FULL FLOW CONTROL VALVE is CLOSED.

1N27-F010

• MFP LOW FLOW CONTROL VALVE is CLOSED.

1N27-F110

• RFP A DISCH VALVE is CLOSED.

1N27-F100A

• RFP B DISCH VALVE is CLOSED.

1N27-F100B

• FDW PUMPS BYPASS VALVE is CLOSED.

1N27-F200 BOP Start Hydrogen Igniters and Analyzers hardcard ATC Report to SRO when APRMs are downscale.

ATC Maintain directed Rx Level Band ATC/BOP Maintain Rx Pressure 5°F to 10°F below HCL (Critical Task 4)

Evaluator It is not anticipated that conditions will require the crew to perform Emergency Depressurization. However, if the crew determines they cannot Restore and Maintain RPV pressure and Suppression Pool temperature below HCL, the following (CONT.) steps will need to be performed to Emergency Depressurize the RPV.

CONT.

ATC/BOP Report cannot Maintain Rx Pressure 5°F to 10°F below HCL CONT.

SRO Determine RPV pressure and Suppression Pool temperature cannot be Restored and Maintained below HCL. Transition to EOP-4-2 via EOP-1A.

CONT.

SRO Direct EOP-01A actions Reactor Level Control leg Terminate and Prevent (T&P) ECCS Injection (Critical Task 5)

Terminate and Prevent (T&P) Feedwater Injection (Critical Task 5)

CONT.

BOP Verify ECCS previously Terminated and Prevented.

CONT.

ATC Terminate Feedwater Injection hardcard (Critical Task 5)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 14 of 26 Event

Description:

7 - ATWS >4% EOP-01A & EOP-02 Cue: APRM Down-scale lights are not illuminated Time Position Applicants Actions or Behavior FEEDWATER TERMINATE AND PREVENT HARDCARD (@ P680-3 &

DFWLC Screens)

• VERIFY the following (preferred for Level Control):

• RFPT A is Tripped.

1N27-S24

• RFPT B is Tripped.

1N27-S28

• MFP in OFF.

1N27-C004

• Heater 6A FDW BYPASS VALVE is CLOSED.

1N27-F135

• Heater 6A OUTLET VALVE is CLOSED.

1N27-F130A

• Heater 6B OUTLET VALVE is CLOSED.

1N27-F130B

• LOW FLOW CONTROLLER 1N27-F175 MANUAL/AUTO station in Manual with Output set to 0%.

1N27-F175

• FDW S/U VLV POSIT is 0.

1N27-R179 CONT.

SRO Direct EOP-4-2 actions Directs BOP to open 8 ADS Valves (Critical Task 6)

CONT.

BOP/ATC Opens 8 ADS Valves. Report 8 SRVs are open (Critical Task 6)

CONT.

SRO Direct EOP-01A actions Reactor Level Control leg Direct ROs to establish RPV level band of 150 to 219 using Feedwater and ECCS when RPV pressure < MSCP (160 psig) (Critical Task 7)

CONT.

ATC/BOP When RPV pressure < MSCP, commence feeding RPV and establish level band of 150 to 219. Report to SRO when in directed level band. (Critical Task 7)

Crew Monitors Containment parameters for EOP-2, Primary Containment Control entry SRO Announces entry into EOP-2 on SP Temperature and SP Level SRO Direct EOP-2 actions Suppression Pool Temperature leg

• Monitor and Control Suppression Pool Temperature

• Use one or more Suppression Pool Cooling Systems o RHR A o RHR B

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 15 of 26 Event

Description:

7 - ATWS >4% EOP-01A & EOP-02 Cue: APRM Down-scale lights are not illuminated Time Position Applicants Actions or Behavior Suppression Pool Level leg

• Monitor and Control Suppression Pool Temperature

• Maintain Suppression Pool level between 17.8 ft. and 18.5 ft.

BOP Places RHR Loops into SPC Mode as directed

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 16 of 26 Event

Description:

8 - ESW A fails auto start, manually start ESW A Cue:

Time Position Applicants Actions or Behavior Evaluator The following failure should be caught when verifying Isolations and Actuations.

BOP Observes ESW A pump failed to start and starts ESW A pump and informs SRO.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 17 of 26 Event

Description:

9 - E12-F042B will not override shut, trip RHR B pump Cue:

Time Position Applicants Actions or Behavior Evaluator The following failure should be caught when terminating and preventing ECCS.

BOP Observe LPCI B INJECTION VALVE. 1E12-F042B opening when control switch returned to AUTO. Terminate RHR B injection by taking RHR B pump to STOP and inform the SRO.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 18 of 26 Event

Description:

Termination Criteria Cue:

Time Position Applicants Actions or Behavior

1.

Reactor is subcritical with Control Rods being inserted.

2.

Reactor pressure being maintained below HCL or Emergency Depressurization performed.

3.

RPV water level maintained level between -25 and +100.

4.

If ED performed, RPV water level maintained level between 150 and 219.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 19 of 26 Event

Description:

Critical Task #1 Time Position Applicants Actions or Behavior With reactor scram required and the reactor not shutdown, to prevent an uncontrolled RPV depressurization and subsequent power excursion, inhibit ADS.

1. Safety Significance:

Precludes core damage due to an uncontrolled reactivity addition.

2. Cues:

Procedural compliance.

3. Measured by:

ADS logic inhibited prior to an automatic initiation unless all required injection systems are Terminated and Prevented.

4. Feedback:

RPV pressure trend.

RPV level trend.

ADS "ADS OUT OF SERVICE" annunciator status.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 20 of 26 Event

Description:

Critical Task #2 Time Position Applicants Actions or Behavior With a reactor scram required and the reactor not shutdown, initiate action to reduce power by inserting control rods.

1. Safety Significance:

Shutting down reactor can preclude failure of containment or equipment necessary for the safe shutdown of the plant.

2. Cues:

Procedural compliance.

Suppression Pool temperature.

3. Measured by:

Observation - Control Rod insertion commenced in accordance with Section 1.0 of EOP-SPIs.

4. Feedback:

Reactor Power trend.

Control Rod indications.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 21 of 26 Event

Description:

Critical Task #3 Time Position Applicants Actions or Behavior During an ATWS, when conditions are met to deliberately lower RPV level; Terminate and Prevent injection into the RPV from ECCS and Feedwater until conditions are met to reestablish injection.

1. Safety Significance:

Precludes loss of primary containment integrity and uncontrolled release of radioactivity into the environment.

Failure to stop RPV injection flow would delay the reduction in core inlet subcooling, thus increasing the potential for flux oscillations.

2. Cues:

Procedural compliance.

3. Measured by:

Observation - With Emergency Depressurization not required and the deliberate lowering level override met (>4% power, and > 110° Suppression Pool temperature, and >16.5" RPV level, and > 1.68# Drywell pressure or SRV open) injection systems are terminated and prevented until <4% power, or 16.5" RPV level, or SRV's closed with <1.68# Drywell pressure.

4. Feedback:

Injection system flow rates into RPV.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 22 of 26 Event

Description:

Critical Task #4 Time Position Applicants Actions or Behavior Maintain or restore and maintain RPV pressure/Suppression Pool temperature below HCL.

1. Safety Significance:

Precludes failure of containment.

2. Cues:

Procedural compliance.

3. Measured by:

Observation - RPV pressure control methods maintain operation below the HCL.

4. Feedback:

RPV pressure trend.

Suppression Pool temperature trend.

SRV open status indications.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 23 of 26 Event

Description:

Critical Task #5 (Contingency)

Time Position Applicants Actions or Behavior During an ATWS, with Emergency Depressurization required, Terminate and Prevent RPV injection from ECCS and Feedwater until reactor pressure is below the MSCP.

1. Safety Significance:

Prevention of fuel damage due to uncontrolled RPV injection.

2. Cues:

Procedural compliance.

3. Measured by:

Observation - No ECCS injection prior to being less than the MSCP.

AND Observation - Feedwater terminated and prevented until less than the MSCP.

4. Feedback:

Reactor power trend, power spikes, reactor short period alarms.

Injection system flow rates into RPV.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 24 of 26 Event

Description:

Critical Task #6 (Contingency)

Time Position Applicants Actions or Behavior When RPV pressure and Suppression Pool temperature cannot be restored and maintained below HCL the US determines that Emergency Depressurization is required and RO initiates Emergency Depressurization, as directed by US.

1. Safety Significance:

Precludes failure of containment.

2. Cues:

Procedural compliance.

3. Measured by:

When RPV pressure control methods cannot restore and maintain operation below the HCL, US determines that Emergency Depressurization is required.

AND Observation - RO opens at least 6 SRV's during performance of Emergency Depressurization actions.

4. Feedback:

RPV pressure trend.

Suppression Pool temperature trend.

SRV open status indications.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 25 of 26 Event

Description:

Critical Task #7 (Contingency)

Time Position Applicants Actions or Behavior With RPV pressure <MSCP, slowly increase and control injection into RPV to restore and maintain RPV level above MSCRWL (-25") as directed by US.

1. Safety Significance:

Maintaining adequate core cooling and preclude possibility of large power excursions.

2. Cues:

Procedural compliance.

RPV pressure indication.

3. Measured by:

Observation - Injection not commenced until less than MSCP, and injection controlled such that power spikes are minimized, level restored and maintained greater than or equal to -25".

4. Feedback:

RPV level trend.

RPV pressure trend.

Injection system flow rate into RPV.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 26 of 26 Procedures to verify clean Procedure Number Check IV Procedure Number Check IV ARI H13-P680-05-D8 Scram Hardcard ARI-H13-P601-18-A4 Feedwater Hardcard ARI-H13-P601-19-C3 Pressure Control Hardcard ARI-H13-P680-03-B9, C2, & E3 Hydrogen Analyzer Startup Hardcard EOP-1 Chart Hydrogen Igniter Startup Hardcard EOP-1A Chart Isolation & Actuations Hardcards EOP-2 Chart Margins and Limits Hardcard EOP-4-2 Chart Feedwater T & P Hardcard EOP-SPI 1.2 ECCS T & P Hardcard EOP-SPI 1.3 SRO oversight flip packs EOP-SPI 2.3 ONI-C11-1 ONI-C51 ONI-C51 Chart ONI-SPI-G4 ORM 6.1.2 SOI-C11(RCIS), Section 7.19 & Book SOI-N27 Section 7.3 SOI-P40/41 Section 7.1 T.S. 3.1.3 T.S. 3.1.5 T.S. 3.1.7

Appendix D Scenario Outline Form ES-D-1 NUREG 1021, Rev. 10 Page 1 of 1 FENOC Facsimile Facility: Perry Scenario No.: 3 - 40%

Op-Test No.: 2017-1 Examiners:

Operators:

(SRO)

(ATC)

(BOP)

Initial Conditions: Soft Plant S/D in progress due to leaking SRV following an earthquake.

ONI-D51 has been exited. RWCU F/D A is in Hold awaiting backwash. ESW A and ECC A running to support RHR run. Stator Water Cooling pump B tagged out for high vibrations. In IOI-3, Step 4.7.30. I&C Tech just completed adjusting APRM gains. eSOMS Narrative Log is down.

Turnover: Planned activities; Place RHR A in SP cooling. NLO is on station to assist with Suppression Pool Cooling. Then, transfer Recirc Pumps to slow speed and continue with plant S/D. Make your Narrative Log entries on your note pads.

Event No.

Malf.

No.

Event Type*

Event Description 1

N-(BOP)

N-(SRO)

Place RHR A in Suppression Pool Cooling TS 3.5.1 2

I-(SRO)

LLS Instrument fails high on 1 channel TS 3.3.6.4 3

C-(BOP)

C-(SRO)

TBCC pump trip 4

C-(BOP)

C-(SRO)

Control Complex Chiller C trip 5

SW06M C-(ATC)

C-(SRO)

RWCU Pump B Gland Seal Temp High 6

R-(ATC)

R-(SRO)

Shift Rx Recirc pumps from Fast to Slow speed 7

M-(Crew)

Multiple SRVs fail open. Enter EOP-2 8

M-(Crew)

Scram Rx on rising Suppression Pool temperature. ATWS and Steam leak in DW with bypass leakage into containment. Re-enter EOP-2 9

C-(ATC)

C-(SRO)

Feed pump turbine fails on scram - Start Motor Feed Pump (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Narrative Summary - Initial Scenario 3 40%

Event

1.

The BOP places RHR A loop in Suppression Pool Cooling.

2.

A Low-Low-Set instrument will fail high (1 channel). The SRO will enter Tech Spec 3.3.6.4.

3.

One of the running TBCC pumps will trip. The SRO enters ONI-P44, Loss of TBCC. The BOP will start an additional TBCC pump.

4.

Nuclear Closed Cooling flow will degrade to RWCU pump B resulting in a high gland seal temperature. The ATC will shutdown the B RWCU pump IAW SOI-G33 and adjust RWCU inlet flow.

5.

Control Complex Chiller C will trip. The BOP will shift Control Complex Chillers to the A Chiller.

6.

The ATC will down-shift Recirc Pumps IAW IOI-3. The SRO will provide reactivity oversight.

7.

Two SRVs fail open. The SRO enters ONI-B21-1, SRV Inadvertent Opening/Stuck Open and EOP-2, Primary Containment Control. The SRO will direct scramming the Rx prior to reaching 110°F in the Suppression Pool.

8.

The Rx scram will result in an ATWS<4% and a steam leak in the Drywell with bypass leakage into Containment. The SRO will enter ONI-C71-1, Rx Scram and re-enter EOP-2 on high DW temperature. Control rods will need to be manually inserted in order to depressurize the Rx and stop the steam leak.

9.

Feedwater is lost on the scram. Motor Feed Pump must be manually initiated in order to recover RPV level.

EOPs:

EOP-2 EOP-1 EOP-1A ABNORMALs:

ARI for RWCU ARI for CC Chiller C ONI-P44 ONI-B21-1 Critical tasks:

1. Scram Prior to exceeding 110°F in Suppression Pool

2. Insert Control Rods

3. Terminated and Prevent ECCS injection

Appendix D, Rev. 10 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 1 of 26 Event

Description:

N/A - Driver Instructions Cue:

Time Position Applicants Actions or Behavior Driver Driver Simulator Setup:

Reset Simulator to IC 133.

Load Schedule File: NRC2017-S3.sch.

Verify Schedule File: NRC2017-S3-1.sch & NRC2017-S3-2.sch loads.

Verify Event File: NRC2017-S3.evt loads.

Load patch file RD15 1% power.dat from PSIMA Initiate Event 30 to adjust APRM gains. (It takes several minutes for APRM's to stabilize).

Adjust white o-rings and Remove Requal IOI-3 and Rod Book from horseshoe.

Reset NUMACS and acknowledge alarms on Yokagawas (P632/P642 & P614)

Verify Control Complex Chiller loop sign is marked up to A loop.

Driver Driver Verify Initial Conditions:

Reactor Power ~38%. Pull Sheets, Rods @ Step 61 @ 12.

IOI-3 Step 4.7.30 is complete through d.

ESW A and ECC A running to support RHR run.

Place yellow switch cap on Stator Water Cooling Pump B.

APRM gains B & C @ +4% - rest at +1.5%

Green Risk traffic light.

Driver Driver Initial Conditions:

Soft Plant S/D in progress due to leaking SRV following an earthquake. ONI-D51 has been exited. RWCU F/D A is in Hold awaiting backwash. ESW A and ECC A running to support RHR run. Stator Water Cooling pump B tagged out for high vibrations In IOI-3, Step 4.7.30. I&C Tech just completed adjusting APRM gains.

eSOMS is down.

Turnover: Planned activities; Place RHR A in Suppression Pool Cooling. NLO is on station to assist with Suppression Pool Cooling. Then, transfer Recirc Pumps to slow speed and continue with plant shutdown. Make Plant Narrative Log entries on your note pads.

Driver Driver In Insight: THK_VLV(873)=TRUE THRVASNW=0.25 Monitor cell 854 temperature

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 2 of 26 Event

Description:

1 - Place RHR A in Suppression Pool Cooling Cue: From Turnover Time Position Applicants Actions or Behavior SRO Direct BOP to start RHR A Loop in Suppression Pool Cooling.

Give temperature band or direct not to lower SP temperature to less than 60°F.

SRO Evaluate Tech Specs - for RHR A in secondary mode of operation T.S. 3.5.1 Action A.1 - Restore low pressure ECCS injection/spray subsystem to OPERABLE status

- 7 days.

BOP Should discuss/identify expected alarm prior to starting pump.

BOP Perform SOI-E12 Section 4.6 to startup RHR A in SP Cooling 4.6.2 NOTIFY Radiation Protection of the following:

• A Suppression Pool evolution will be conducted which may affect suppression pool water level and/or activity.

• Surveys should be performed for Containment 599 elevation to evaluate the radiological impact of the evolution.

4.6.3 IF operation is NOT exempted, THEN REFER TO SOI-P45/49 and VERIFY the associated Emergency Service Water System Loop is in operation.

Loop A 4.6.4 REFER TO SOI-P42 and VERIFY the associated Emergency Closed Cooling System Loop is in operation.

Loop A 4.6.5 IF the RHR Loop will be placed in the Suppression Pool Cooling/Test mode prior to shutting down to standby Readiness, THEN PERFORM the following:

4.6.5.a RECORD the appropriate Plant Narrative Log entry.

4.6.5.b HOLD the RHR HXS OUTLET VALVE in CLOSE, UNTIL closed.

1E12-F003A 4.6.5.c VERIFY the RHR HXS BYPASS VALVE is open.

1E12-F048A 4.6.5.d THROTTLE the RHR HXS BYPASS VALVE CLOSED for 48 to 52 seconds.

1E12-F048A 4.6.6 TAKE the RHR PUMP to START.

1E12-C002A 4.6.9 GO TO Suppression Pool Cooling/Test Mode Operations for RHR A(B).

7.2 Suppression Pool Cooling/Test Mode Operations for RHR A(B) 7.2.2 OBSERVE the following limitations when in Suppression Pool Cooling:

• MAINTAIN Suppression Pool temperature above 60°F.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 3 of 26 Event

Description:

1 - Place RHR A in Suppression Pool Cooling Cue: From Turnover Time Position Applicants Actions or Behavior

• MAINTAIN RHR Pump flow at 7100-7300 gpm during steady state conditions.

• MAINTAIN RHR Pump flow at 6000-7300 gpm during system adjustments (unless stated otherwise).

7.2.3 IF the Oncoming RHR TEST VALVE TO SUPR POOL is closed, THEN PERFORM the following:

1E12-F024A 7.2.3.a TAKE the Oncoming RHR TEST VALVE TO SUPR POOL to OPEN.

1E12-F024A 7.2.3.b WHEN time permits, THEN RECORD the opening of RHR TEST VALVE TO SUPR POOL in the Plant Narrative Log.

7.2.3.c WHEN the RHR PUMP FLOW is greater than1650 gpm, THEN VERIFY the RHR PUMP MIN FLOW VALVE closes.

1E12-F064A 7.2.5 IF desired to operate in the Suppression Pool Cooling Mode, THEN PERFORM the following:

7.2.5.a REFER TO SOI-P45/49 and VERIFY the associated Emergency Service Water System Loop is in operation.

7.2.5.b PERFORM the following as need, to maintain Suppression Pool temperature maintained between 60°F and 95°F:

• THROTTLE the RHR HXS OUTLET VALVE.

1E12-F003A

• THROTTLE the RHR HXS BYPASS VALVE.

1E12-F048A BOP Periodically monitor operation of RHR A and Suppression Pool temperature.

Evaluator Cooldown can be established with E12-F003A open ~3040%.

Candidate can observe Suppression Pool cooldown more quickly on Suppression Pool Temperature Validation ICS screen

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 4 of 26 Event

Description:

2 - LLS Instrument fails high on 1 channel Cue: ARI-H13-P601-19-C7 & White light above LLS Reset pushbutton Time Position Applicants Actions or Behavior Driver Place picture of 1B21-N616E on H13-P629 prior to initiating Event 2 Driver When directed initiate Event 2. Role play as needed ATC Announce unexpected SRV LOGIC RX PRESSURE HIGH alarm and give stability report.

BOP Walkdown back-panels and determine and announce that 1B21-N616E has TRIP and GROSS FAIL LEDs on with all other RPV Pressure trip units reading normally.

SRO Direct BOP to perform Subsequent Operator Actions of ARI H13-P601-19-C7 BOP Perform applicable Subsequent Operator Actions of ARI H13-P601-19-C7 4.2 If the alarm is not due to a valid pressure condition, then contact I&C.

Driver If contacted as I&C, report that you will write a Notification.

SRO Evaluate Tech Specs T.S. 3.3.6.4 Action A.1 - Restore trip system to OPERABLE status - 7 days Or A.2 - Declare associated relief and LLS valve(s) INOPERABLE - 7 days Evaluator T.S. 3.3.6.4 Action A.2 will require entry into T.S. 3.6.1.6.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 5 of 26 Event

Description:

3 - TBCC pump trip Cue: ARI-H13-P870-01-B6 Time Position Applicants Actions or Behavior Driver When directed initiate Event 3. Role play as needed Driver When directed to throttle 1P44-F513C, wait one minute then report as complete.

Driver When directed to open 1P44-F513C, initiate Event 13, wait one minute, then report complete ATC Announce unexpected panel P870 alarm or BUS F-1-F BREAKER TRIP alarm and give stability report.

BOP Review ARI and determine TBCC B pump has tripped.

Report ONI-P44 entry condition.

Driver If NLO is dispatched to investigate, report breaker F1F07 has overcurrent trip indicated.

Driver If directed to reset Bell alarm, delete malfunction cp02_1p44c0001b and report.

SRO Announce entry into ONI-P44, Loss Of Turbine Closed Cooling.

Direct BOP to perform ONI-P44 Supplemental Actions BOP Reviews Supplemental Actions and determines starting additional TBCC pump is required.

4.2 IF a TBCC Pump has tripped, THEN PERFORM one of the following:

4.2.1 IF a TBCC pump is running, THEN REFER TO SOI-P44 and PERFORM Additional Pump Startup.

BOP Starts additional TBCC pump per SOI-P44 Section 4.2.

4.2.1 VERIFY the oncoming TBCC Pump Discharge Valve is throttled to 20%

open.

1P44-F513C 4.2.2 TAKE the oncoming TBCC PUMP control switch to START.

1P44-C001C 4.2.3 WHEN the pump discharge pressure has stabilized, SLOWLY OPEN the oncoming TBCC Pump Discharge Valve.

1P44-F513C 4.2.4 VERIFY the TBCC Pump Discharge Valve for the other currently running pump is open.

1P44-F513A BOP Report completion of TBCC pump start.

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Description:

4 - Control Complex Chiller C trip Cue: ARI-H13-P600-08-A3 and ARI-H13-P904-02-A7 Time Position Applicants Actions or Behavior Driver When directed initiate Event 4. Role play as needed ATC Announce unexpected panel P904 alarm and give stability report.

BOP Evaluate P904 and review ARI and determine Control Complex Chiller C chill water pump and chiller have tripped.

Direct NLO to investigate cause of Complex Chiller C trip.

Driver If directed to investigate EF2B05 (breaker for Chill Water Pump C), after 4 minutes, report the breaker indicates trip on over current.

Driver If directed to investigate Chiller C trip locally, report annunciator EVAPORATOR LOW WATER FLOW C. W. PUMP is in alarm.

Driver If directed to walkdown Chiller A for start, report ready for start.

Driver If directed to perform Local stop and start of chillers, report that Maintenance has the area immediately around P47A control panel blocked off for work in the overhead. Estimate will be able to get to in in 20 minutes.

SRO Direct BOP to shift to Control Complex Chiller A BOP Review SOI-P47 and shifts Control Complex Chillers per SOI-P47 7.5 Shifting from the Operating to the Standby Chiller Within a Chilled Water Loop 7.5.1 IF SHIFTING from CCCW Chiller C to the CCCW Chiller of the inservice CCCW Loop, THEN PERFORM the following:

Loop A 7.5.1.a REFER TO Manual Shutdown of CCCW Chiller and Chilled Water Pump and SHUTDOWN C CCCW Chiller and Chilled Water Pump. P47-B001C P47-C001C 6.2 Remote Manual Shutdown of CCCW Chiller and Chilled Water Pump 6.2.1 IF the offgoing CCCW Chiller is running, THEN TAKE the offgoing CCCW CHILLER to STOP.

P47-B001C 6.2.3 TAKE the offgoing CCCW CHILLED WATER PUMP to STOP at H13-P904.

P47-C001C

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Description:

4 - Control Complex Chiller C trip Cue: ARI-H13-P600-08-A3 and ARI-H13-P904-02-A7 Time Position Applicants Actions or Behavior 7.5.1.b REFER TO Manual Startup of CCCW Chiller and Chilled Water Pump and STARTUP the oncoming CCCW Chiller and Chilled Water Pump.

P47-B001A P47-C001A 4.3 Remote Manual Startup of CCCW Chiller and Chilled Water Pump 4.3.1 IF the selected Chilled Water Pump is already in operation, THEN GO TO Step 4.3.6.

4.3.2 IF starting CCCW Chiller A or B and Chilled Water Pump A or B, THEN CONFIRM the CCCW Chiller and Chilled Water Pump are in Standby Readiness.

P47-C001A 4.3.4 TAKE the oncoming CCCW CHILLED WATER PUMP to START.

P47-C001A 4.3.6 IF starting CCCW Chiller A or B, THEN CONFIRM the applicable ECC (P42) loop is in operation.

ECC A 4.3.8 TAKE the oncoming CCCW CHILLER to START at H13-P904.

P47-B001A 4.3.9 IF Chiller Outlet Flow is NOT between 1400 and 1600 gpm, THEN ADJUST Chiller Outlet Flow as follows:

Driver When asked about chiller outlet flow, it is 1550 gpm.

If asked, guide vanes are operating properly.

BOP Direct NLO to perform Step 4.3.10 4.3.10 CONFIRM proper operation of the load-step (cycle) timer by one of the following:

Observe the guide vanes opening.

Chilled water temperature is being maintained 42 - 48°F.

Driver Report operation of the load-step timer.

BOP Report P47 Chiller and Chill Water Pump have been shifted.

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Description:

5 - RWCU Pump B Gland Seal Temp High Cue: ARI-H13-P680-01-A5 Time Position Applicants Actions or Behavior Driver When directed initiate Event 5. Role play as needed Evaluator Second alarm (Gland Seal Temp High) takes ~3 minutes to come in.

ATC Announce unexpected RWCU PUMP B NCC FLOW LO alarm and give stability report.

ATC Review ARI Subsequent Operator Actions and recommend shutting down RWCU Pump B ATC Announce unexpected RWCU PUMP B GLAND SEAL TEMP HIGH alarm and give stability report.

ATC Review ARI Subsequent Operator Actions and recommend shutting down RWCU Pump B Driver If directed to monitor RWCU pump temperatures locally, report RWCU B pump seal temperature is 255°F and rising. RWCU A pump temp is 170°F and stable.

If directed to monitor for damage, report unable to determine with camera.

Driver If asked about water in RWCU or RCIC rooms, respond no water is visible.

SRO Direct ATC to shutdown RWCU Pump B.

ATC Shutdown B RWCU pump and throttle closed 1G33-F044 to obtain 140-240 gpm inlet flow IAW SOI-G33.

6.3 Shutdown of a RWCU Pump When Both Pumps are in Operation 6.3.1 IF RWCU Pump B is to be shutdown, THEN DIRECT Chemistry to shutdown the MMS skid.

6.3.2 VERIFY one or less F/D in service.

6.3.3 TAKE the offgoing RWCU PUMP to STOP.

1G33-C001B 6.3.4 THROTTLE the RWCU FILTER/DEMIN BYPASS VALVE to maintain RWCU INLET FLOW in accordance with Normal Operations/Data.

1G33-F044 Driver As Shift Manager, inform US that the OCC will isolate B RWCU pump.

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Description:

5 - RWCU Pump B Gland Seal Temp High Cue: ARI-H13-P680-01-A5 Time Position Applicants Actions or Behavior ATC Direct NLO to isolate RWCU pump B.

6.3.6 IF the idle RWCU Pump will remain shutdown for more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, THEN ISOLATE the idle RWCU Pump as follows:

• CLOSE the idle RWCU Pump Disch Man Isolation Vlv 1G33-F013B

• CLOSE the idle RWCU Pump Suction Shutoff Valve 1G33-F005B 6.3.7 MONITOR Nuclear Heat Balance.

6.3.8 IF the Nuclear Heat Balance becomes invalid due to removal of RWCU from service, THEN REFER TO Nuclear Heat Balance Recovery Operations and PERFORM the actions.

Evaluator SOI-G33 Section 6.3, Step 6.3.5 is N/A.

Driver If the crew delays downshifting Recirc Pumps, as Shift Manager, direct US to continue with Recirc Pump downshift.

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Description:

6 - Shift Rx Recirc pumps from Fast to Slow speed Cue: ARI-H13-P601-17-F5 and ARI-H13-P601-20-F3 Time Position Applicants Actions or Behavior SRO Direct ATC to shift Recirc Pumps from Fast to Slow speed.

ATC Shifts Recirc Pumps from Fast to Slow IAW SOI-B33 7.6 Transferring Rcirc Pumps from Fast to Slow Speed 7.6.1 IF WHILE EXECUTING this section, a FCV runback occurs, THEN REFER TO Section 7.22, Resetting RCIRC Flow Control Cavitation Runback and PERFORM the actions.

7.6.2 IF time permits, THEN PERFORM the following:

7.6.2.a TAKE the LFMG A SUPPLY BRKR to CLOSE. BRKR 1A 7.6.2.b CONFIRM LFMG A supply voltage is 1190 - 1310 vac. (Check one or both indications)

Computer Point (on SPDS screen RPMPR)

B33EA093 LFMG Panel Voltmeter B33-Q5002A 7.6.2.c TAKE the LFMG B SUPPLY BRKR to CLOSE. BRKR 1B 7.6.2.d CONFIRM LFMG B supply voltage is 1190 - 1310 vac. (Check one or both indications)

Computer Point (on SPDS screen RPMPR)

B33EA094 LFMG Panel Voltmeter B33-Q5002B 7.6.3 SIMULTANEOUSLY PERFORM the following:

TAKE the RCIRC PUMP A BRKR 5 to XFER.

BRKR 5A TAKE the RCIRC PUMP B BRKR 5 to XFER.

BRKR 5B 7.6.4 VERIFY the RCIRC PUMP A BRKR opens.

BRKR 5A 7.6.5 VERIFY the RCIRC PUMP B BRKR opens.

BRKR 5B NOTE Both Rcirc Pumps must be transferred to slow speed.

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Description:

6 - Shift Rx Recirc pumps from Fast to Slow speed Cue: ARI-H13-P601-17-F5 and ARI-H13-P601-20-F3 Time Position Applicants Actions or Behavior 7.6.7 WHEN RCIRC PUMP SPEED indicates approximately 450 rpm, THEN VERIFY the following breakers close:

1B33-R651A LFMG OUTPUT BRKR BRKR 2A LFMG OUTPUT BRKR BRKR 2B 7.6.8 NOTIFY B33 RSE that the LFMG is running and to conduct trending as desired.

Evaluator FCV Cavitation Runback Signals may or may not be generated when pumps are shifted ATC Perform SOI-B33 Section 7.22 to reset RCIRC Flow Control Cavitation Runback if runback signal is received.

7.22.1 RESET the RCIRC Flow Control A as follows:

7.22.1.a ADJUST the RCIRC Flow Control to obtain 0% LIMITER ERROR on RCIRC LOOP FLOW CONTROL.

1B33-K603A 7.22.1.b ADJUST the RCIRC FLUX CONTROL, slide switch on P680 to obtain 0% M/A ERROR on RCIRC LOOP FLOW CONTROL.

1B33-K602 1B33-K603A 7.22.1.c TAKE the CAVITATION/FCV LIMIT RCIRC RESET to the A position.

1B33A-S111 7.22.2 RESET the RCIRC Flow Control B as follows:

7.22.2.a ADJUST the RCIRC Flow Control to obtain 0% LIMITER ERROR on RCIRC LOOP FLOW CONTROL.

1B33-K603B 7.22.2.b ADJUST the RCIRC FLUX CONTROL, slide switch on P680 to obtain 0% M/A ERROR on RCIRC LOOP FLOW CONTROL.

1B33-K602 1B33-K603B 7.22.2.c TAKE the CAVITATION/FCV LIMIT RCIRC RESET to the B position.

1B33A-S111 SRO Direct ATC to open Flow Control Valves per IOI-3.

ATC Open Flow Control Valves fully.

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Description:

7 - Multiple SRVs fail open. Enter ONI-B21-1 & EOP-2 Cue: ARI-H13-P601-17-F5 and ARI-H13-P601-20-F3 Time Position Applicants Actions or Behavior Driver When directed initiate Event 7. Role play as needed ATC Announce unexpected alarms and give stability report.

ATC/BOP Announce multiple SRVs open - ONI-B21-1 entry condition.

Observe RPV power and RPV level for changes - ONI-C51 Entry Condition SRO Enters ONI-B21-1, SRV Inadvertent Opening/Stuck Open and ONI-C51 UNPLANNED CHANGE IN REACTOR POWER OR REACTIVITY Evaluator Crew may not have time to perform any actions of ONI-C51 prior to scram.

ATC/BOP Perform Immediate Actions of ONI-B21-1 3.1 PRIOR TO any of the following:

• Suppression Pool Average Temperature reaching 110°F.

• RPV Pressure reaching 1065 psig.

SCRAM the Reactor.

3.3 EVACUATE the Containment.

3.5 WHEN reactor power is 96%, THEN PERFORM the following:

3.5.1 VERIFY that Reactor pressure is less than 1033 psig.

3.5.2 ATTEMPT to close the SRV by placing both of the associated SRV control switches from AUTO to OFF at the following panels:

• ECCS Benchboard 1H13-P601.

• ADS Relay Panel Division 2 1H13-P631.

SRO Perform Supplemental Actions of ONI-B21-1.

4.5 EVALUATE entry into Primary Containment Control, EOP-02.

SRO Enter EOP-2 when Suppression Pool Temperature exceeds 95°F.

SRO Direct BOP to perform Supplemental Actions of ONI-B21-1.

SRO Direct EOP-2 Actions Drywell Temperature control leg

• Monitor and control Suppression Pool Temperature below 95°F using available Suppression Pool cooling

• Maximize Suppression Pool cooling

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Description:

7 - Multiple SRVs fail open. Enter ONI-B21-1 & EOP-2 Cue: ARI-H13-P601-17-F5 and ARI-H13-P601-20-F3 Time Position Applicants Actions or Behavior o RHR A o RHR B Before Suppression Pool Temperature reaches 110°F Enter EOP-1 BOP Perform Supplemental Actions of ONI-B21-1 to close SRVs.

4.2 IF the SRV remains open, THEN CYCLE the associated SRV control switch at 1H13-P601 in the following sequence:

4.2.1 PLACE control switch in AUTO.

4.2.2 PLACE control switch in OPEN.

4.2.3 PLACE control switch in AUTO.

4.2.4 PLACE control switch in OFF.

Evaluator Actions to close SRVs will be unsuccessful.

SRO Direct ATC to scram reactor prior to exceeding 110°F in Suppression Pool.

(CRITICAL TASK 1)

ATC Scram reactor as directed prior to exceeding 110°F in Suppression Pool.

(CRITICAL TASK 1)

Evaluator Next event will be automatically initiated after scramming the Rx.

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Description:

8 - Scram Rx on rising Suppression Pool temperature. ATWS and Steam leak in DW with bypass leakage into containment. Re-enter EOP-2 Enter ONI-C71 Cue: ARI-H13-P601-17-F5 and ARI-H13-P601-20-F3 Time Position Applicants Actions or Behavior Crew Announce unexpected DRYWELL AVERAGE TEMP A(B) HIGH alarm.

Report rise in Drywell temperature and pressure (values and trends).

SRO When Drywell temperature exceeds 145°F, announce entry into EOP-2, Primary Containment Control.

SRO Direct EOP-02 actions Drywell Temperature control leg

• Monitor and control Drywell Temperature below 145°F using available Drywell cooling

• Maximize Drywell cooling o Operate all available Drywell cooling o Direct Bypass of NCC Isolation, EOP-SPI 2.1

• Before Drywell Temperature reaches 330°F Enter EOP-1

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Description:

8 - Scram Rx on rising Suppression Pool temperature. ATWS and Steam leak in DW with bypass leakage into containment. Re-enter EOP-2 Enter ONI-C71 Cue: Margins and Limits Hardcard Time Position Applicants Actions or Behavior ATC Place Mode Switch in SHUTDOWN as directed.

Evaluator Mode Switch and RPS Pushbuttons will fail. ARI will insert some rods. Rx power after ATWS will be < 4%.

ATC Performs Scram Hardcard actions (OAI-1703 att. 10)

1.

VERIFY the following actions completed:

• Mode Switch Locked in Shutdown

• RPS Initiated (if all control rods are not fully inserted)

• ARI Initiated (if RPS failed to Scram the reactor)

2.

IF Reactor Recirc Pumps are running in fast speed, THEN SIMULTANEOUSLY TAKE RCIRC PUMP BRKRs 5A and 5B to XFER.

3.

IF Reactor power is above 4%: THEN PERFORM THE FOLLOWING:

• INHIBIT ADS (with US concurrence)

• INITIATE SLC

4.

STABILIZE Reactor level using Feedwater / RCIC / HPCS

5.

STABILIZE Reactor pressure using Turbine / Turbine Bypass valves /

SRVs

6.

PERFORM crew update.

ATC Updates crew on scram status and EOP 1 Entry conditions and identifies Time Critical Operator Action to establish Suppression Pool Cooling.

SRO Announce entry into EOP-1, RPV Control Announce transition to EOP-1A, level Power since Rx is NOT shutdown.

SRO Direct ATC to Monitor and Control Rx Power, Stabilize Rx water level using the Feedwater Hardcard and Stabilize Rx pressure using Pressure Control Hardcard ATC Continue Scram Hardcard actions.

7.

RECORD the TIME: _____________

8.

STABLIZE reactor water level:

a) Feedwater REFER TO the FEEDWATER HARDCARD b) RCIC c) HPCS

9.

STABLIZE reactor pressure:

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Description:

8 - Scram Rx on rising Suppression Pool temperature. ATWS and Steam leak in DW with bypass leakage into containment. Re-enter EOP-2 Enter ONI-C71 Cue: Margins and Limits Hardcard Time Position Applicants Actions or Behavior a) Turbine / Turbine Bypass valves:

• REFER TO the PRESSURE CONTROL HARDCARD b) SRVs:

• EVACUATE Containment

• REFER TO the PRESSURE CONTROL HARDCARD

• EVALUATE placing RCIC in pressure CONTROL MODE

10.

INSERT Nuclear Instruments:

• SRMs

• IRMs

• PLACE recorders in IRM (Leave A or E in APRM for digital display)

11.

IF the generator was synchronized at the time of the reactor scram, THEN WHEN generator load is reduced to less than 90 MWe,TRIP the main turbine by depressing the TURBINE TRIP push-button.

VERIFY the following have occurred:

• Main Stop Valves are shut (Four Valves)

• Turbine Control Valves are shut (Four Valves)

• Turbine Combined Intermediate Valves are shut (Six Valves)

• GEN BRKR S-610-PY-TIE is open

• GEN BRKR is S-611-PY-TIE is open

• GEN FIELD BREAKER is open

12.

VERIFY HST LVL CV MANUAL CONTROL, N21-S19, IN OFF.

Evaluator Initiating SLC in the Reactor Power Control leg will become Critical if Suppression Pool temperature reaches 110°F SRO Direct EOP-01A actions Reactor Power Control leg

• Monitor and Control Rx Power

• Insert Control Rods EOP-SPI 1.1-1.7 (Critical Task 2)

• Initiate SLC (Critical Task 2)

Reactor Level Control leg Stabilize Rx water level

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Description:

8 - Scram Rx on rising Suppression Pool temperature. ATWS and Steam leak in DW with bypass leakage into containment. Re-enter EOP-2 Enter ONI-C71 Cue: Margins and Limits Hardcard Time Position Applicants Actions or Behavior Verify Isolations and Actuations Inhibit ADS Maintain MSIVs open and override ECCS interlocks EOP-SPI 2.3 Terminate and Prevent (T&P) ECCS Injection Direct a level band 178 to 219 Start Hydrogen Igniters and Analyzers Reactor Pressure Control Leg Stabilize Reactor Pressure Direct pressure band of 800 to 1000 psig BOP Verify Isolations and Actuations hardcards BOP/ATC Insert control rods using EOP-SPI 1.1-1.7 (Critical Task 2)

EOP-SPI 1.2 3.0 VERIFY the following RPS jumpers are INSTALLED:

Panel From To H13-P694 6X1 33T H13-P691 X1 03T H13-P692 2X1 13T H13-P693 4X1 23T 4.0 REMOVE following fuses to de energize ARI solenoid valves:

Panel Bay Fuse Block (Clip)

Wire C22-P001 B

F268 (F6A)

C22A032N1 C22-P002 B

F268 (F6B)

C22A048N1 5.0 AT H13-P680, DEPRESS the following pushbuttons to reset the scram:

SCRAM RESET CH A C71A-S5A SCRAM RESET CH C C71A-S5C SCRAM RESET CH B C71A-S5B SCRAM RESET CH D C71A-S5D

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Description:

8 - Scram Rx on rising Suppression Pool temperature. ATWS and Steam leak in DW with bypass leakage into containment. Re-enter EOP-2 Enter ONI-C71 Cue: Margins and Limits Hardcard Time Position Applicants Actions or Behavior 7.0 AT H13-P877 (Division 1 Section), VERIFY BUS XH11 LOCA BYPASS keylock switch is in BYPASS.

8.0 AT H13-P877 (Division 2 Section), VERIFY BUS XH12 LOCA BYPASS keylock switch is in BYPASS.

10.0 MOMENTARILY DEPRESS the RESET DRIFT pushbutton in the SYSTEM MODE section.

11.0 WHEN Scram Discharge Volume drains as indicated by cleared RPS INST VOL LEVEL HI annunciator (H13-P680-5A-A7), THEN PROCEED with the remainder of this instruction.

12.0 A CRD Pump is running NO CRD Pump is running CRD flow is less than 100 gpm as indicated on C11-R606, CRD FLOW-TOTAL SYSTEM THEN PROCEED with the remainder of this instruction.

13.0 WHEN scram signals are inserted, THEN MONITOR control rod positions for inward rod motion.

14.0 ARM AND DEPRESS the following pushbuttons to insert a scram signal:

RPS MANUAL SCRAM CH A C71A-S3A RPS MANUAL SCRAM CH C C71A-S3C RPS MANUAL SCRAM CH B C71A-S3B RPS MANUAL SCRAM CH D C71A-S3D ATC Maintains RPV water level with Feedwater and RPV pressure using Pressure Control Hardcard.

BOP/ATC When directed Terminate and Prevent ECCS Injection - hardcard (Critical Task 3)

ECCS TERMINATE AND PREVENT HARDCARD 1 PERFORM the following actions for ECCS systems that are in Standby or Operating conditions.

2. TERMINATE AND PREVENT HPCS as follows: (@ P601-16)

A. HOLD the HPCS INJECTION VALVE in CLOSED. 1E22-F004 B. IF HPCS initiation signal is NOT present, THEN ARM AND DEPRESS HPCS MANUAL INITIATION pushbutton to obtain white HPCS SEAL IN RESET light.

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Description:

8 - Scram Rx on rising Suppression Pool temperature. ATWS and Steam leak in DW with bypass leakage into containment. Re-enter EOP-2 Enter ONI-C71 Cue: Margins and Limits Hardcard Time Position Applicants Actions or Behavior C. PERFORM one of the following,

1) VERIFY HPCS INJECTION VALVE is CLOSED. 1E22-F004

2) TAKE the HPCS PUMP to STOP. 1E22-C001

4. PERFORM Step 5 and Step 6 in any logical order.

5. TERMINATE AND PREVENT Division 1 as follows: (@ P601-15 & 17)

A. HOLD the following switches in CLOSE:

LPCS INJECTION VLV. 1E21-F005 LPCI A INJECTION VALVE. 1E12-F042A B. IF LPCS and LPCI A initiation signal is NOT present, THEN ARM AND DEPRESS LPCS & LPCI A MANUAL INITIATION pushbutton to obtain the white LPCS & LPCI A SEAL IN RESET light.

C. PERFORM one of the following,

1) VERIFY LPCS INJECTION VALVE is CLOSED. 1E21-F005

2) TAKE LPCS PUMP to STOP. 1E21-C001 D. PERFORM one of the following,

1) VERIFY the following valves are CLOSED:

• LPCI A INJECTION VALVE. 1E12-F042A

• SHUTDOWN COOLING A TO FDW SHUTOFF valve. 1E12-F053A

• RHR A HEAD SPRAY ISOL valve. 1E12-F023

2) TAKE RHR A PUMP to STOP. 1E12-C002A

6. TERMINATE AND PREVENT Division 2 as follows: (@ P601-14)

A. HOLD the following switches in CLOSE:

• LPCI B INJECTION VALVE. 1E12-F042B

• LPCI C INJECTION VALVE. 1E12-F042C B. IF LPCI B and LPCI C initiation signal is NOT present, THEN ARM AND DEPRESS LPCI B & C MANUAL INITIATION pushbutton to obtain the white LPCI B & C SEAL IN RESET light.

C. PERFORM one of the following,

1) VERIFY RHR C INJECTION VALVE is CLOSED. 1E12-F042C

2) TAKE RHR C PUMP to STOP. 1E12-C002C D. PERFORM one of the following,

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

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Page 20 of 26 Event

Description:

8 - Scram Rx on rising Suppression Pool temperature. ATWS and Steam leak in DW with bypass leakage into containment. Re-enter EOP-2 Enter ONI-C71 Cue: Margins and Limits Hardcard Time Position Applicants Actions or Behavior

1) VERIFY the following valves are CLOSED:

• LPCI B INJECTION VALVE. 1E12-F042B

• SHUTDOWN COOLING B TO FDW

• SHUTOFF valve. 1E12-F053B

2)

TAKE the RHR B PUMP to STOP. 1E12-C002B BOP Start Hydrogen Igniters and Analyzers per hardcard ATC/BOP Report to SRO when APRMs are downscale.

ATC Maintain directed Rx Level Band ATC/BOP Maintain directed Rx Pressure Band.

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Description:

9 - Feed pump turbine fails on scram Cue:

Time Position Applicants Actions or Behavior Evaluator RFPT A shaft breaks on Rx scram and RPV water level starts to lower.

ATC Starts motor feed pump and control RPV level 178 to 219 inches Scram Hardcard

8.

STABLIZE reactor water level:

a) Feedwater REFER TO the FEEDWATER HARDCARD OAI-1703 - Feedwater Hardcard As necessary to control RPV level

• If desired, then verify MFP auto xfer disabled

• If desired, then start the MFP.

• Control RPV level using RFPT/MFP FCV MAN/AUTO STATIONS

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Description:

Scenario Termination Criteria Time Position Applicants Actions or Behavior

1. All control rods are inserted to 00.

2. Control RPV level between 178 and 219.

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Description:

Critical Task #1 Time Position Applicants Actions or Behavior Prior to exceeding 110°F in the Suppression Pool, crew places REACTOR MODE SWITCH in SHUTDOWN.

1.

Safety Significance:

Prevent a violation of the facility license condition (T.S. 3.6.2.1).

2.

Cues:

Procedural compliance.

Suppression Pool temperature trend.

3.

Measured by:

With rising Suppression Pool Temperatures, the REACTOR MODE SWITCH is placed in SHUTDOWN prior to exceeding 110°F in the Suppression Pool.

4.

Feedback:

Reactor Power trend.

Control Rod indication.

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Description:

Critical Task #2 Time Position Applicants Actions or Behavior With reactor scram required and the reactor not shutdown, initiate action to reduce power by inserting control rods and/or injecting Boron with SLC prior to Suppression Pool Temperature exceeding 110°F.

1.

Safety Significance:

Shutting down reactor can preclude failure of Containment or equipment necessary for the safe shutdown of the plant.

2.

Cues:

Procedural compliance.

3.

Measured by:

Control rod insertion commenced in accordance with Section 1.0 of EOP-SPI's.

4.

Feedback:

Reactor Power trend.

Control Rod indication.

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Page 25 of 26 Event

Description:

Critical Task #3 Time Position Applicants Actions or Behavior During an ATWS, to control RPV level; Terminate and Prevent injection into the RPV from ECCS until conditions are met to reestablish injection.

1. Safety Significance:

Precludes injection inside the shroud during an ATWS.

Failure to stop RPV injection flow inside shroud could large power excursions.

2. Cues:

Procedural compliance.

3. Measured by:

Observation - When operating in EOP-1A, Reactor Power Control, and US determines Termination/Prevention of ECCS is required (indicated by verbal direction or EOP placekeeping action)

AND RO places ECCS injection valves in close or stops the ECCS pumps.

4. Feedback:

Injection system flow rates into RPV.

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op-Test No.:

2017-01 Scenario No.: 3 - 40%

Page 26 of 26 Procedures to verify clean Procedure Number Check IV Procedure Number Check IV ARI H13-P601-19-C7 Scram Hardcard ARI-H13-P601-17-F5 Feedwater Hardcard ARI-H13-P601-20-F3 Pressure Control Hardcard ARI-H13-P680-01-A5 Hydrogen Analyzer Startup Hardcard ARI-H13-P680-08-A3 Hydrogen Igniter Startup Hardcard ARI-H13-P870-01-B6 Isolation & Actuations Hardcards ARI-H13-P904-02-A7 Margins and Limits Hardcard EOP-1 Chart Feedwater T & P Hardcard EOP-1A Chart ECCS T & P Hardcard EOP-2 Chart SRO oversight flip packs EOP-SPI 1.2 EOP-SPI 1.3 EOP-SPI 2.1 ONI-B21-1 ONI-C71-1 ONI-P44 SOI-B33 Section 7.6 & 7.22 SOI-E12 Section 4.6 SOI-G33 Section 6.3 SOI-P44 Section 4.2 SOI-P47 Sects 7.5, 6.2, & 4.3 T.S. 3.3.6.4 T.S. 3.5.1 T.S. 3.6.1.6