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2017 Dresden Initial License Exam Simulator Scenarios
	ML17271A106
Person / Time
Site:	Dresden
Issue date:	08/21/2017
From:	Walton R; NRC/RGN-III/DRS/OLB
To:	; Exelon Generation Co
	Walton R
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ML17068A432	List: ML17271A091; ML17271A094; ML17271A103; ML17271A106; ML17271A111;
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Dresden Generating Station 2017-301 ILT-N-1 Place IC in Standby Lineup Raise power with rods to open bypass valves CRD Pump trip (Overcurrent)

EDG CWP failure - EDG INOP IRM Fails upscale with partial 1/2 scram Swap SAC due to oil leak 2nd CRD pump trip with accumulator trouble alarm Hydraulic ATWS - ARI unsuccessful EXAM MATERIAL Rev. 00 05/17 Developed By:

Exam Author Date Approved By:

Facility Representative Date

Station: Dresden Generating Station Scenario No.: 2017-301 ILT-N-1 Class ID: 2017-301 Evaluators Operators / crew position

/ ATC

/ BOP

/ CRS Initial Conditions: Unit 2 is in Mode 2. DGP 01-01 is in progress.

Turnover: Place Isolation Condenser in a Standby Lineup in preparation for RPV pressure reaching 150 psig. When the Isolation Condenser has been placed in a Standby Lineup continue startup per DGP 01-01. Raise reactor power by control rod withdrawal until 2 Main Turbine Bypass Valves are fully opened.__________________________________________________________________

Critical Tasks: RPV-5.1 - With a reactor scram required and the reactor not shutdown, take action per DEOP 400-5, Failure to Scram, to reduce power by inserting control rods. ________

RPV-5.12 - When executing DEOP 400-5, Failure to Scram, reactor pressure is controlled as __

necessary to prevent an uncontrolled positive reactivity excursion of > 5% power. __________

Event Malf. Event Event No. No. Type* Description 1 NONE N BOP IC - Place Isolation Condenser in a Standby Lineup NONE REACTIVITY - Raise reactor power by withdrawing control 2 R ATC rods.

3 RDPPATRP C ATC CRD - CRD Pump trip (Overcurrent) 4 T18 C/T BOP AUX POWER - EDG INOP due to EDGCW pump failure NII17POT 5 I/T ATC NI - IRM fails upscale with partial 1/2 scram B15 6 N01 C BOP SERVICE AIR - Swap SAC due to oil leak CRD - CRD pump trip and accumulator trouble alarm 7 RDPPBTRP M TEAM (Manual Scram)

RDHLVFPA RDHLVFPB 8 RDHLDEGA M TEAM Hydraulic ATWS/ARI unsuccessful - Scram Resets RDHLDEGB RDFHYLK

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2017-301 ILT-N-1 Page 2 of 19 Rev. 00 (05/17)

Scenario Objective Evaluate the Teams ability to operate the plant with a failure of control rods to fully insert upon receipt of a scram signal.

Scenario Summary

1. Unit startup is in progress.

2. The following equipment is OOS:

a. None

3. LCOs:

a. None Scenario Sequence

The team will take the shift with DGP 01-01 Unit Startup, in progress. The team will place the Isolation Condenser in a standby lineup per DGP 01-01.

Immediately following placing the Isolation Condenser in a standby lineup, the team will continue raising reactor power by withdrawing control rods until 2 main turbine bypass valves are fully opened.

When the 2nd main turbine bypass valve is fully opened, the 2A CRD pump will trip on overcurrent. The ATC operator will take actions to start the 2B CRD pump and the team will execute DOA 0300-01, Control Rod Drive System Failure and DOA 6500-10, 4KV Circuit Breaker Trip.

After the 2B CRD pump has been started and action of DOA 6500-10 and DOA 0300-01 are completed, the Unit 2 Emergency Diesel Generator Cooling Water Pump will experience a power failure due to a blown fuse. The team will declare the Unit 2 EDG inoperable and Tech Specs 3.8.1 and 3.7.2 are not met.

After Tech Specs are addressed for the Unit 2 EDG failure, IRM #17 will fail upscale causing a 1/2 scram; a partial 1/2 half scram will occur. The team will perform DOA 0500-02, Partial Half or Full Scram Actuation, and insert the RPS Channel B 1/2 scram and determine that Tech Spec 3.3.1.1 is not met until the 1/2 scram is inserted.

After Tech Specs are addressed for the Partial 1/2 scram, an oil leak will develop on the Unit 2 Service Air Compressor.

The team will start the Unit 3 Service Air Compressor and secure the Unit 2 Service Air Compressor per DOA 4600-01, Service Air System Failure.

Once the Service Air System has been restored, the 2B CRD pump will trip. After the team enters DOA 0300-01 and DOA 6500-10, CRD N-09 accumulator alarm will illuminate and the team will insert a manual scram IAW DOA 0300-01.

The manual scram will fail to insert control rods fully. ARI will also fail to insert the control rods due to a hydraulic lock in the Scram Discharge Volume.

The team will ultimately be successful in achieving reactor shutdown by driving control rods and performing repeated scram resets.

2017-301 ILT-N-1 Page 3 of 19 Rev. 00 (05/17)

Event One - Place Isolation Condenser in a standby Lineup

Preparation of the Isolation Condenser Lineup for RPV pressure > 150 psig.

Malfunctions required: 0 Success Path:

2-1301-3, 2-1301-17&20 valves are open

2-1301-1, 2-1301-2, and 2-1301-4 valves are closed.

Event Two - Raise Reactor Power to Establish 2 Main Turbine Bypass Valves Fully Opened.

Reactor Power ascension.

Malfunctions required: 0 Success Path:

Crew withdraws control rods per Control Rod Sequence package and REMA until 2 Main Turbine Bypass Valves are fully opened.

Event Three - Control Rod Drive (CRD) Pump Trip

2A CRD pump trips on overcurrent.

Malfunctions required: 1

(2A CRD Pump Overcurrent)

Success Path:

Starts 2B CRD Pump

Addresses actions of DOA 6500-10, 4KV Circuit Breaker Trip Event Four - EDG Cooling Water Pump Failure

Fuse failure occurs resulting in loss of power to Unit 2 EDG Cooling Water Pump Malfunctions required: 1

(EDG Cooling Water Pump Fuse)

Success Path:

Performs DOA 6600-01, Diesel Generator Failure

Declares TS 3.8.1 Condition B and TS 3.7.2 Condition A not met.

2017-301 ILT-N-1 Page 4 of 19 Rev. 00 (05/17)

Event Five - IRM Fails upscale with Partial Half Scram

IRM #17 fails upscale with partial half scram.

Malfunctions required: 2

(IRM #17 fails upscale)

(Partial half scram)

Success Path:

IRM #17 placed in bypass and RPS Channel B 1/2 scram is completed.

Event Six - Oil leak on U2 Service Air Compressor

An oil leak is reported from the U2 EO and the team will swap the Service Air Compressors. The U2 Service Air will trip if the swap is not completed within 10 minutes.

Malfunctions required: 1

(Service Air Compressor trip)

Success Path:

U3 SAC is running

U2 SAC is secured Event Seven - 2nd CRD Pump trip with Accumulator Trouble alarm

2B CRD Pump trips.

CRD N-09 accumulator alarm comes in.

Malfunctions required: 2

(2B CRD Pump trip)

(CRD N-09 accumulator alarm)

Success Path:

Manual Reactor Scram.

Event Eight - Hydraulic ATWS/ARI Unsuccessful

A Hydraulic ATWS occurs when the reactor is scrammed. ARI is unsuccessful Malfunctions required: 1

(Hydraulic ATWS)

Success Path:

Team inserts control rods by manually driving control rods and performing repeated scrams.

2017-301 ILT-N-1 Page 5 of 19 Rev. 00 (05/17)

PRE-SCENARIO ACTIVITIES Evolution Malfunctions / CAEP Instructor Information

Initialize the simulator in IC 163 (password 2017ilt)

Run Pump_Sumps.cae

Run caep file: 16-1 ILT-N-1.cae

Provide crew with a marked up copy of DGP 01-01 (to step 37)

Provide crew with appropriate REMA and control rod move sheets

Verify 2A CRD pump is operating

Verify 2A and 2B IAC are running

Verify placard for 3C IAC indicates lined Simulator up to Unit 2 Setup

Verify U2 SAC is running

Verify U3 SAC in PTL

Verify the U2 to U3 SA crosstie open

Verify RB Vent lineup on Units 2 & 3

Remove PPC Alarm E207 from scan

Verify RWM sequence is correct (2.I.0 0E9C)

Ensure HPCI Turbine is reset

Range IRMs UP as high as possible

Reset all annunciators

Complete Simulator Setup Checklist 2017-301 ILT-N-1 Page 6 of 19 Rev. 00 (05/17)

Event One - Place Isolation Condenser in Standby Lineup Trigger Position Crew Actions or Behavior CRS Directs BOP to place IC in standby lineup per DGP 01-01, Unit Startup BOP Places Isolation Condenser in Standby Lineup per DOP 1300-01, Standby Operation of the Isolation Condenser System Verifies or manipulates the following valves:

MO 2(3)-1301-1, RX OUTLET ISOL, open.

MO 2(3)-1301-2, RX OUTLET ISOL, open.

MO 2(3)-1301-3, RX INLET ISOL, closed.

AO 2(3)-1301-17 AND AO 2(3)-1301-20, VENT VLVs, open.

MO 2(3)-1301-4, RX INLET ISOL, open.

Informs US IC is in a standby lineup US Directs the team to continue startup per DGP 01-01 Event One is complete when:

IC is in a standby lineup

-- AND/OR --

At the discretion of the lead evaluator 2017-301 ILT-N-1 Page 7 of 19 Rev. 00 (05/17)

Event Two - Withdraw Control Rods to Open Bypass Valves Trigger Position Crew Actions or Behavior NOTE:

If Reactivity SRO is requested, inform the crew: No reactivity SRO is available CRS Directs NSO to continue startup per DPG 01-01 and REMA to establish 2 bypass valves open.

Performs brief ATC Withdraws control rods per control rod move sheets to establish 2 bypass valves open.

Verifies RWM in service May request QNE/reactivity SRO.

Withdraws control rods IAW DGP 03-04, Control Rod Movements Performs coupling check for all control rods moved to position 48 Monitors reactor response Informs US when 2 bypass valves are open BOP Acts as verifier for control rod moves Monitors Reactor Pressure and Bypass valve position Event Two is complete when:

2 Bypass Valves are open

-- AND/OR --

At the discretion of the lead evaluator 2017-301 ILT-N-1 Page 8 of 19 Rev. 00 (05/17)

Event Three - CRD Pump Trip Trigger Position Crew Actions or Behavior 30 SIMULATOR OPERATOR / ROLE PLAY:

If requested, insert TRIGGER 30, to set gains.

1 At the discretion of the Lead Examiner, activate TRIGGER 1. This will trip the 2A CRD pump on overcurrent.

If contacted to check the breaker on Bus 23 (wait 3 minutes) and respond, The breaker for the 2A CRD pump is open with an overcurrent target up.

If contacted to 2A CRD pump locally (wait 3 minutes) and respond, The 2A CRD pump is at rest and the motor is hot to the touch.

If contacted to verify proper operation of the 2B CRD pump (wait 3 minutes after the pump has been started) and respond, The 2B CRD pump is operating normally.

Acknowledge communications to organizations outside the MCR. No response is intended.

ATC Announces alarms 902-5 B-2, ROD DRIVE PP TRIP Takes actions per DAN 902-5 B-2 and/or DOA 0300-01, Control Rod Drive System Failure:

Takes manual control of FIC 2-340-1 CRD FLOW CONTRL (if valve has gone open).

Starts 2B CRD pump.

Verifies CRD parameters return to previous values (May take FIC 2-340-1 CRD FLOW CONTRL to open/automatic, if closed previously).

Place the control switch for 2A CRD pump in PTL IAW DOA 6500-10, 4kV Circuit Breaker Trip CRS Directs entry into DOA 0300-01 and DOA 6500-10 Establishes contingency actions if 2nd CRD pump fails Contacts outside organizations for assistance May reference TRM 3.3.h, Reactor Vessel Water Level Instrumentation System (RVWLIS) Backfill System, due to short loss of RVWLIS supply.

BOP Monitors panels and assists as directed.

Event Three is complete when:

2B CRD pump has been started and the actions of DOA 0300-01 and DOA 6500-10 are complete,

-- AND/OR -

At the discretion of the lead evaluator 2017-301 ILT-N-1 Page 9 of 19 Rev. 00 (05/17)

Event Four - EDG Cooling Water Pump Failure Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR:

3 At the direction of the Lead Examiner, activate TRIGGER 3 to fail the U2 EDG Cooling Water Pump ROLE PLAY:

If dispatched in investigate the U2 EDG (wait 3 minutes) and report: I see nothing abnormal with the U2 EDG, but alarm DG2 C-3, DIESEL CLG WTR PUMP FAILURE OR LOCKED OUT is in.

If dispatched to MCC 29-2 to check status of EDG CWP breaker, (wait 3 minutes) and report: The breaker for the U2 EDG CWP is closed.

If dispatched in investigate 2-3903-F1 (Fuse in the U2 EDG control cabinet) wait 3 minutes and report: Fuse 2-3903-F1 is blown. I will contact the Field Supervisor to obtain a replacement.

(It is not intended to replace this fuse. If further requests for fuse replacement are made delay by searching for a like for like fuse)

Respond as outside organizations as appropriate BOP Announces alarm 902-7 G-8, U2 Diesel Gen Clg Wtr Pp Trip Lkout.

Dispatches EO to U2 EDG to investigate.

Enters and performs actions of DOA 6600-01, Diesel Generator Failure o Places U2 EDG control switch to STOP o Places the U2 EDG to Bus 24-1 Breaker control switch to PTL CRS Announces entry into DOA 6600-01 and directs team actions.

Reviews Tech Specs and determines TS 3.8.1 Condition B.1, B 3.1 or B 3.2 and B.4 and 3.7.2 Condition A.1 are not met.

May direct placing the U2 EDG control switch in STOP FLOOR INSTRUCTOR NOTE:

If Appendix X is directed to be performed, intervene and inform the US another NSO will perform Appendix X Event Four is complete when:

Tech Spec call is completed,

-- AND/OR --

At the discretion of the lead evaluator 2017-301 ILT-N-1 Page 10 of 19 Rev. 00 (05/17)

Event Five - IRM Fails upscale with Partial Half Scram Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR:

5 At the direction of the Lead Examiner, activate TRIGGER 5 to fail IRM #17 upscale.

Verify TRIGGER 29 automatically activates when the B Manual Scram Pushbutton 29 is depressed to remove the partial 1/2 scram malfunction.

ATC Announces alarm 902-5 C-15, Channel B IRM HI HI/INOP.

Reports IRM #17 failed upscale.

Announces the RPS Channel B Partial 1/2 Scram.

CRS Acknowledges IRM #17 failed upscale and Partial 1/2 scram.

Directs entry into DOA 0500-02, Partial 1/2 Scram or Full Scram Actuation BOP Investigates IRM #17 on panel 902-36.

Reports IRM #17 is reading upscale on panel 902-36 CRS Refers to Tech Spec 3.3.1.1 and determines that 3 IRMs are required per channel and that the LCO is met.

o Directs IRM #17 to be bypassed.

Refers to Tech Spec 3.3.1.1 and determines that RPS Channel B is INOP and that Condition A is not met and that the RPS Channel B must be placed in Trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . And condition C1 may apply.

o Directs B 1/2 scram to be put in manually.

May Refer to TRM 3.3.a Control Rod Block Instrumentation.

ATC Inserts B 1/2 scram manually be depressing the B Manual Scram Button.

Event Five is complete when:

RPS Channel B 1/2 Scram inserted

Tech Spec call is completed,

-- AND/OR --

At the discretion of the lead evaluator 2017-301 ILT-N-1 Page 11 of 19 Rev. 00 (05/17)

Event Six - Service Air Compressor Oil Leak / Swap Service Air Compressors Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR:

At the discretion of the Lead Examiner, activate call as EO on rounds, and report:

There is an oil leak coming from the U2 Service Air Compressor (SAC). The oil is contained.

7 After the report is made regarding oil leak, Insert TRIGGER 7 which trips the U2 SAC after 10 minutes If required, as directed by the Lead Evaluator, call the unit as the U2 EO and Recommend removing the U2 SAC from service without delay.

ROLE PLAY:

If dispatched to the U3 SAC (wait 2 minutes) and report: U3 SAC is ready to start.

If requested after U3 SAC is running, report: U3 SAC is operating normally.

If U2 SA Trips If dispatched to Bus 26 to check status of U2 SAC breaker, (wait 3 minutes) and report: The breaker for the U2 SAC is open with overcurrent trip indicated.

Respond as outside organizations as appropriate BOP Informs US of degrading SAC Directs EO to check U3 SAC is ready to be started Starts U3 SAC per DOP 4600-01, Unit 3 Service Air System Operation Secures U2 SAC per DOP 4600-04, Unit 2 Service Air Compressor Startup, Operation, Shutdown If the U2 SAC trips before securing, performs the following:

Starts U3 SAC per DOA 4600-01, Service Air System Failure Performs DOP 6700-20 480V Circuit Breaker Trip to place the U2 SAC breaker in PTL.

CRS Directs BOP to perform the following:

Start U3 SAC IAW DOP 4600-01 Secure U2 SAC IAW DOP 4600-04 If the U2 SAC trips before securing, enters the following:

DOA 4600-01 DOP 6700-20 Event Six is complete when:

U3 SAC is started and U2 SAC is secured,

-- AND/OR --

At the discretion of the floor instructor 2017-301 ILT-N-1 Page 12 of 19 Rev. 00 (05/17)

Event Seven - Trip of 2nd CRD pump Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR:

9 At the direction of the Lead Examiner, activate TRIGGER 9 to trip the 2B CRD pump After the trip of the 2B CRD accumulator trouble light for CRD N-09 will illuminate.

If contacted to check the breaker on Bus 24 (wait 3 minutes) and respond, The breaker for the 2B CRD pump is open with no targets up. There is an acrid odor coming from the breaker. No signs of fire.

ATC Announces alarms 902-5 B-2, ROD DRIVE PP TRIP; 902-5 G-2, ACCUMULATOR LVL HI/PRESS LO Dispatches EO to 2B CRD pump to investigate.

Monitors full core display for accumulator trouble lights When N-09 accumulator alarm illuminates, inserts a manual scram IAW DOA 0300-01 CRS Announces entry into DOA 0300-01, Control rod drive system failure, and DOA 6500-10, 4KV Breaker Trip Directs team actions.

Sets contingency for accumulator trouble alarm Directs insertion of manual scram after accumulator trouble alarm illuminates.

Event Seven is complete when:

Manual scram has been attempted,

-- AND/OR --

At the discretion of the lead evaluator 2017-301 ILT-N-1 Page 13 of 19 Rev. 00 (05/17)

Event Eight - Hydraulic ATWS / ARI Unsuccessful Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR / ROLE PLAY:

When requested: Wait several minutes and as directed by the Floor Instructor, activate the appropriate trigger and report completed.

11 TRIGGER 11 inserts automatically to insert Full Hydraulic Lock 30 seconds after the Mode Switch is placed in S/D 13 TRIGGER 13: Closes the CRD Charging Water Valve.

15 TRIGGER 15: bypasses MSL GP 1 RPV/L and Offgas High Rad.

17 TRIGGER 17: pulls ARI fuses.

19 TRIGGER 19: installs scram jumpers 21 TRIGGER 21: Crossties CRD with Unit 3 When directed by Lead Evaluator/Floor Instructor: Run clrhydlk.cae to clear the hydraulic lock.

ATC Performs the following actions per DGP 02-03, Reactor Scram, as directed:

Presses scram pushbuttons Places mode switch in shutdown Check rods inserted / Determines control rods did not insert.

Initiates ARI / Determines ARI did not insert control rods.

Announces ATWS condition and RX power is < 6%

Runs Recirc pumps back to minimum.

Lowers FWLC setpoint to -40 inches.

BOP Performs DGP 02-03 as directed.

CRS Enters DEOP 100, RPV Control (as directed by DGP 02-03), and directs actions.

Due to report of ATWS condition, exits DEOP 100 AND enters DEOP 0400-05, Failure to Scram, and directs/performs:

Placing ADS to inhibit. (Not expected to be a Critical Task for this scenario)

Placing Core Spray pumps in PTL.

Verifying required auto actions.

May direct initiation of SBLC Installing of the jumpers for the MSIV low level isolations and the Off Gas high Rad isolations.

Continues DEOP 0400-05, Failure to Scram, and directs/performs:

Inserting control rods using Alternate Rod Insertion. (RPV-5.1)

Directs CRD crosstie with Unit 3 Directs driving control rods.

Directs repeated scram/resets defeating RPS logic.

Based on report that SBLC failed, directs DEOP 0500-01, Alternate Boron Injection, performed. (If SBLC start was attempted) 2017-301 ILT-N-1 Page 14 of 19 Rev. 00 (05/17)

Event Eight - Hydraulic ATWS / ARI Unsuccessful Trigger Position Crew Actions or Behavior ATC Inserts control rods per DEOP 500-05, Alternate Insertion Of Control Rods, as follows: (RPV-5.1) o Drives rods by:

o Bypassing the RWM.

o Uses either the ROD MOVEMENT CONTROL switch or the EMERG ROD IN position of the ROD OUT NOTCH OVERRIDE switch.

o Performs repeated scram/resets defeating RPS logic:

o Directs ARI fuses pulled if RPV level is lowered below - 59 in.

o Directs scram jumpers installed.

o Places SDV Hi Water Bypass in the BYPASS position.

o Closes the SDV vent and drain valves.

o Resets the scram.

o Opens SDV Vent and Drain valves.

o Manually scrams the reactor when the SDV is drained.

o Repeats as necessary.

CRS Based on report that all control rods are inserted, exits DEOP 0400-05 and enters DEOP 0100.

ATC / BOP Performs as directed:

o Re-establishes injection using available injection systems to MAINTAIN RPV water level above TAF (in band directed by Unit Supervisor).

Event Eight / Scenario Completion Criteria:

Control rods inserted,

-- AND/OR --

At the discretion of the Lead Examiner.

2017-301 ILT-N-1 Page 15 of 19 Rev. 00 (05/17)

SUPPORTING PROCEDURES Procedure Numbers Title DAN 902(3)-5 B-2 Rod Drive Pp Trip DAN 902(3)-5 C-15 Channel B IRM HI HI/INOP DAN 902-7 G-8 U2 Diesel Gen Clg Wtr Pp Trip Lkout DEOP 100 RPV Control DEOP 400-5 Failure To Scram DEOP 500-5 Alternate Insertion Of Control Rods DGP 01-01 Unit Startup DGP 02-03 Reactor Scram DGP 03-04 Control Rod Movements DOA 0300-01 Control Rod Drive System Failure DOA 0500-02 Partial 1/2 Scram or Full Scram Actuation DOA 4600-01 Service Air System Failure DOA 6500-10 4kV Circuit Breaker Trip DOA 6600-01 Diesel Generator Failure DOP 1300-01 Standby Operation Of The Isolation Condenser System DOP 4600-01 Unit 3 Service Air System Operation DOP 4600-04 Unit 2 Service Air Compressor Startup, Operation, Shutdown TRM 3.3.h Reactor Vessel Water Level Instrumentation System TS 3.3.1.1 Reactor Protection System Instrumentation TS 3.7.2 Diesel Generator Cooling Water (DGCW) System TS 3.8.1 AC Sources - Operating 2017-301 ILT-N-1 Page 16 of 19 Rev. 00 (05/17)

Critical Tasks With a reactor scram required and the reactor not shutdown, take RPV-5.1 action per DEOP 400-5, Failure to Scram, to reduce power by inserting control rods.

When executing DEOP 400-5, Failure to Scram, reactor pressure is RPV-5.12 controlled as necessary to prevent an uncontrolled positive reactivity excursion of > 5% power.

2017-301 ILT-N-1 Page 17 of 19 Rev. 00 (05/17)

CAEP Files:

16-1 ILT-N-1.cae

For ILT Class 16-1 NRC Exam

Written by DSS

Rev 00

Date 4/17

1. 1. 1. INITIAL CONDITIONS ####

Sets APRM Master Gain pot to 1.0 irf niagain 1.0

Sets scram discharge volume hydraulic blockage and degradation to 94%.

imf rdhlvfpa 94.0 imf rdhlvfpb 94.0 imf rdhldega 94.0 imf rdhldegb 94.0

Inserts partial 1/2 scram on RPS Channel B imf b15

Overrides CST High Level Alarms off imf ser1204 off imf ser1200 off

1. 1. 1. EVENT TRIGGERS ####

Event Trigger 1 trips the 2A CRD Pump trgset 2 "0"l2 imf rdppatrp (1)l2

Event Trigger 3 Simulates U2 EDG cooling water pump breaker control power transformer failure:

Forces up alarm 902-8 A-7, U2 Diesel Gen Trouble.

Forces up alarm 902-7 G-8, U2 Diesel Gen Clg Wtr PP Trip/lkout.

Inserts U2 Diesel Gen Clg Wtr PP Trip malfunction.

trgset 3 "0"l2 imf ser1589 (3) onl2 imf ser0710 (3) onl4 imf t18 (3)l4

Event Trigger 5 fails IRM #17 upscale trgset 5 "0"l4 imf nii17pot (5) 125.0 30.0l4

Event Trigger 7 trips the U2 SAC 10 minutes after trigger is activated trgset 7 "0"l6 imf n01 (7 10:00)l6

Event Trigger 9 trips the 2B CRD Pump and drives up N-09 accumulator alarm trgset 9 "0"l6 imf rdppbtrp (9)l6 ior rdlacuma124 (9 10) onl8 imf ser1009 (9 10) onl8

Event Trigger 11 inserts the Full Hydraulic Lock malfunction 30 seconds after MODE switch in S/D to prevent rods from moving on their own trgset 11 "rpdmode4"l8 imf rdfhylk (11 30)l8 2017-301 ILT-N-1 Page 18 of 19 Rev. 00 (05/17)

Event Trigger 13 Closes the CRD Charging Water Valve trgset 13 "0"l8 irf rd25pos (13) 0.0l10

Event Trigger 15 Installs jumpers to bypass RPV low level MSIV and Off Gas Hi Rad Isolations trgset 15 "0"l10 irf ci59jp (15) inl10 irf ogogjp (15) inl10

Event Trigger 17 Pulls ARI fuses.

trgset 17 "0"l12 irf aw4 (17) pulledl12

Event Trigger 19 Installs RPS Jumpers.

trgset 19 "0"l12 irf rpjumpas (19) onl12

Event Trigger 21 crossties CRD with Unit 3 trgset 21 "0"l14 irf rdxtieu3 (21) truel14

Event Trigger 29 activates when the B RPS channel pushbutton is depressed and removes malfunction B13 trgset 29 "rpd301b"l14 trg 29 "dmf b13"l14

Event Trigger 30 sets gain for all 6 APRMs.

trgset 30 "0"l16 trg 30 "irf niagainf true"l16

1. 1. 1. END ####

2017-301 ILT-N-1 Page 19 of 19 Rev. 00 (05/17)

Dresden Generating Station 2017-301 ILT-N-2 Pump DWED Sump Control Rod Drift IC - Spurious Initiation RB Vent Rad monitor failure w/ failure of SBGT to Auto Start Stator Water Cooling pump trip Emergency Load Reduction Recirc Leak Aux Power fails to transfer - ED on RPV level EXAM MATERIAL Rev. 00 05/17 Developed By:

Exam Author Date Approved By:

Facility Representative Date

Facility: Dresden Generating Station Scenario No.: 2017-301 ILT-N-2 Op-Test No.: 2017-301 Examiners Operators / crew position

/ ATC

/ BOP

/ CRS Initial Conditions: Unit 2 is at 62% Rx Power. No equipment is OOS, and no LCO required actions.

Unit 3 is at full power. No equipment is out of service, no evolutions in progress, no LCO required actions.

Turnover: Unit 2: Pump DWEDS IAW DOP 2000-180 at request of Engineering Maintain load per TSO direction.

Critical Tasks: RPV-1.1 - If the RPV level trend is not reversible with an RPV injection source lined up with a pump running, initiate emergency depressurization between an RPV water level between the Top-of-Active Fuel and the Minimum Steam Cooling RPV Water Level or within 1 minute after TAF is reached, whichever is later.

RPV-1.2 - When high and low pressure systems are available for RPV injection, do not stop or divert injection from the RPV until level is restored to above the Top-of-Active Fuel (TAF).

RPV-1.3 - Upon RPV level restoration following a loss of vessel inventory, all available injection systems are controlled in such a fashion that RPV overfill does not result in compromise of the HPCI system due to steam line flooding (+55 inches).

RPV-1.5 - Per DEOP 100, RPV Control, with the automatic ADS timer initiated, inhibit ADS before an automatic actuation occurs.

RPV-2.1 - When conditions are met per DEOP 400-2, Emergency Depressurization, the minimum number of available SRVs required for emergency depressurization (MNSRED) are opened.

PC-1.1 - While executing DEOP 200-1, Primary Containment Control, when drywell pressure exceeds 9 psig and only if operating within the safe region of the drywell spray initiation limit (DSIL), initiate drywell sprays.

Event Malf. Event Event No. No. Type* Description 1 NONE N ATC CONTAINMENT - Pump DWED Sump 2 RODH06DO C ATC CRD - Control Rod H-06 Drift Out 3 ICSPDFT C/T BOP IC - Spurious Initiation RADRBVAH VRD5741C CONTAINMENT - RB Vent Rad monitor failure w/ failure of SBGT to 4 VRD741C3 C/T BOP VRD742C3 AutoStart VGLAUA06 T47 SWC - Stator Water Cooling Pump Trip/Failure of Standby Pump to 5 C BOP T50 Start 6 NONE R ATC REACTIVITY - Emergency Load Reduction F43 RECIRC - Recirc System Leak (Manual Scram); AUX PWR - Auxiliary 7 L72 M ALL Power Fails to Transfer / Emergency Depressurization due to Low RPV AT46 Level

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 2017-301 ILT-N-2 Page 2 of 22 Rev. 00 (05/17)

Scenario Objective Evaluate the Teams ability to operate the plant with an Emergency Depressurization on RPV low level.

Scenario Summary

1. Unit is at 62% power.

2. The following equipment is OOS:

a. None.

3. LCOs:

a. None Scenario Sequence

The team will take the shift and pump the Drywell Equipment Drain sumps.

After the sumps are pumped, a control rod will drift out. This will result in the team executing DOA 0300-05 and DOA 0300-01.

Following the control rod drift, a spurious initiation of the IC will occur. This will result in the IC being declared inoperable. The IC may still be considered available.

The RB Vent rad monitor will fail upscale and SBGT will fail to start. This will result in both trains of SBGT being declared inoperable.

The running stator water cooling pump will trip and the standby will fail to start. This will result in a runback. DOA 7400-01 will direct the team to execute an emergency load reduction.

Following the load reduction a leak develops from the recirc system. This will result in RPS scram setpoints being challenged. The team will execute a manual reactor scram.

Following the scram, Aux power will fail to transfer to offsite power, resulting in a loss of the feed system. HPCI is degraded. With insufficient HP injection sources available to overcome the leak rate, an ED will be performed on low RPV level. The team will recover RPV level with LP ECCS systems.

Symbols are used throughout the text to identify specific items as indicated below:

Critical Tasks Time Critical Tasks PRA Key Operator Actions 2017-301 ILT-N-2 Page 3 of 22 Rev. 00 (05/17)

Event One - Pump DWEDS

Pumps Drywell Equipment Drain Sump.

Malfunctions required: 0 Success Path:

DWEDs is pumped Event Two - CRD FCV Controller Fails High Causing a Rod to Drift Out.

CRD FCV failure causes Control Rod H-06 to drift out.

Malfunctions required: 1

(Rod H-6 drift out)

Success Path:

Crew inserts control rod H-06 to position 00. CRD H-06 has been removed from service on RWM.

Event Three - Isolation Condenser Inadvertent Initiation

The Isolation Condenser Initiation setpoint drifts causing initiation..

Malfunctions required: 1

(Iso Cond Initiation setpoint)

Success Path:

Isolation condenser removed from operation.

Declares TS 3.5.3 Condition A.1 and A.2 not met Event Four - Rx Bldg Vent Rad Fails Upscale With Failure of SBGT To Auto Start

Fuse failure occurs resulting in loss of power to Unit 2 EDG Cooling Water Pump Malfunctions required: 3

(RX Bldg Vent Rad monitor)

(2/3A SBGT C/S)

(2/3B SBGT C/S)

Success Path:

Performs DOA 7500-01, Standby Gas Treatment Fan Trip

Declares TS 3.3.6.2 Condition A.1; 3.3.7.1 Condition A and TS 3.6.4.3 Condition A & D not met.

2017-301 ILT-N-2 Page 4 of 22 Rev. 00 (05/17)

Event Five - Stator Water Cooling Pump Trips

2A and 2B stator cooling water pumps trip.

Malfunctions required: 2

(2A Stator Cooling Pump)

(2B Stator Cooling Pump)

Success Path:

Load Reduction in progress to close bypass valves Event Six - Load Reduction

Emergency load reduction due to loss of Stator water cooling.

Malfunctions required: 0 Success Path:

Bypass valves closed or Reactor power is 45%

Event Seven - Loss Of High Pressure Feed / Recirc Loop Leak / Emergency Depressurization

Recirc loop leak

HPCI isolation.

Failure of Aux power to transfer.

Malfunctions required: 3

(Recirc Leak)

(Group IV isolation)

(TR-22 trip)

Success Path:

Emergency Depressurization, RPV level restored above TAF.

2017-301 ILT-N-2 Page 5 of 22 Rev. 00 (05/17)

PRE-SCENARIO ACTIVITIES Evolution Malfunctions / CAEP Instructor Information

Initialize the simulator in IC 169

Run caep file: Pump_Sumps.cae

Run caep file: 16-1 ILT-N-2.cae

Provide the crew with a copy of DOP 2000-180 and Appendix with sump data

Provide Pre-Job Brief sheet to crew

Verify 2A Stator Water Cooling pump running and 2B in standby

Verify 2D Condensate pump selected for standby Simulator

Verify 2C Feed pump on Bus 22 selected Setup for standby

Verify Condensate Demin DP within limits

Run Floordrainmass SimView file and change DWEDS mass to 4000

Cycle power to DWEDS recorder

Remove PPC Alarm E208 from scan

Verify RB Vent lineup on Units 2 & 3

Verify CRAM rod move sheet

Verify CRD system parameters are normal

Verify Control Rod Sequence 2.S.0.0.909D is loaded in RWM 2017-301 ILT-N-2 Page 6 of 22 Rev. 00 (05/17)

Event One - Pump DWEDS Trigger Position Crew Actions or Behavior CRS Directs NSO to pump DWEDS per DOP 2000-180, Drywell Sump Operation with the Unit On-Line ATC Pumps Drywell Equipment Drain Sump:

Verifies AO 2-2001-3 open Open AO-2-2001-5 and 6 Verify recorder 2(3)-2040-2, D/W EQUIPMENT DRAIN SUMP FLOW:

o Indicates RCD on digital display.

o Integrator value resets to approximately zero.

Start 2A or 2B EQUIP DRN PP.

Secures pump Shut AO-2-2001-5 and 6 Event One is Complete When:

DWEDS is pumped

-- AND/OR --

At the discretion of the lead evaluator 2017-301 ILT-N-2 Page 7 of 22 Rev. 00 (05/17)

Event Two - CRD FCV Controller Fails High Causing a Rod to Drift Out Trigger Position Crew Actions or Behavior Simulator Operator:

1 At the discretion of the Lead examiner, activate TRIGGER 1, which causes:

Control Rod H-06 to drift out.

Role Play:

EO to check H-06 accumulator: Wait 2 min, then report At the HCU for H-06, I see nothing abnormal.

WEC/EO to hydraulically isolate and electrically disarm H-06: acknowledge the request.

It is not intended to complete the request.

QNE to evaluate core limits: Acknowledge the request. Wait 2 min. and report, core parameters are within limits.

Simulator Operator:

16 Verify TRIGGER 16 activates when H-06 is selected and Emergency In signal is given.

This deletes the Drift Out malfunction ATC Announces 902-5 A-3, Rod Drift, alarm.

Notices and announces that Control Rod H-06 is drifting out.

Performs actions of DOA 0300-05, Inoperable Or Failed Control Rod Drives as directed.

Immediate:

Bypasses the Rod Worth Minimizer.

Inserts the CRD to 00 using Emergency Rod In.

CRS Enters DOA 0300-05, Inoperable or Failed Control Rod Drives, and directs actions.

May refer to Tech. Spec 3.3.2.1 Condition C. (Not required with RX power >10%)

May enter DGA 07, Unpredicted Reactivity Addition.

ATC Announces that procedure directs entering DOA 0300-12, Mispositioned Control Rod.

Discontinues ALL non-emergency control rod motion and notifies CRS and QNE to evaluate core parameters.

CRS May reference TS 3.1.3, Condition C, and determine the following actions may be required:

o C.1 Fully insert inoperable control rod within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . (DOA 0300-05, Inoperable or Failed Control Rod Drives, directs inserting the rod) o C.2 Disarm the associated CRD within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Directs disarming rod H-06 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

CRS Enters DOA 0300-12, Mispositioned Control Rod.

Directs taking rod H-06 OOS on the RWM.

ATC Takes rod H-06 OOS on the RWM.

2017-301 ILT-N-2 Page 8 of 22 Rev. 00 (05/17)

Event Two - CRD FCV Controller Fails High Causing a Rod to Drift Out Trigger Position Crew Actions or Behavior BOP Monitor panels and assists as directed.

Provides peer check for taking rod H-06 OOS on RWM Event Two Completion Criteria:

Control Rod H-06 Has Been Inserted To Position 00, AND

CRD H-06 has been removed from service on RWM, AND

Tech Specs Have Been Addressed,

-- AND/OR --

At the direction of the Lead Examiner 2017-301 ILT-N-2 Page 9 of 22 Rev. 00 (05/17)

Event Three - Isolation Condenser Inadvertent Initiation Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR:

3 At the discretion of the Lead Examiner, activate TRIGGER 3, which drifts the isolation Condenser Initiation setpoint.

ROLE PLAY:

Respond as Outside Organizations contacted for help.

BOP Reports and responds to DANs:

902-3 B-4, ISOL CONDR VLVS OFF NORM.

902-3 C-4, ISOL CONDR TEMP HI.

902-4 A-15, ISOL CONDR CH A/B INITIATION.

Determines Isolation Condenser in operation due to MO 2-1301-3 valve open.

TEAM Determines Isolation Condenser initiation spurious due to RPV pressure in normal band.

US Directs removing the Isolation Condenser from service.

BOP Takes action per DAN 902-4 A-15, ISOL CONDR CH A/B INITIATION.

May utilize Hard Card for Securing Iso Condenser Places MO 2-1301-3 in PTL.

When MO 2-1301-3 indicates closed, reports that the Isolation Condenser is removed from service.

ATC Monitors reactor water level, pressure, and power.

TEAM May enter DGA-07, Unexpected Reactivity Change.

US References appropriate plant licensing documents and determines:

TS 3.5.3, condition A. required actions:

A.1 Verify by administrative means High Pressure Coolant Injection System is OPERABLE immediately, AND, A.2 Restore IC System to OPERABLE status within 14 days.

TS 3.3.5.2, condition A. required actions: (May wait for IMD investigation)

A.1 Declare IC System inoperable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; AND, A.2 Place channel(s) in trip within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

TEAM Notifies Security to limit access to area under Isolation Condenser vent.

Notifies Radiation Protection to survey under the Isolation Condenser vent.

Event Three is complete when:

Isolation condenser removed from operation,

Technical specifications have been referenced,

-- AND/OR --

At the discretion of the lead examiner 2017-301 ILT-N-2 Page 10 of 22 Rev. 00 (05/17)

Event Four - Rx Bldg Vent Rad Fails Upscale With Failure of SBGT To Auto Start Trigger Position Crew Actions or Behavior Simulator Operator:

5 At the discretion of the Floor Instructor / Lead Evaluator, activate TRIGGER 5. This fails 2A RX Bldg Vent Rad monitor upscale.

Note: BOTH SBGT system trains fail to automatically start.

Role Play:

Operator/maintenance sent to in-plant panel 2223-28A for 2/3A SBGT system: Wait 4 min, then report that: smoke came from the panel when I opened it, but there is no fire.

It smells like burnt electrical insulation.

If directed to check fuses in panel 2223-28A, wait 2 min. and report: fuse FU2 is blown.

Role Play:

EO to check RX Bldg to Atmosphere D/P on the Refuel floor: wait 2 min, the report the RX Bldg to Atmosphere D/P is (Insert the value from Instructor Station drawing 923 03 OR variable VRP4).

Acknowledge requests as plant support groups.

BOP Announces alarms indicating 2A RX Bldg Vent Rad high and a Secondary Containment Isolation have occurred:

902-3 F-14, Rx BLDG Vent Ch A Rad Hi Hi.

923-5 A-1(4), U2(3) Rx BLDG Vent/Exh Fan Trip.

923-5 C-1, Rx Bldg DP Lo.

Checks back panels and determines that 2A RX Bldg Vent Rad monitor has failed high (all other monitors are indicating normal levels).

Verifies expected automatic actions have occurred. Discovers and announces the following:

Both SBGT system trains failed to automatically start.

CRS Acknowledges reports of failed 2A RX Bldg Vent Rad monitor and the Secondary Containment Isolation.

Acknowledges report of SBGT system failure Enters DOA 7500-01, Standby Gas Treatment System Fan Trip.

BOP Performs the following to complete the Secondary Containment Isolation:

Places 2/3B SBGT train control switch to START (Per DOA 7500-01, Standby Gas Treatment Fan Trip)

May place 2/3A SBGT Train control switch to OFF.

2017-301 ILT-N-2 Page 11 of 22 Rev. 00 (05/17)

Event Four - Rx Bldg Vent Rad Fails Upscale With Failure of SBGT To Auto Start Trigger Position Crew Actions or Behavior CRS Refers to Technical Specifications and determines:

Technical Specification 3.3.6.2 Table 3.3.6.2-1 Function 3: Place channel in trip within 24 hrs. (Condition met)

Technical Specification 3.6.4.1.A: Restore secondary containment to OPERABLE status within 4 hrs. (If D/P drops to below -0.25 inches)

Technical Specification 3.6.4.3.D: Restore one SGT subsystem to Operable status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Technical Specification 3.3.7.1.A.2: Restore CREV System Instrument Channel to OPERABLE within 6 hrs.

Event Four Completion Criteria:

Secondary Containment Isolation completed; AND,

Technical Specifications have been referenced and required LCOs identified.

-- AND/OR --

At the discretion of the Floor Instructor/Lead Evaluator.

2017-301 ILT-N-2 Page 12 of 22 Rev. 00 (05/17)

Event Five - Stator Water Cooling Pump Trips Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR / ROLE PLAY:

7 At the discretion of the Lead Examiner, activate TRIGGER 7, which causes 2A stator cooling water pump to trip on overload and 2B to fails to auto start.

BOP Announces the following alarms:

DAN 902-7 B-10, Stator Clg PP Trip DAN 902-7 C-10, Stator Clg Panel Trouble DAN 902-7 E-11, H2 Seal Oil & Alterrex Pnl Trouble DAN 902-7 C-3, Turb Stator Coolant Runback DAN 902-7 A-5, Turbine Control Major Trouble Performs appropriate actions per DOA 7400-01, Failure of the Stator Coolant System:

Starts 2B Stator Cooling Water Pump (Immediate Action)

Announces 2B Stator Cooling Water pump failed to start Sends EO to check breaker and 2A Stator Cooling Water Pump for cause of trip.

Performs DOP 6700-20, 480V Circuit Breaker Trip.

Places 2A Stator Cooling Water Pump control switch in PTL.

SIMULATOR OPERATOR / ROLE PLAY:

As the EO sent to acknowledge the stator cooling water trouble and/or the H2 Seal Oil & Alterrex 9 Pnl Trouble alarm (wait 2 min), activate TRIGGER 9 and report: I have acknowledged stator cooling water trouble and/or the H2 Seal Oil & Alterrex Pnl Trouble alarm. The alarms are cleared and were . (Use table below to determine report) 902-7 alarm received Local alarm to report Inlet Flow Low, &

902-7 C-10, Stator Clg Panel Trouble Inlet Pressure Low 902-7 E-11, H2 Seal Oil & Alterrex Pnl Trouble Rectifier Coolant Flow Low.

902-7 C-3, Turb Stator Coolant Runback Turbine Runback ROLE PLAY:

As the EO sent to check cause of 2A Stator Cooling Water Pump trip (wait 2 min), then report:

2A Stator Cooling Water Pump tripped on overload.

As the EO sent to check cause of 2B Stator Cooling Water Pump trip (wait 2 min), then report:

2B Stator Cooling Water Pump breaker is open with no indication for the cause of the trip.

As the EO sent to check Conductivity (wait 2 min), the report: Stator cooling water conductivity is

.08µmhos.

CRS Enters and directs performance of DOA 7400-01, Failure of the Stator Coolant System.

Enters and directs performance of DOP 6700-20, 480V Circuit Breaker Trip.

Notifies Work Week Manager, IMD and/or EMD Directs load reduction per DGP 03-04 and DOA 7400-01 ATC Performs Load Reduction per DGP 03-01, DGP 03-04 and DOA 7400-01 Event 5 Completion Criteria:

Load Reduction in progress (Next event) ,

-- AND/OR --

At the discretion of the Lead Examiner.

2017-301 ILT-N-2 Page 13 of 22 Rev. 00 (05/17)

Event Six -Load Reduction Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR / ROLE PLAY:

Respond as support organizations as necessary ROLE PLAY:

If the crew does not perform the load reduction due to <81/2 bypass valves being open, direct them as the Shift Manager to lower power to close the bypass valves.

ATC Performs the following:

Lowers Recirc flow to no less than 56Mlbm/hr

Inserts CRAM rods per DGP 03-04 as necessary to lower reactor power to no less than 33% to reclose bypass valves US Directs load reduction Directs NSO to maintain < 81/2 bypass valves open May enter DOA 0500-03, 38.5% REACTOR SCRAM BYPASS May direct continued power reduction to close bypass valves Sets contingency to insert manual scram if >81/2 bypass valves are open May direct WEC to pull fuses to defeat 38.5% Scram bypass May reference T.S. 3.3.1.1 BOP Monitors BOP parameters Directs FS/EO to remove service units from service Provides peer check for rod moves Event 6 Completion Criteria:

2 Bypass valves closed

-- OR --

Reactor power is 45%

-- AND/OR --

At the discretion of the Floor Instructor/Lead Evaluator.

2017-301 ILT-N-2 Page 14 of 22 Rev. 00 (05/17)

Event Seven - Loss Of High Pressure Feed / Recirc Loop Leak / Emergency Depressurization Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR:

11 At the discretion of the Lead Evaluator, activate TRIGGER 11 which cause a Recirc loop leak.

18 Verify TRIGGER 18 automatically activates when the Mode Switch is placed to S/D.

This causes a failure of aux power to fast transfer Verify TRIGGER 20 automatically activates when the Mode Switch is placed to S/D.

20 This causes a Group IV isolation.

Verify TRIGGER 22 automatically activates when Drywell pressure is >4.0 psig. This 22 increases the size of the leak.

ROLE PLAY:

EO sent to check EDG operation: wait 3 min, then report: Both EDGs are operating normally.

EO sent to cut out Cond Demin beds: wait 3 min, cutout Demin beds as needed (using instructor station), then report: Cond Demin beds cutout.

ROLE PLAY:

Acknowledge other requests; delay as necessary.

ATC Recognizes DW pressure going up CRS Assigns DW pressure as a critical parameter and directs insertion of manual scram at or before DW pressure reaching 1.5 psig May direct entry into DOA 0040-01 Directs BOP to establish max torus cooling BOP Validates DW pressure increase and investigates cause Establishes max Torus cooling per the hardcard (DOA 0040-01 action)

ATC Inserts a manual scram when DW pressure reaches contingency threshold Takes actions per DGP 02-03 BOP Announces failure of aux power to transfer Execute DGA-12 as directed.

CRS Enters DEOP 100 on RPV level less than +8 TEAM Determines/announces Drywell pressure rising more rapidly.

Determines/announces RPV level is dropping.

CRS Directs starting HPCI to maintain Level.

BOP Starts HPCI as directed.

Determines/announces HPCI isolated.

CRS Determines insufficient high pressure feed is available, then performs/directs:

Inhibiting ADS before -59 inches.

Initiating the Isolation Condenser Lining up high pressure Alternate Injection systems.

Verifying at least two low pressure injection systems available.

Waiting until RPV level drops to TAF.

Verifying any low pressure system lined up with a pump running.

2017-301 ILT-N-2 Page 15 of 22 Rev. 00 (05/17)

Event Seven - Loss Of High Pressure Feed / Recirc Loop Leak / Emergency Depressurization Trigger Position Crew Actions or Behavior BOP Inhibits ADS as directed.

CRS Enters DEOP 0200-01, Primary Containment Control, when PC/P reaches 2 psig and performs/directs:

Monitoring of PC/P.

Initiation of torus sprays before PC/P of 9 psig.

When PC/P is above 9 psig:

Verification of DSIL.

Tripping of recirc pumps.

Tripping of DW coolers.

Initiation of DW sprays.

Monitoring of DW/T. (D/W sprays may be initiated for temp control)

Monitoring of SP/T and initiation of torus cooling.

Monitors SP/L.

Verifies initiation of drywell and torus H2/O2 monitors.

BOP Performs DEOP 0200-01, Primary Containment Control, actions as directed:

Monitors PC/P and initiates torus sprays and drywell sprays per Hard Card LPCI/CCSW OPERATION, as directed.

Monitors DW/T.

Monitors SP/T and initiates torus cooling per Hard Card LPCI/CCSW OPERATION as directed.

Monitors SP/L.

Verifies initiation of drywell and torus H2/O2 monitors.

NOTE:

Above a RPV pressure of 500 psig, TAF is -170 inches on the Fuel Zone indicators.

Below 500 psig, TAF is -143 inches.

CRS Before RPV level reaches -191 inches (-209 inches corrected), enters DEOP 0400-02, Emergency Depressurization, and directs:

Initiation of Iso Condenser to maximum flow.

Verification that SP/L >6 feet.

Opening all ADS valves.

Verification all relief valves are open.

BOP Performs DEOP 0400-02, Emergency Depressurization, as directed:

Initiates Iso Condenser to maximum flow per Hard Card, ISOLATION CONDENSER.

Verifies SP/L >6 feet.

Opens all ADS valves.

Verifies all relief valves are open.

CRS Directs maximizing injection flow with minimum ECCS Pump lineups prescribed by the transient mitigation guidelines (OP-DR-103-102-1002) to the reactor when pressure drops below 350 psig until level is restored to > TAF 2017-301 ILT-N-2 Page 16 of 22 Rev. 00 (05/17)

Event Seven - Loss Of High Pressure Feed / Recirc Loop Leak / Emergency Depressurization Trigger Position Crew Actions or Behavior ATC / Maximizes injection flow with minimum ECCS Pump lineups prescribed by the BOP transient mitigation guidelines (OP-DR-103-102-1002) to the reactor when pressure drops below 350 psig to restore level to above TAF.

Event 6 / Scenario Completion Criteria:

Sprays the Drywell

Performs an Emergency Depressurization

Restores RPV level above TAF

-- AND/OR --

At the direction of the Lead Examiner 2017-301 ILT-N-2 Page 17 of 22 Rev. 00 (05/17)

SUPPORTING PROCEDURES Procedure Numbers Title DAN 902-3 B-4 ISOL CONDR VLVS OFF NORM DAN 902-3 C-4 ISOL CONDR TEMP HI DAN 902-3 F-14 RX BLDG VENT CH A RAD HI-HI DAN 902-4 A-15 ISOL CONDR CH A/B INITIATION DAN 902-5 A-3 ROD DRIFT DAN 902-7 A-5 TRUBINE CONTROL MAJOR TROUBLE DAN 902-7 B-10 STATOR CLG PP TRIP DAN 902-7 C-10 STATOR CLG PANEL TROUBLE DAN 902-7 C-3 TRUB STATOR COOLANT RUNBACK DAN 902-7 E-11 H2 SEAL OIL & ALTERREX PNL TROUBLE DAN 923-5 A-1(4) UNIT 2(3) RX BLEDG VENT/EXH FAN TRIP DAN 923-5 C-1 RX BLDG DP LO DEOP 100 RPV CONTROL DEOP 200-1 PRIMARY CONTAINMENT CONTROL DEOP 400-2 EMERGENCY DEPRESSURIZATION DGA-07 UNEXPECTED REACTIVITY CHANGE DGA-12 LOSS OF OFFSITE POWER DGP 02-03 REACTOR SCRAM DGP 03-01 POWER CHANGES DGP 03-04 CONTROL ROD MOVEMENTS DO 6700-20 480V CIRCUIT BREAKER TRIP DOA 0040-01 SLOW LEAK DOA 0300-05 INOPERABLE OR FAILED CONTROL ROD DRIVES DOA 0300-12 MISPOSITIONED CONTROL ROD 2017-301 ILT-N-2 Page 18 of 22 Rev. 00 (05/17)

Procedure Numbers Title DOA 7400-01 FAILURE OF THE STATOR COOLANT SYTEM DOA 7500-01 STANDBY GAS TREATMENT SYSTEM FAN TRIP DOP 2000-180 DRYWELL SUMP OPERATION WITH THE UNIT ON-LINE OP-DR-103-102-1002 STRATETIES FOR SUCCESSFUL TRANSIENT MITIGATION TS 3.1.3 CONTROL ROD OPERABILITY TS 3.3.2.1 CONTROL ROD BLOCK INSTRUMENTATION TS 3.3.5.2 ISOLATION CONDENSER (IC) SYSTEM INSTRUMENTATION TS 3.3.6.2 SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM TS 3.3.7.1 INSTRUMENTATION TS 3.5.3 IC SYSTEM TS 3.6.4.1 SECONDARY CONTAINMENT TS 3.6.4.2 SECONDARY CONTAINMENT ISOLATION VALVES (SCIVs)

TS 3.6.4.3 STANDBY GAS TREATMENT SYSTEM (SBGT) 2017-301 ILT-N-2 Page 19 of 22 Rev. 00 (05/17)

Critical Tasks If the RPV level trend is not reversible with an RPV injection source lined up with a pump running, initiate emergency depressurization between an RPV-1.1 RPV water level between the Top-of-Active Fuel and the Minimum Steam Cooling RPV Water Level or within 1 minute after TAF is reached, whichever is later.

When high and low pressure systems are available for RPV injection, do RPV-1.2 not stop or divert injection from the RPV until level is restored to above the Top-of-Active Fuel (TAF).

Per DEOP 100, RPV Control, with the automatic ADS timer initiated, RPV-1.5 inhibit ADS before an automatic actuation occurs.

When conditions are met per DEOP 400-2, Emergency RPV-2.1 Depressurization, the minimum number of available SRVs required for emergency depressurization (MNSRED) are opened.

While executing DEOP 200-1, Primary Containment Control, when drywell PC-1.1 pressure exceeds 9 psig and only if operating within the safe region of the drywell spray initiation limit (DSIL), initiate drywell sprays.

2017-301 ILT-N-2 Page 20 of 22 Rev. 00 (05/17)

CAEP Files:

16-1 ILT-N-2.cae

CAEP for Scenario 16-1 ILT-N-2

Written by DSS

05/17

1. 1. 1. INITIAL CONDITIONS ####

Causes the 2B Stator Cooling Pump to trip as soon as the control switch is taken to run imf t47

Overrides OFF the alarm that comes up due to the 2/3A SBGT control switch in OFF imf ser1896 off

Fails 2/3A SBGT by overriding its control switch ior vgdstbya off ior vgdprima off ior vgdstrta off

Overrides OFF the alarm that comes up due to the 2/3B SBGT control switch in OFF imf ser1910 offl2

Fails 2/3B SBGT STBY position of its control switch.

ior vgdstbyb offl2

1. 1. 1. EVENT TRIGGERS ####

Event Trigger 1 will cause Rod H-6 to drift out trgset 1 "0"l2 imf rodh06do (1)l2

Event Trigger 3 Drifts the Iso Cond Initiation setpoint.

trgset 3 "0"l4 imf icspdft (3) 0.0l4

Event Trigger 5 fails RX Bldg Vent Rad monitor upscale.

trgset 5 "0"l4 imf radrbvah (5)l4 ior vglaua06 (5) truel6

Event Trigger 7 trips the 2A Stator Cooling pump trgset 7 "0"l8 imf t50 (7)l8

Event Trigger 9 acknowledges Stator Water Cooling panel and H2 Seal Oil Panel Trouble trgset 9 "0"l14 irf t22 (9) ackl14 2017-301 ILT-N-2 Page 21 of 22 Rev. 00 (05/17)

irf t81 (9) truel14

Event Trigger 11 inserts a small Recirc leak trgset 11 "0"l8 imf f43 (11) 0.1 2:00l8

Event Trigger 16 will auto initiate to delete the drift out malfunction for Rod H-6 when Trigger 1 is active and the Emergency In is used on the RONOR switch trgset 16 "rds303em .and. et_array(1)"l4 trg 16 "dmf rodh06do"l4

Event Trigger 18 will auto trip TR-22 when the MODE switch is taken to SHUTDOWN trgset 18 "rpdmode4"l10 imf l72 (18)l10

Event Trigger 20 causes a Group IV isolation when the MODE switch is taken to SHUTDOWN trgset 20 "rpdmode4"l10 imf at46 (20) 1038.5l10

Event Trigger 22 increases the size of the Recirc leak when Drywell pressure >4.0 psig trgset 22 "ppc268 .gt. 4.0"l12 trg 22 "mmf f43 0.5 10:00 0.1"l12

1. 1. 1. End ####

2017-301 ILT-N-2 Page 22 of 22 Rev. 00 (05/17)

Dresden Generating Station 2017-301 ILT-N-3 Swap Reactor Water Cleanup Pumps 100 MWE Tso Initiated Load Reduction NBI / MR Level Inst. Fails With Partial Half Scram Main Steam / ERV Spurious Opening Swap CRD Pumps Due To Suction Filter Clogging Containment / Controller, Drywell To Torus D/P Failure FW / RFP, Secure Due To High Vibrations Emergency Depressurize On 2 Areas Above Max Safe Water Levels Due To Unisolable RWCU Leak And Flooding LPCI Corner Rooms EXAM MATERIAL Rev. 00 05/17 Developed By:

Exam Author Date Approved By:

Facility Representative Date

Scenario Outline Facility: Dresden Generating Station Scenario No.: 2017-301 ILT-N-3 Op-Test No.: 2017-301 Examiners Operators / crew position

/ ATC

/ BOP

/ CRS Initial Conditions: Unit 2 is at Full Power. No equipment is OOS, and no LCO required actions.

Unit 3 is at full power. No equipment is out of service, no evolutions in progress, no LCO required actions.

Turnover: Swap RWCU recirc pumps to allow for maintenance on 2A pump.

Maintain load per TSO direction.

Critical Tasks: RPV-2.1 - When conditions are met per DEOP 400-2, Emergency Depressurization, the minimum number of available SRVs required for emergency depressurization (MNSRED) are opened.

RPV-2.3 - After DEOP 400-2, Emergency Depressurization, has been entered, an attempt hasbeen made to open all ERVs, and less than the minimum number of available SRVs required for emergency depressurization (MNSRED) are open, alternate emergency depressurization methods are used until RPV pressure is less than the decay heat removal pressure (DHRP).

SC-1.1 - When executing DEOP 300-1, Secondary Containment Control, before any critical area(s) reach their respective maximum safe operating values with an unisolable primary system discharging into the respective area(s), manually scram the reactor.

SC-1.2 - When executing DEOP 300-1, Secondary Containment Control, when more than one critical area reaches their respective maximum safe operating values for the same parameter with an unisolable primary system discharging into the respective area(s), perform an emergency depressurization of the reactor.

Event Malf. Event Event No. No. Type* Description 1 NONE N BOP RWCU - Swap RWCU pumps 2 NONE R ATC REACTIVITY - Lower power 100 MWe using Rods and Recirc.

B15 NBI - MR level instrument fails downscale with RPS failure to 1/2 3 I/T ATC NVM100BP scram ADS3CBN 4 C/T BOP MAIN STEAM - ERV spurious opening ADS3CSD 5 SCAFILOF C ATC CRD - Swap Pumps Due To Suction Filter Clogging 6 PCVDMD14 I BOP CONTAINMENT - DW to Torus D/P controller failure.

7 SER1363 M ALL FEEDWATER - System high vibes (Manual Scram).

CIRWCUJP EMERGENCY DEPRESSURIZE - On 2 areas above max safe 8 U34 M ALL water levels due to unisolable RWC system leak and flooding U71 LPCI corner rooms.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor SCENARIO ILT-N-3 Page 2 of 27 Rev. 00 (05/17)

Scenario Objective Evaluate the Teams ability to operate the plant with an unisolable leak into the reactor building from a primary system requiring an emergency depressurization.

Scenario Summary

1. Unit is at Full Power ~100%.

2. The following equipment is OOS:

a. None

3. LCOs:

a. None Scenario Sequence

The team will Transfer RWCU Recirc pumps using DOP 1200-03 which was provided during the turnover to allow for maintenance on the 2A pump.

The TSO will call to request a 100 MWe load drop for U2 due to grid instabilities. The team will use rods and Recirc to reduce power per DGP 03-01.

Medium Range B RPV level instrument fails low. A partial half scram results requiring the Team to insert a manual half scram on the B RPS channel. The SRO will reference Tech Specs for failed level instrument and partial half scram.

The ERV 2E spuriously opens. The BOP must perform actions per DOA 0250-01, Relief Valve Failure, to close the ERV. Technical Specifications 3.4.3.A.1, 3.5.1.H.1 and 3.6.1.8 apply.

Swap CRD Pumps Due To Suction Filter Clogging.

Drywell to Torus differential pressure controller demand fails downscale. Pressure control is regained when the BOP directs an operator to open the drywell to torus differential pressure control valve bypass or vents the torus.

Action will be delayed so the DP drops to <1.0 psid requiring Tech Spec LCO entry.

High Feedwater vibrations will come in one at a time until action is taken to insert a Manual Scram and secure all Reactor feed pumps.

A RWCU system leak which cannot be isolated occurs in the RWCU pump room. Failure of the Reactor Building floor drains results in the LPCI/CS Corner Rooms filling with water. Eventually level in both LPCI/CS Corner Rooms will fill to above Max Safe levels. The Team will perform an Emergency Depressurization.

SCENARIO ILT-N-3 Page 3 of 27 Rev. 00 (05/17)

Event One - RWCU Recirc pump swap

Starts the 2B RWCU Recirc pump and secures 2A RWCU Recirc pump.

Malfunctions required: 0

(None)

Success Path:

The Team starts the 2B RWCU Recirc pump.

The Team secures the 2A RWCU Recirc pump.

Event Two - Lower power 100 MWe using Rods and Recirc

TSO calls to request 100 MWE load drop on Unit 2.

Malfunctions required: 0

(None)

Success Path:

Crew lowers power 100 MWe using the following:

Inserts Control Rods to reduce FCL to less than 93%.

Reduces Recirc Flow.

Event Three - B Med Range Level Instrument Fails Low with a Partial Half Scram

B Medium Range Level Instrument fails low and a partial half scram occurs.

Malfunctions required: 2

(Failure of Medium Range B level Instrument)

(Partial Half Scram on the B channel)

Success Path:

Manually inserts a B RPS channel half scram.

References the Tech Specs for an inoperable level instrument and the partial half scram.

Event Four - ERV Spurious Opening

ERV 2E spuriously opens.

Malfunctions required: 1

(ERV 2E spuriously opens)

Success Path:

Performs DOA 0250-01, Relief Valve Failure. Pulling the control power fuses is successful.

SCENARIO ILT-N-3 Page 4 of 27 Rev. 00 (05/17)

Event Five - Swap CRD Pumps Due To Suction Filter Clogging 2B CRD pump suction filter clogs causing the Team to swap CRD pumps, placing 2A CRD pump in service. If the operators do not swap CRD pumps in a timely manner, 2B CRD pump eventually trips.

Malfunctions required: 1

(Simulated Plugging of CRD pump suction filter and trip pump on pressure if not pumps swapped)

Success Path: 2A CRD Pump has been started and the immediate actions of DOA 300-01 are complete Event Six - Drywell to Torus Differential Pressure Controller Failure

The team recognizes and responds to a failure of the drywell to torus differential pressure controller.

Malfunctions required: 1

(Controller demand fails downscale)

Success Path:

Restores Drywell to Torus DP using any of the following:

Cycle AO 2-1601-58.

Vent the Torus.

Open the Drywell to Torus DP control valve manual bypass valve.

Event Seven - Feedwater high vibration/Reactor Scram

2A, 2B, 2C, RFP Hi Vibration alarm is received.

Feedwater Reg Station vibration Hi alarm is received.

Malfunctions required: 4

(2A RFP Hi Vibration alarm)

(2B RFP Hi Vibration alarm)

(2C RFP Hi Vibration alarm)

( Feedwater Reg Station Vibration Hi alarm)

Success Path:

Feedwater system secured and Manual Reactor Scram.

Event Eight - Unisolable RWCU System Leak / Emergency Depressurization

An unisolable leak occurs in the RWCU pump room which fills the LPCI/CS Corner Rooms to above MAX Safe water level.

Malfunctions required: 1

(RWCU system leak)

Success Path:

Performs an Emergency Depressurization.

SCENARIO ILT-N-3 Page 5 of 27 Rev. 00 (05/17)

PRE-SCENARIO ACTIVITIES 1 If applicable, conduct pre-scenario activities in accordance with TQ-AA-155-J040, SIMULATOR EXAMINATION BRIEFING.

a. Direct the crew to perform their briefs prior to entering the simulator.

b. Provide the Team a copy of DOP 1200-03, RWCU System Operation with the Reactor at Pressure.

2 Simulator Setup (the following steps can be done in any logical order)

a. Initialize simulator in an IC with Reactor power ~100%. (IC 168 used)

b. IC 168 uses control rod sequence 2.S.0.0 909D

c. Cut in/out Cond Demins as needed, to maintain DP within limits.

d. Advance the chart recorders.

e. Run the CAEP file: Pump_Sumps.cae

f. Verify Cram Sheet is correct for RWM sequence and correctly marked 3 Verify the following simulator conditions:

a. Verify 2A FWRV in Master Auto.

b. Verify 2B FWRV in Master Auto.

c. Verify 2B CRD pump running with 2A OFF.

d. Verify TR 86 LTC in AUTO.

e. Verify U2 SAC running and the U3 SAC in PTL with the U2 to U3 SA crosstie valve open

f. Verify 2A and 2/3 RBCCW pumps are running and lined up to Unit 2

g. Verify 2B RBCCW pump is secured

h. Verify 2A RWCU pump running with 2B RWCU pump secured.

i. Verify U2 and U3 RB Ventilation lineup.

NOTE: Do NOT run the initial setup CAEP file until the above setup is completed.

4 Run the initial setup CAEP file: ILT-N-3.cae 5 Place the following equipment out of service:

a. None 6 Complete the Simulator Setup Checklist.

Symbols are used throughout the text to identify specific items as indicated below:

Critical Tasks Required Actions Optional Actions SCENARIO ILT-N-3 Page 6 of 27 Rev. 00 (05/17)

Event One - RWCU Recirc pump swap Trigger Position Crew Actions or Behavior Simulator Operator:

When directed by the lead evaluator, call as the Shift Manager, and direct the team to swap RWCU recirc pumps to allow for maintenance on 2A pump.

ROLE PLAY:

If contacted as EO report:

2B RWCU pump is operating normally 2A RWCU pump is at rest.

CRS Directs BOP to swap RWCU recirc pumps per DOP 1200-03, RWCU system operation with the reactor at pressure BOP Swaps RWCU recirc pumps when directed o Slowly lower demand on RMC 2-1290-10, FLOW CONTLR, to reduce RWCU system flow to approximately 400 gpm.

o Verify closed MO 2-1201-9B, B RWCU PP DISCH, for standby pump.

o Start 2B RWCU RECIRC PP AND immediately open MO 2-1201-9B, 2B RWCU PP DISCH.

o Verify RWCU system flow and pressure are steady.

o Close MO 2-1201-9A, 2A RWCU PP DISCH o Stop 2A RWCU RECIRC PP.

o Adjust demand on RMC 2-1290-10, FLOW CONTLR, to restore proper system flow.

o Verify RWCU system flow AND pressure are steady.

Event 1 Completion Criteria:

U2 RWCU RECIRC PUMP SWAP COMPLETED

-- AND / OR --

At the discretion of the Lead Examiner SCENARIO ILT-N-3 Page 7 of 27 Rev. 00 (05/17)

Event Two - Lower Power 100 MWe Trigger Position Crew Actions or Behavior When directed by the lead evaluator, call as the TSO, and report: This is TSO, Mark Jenga. Due to unstable grid conditions execute emergency load following contingencies and immediately drop 100 MWe.

CRS Directs 100 MWe emergency power reduction per DGP 03-01, Power Changes.

May designate second verifier.

Directs ATC to insert rods.

ATC Performs the following actions per DGP 03-01, Power Changes, as directed Reduces power as follows:

Inserts control via CRAM rod insertion for 90 MWe of generator power OR 9% of APRM power.

Moves the Rod Movement Control switch to ROD IN.

Verifies ON light and proper Control Rod Timer operation.

Verifies rod settles to target position and proper response of nuclear instrumentation.

Reduces Reactor power by decreasing core flow to complete 100 MWe load drop.

BOP Monitors BOP parameters Directs FS/EO to remove service units from service Provides peer check for rod moves Event 2 Completion Criteria:

Load dropped by 100 MWe

-- AND / OR --

At the discretion of the Lead Examiner.

SCENARIO ILT-N-3 Page 8 of 27 Rev. 00 (05/17)

Event Three - B Med Range Level Instrument Fails Low with a Partial Half Scram Trigger Position Crew Actions or Behavior Simulator Operator / Role Play:

3 At the discretion of the Lead Examiner, activate TRIGGER 3, which fails B medium range downscale. The B RPS partial half scram was inserted during initial setup.

ATC Notices and reports the B Medium Range level instrument trending down.

Announces:

The partial half scram condition on the B RPS channel.

Scram Solenoid Group lights B2 and B3 did NOT extinguish.

Refers to DOA 0500-02, Partial 1/2 or Full Scram Actuation.

Depresses RPS Channel B Manual Scram pushbutton.

Acknowledges appropriate annunciators.

Simulator Operator / Role Play:

As the EO sent to the ATS Panel (wait 2 min AND the 902-4 G-20 alarm is up), then report: The B medium range level instrument MTU LIS 2-263-140B is reading full downscale and its gross failure light is lit.

As the EO sent to the MCC 28-1 circuit 15 and/or 125vdc Bus 2A-1 Dist Panel, circuit 27 (wait 3 min), then report: The breaker is NOT tripped and looks normal.

If requested to reset gross fail light then report back (after 1 minute): attempt was made and the gross fail light is still lit.

IF asked: The Yarway LI-2(3)-263-59A on the 2202-5 rack is indicating 30 inches and steady.

ATC / Refers to DAN 902-4 G-20:

BOP Dispatches an operator to inspect the Div 1 ATS panel 2202-73A Notifies the Unit Supervisor of inspection results.

CRS Announces entry into DOA 0500-02, Partial 1/2 or Full Scram Actuation and performs/directs:

Directs NSO to insert manual scram on RPS Channel B.

May refer to DOP 0010-10, Unit 2(3) Technical Specification Instrumentation Operability Manual.

References Technical Specifications and determines:

Refers to Tech Spec 3.3.1.1 and determines that RPS Channel B is INOP and that Condition A is not met and that the RPS Channel B must be placed in Trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . And condition C1 may apply.

o Directs B 1/2 scram to be put in manually.

TS 3.3.3.1 Action A1. Restore required channel to OPERABLE status within 30 days.

o May review TS 3.3.6.1 Condition A1. Place channel in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

o May review TS 3.3.6.2 Condition A1. Place channel in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Event 3 Completion Criteria:

Half Scram inserted

-- AND --

Appropriate Tech Specs referenced

-- AND / OR --

At the discretion of the Lead Examiner.

SCENARIO ILT-N-3 Page 9 of 27 Rev. 00 (05/17)

Event Four - ERV Spurious Opening Trigger Position Crew Actions or Behavior Simulator Operator / Role Play:

At the discretion of the Lead Examiner, activate TRIGGER 5, which causes E ERV to spuriously open due to an electrical failure.

5 As the EO sent to pull control power fuses for the E ERV (wait 3 min) activate TRIGGER 7, which removes control power fuses for the E ERV, then call the control room on the 7 phone and report: I have pulled the E ERV fuses.

As the QNE called to evaluate core parameters (wait 2 min) then report: core parameters are within limits.

BOP Determines/announces that E ERV is open. Performs DOA 0250-01, Relief Valve Failure, immediate actions:

Places the E ERV control switch to OFF.

ATC Verifies FWLCS has stabilized level.

CRS Enters DOA 0250-01, Relief Valve Failure, and directs actions.

May enter DOA 0040-01, SLOW LEAK BOP Determines that E ERV is still open and performs subsequent actions of DOA 0250-01:

Cycles E ERV control switch to MAN and OFF twice.

Cycles the ADS INHIBIT switch from NORMAL to INHIBIT to NORMAL several times.

Directs E ERV control power fuses pulled.

If torus temp is greater than circulating water inlet temperature, starts torus cooling as directed. (Steps listed later in this Event)

If > 95° and DEOP 0200-01, Primary Containment Control, entry is required.

Monitors Turbine Control / Bypass Valve Operation.

May check hydrogen addition operation.

May monitor torus temp per DOS 1600-20, Suppression Pool Temp Monitoring.

CRS May direct scram preparatory actions per DGP 02-03, Reactor Scram.

May enter DEOP 0200-01, Primary Containment Control, for high Torus level.

If Torus temperature reaches 95°F, then enters DEOP 0200-1, Primary Containment Control, and performs/directs:

Monitoring of PC/P Initiation of torus cooling. (May already be started per DOA 0250-01)

Monitoring of Torus level.

Verifying initiation of drywell and torus H2/O2 monitors.

ATC Performs scram preparatory actions per DGP 02-03, Reactor Scram, (if directed).

BOP Determines/announces that E ERV closed when fuses pulled.

Resets the acoustic monitor.

SCENARIO ILT-N-3 Page 10 of 27 Rev. 00 (05/17)

Event Four - ERV Spurious Opening Trigger Position Crew Actions or Behavior BOP Initiates Torus cooling per Hard Card:

Places 316A/B and 318A/B keylock switches in MANUAL OVERRD.

Verifies the third circ water pump is secured prior to starting the first CCSW pump.

IF starting torus cooling during a LOCA, THEN verifies RWCU recirc pump is tripped PRIOR to starting the first CCSW pump.

Starts one CCSW pump in each loop and verifies 3A/B valves open.

Starts at least one LPCI pump in each loop. (Starts additional LPCI pumps as required.)

Adjusts CCSW flow controller to approximately 3500 gpm for one pump; > 5000 gpm two pumps. [Maintain LPCI/CCSW dP 7 psid (1 LPCI Pump/loop) OR 20 psid (two LPCI Pumps/loop)]

Momentarily places 11A/B valve control switches to close. (IF 11A/B remain open or re-opened due to LPCI logic, then close valves as soon as possible.)

IF required, obtains Unit Supervisor permission, THEN places 317 keylock switches to MANUAL OVERRD.

Opens 21A/B and 20A/B valves in desired loop.

Throttles open 38A/B valves until > 5000 gpm per LPCI pump is established (maintains LPCI pump discharge pressure > 125 psig).

Starts additional CCSW pumps if desired:

o IF TR 86(32) LTC in MANUAL, THEN PRIOR to starting 3rd OR 4th CCSW PP, verifies voltage on applicable ECCS bus > 4000 volts, preferred target 4160V.

o (Unit 2 Only) If 2/3 EDG is loaded, then refers to DOP 1500-02 prior to starting additional pumps.

Adjusts CCSW flow controller to > 5000 gpm for two CCSW pumps [Maintain LPCI/CCSW dP 7 psid (1 LPCI Pump/loop) OR 20 psid (two LPCI Pumps/loop)].

CRS Declares E ERV inoperable.

Determines following Technical Specifications apply:

3.4.3, Safety and Relief Valves, Condition A.1: Restore the relief valve to OPERABLE status within 14 days.

3.5.1, ECCS Operating, Condition H.1: Restore the ADSV to OPERABLE status within 14 days.

3.6.1.8, Suppression Chamber-to-Drywell Vacuum Breaker, SR 3.6.1.8.2:

Perform a functional test of each required vacuum breaker within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

May refer to 3.3.6.3, A.1 Relief Valve Instrumentation.

Directs performance of Suppression Chamber-to-Drywell Vacuum Breaker testing.

TEAM May enter and perform DGA-07, Unpredicted Reactivity Addition Event 4 Completion Criteria:

The failed ERV is closed

-- AND --

Appropriate Tech Specs referenced

-- AND / OR --

At the discretion of the Lead Examiner.

SCENARIO ILT-N-3 Page 11 of 27 Rev. 00 (05/17)

Event Five - Swap CRD Pumps Due To Suction Filter Clogging Trigger Position Crew Actions or Behavior Floor Instructor / Simulator Operator / Role Play:

9 At the discretion of the Lead Examiner, activate TRIGGER 9 to cause a simulated Plugging of 2B CRD pump suction filter, and finally trip the pump on low suction pressure if the crew has not swapped the pump yet.

Verify TRIGGER 10 automatically activates when the 2B CRD pump is secured 10 to normalize alarm 902-5 D-2.

NOTE: It may take several minutes before an alarm occurs.

As the EO, if asked, wait 1 min. and then report: The 2B CRD pump suction pressure is 14 in. Hg and getting worse.

As the EO, if asked, wait 1 min. and then report: The 2B CRD pump suction filter DP is 20 psid and getting worse.

NSO may follow DOP 0300-01 and have the EO check 2A CRD pump ready to start Wait 1 min, then report: 2A CRD pump is ready to start.

ATC Announces alarms 902-5 D-2, 2B ROD DRIVE PP SUCT LO AND 902-5 F-2, ACCUMULATOR CHARGING WTR PRESS LO, and degrading CRD system parameters.

Carries out actions of DOA 0300-01, Control Rod Drive System Failure:

Starts 2A CRD pump.

Secures 2B CRD pump.

Verifies normal CRD system pressures and flow.

ROLE PLAY:

As the EO, if asked, report: The 2A CRD pump is operating and everything appears normal.

CRS Directs swapping CRD pumps per DOA 0300-01, Control Rod Drive System Failure, due to degrading operation of 2B CRD pump.

BOP Monitors panels and assists as directed.

NOTE: If the Team waits until the 2B CRD pump trips, the following actions apply.

ROLE PLAY:

As the EO, sent to Bus 24, report: The 2B CRD pump is OPEN with no targets up.

As the EO, sent to 2B CRD pump, report: I see nothing abnormal with the 2B CRD pump ATC If occurs, announces 2B CRD pump trip.

Performs actions of DAN 902-5 B-2 Rod Drive PP Trip, starts the standby CRD pump.

Takes manual control of FIC 2-340-1 CRD FLOW CONTRL (if valve has gone open).

Verifies CRD parameters return to previous values (May take FIC 2-340-1 CRD FLOW CONTRL to open/automatic, if closed previously).

SCENARIO ILT-N-3 Page 12 of 27 Rev. 00 (05/17)

Event Five - Swap CRD Pumps Due To Suction Filter Clogging Trigger Position Crew Actions or Behavior CRS Enters DOA 0300-01, Control Rod Drive System Failure, due to failure of 2B CRD pump.

Enters DOA 6500-10, 4KV Circuit Breaker Trip, due to trip of 2B CRD pump.

May reference TRM 3.3.h Reactor Vessel Water Level Instrumentation System (RVWLIS) Backfill System due to short loss of RVWLIS supply.

May direct changing CRD suction filters for 2B CRD pump Event 5 Completion Criteria:

2A CRD Pump has been started and the immediate actions of DOA 300-01 are complete,

-- AND / OR --

At the discretion of the Lead Examiner.

SCENARIO ILT-N-3 Page 13 of 27 Rev. 00 (05/17)

Event Six - Drywell to Torus Differential Pressure Controller Failure Trigger Position Crew Actions or Behavior NOTE:

After activating the Trigger to start this Event, depending on how high the DW to Torus D/P is to start with, it may take several minutes for D/P to drop enough to receive the alarm at 1.05 psid. If desired, start this event during the previous event.

SIMULATOR OPERATOR:

11 At the discretion of the Lead Examiner, activate TRIGGER 11, which causes drywell to torus differential pressure controller demand to fail downscale. (NOTE: The demand meter on the controller will appear to be operating normally, but the demand sent to the PCV is what is failed downscale)

ROLE PLAY:

EO to check PCV 2-8599-556: Wait until Drywell to Torus D/P is <1.0 psid, then report that 2-8599-556 is closed EO to check Pumpback air compressor operation (Wait 3 minutes) and report: The running pumpback air compressor is operating normally.

BOP Acknowledges and announces alarm 902-4 B-15, DW to Torus DP Hi/Lo, and performs the following:

Diagnoses that the drywell to torus differential pressure controller appears to be operating normally.

Closes AO 2-1601-58, TORUS M/U VLV.

Control Drywell to Torus dP as directed.

CRS To maintain Primary Containment pressures to those specified in DOP 1600-05, Primary Containment Inerting and Atmosphere Control, should direct performance of any of the following:

Placing the drywell torus differential pressure controller to MAN and controlling Drywell to Torus differential pressure manually; Directs controlling DW to Torus DP via the Drywell to Torus DP PCV bypass 2-8599-558.

AND / OR, venting to Reactor Building Ventilation per DOP 1600-05, Primary Containment Inerting and Atmosphere Control, to maintain the required differential pressure.

May notify Work Week Manager.

ROLE PLAY:

Chemistry for most recent Drywell sample results: Wait until Drywell to Torus D/P is <1.0 psid, then call and report The most recent Drywell sample results are one hour old and are:

Beta Gamma 7.5 x 10-10 Iodine 5.5 x 10-10 SCENARIO ILT-N-3 Page 14 of 27 Rev. 00 (05/17)

Event Six - Drywell to Torus Differential Pressure Controller Failure Trigger Position Crew Actions or Behavior BOP Performs any of the following as directed:

Places the drywell to torus differential pressure controller to MAN and observes demand appears to follow. However, DP continues to drop. (Unsuccessful)

Directs an operator to open Drywell to Torus DP PCV bypass 2-8599-558 AND / OR Vents the torus to Reactor Building Ventilation per DOP 1600-05, Primary Containment Inerting and Atmosphere Control:

Closes or verifies closed TORUS M-U VLV, AO 2-1601-58.

Verifies the DW PRESS CONTLR, PIC 2-8540-1 is in AUTO with the setpoint at approximately 1.1 psig.

At the DW/TORUS DP CONTLR, PIC 2-1602-14 reduces the auto setpoint to 0.0 psid OR places PIC 2-1602-14 in MAN with full closed demand.

Vents the torus as necessary to control drywell-to-torus DP between 1.05 to 1.3 psid (DOP 1600-01).

ATC Monitors panels and assists as directed.

ROLE PLAY:

As Plant Support called to assist, respond: I will send a team to investigate.

EO to open Drywell to Torus DP PCV bypass 2-8599-558: Wait until Drywell to Torus 13 DP drops to <1.0 psid, (Stall as necessary) then Insert TRIGGER 13 to open 2-8599-558 10%.

NOTE:

The following Tech Spec applies only if Drywell to Torus DP drops below 1.0 psid.

CRS Determines following Technical Specifications apply if drywell to Torus DP drops below 1.0 psid.:

TS 3.6.2.5.A.1: Restore differential pressure to within limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Event 6 Completion Criteria:

Drywell to Torus DP restored and TS addressed

-- AND / OR --

At the direction of the Lead Examiner SCENARIO ILT-N-3 Page 15 of 27 Rev. 00 (05/17)

Event Seven - Feedwater system high vibrations (Manual Scram)

Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR:

At the discretion of the Lead Examiner, simulate a Feedwater System high vibration by performing the following:

RUN CAEP file 2017-301 ILT-N-3 SUPPLEMENTAL.cae, which causes CAEP Feedwater System parameters to oscillate by varying MO 3206A & B valve positions.

When the Team secures the RFPs, PAUSE AND EXIT CAEP 2017-301 ILT-N-3 SUPPLEMENTAL.cae which stops varying MO 3206A & B valve positions to stop the Feedwater System high vibration.

ROLE PLAY:

If RFPs are running:

As the EO sent to Feedwater Regulating Valve station: (wait 2 min) then report:

Feedwater Regulating Valve pipes are swinging.

As the EO sent to Feedwater Pump room: (wait 2 min) then report: Feedwater System pipes are swinging outside the RFP room.

If RFPs are secured:

Report there is insulation on the floor and a large amount of dust in the air. There is no evidence of a leak.

ATC / Announces following alarms and refers to DANS:

BOP

902-6 E-12, FEEDWATER REG STATION VIBRATION HI.

902-6 F-12, 2A RFP VIBRATION HI.

CRS Enters DOA 3200-01, Feedwater System High Vibration, and directs actions.

ATC / Observes and announces Feedwater parameters are swinging.

BOP Dispatches EO to check Feedwater System.

CRS May direct scram preparatory actions per DGP 02-03, Reactor Scram.

ATC / Performs scram preparatory actions per DGP 02-03, Reactor Scram, as directed.

BOP o Reduces FCL to <93% by inserting control rods.

o Reduce Recirc flow to 56 Mlbm/hr core flow.

o Start the motor suction pump AND turning gear oil pump.

o Trip hydrogen addition.

CRS Directs manual scram per DGP 02-03, Reactor Scram.

Tripping RFPs when DOA 3200-01 requirements met.

ATC / Performs manual scram per DGP 02-03, Reactor Scram.

BOP Trips RFPs when RPV time/level directions of DOA 3200-01 are met.

SCENARIO ILT-N-3 Page 16 of 27 Rev. 00 (05/17)

Event Seven - Feedwater system high vibrations (Manual Scram)

Trigger Position Crew Actions or Behavior TEAM Performs the following actions per DGP 02-03, Reactor Scram, and DEOP 100, RPV Control, as directed:

Depresses BOTH Scram buttons.

Places RX MODE SW in SHUTDOWN.

Verifies Recirc pumps run back to minimum.

Inserts SRMs and IRMs.

Controls reactor water level +8 to +48 inches or as directed by the Unit Supervisor.

Controls RPV/P <1060 psig using the Iso Cond and/or bypass valves Verifies turbine tripped.

Verifies generator tripped.

Verifies aux power transfers.

CRS Enters DEOP 100, RPV Control, Directs actions of DEOP 100.

Directs actions of DGP 02-03.

Maintaining RPV/P <1060 psig using the Isolation Condenser and/or bypass valves Maintaining RPV/L +8 to +48 using CRD, HPCI and/or closing MSIVs.

Event 7 Completion Criteria:

Reactor scrammed,

-- AND / OR --

At the direction of the Lead Examiner.

SCENARIO ILT-N-3 Page 17 of 27 Rev. 00 (05/17)

Events Eight - Unisolable RWCU System Leak / Emergency Depressurization Trigger Position Crew Actions or Behavior SIMULATOR OPERATOR:

15 At the discretion of the Lead Examiner, activate TRIGGER 15 which causes a leak from the RWCU system in the pump room.

NOTE: DO NOT SILENCE COMMON PANEL ALARMS AFTER LEAK IS INSERTED.

ROLE PLAY:

As a dispatched EO OR as an EO on rounds, (wait 2 min. after the leak starts) then report over the radio: There is a large amount of steam and water running from the RWCU pump room. The water is flowing down the stairs to the Reactor Building 1st floor.

The floor drains appear to be plugged up.

As a dispatched EO OR as an EO on rounds, wait until the LPCI/CS corner room sump alarms are up, and then report water is accumulating on the floor in both corner rooms.

At the discretion of the Lead Evaluator, report as the EO that both corner room water levels have reached the DEOP 8 in. lines on the wall.

As the EO sent to install control power fuses for the E ERV (wait 2 min) activate 17 TRIGGER 17, which installs control power fuses for the E ERV, then call the control room on the phone and report: I have installed the E ERV fuses.

BOP Announces alarms due to the RWCU leak:

O 902-4 C-19, LPCI/CS EAST SUMP LEVEL HI.

O 902-4 D-19, LPCI/CS WEST SUMP LEVEL HI.

O 923-4 A-3, U2 E RBFD SUMP LVL HI HI.

O 923-4 B-2, U2 W RBFD SUMP LVL HI HI.

Dispatches EO(s) to check areas for leaks.

Announces that the RWCU system has indication of flow.

Determines PCIS GRP III Isolation Failed to Occur Attempts to complete the isolation Closes MSIVs for inventory control (if directed)

CRS Enters DEOP 0300-01 Secondary Containment Control, when informed a LPCI/CS Corner room water level is above 0 in.

May direct cooldown to lower RPV pressure in efforts to mitigate leakage rate May anticipate Blowdown IAW DEOP 100 May direct closing MSIVs for inventory control May direct operator briefed and standing by to re-install 2E ERV fuses.

BOP Directs equipment operator to report if the corner room levels reach the DEOP lines on the wall.

Ensures all sump pumps are operating Attempts to restart RB Vent (if RB exhaust rad is below 4 mr/hr)

CRS When notified of 2 or more areas above Max Safe (water level), enters DEOP 0400-02, Emergency Depressurization, and directs:

Verifying all rods in to at least position 04.

Drywell Pressure < 2.0 psig.

Verifying SP/L >6 feet.

Verifying all available ADS valves are open. (only 4 will open due to fuses removed from previous event)

Complete Emergency Depressurization actions by one of the following:

o Direct ERV fuses to be re-installed to open all 5 ADS valves.

o Execute alternate emergency depressurization methods (DEOP 0400-02 Fig O)

SCENARIO ILT-N-3 Page 18 of 27 Rev. 00 (05/17)

Events Eight - Unisolable RWCU System Leak / Emergency Depressurization Trigger Position Crew Actions or Behavior BOP Executes DEOP 0400-02, Emergency Depressurization, as directed:

Verifies SP/L >6 feet.

Opens all ADS valves.

Verifies all AVAILABLE ADS valves are open Reports 4 ERVs are open Events 8 / Scenario Completion Criteria:

Emergency Depressurization in progress,

-- AND / OR --

At the direction of the Lead Examiner.

SCENARIO ILT-N-3 Page 19 of 27 Rev. 00 (05/17)

PROCEDURE TITLE DAN 902-3 C-12 HPCI STM LINE FLOW HI DAN 902-4 B-15 DW TO TORUS DP HI/LO DAN 902-4 C(D)-19 LPCI/CS EAST (WEST) SUMP LEVEL HI DAN 902-5 D-2 2B ROD DRIVE PP SUCT LO DAN 902-5 F-2 ACCUMULATOR CHARGING WTR PRESS LO DAN 902-6 H-3 FW CONTROL SYSTEM PANEL TROUBLE DAN 923-1 C-3 SW Pump Trip DAN 923-1 G-4 2/3 DIESEL FIRE PP RUNNING DAN 923-1 F-4 U2 INST AIR PRESS LOW DAN 923-4 A-3(B-2) U2 E(W) RBFD SUMP LVL HI HI.

DEOP 0100 RPV CONTROL DEOP 0300-01 SECONDARY CONTAINMENT CONTROL DEOP 0400-02 EMERGENCY DEPRESSURIZATION DGP 02-03 REACTOR SCRAM DOA 0300-01 CONTROL ROD DRIVE SYSTEM FAILURE DOA 0600-01 TRANSIENT LEVEL CONTROL DOA 3800-01 LOSS OF TURBINE BUILDING CLOSED COOLING WATER DOA 4700-01 INSTRUMENT AIR SYSTEM FAILURE DOA 6500-10 4KV CIRCUIT BREAKER TRIP DOP 0300-01 CONTROL ROD DRIVE SYSTEM START UP AND OPERATION DOP 0600-06 FEEDWATER REGULATING VALVE (FWRV) OPERATION DOP 1600-05 PRIMARY CONTAINMENT INERTING AND ATMOSPHERE CONTROL DOP 4700-03 U2/3 IA CROSS-CONNECT OPERATION TRM 3.3.h REACTOR VESSEL WATER LEVEL INSTRUMENTATION SYSTEM (RVWLIS)

BACKFILL SYSTEM TRM 3.6.c DRYWELL-TO-SUPPRESSION CHAMBER DIFFERENTIAL PRESSURE TS 3.3.6.1 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TS 3.5.1 ECCS - OPERATING TS 3.6.2.5 DRYWELL TO SUPPRESSION CHAMBER DIFFERENTIAL PRESSURE DOP 1200-02 RWCU SYSTEM OPERATION WITH THE REACTOR AT PRESSURE DGP 03-01 POWER CHANGES DGP 03-04 CONTROL ROD MOVEMENTS DOP 0400-01 REACTOR MANUAL CONTROL SYSTEM DAN 902-4 G-20 ANALOG TRIP SYS DIV 1 2202-73A TROUBLE ANALOG TRIP SYS DIV 1 2203-73A TROUBLE DOA 0500-02 PARTIAL 1/2 OR FULL SCRAM ACTUATION TS 3.3.1.1 REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION SCENARIO ILT-N-3 Page 20 of 27 Rev. 00 (05/17)

PROCEDURE TITLE TS 3.3.6.1 PRIMARY CONTAINMENT ISOLATION SYSTEM INSTRUMENTATION TS 3.3.6.2 SECONDARY CONTAINMENT ISOLATION SYSTEM INSTRUMENTATION TS 3.4.3 SAFETY AND RELIEF VALVES TS 3.5.1 ECCS OPERATING TS 3.6.1.8 SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKERS TS 3.3.6.3 RELIEF VALVE INSTRUMENTATION DOP 0010-10 UNIT 2(3) TECHNICAL SPECIFICATION INSTRUMENTATION OPERBILITY MANUA DOA 0250-01 RELIEF VALVE FAILURE DEOP 200-1 PRIMARY CONTAINMENT CONTROL DOS 1600-20 SUPPRESSION POOL TEMP MONITORING DGP 02-03 REACTOR SCRAM DGA-07 UNEXPECTED REACTIVITY CHANGE DOA 6500-10 4KV CIRCUIT BREAKER TRIP DAN 902-4 B-15 DW TO TORUS DP HI/LO DOP 1600-05 PRIMARY CONTAINMENT INERTING AND ATMOSPHERE CONTROL TS 3.6.2.5 DRYWELL TO SUPPRESSION CHAMBER DIFFERENTIAL PRESSURE TRM 3.6.c DRYWELL TO SUPPRESSION CHAMBER DIFFERENTIAL PRESSURE DAN 902-6 E-12 FEEDWATER REG STATION VIBRATION HI DAN 902-6 F-12 2A RFP VIBRATION HI DOA 3200-01 FEEDWATER SYSTEM HIGH VIBRATION DEOP 100 RPV CONTROL DEOP 0300-1 SECONDARY CONTAINMENT CONTROL DEOP 400-2 EMERGENCY DEPERESSURIZATION DAN 902-4 C-19 LPCI/CS EAST SUMP LEVEL HI DAN 902-4 d-19 LPCI/CS WEST SUMP LEVEL HI DAN 923-4 A-3 U2 E RBFD SUMP LVL HI HI DAN 923-4 B-2 U2 W RBFD SUMP LVL HI HI SCENARIO ILT-N-3 Page 21 of 27 Rev. 00 (05/17)

Critical Tasks When conditions are met per DEOP 400-2, Emergency Depressurization, the RPV-2.1 minimum number of available SRVs required for emergency depressurization (MNSRED) are opened.

When executing DEOP 300-1, Secondary Containment Control, when more than one critical area reaches their respective maximum safe operating values SC-1.2 for the same parameter with an unisolable primary system discharging into the respective area(s), perform an emergency depressurization of the reactor.

After DEOP 400-2, Emergency Depressurization, has been entered, an attempt has been made to open all ERVs, and less than the minimum number of available SRVs required for emergency depressurization RPV-2.3 (MNSRED) are open, alternate emergency depressurization methods are used until RPV pressure is less than the decay heat removal pressure (DHRP).

SCENARIO ILT-N-3 Page 22 of 27 Rev. 00 (05/17)

ILT N-3.cae

ILT 16-1 NRC Exam Scernario 3

Written by DSS

06/17

1. 1. 1. Initial Conditions #####

Inserts a RPS Channel B partial half scram imf b15

Sets E ERV binding malfunction to 25%

imf ads3ebn 25

Defeats RWCU isolations and overrides MO 2-1201-1 and 2 control switches to OFF imf cirwcuap imf cirwcubp ior rtdcl1 off ior rtdcl2 offl2

Opens the U2 to U3 Service Air Cross-tie valve irf vpc 100l2

1. 1. 1. EVENT TRIGGERS ####

Event Trigger 3 fails B medium range level instrument downscale over 4 minutes trgset 3 "0"l2 imf nvm100bp (3) -120.0 4:00l2

Event Trigger 5 causes the E ERV setpoint to drift to fail it open trgset 5 "0"l4 imf ads3esd (5) 75.0l4

Event trigger 7 deletes E ERV binding malfunction so valve will close and removes fuses for E ERV trgset 7 "0"l4 trg 7 "dmf ads3ebn"l4 irf adsrfe (7) pulledl6

Event trigger 9 drives up the 902-5 D-2 alarm and isolates 2B CRD tripping 2B CRD Pump on low suction pressure trgset 9 "0"l6 imf ser0945 (9) onl6 irf rdfiltb (9 3:00) falsel6

Event Trigger 10 normalizes the 902-5 D-2 Alarm after the 2B CRD is off trgset 10 "hwrdlpmpg(2)"l8 trg 10 "mmf ser0945 normal"l8

Event Trigger 11 fails drywell to torus DP controller demand downscale.

trgset 11 "0"l8 irf p33 (11) falsel8 irf p37 (11) truel10 ior pcvdmd14 (11) 0.0l10

Event Trigger 13 opens 2-8599-558 10%

trgset 13 "0"l10 irf pp3 (13) 10l10

Event Trigger 15 Starts a RWCU leak from the Main Pump suction.

Opens the RWCU PCV bypass to maintain flow if the PCV is closed.

Overrides RWCU DRN FLOW CONTLR RMC 2-1290-14 pot to 0.0

After 3 min, drives up alarm 902-4 D-19, LPCI/CS West Sump Level Hi.

SCENARIO ILT-N-3 Page 23 of 27 Rev. 00 (05/17)

After 5 min, drives up alarm 902-4 C-19, LPCI/CS East Sump Level Hi.

trgset 15 "0"l12 imf u34 (15) 10.0 1:00l12 irf u71 (15) 3.0 1:00l12 ior rtwmn14 (15) 0.0l12 imf ser0557 (15 3:00) onl14 imf ser0555 (15 5:00) onl14

Event trigger 17 installs fuses for E ERV trgset 17 "0"l14 trg 17 "irf adsrfe in"l14 ior add303ea (17) autol16

Event Trigger 19 automatically activates when Trigger 17 is activated to make the E ERV open trgset 19 "et_array(17)"l16 trg 19 "imf ads3esd 75.0"l16

1. 1. 1. End ####

ILT-N-3 SUPPLEMENTAL.cae

Revised by DSS

05/17

The following drives up the following vibration alarms:

2A RFP after 40 seconds

FRWV Station after 60 seconds

2B RFP after 65 seconds

2C RFP after 75 seconds imf ser1363 onl40 imf ser1361 onl60 imf ser1397 onl65 imf ser1399 onl75

The following cycles MO 3206A & B valve positions to simulate FW Sys Hi Vibes.

set fwv3206a(1) = 0.4 set fwv3206a(2) = 0.4 set fwv3206a(1) = 0.6l3 set fwv3206a(2) = 0.6l3 set fwv3206a(1) = 0.4l6 set fwv3206a(2) = 0.4l6 set fwv3206a(1) = 0.6l9 set fwv3206a(2) = 0.6l9 set fwv3206a(1) = 0.4l12 set fwv3206a(2) = 0.4l12 set fwv3206a(1) = 0.6l15 set fwv3206a(2) = 0.6l15 set fwv3206a(1) = 0.4l18 set fwv3206a(2) = 0.4l18 set fwv3206a(1) = 0.6l21 set fwv3206a(2) = 0.6l21 set fwv3206a(1) = 0.4l24 SCENARIO ILT-N-3 Page 24 of 27 Rev. 00 (05/17)

set fwv3206a(2) = 0.4l24 set fwv3206a(1) = 0.6l27 set fwv3206a(2) = 0.6l27 set fwv3206a(1) = 0.4l30 set fwv3206a(2) = 0.4l30 set fwv3206a(1) = 0.6l33 set fwv3206a(2) = 0.6l33 set fwv3206a(1) = 0.4l36 set fwv3206a(2) = 0.4l36 set fwv3206a(1) = 0.6l39 set fwv3206a(2) = 0.6l39 set fwv3206a(1) = 0.4l42 set fwv3206a(2) = 0.4l42 set fwv3206a(1) = 0.6l45 set fwv3206a(2) = 0.6l45 set fwv3206a(1) = 0.4l48 set fwv3206a(2) = 0.4l48 set fwv3206a(1) = 0.6l51 set fwv3206a(2) = 0.6l51 set fwv3206a(1) = 0.4l54 set fwv3206a(2) = 0.4l54 set fwv3206a(1) = 0.6l57 set fwv3206a(2) = 0.6l57 set fwv3206a(1) = 0.4l60 set fwv3206a(2) = 0.4l60 set fwv3206a(1) = 0.65l63 set fwv3206a(2) = 0.65l63 set fwv3206a(1) = 0.25l66 set fwv3206a(2) = 0.25l66 set fwv3206a(1) = 0.65l69 set fwv3206a(2) = 0.65l69 set fwv3206a(1) = 0.25l72 set fwv3206a(2) = 0.25l72 set fwv3206a(1) = 0.65l75 set fwv3206a(2) = 0.65l75 set fwv3206a(1) = 0.25l78 set fwv3206a(2) = 0.25l78 set fwv3206a(1) = 0.65l81 set fwv3206a(2) = 0.65l81 set fwv3206a(1) = 0.25l84 set fwv3206a(2) = 0.25l84 set fwv3206a(1) = 0.65l87 set fwv3206a(2) = 0.65l87 set fwv3206a(1) = 0.25l90 set fwv3206a(2) = 0.25l90 set fwv3206a(1) = 0.65l93 set fwv3206a(2) = 0.65l93 set fwv3206a(1) = 0.25l96 set fwv3206a(2) = 0.25l96 SCENARIO ILT-N-3 Page 25 of 27 Rev. 00 (05/17)

set fwv3206a(1) = 0.65l99 set fwv3206a(2) = 0.65l99 set fwv3206a(1) = 0.25l102 set fwv3206a(2) = 0.25l102 set fwv3206a(1) = 0.65l105 set fwv3206a(2) = 0.65l105 set fwv3206a(1) = 0.25l108 set fwv3206a(2) = 0.25l108 set fwv3206a(1) = 0.65l111 set fwv3206a(2) = 0.65l111 set fwv3206a(1) = 0.25l114 set fwv3206a(2) = 0.25l114 set fwv3206a(1) = 0.65l117 set fwv3206a(2) = 0.65l117 set fwv3206a(1) = 0.25l120 set fwv3206a(2) = 0.25l120 set fwv3206a(1) = 0.7l123 set fwv3206a(2) = 0.7l123 set fwv3206a(1) = 0.3l126 set fwv3206a(2) = 0.3l126 set fwv3206a(1) = 0.7l129 set fwv3206a(2) = 0.7l129 set fwv3206a(1) = 0.3l132 set fwv3206a(2) = 0.3l132 set fwv3206a(1) = 0.7l135 set fwv3206a(2) = 0.7l135 set fwv3206a(1) = 0.3l138 set fwv3206a(2) = 0.3l138 set fwv3206a(1) = 0.7l141 set fwv3206a(2) = 0.7l141 set fwv3206a(1) = 0.3l144 set fwv3206a(2) = 0.3l144 set fwv3206a(1) = 0.7l147 set fwv3206a(2) = 0.7l147 set fwv3206a(1) = 0.3l150 set fwv3206a(2) = 0.3l150 set fwv3206a(1) = 0.7l153 set fwv3206a(2) = 0.7l153 set fwv3206a(1) = 0.3l156 set fwv3206a(2) = 0.3l156 set fwv3206a(1) = 0.7l159 set fwv3206a(2) = 0.7l159 set fwv3206a(1) = 0.3l162 set fwv3206a(2) = 0.3l162 set fwv3206a(1) = 0.7l165 set fwv3206a(2) = 0.7l165 set fwv3206a(1) = 0.3l168 set fwv3206a(2) = 0.3l168 set fwv3206a(1) = 0.7l171 SCENARIO ILT-N-3 Page 26 of 27 Rev. 00 (05/17)

set fwv3206a(2) = 0.7l171 set fwv3206a(1) = 0.25l174 set fwv3206a(2) = 0.25l174 set fwv3206a(1) = 0.75l177 set fwv3206a(2) = 0.75l177 set fwv3206a(1) = 0.25l180 set fwv3206a(2) = 0.25l180 set fwv3206a(1) = 0.75l183 set fwv3206a(2) = 0.75l183 set fwv3206a(1) = 0.25l186 set fwv3206a(2) = 0.25l186 set fwv3206a(1) = 0.75l189 set fwv3206a(2) = 0.75l189 set fwv3206a(1) = 0.25l192 set fwv3206a(2) = 0.25l192 set fwv3206a(1) = 0.75l195 set fwv3206a(2) = 0.75l195 set fwv3206a(1) = 0.25l198 set fwv3206a(2) = 0.25l198 set fwv3206a(1) = 0.75l201 set fwv3206a(2) = 0.75l201 set fwv3206a(1) = 0.25l204 set fwv3206a(2) = 0.25l204 set fwv3206a(1) = 0.75l207 set fwv3206a(2) = 0.75l207 set fwv3206a(1) = 0.25l210 set fwv3206a(2) = 0.25l210 set fwv3206a(1) = 0.75l213 set fwv3206a(2) = 0.75l213 set fwv3206a(1) = 0.25l216 set fwv3206a(2) = 0.25l216 set fwv3206a(1) = 0.75l219 set fwv3206a(2) = 0.75l219

1. 1. 1. END ####

SCENARIO ILT-N-3 Page 27 of 27 Rev. 00 (05/17)

ML17271A106

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