Text

Exam Final Items 2B - Delay Release
	ML17181A395
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Site:	Brunswick
Issue date:	06/30/2017
From:	; Duke Energy Corp
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DUKE ENERGY. Run 1 BRUNSWICK TRAINING SECTION OPERATIONS TRAINING INITIAL LICENSED OPERATOR SIMULATOR EVALUATION GUIDE 2016 NRC SCENARIO 2 LOWER POWER, REMOVE 230KV LINE FROM SERVICE, ROD DRIFT, ADHR PP TRIP, RECIRC LOOP FLOW FAILURE, HDD PP TRIP, ATWS, SLC MODE SWITCH FAILURE, ARI FAIL TO RESET REVISION 0 Developer: Date: e7/t7/2O!6 Technical Review: Va% Date: 91/2120/6 Validators: Date: 09/06/16 4a Te Facility Representative: tâe Date: 09/221/6

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 2 of 80 REVISION

SUMMARY

o Scenario developed for 2016 NRC Exam.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev.0 Page 3 of 80 TABLE OF CONTENTS 1.0 SCENARIO OUTLINE 4 2.0 SCENARIO DESCRIPTION

SUMMARY

5 3.0 CREW CRITICAL TASKS 6 4.0 TERMINATION CRITERIA 6 5.0 IMPLEMENTING REFERENCES 7 6.0 SETUP INSTRUCTIONS 8 7.0 INTERVENTIONS 10 8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES 12 ATTACHMENT 1 - Scenario Quantitative Attribute Assessment 49 ATTACHMENT 2 Shift Turnover 80

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 L Page4of8o 1.0 SCENARIO OUTLINE Event MaIf. No. Type* Event Description 1 R ATC

- Lower power to 850 MWe to remove 230 kV Line 30 2 N - BOP Remove 230 kV Line 30 from service RDOOIM C-ATC RodDrift 3 (26-11)

C CRS (TS)

K4526A C BOP

- ADHR Secondary pump trip 4

C-CRS (AOP)

C ATC

- Recirc Loop B Flow transmitter Failure 5

C-CRS (TS)

CFO89F C BOP

- Heater Drain Deaerator Pump Trip 6

C-CRS (AOP)

Small steam leak in DW results in an ATWS requiring 7 CAOO8F M terminate and prevent actions (RSP)(ATWS) 8 K2119A C SLC Mode Switch Failure 9 K2624A C Alternate Rod Insertion reset failure

(N)ormal (R)eactivity, (C)omponent or Instrument, (M)ajor

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev.0 1 Page 5of80 2.0 SCENARIO DESCRIPTION

SUMMARY

Event Description 1 After taking the watch the CRS will direct power reduced to 850 MWe.

2 The BOP will isolate 230 kV Line 30.

Control Rod 26-1 1 will start to drift in. The crew will enter OAOP-02.0 and take action lAW 2APP-A-05 (3-2). When the high temperature alarm is received Engineering will 3 report that scram times cannot be assured based on past history of the control rod.

Determine TS 3.1.3 condition Cl to insert the control rod in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and C2 to disarm the control rod within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

After Tech Specs are addressed the Alternate Decay Heat Removal (ADHR)

Seconday pump will trip. AOP-38.0 will be entered The Recirc Loop B flow transmitter to APRM Channel 4 will fail wiscale resulting in a rod block and a trip input to each voter. The crew will respond per APPs and bypass 5 APRM 4. The APRM will be declared Inoperable perTS 3.3.1.1, Condition A and placed in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . APRM TS Actions to be taken requires the APRM mode selector switch to be place in INOP lAW 001-18 A motor overload will occur on Heater Drain Pump 2A. The crew will reference APP

. 6 UA-06 1-7, Bus 2D 4KV Motor Ovid and determine which pump has the overload condition. The crew should start HDP 2C and secure HDP 2A. The crew may reference AOP-23.0.

A small steam leak in the DW results in rising Drywell pressure requiring a reactor 7 scram. An ATWS will occur, conditions will require terminate and prevent actions to be performed.

When SLC is initiated, the mode switch will fail and the pumps will not start. LEP-03 8

will be executed to inject the boron into the core.

Alternate Rod Insertion (ARI) will not reset, the crew will perform LEP-02 to drive 9 control rods into the core. When level is stabilized after terminating and preventing ARI will be repaired to allow the rods to be manually scrammed.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 6 of 80 3.0 CREW CRITICAL TASKS Critical Task #1 Prevent the automatic actuation of ADS (LL3) to prevent low pressure ECCS injection to the reactor.

Critical Task #2 Reduce reactor power/pressure to prevent exceeding Heat Capacity Temperature Limit (HCTL) 220

..i....r i1.1tt1iIi 210 4 - -- - UNSAFE ABOVE U

0 Lj SELECTED LINE w

200 zi:ETzJ 1.

190 D f::

180 Lii a 170 :L. f-) 025 FT

(-)1.2SFT U 160 %%

I. . :-

(-) 2.50 FT 150 f-)3.25 FT 140 j SAFE BELOW (- ) 4.25 FT 130 ELECTED LINE

(-)5.5OFT 120 4.-

110 : -

100

..+/- 1 1,150 100 300 500 700 900 1,100 0 200 400 600 800 1,000 RPV PRESSURE (PSIG) 4.0 TERMINATION CRITERIA When all rods are inserted and level is being controlled above TAF the scenario may be terminated.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page_7_of 80 5.0 IMPLEMENTING REFERENCES NOTE: Refer to the most current revision of each Implementing Reference.

Number Title A-05, 3-2 ROD DRIFT OAOP-02.0 CONTROL ROD MALFUNCTION/MISPOSITION UA-18, 6-1 BUS E4 4KV MOTOR OVLD.

UA-01, 2-3 ADHR PRIMARY LOOP TROUBLE UA-01, 3-3 ADHR SECONDARY LOOP TROUBLE OAOP-38.O LOSS OF FUEL POOL COOLING A-06, 2-8 APRM UPSCALE A-06, 3-8 APRM UPSCALE TRIP/INOP A-06, 5-7 FLOW REF OFF NORMAL A-05, 2-2 ROD OUT BLOCK A-05, 4-8 OPRM TRIP ENABLED UA-5, 3-5 SBGT SYS B FAILURE UA-5, 4-6 SBGT SYS A FAILURE

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 8 of 80 6.0 SETUP INSTRUCTIONS list for

1. PERFORM TAP-409, Miscellaneous Simulator Training Guidelines, Attachment 5, Check Simulator Exam Security.

2. RESET the Simulator to IC-il.

3. ENSURE the RWM is set up as required for the selected IC.

4. ENSURE appropriate keys have blanks in switches.

5. RESET alarms on SJAE, MSL, and RWM NUMACs.

6. ENSURE no rods are bypassed in the RWM.

7. PLACE all SPDS displays to the Critical Plant Variable display (#100).

8. ENSURE hard cards and flow charts are cleaned up

9. TAKE the SIMULATOR OUT OF FREEZE

10. LOAD Scenario File.

II. ALIGN the plant as follows:

Manipulation Ensure 20 TCC pump is in service on Unit One.

Bypass APRM 2 RCC Pump D in service for ADHR RCC Pump A in service for RBCCW

12. IF desired, take a SNAPSHOT and save into an available IC for later use.

13. PLACE a clearance on the following equipment.

Component Position APRM 2 Blue tag

14. INSTALL Protected Equipment sign age and UPDATE RTGB placard as follows:

Protected Equipment

1. 2A and 2B NSW pumps

2. 2A FPC Pump/Hx, 2D ROC Pump, and 20 Demin Transfer Pump.

2016 NRC SCENARIO 2 LOt SIMULATOR EVALUATION GUIDE Rev. 0 Page 9 of 80

15. VERIFY OENP 24.5 Form 2 (Immediate Power Reduction Form) for IC-Il is in place.

16. ENSURE each Implementing References listed in Section 7 is intact and free of marks.

17. ENSURE all materials in the table below are in place and marked-up to the step identified.

Required Materials Marked up of 20P-50, Section 6.2.6

18. ADVANCE the recorders to prevent examinees from seeing relevant scenario details.

19. PROVIDE Shift Briefing sheet for the CRS.

20. VERIFY all actions contained in TAP-409, Miscellaneous Simulator Training Guidelines, Attachment 4, Simulator Training Instructor Checklist, are complete.

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page lOof8O 7.0 INTERVENTIONS TRIGGERS Trig Type ID 1 Malfunction RD0O1M [CONTROL ROD SLOW INSERTION DRIFT]

2 j Annunciator ZA512 [CRD HYD TEMP HIGH]

3 Trigger Command MFD:RD001M,26-11 4 Remote Function RD_RDELDIS [ELECTRICAL DISARM OF ROD]

5 DI Override K4526A [RBCCW PMP D AUTO]

5 DO Override Q4526AMW [RBCCW PMP D ADHR MODE]

5 DO Override Q4526LG4 [RBCCW PMP D OFF GJ Malfunction RPO11F [ATWS 4]

6 Remote Function CC_MODE [RBCCW/ADHR VALVE LINEUPS]

6 Remote Function CCMSS [RBCCW/ADHR PUMP MODE SELECTOR SWITCH]

7 Remote Function CC_PDV [RBCCW PUMP DISCHARGE VALVE]

8 Malfunction N1063F [RECIRC LOOP B XMIUER FAILURE]

9 Malfunction CF089F [HEATER DRAIN PUMP MOTOR WINDING FAULT]

10 Malfunction NBOO6F [MSL BRK BEFORE FLOW RESIRICTORJ 11 Remote Function EP_IAEOPJP - [BYPASS LL-3 GROUP I ISOL (SEP-10)]

Trig # Trigger Text 3 KM118EDN - [SCRAM TEST SWITCH 26-11] true deletes RDOO1M ANNUNCIATORS Override OVal AVaI Actime Dactime Trig Window Description Tagname 1-2 CRD HYD TEMP HIGH ZA512 ON ON OFF 2

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 11 of 80 MALFUNCTIONS taif Mult CUrreflt Thret Actime Dactime Trig Description CONTROL ROD SLOW INSERTION 1 RDOO1M 26-11 False True N1063F APRM 4 RECIRC LOOP B XMIUER FAILURE 0.00 125.00 8 NBOO6F A MSL BRK BEFORE FLOW RESTRICTOR 0.00 1.Oe-1 0:03:00 10 HEATER DRAIN PUMP MOTOR 9 CFO89F A False True WINDING FAULT RPO11F ATWS 4 False True 5 RPO0SF AUTO SCRAM DEFEAT True True NIO32F APRM 2 APRM FAILS LO ] True True REMOTES CUITeflt ThTt Actime Trig Remf Id Mult Id Description RD_RDELDIS 26-11 ELECTRICAL. DISARM OF ROD ARM DISARM 4 6

CC_MODE PUMP-A

[ RBCCW/ADHR VALVE LINEUPS RBCCW/ADHR PUMP MODE RBCCW ADHR CC MSS A RBCCW ADHR 6 SELECTOR SWITCH CC_PDV A_V38_V5114 RBCCW PUMP DISCHARGE VALVE 1.0000 1.Oe-01 7 CC_IACW4518 2CTBCCW PUMP UNIT ALIGNMENT 1 1 EP_IAEOP]P1 BYPASS LL-3 GROUP I SOC (SEP-10) OFF ON 11 PANEL OVERRIDES Position I Actual Override Actime Dactime Trig Tag ID Description K4526A RBCCW PUMP D OFF OFF/RESEST OFF ON 5 K4526A RBCCW PMP D AUTO AUTO OFF OFF 5 K4526A RBCCW PMP 0 ON ON ON OFF 5 Q4526LG4 RBCCW PMP D OFF G ON/OFF OFF OFF 5 Q4526AMW RBCCW PMP D ADHR MODE ON/OFF ON OFF 5 K2119A S/B LIQ PUMP A & B_______ PUMP_A OFF OFF K2119A S/BLIQPUMPA&B PUMP_A&B OFF OFF K2119A S/B CIQ PUMP A & B PUMP_B OFF OFF

K2624A CS-5562 ARI RESET OFF OFF K2625A CS-5560 ARI INOP OFF OFF

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 12of80 8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES EVENT 1: LOWER POWER TO 850 MWE Simulator Operator Actions Ensure Monitored Parameters is open and Scenario Based Testing Variables are loaded.

Simulator Operator Role Play If asked as the NE, report that reactivity plan is to reduce power with recirc flow.

If asked as the NE, report that 850 MWe gross is 86% power and 65 Mlb/hr core flow Evaluator Notes Plant Response:

Objectives: SRO Directs power to be reduced to 850 MWe BOP Monitor the Plant RO Reduces power to 850 MWe.

Success Path: Power is lowered to 850 MWe Event Termination: When directed by the Lead Evaluator, go to Event 2.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 13 of 80 EVENT 1: LOWER POWER TO 850 MWE Time Pos EXPECTED Operator Response NOTES SRO Conduct shift turnover shift briefing.

Direct power to be reduced using recirc flow to

-850 MWe. (20P-02, Section 6.21)

Contacts chemistry for samples due to 15%

power change.

May contact Load dispatcher to inform of power decrease.

May conduct a brief (See Enclosure 1, page 62 for format of the brief.

Reduces reactor power using recirc lAW 20P-RO 02 Section 6.2.1 May null the DVM meter.

BOP Monitors the plant

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 14 of 80 REACTOR RECIRCULATION SYSTEM OPERATING 20P-02 PROCEDURE Rev 166 Page 45 ot 250 6.2 Shutdown 6.2.1 Lowering SpeedlPower Using Individual Recirculation Pump Control Or Recirc Master Control

1. Contirm reactor recirculation pump in operation in accordance with Section 6.1.2 NOTE Recirculation Pump speed changes ate performed when directed by OGP-05.

Unit Shutdown, and OGP-12, Power Changes. Other operating procedures are used simultaneously with this procedure as directed by OGP-05, Unit Shutdown, and OGP-12, Power Changes C Speed changes are accomplished by depressing Lower Slow. Lower Medium, or Lower Fast pushbuttons The Lower Slow pushbutton changes Recfrc pump speed at 0.06%/decrement at 1 rpm/second The Lower Medium pushbutton changes Recirc pump speed at 0,28%/decrement at 5 rpm/second The Lower Fast pushbutton changes Recirc pump speed at 2.8%/decrement at 100rpm/second C

2. IF AT ANY TIME any ot the following conditions exist.

THEN enter 1AOP-04.0. Low Core Flow.{8.1.9}

Entry into Region A of Power to Flow Map

OPRM INOPERABLE AND any of the following O Entry into Region B of Power to Flow Map O Entry into 5% Buffer Region of Power to Flow Map O Entry into OPRM Enabled Region and indications of THI (Thermal Hydraulic Instability) exist

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 J Pagel5of8O REACTOR RECIRCULATION SYSTEM OPERATING 20P-02 PROCEDURE Rev. 168 Page 46 of 250 6.2.1 Lowering SpeedlPower Using Individual Recirculation Pump Control Or Recirc Master Control (continued)

CAUTION

The OPRM System monitors LPRM5 for indication of thermal hydraulic instability (THI). When greater than or equal to 25% power and less than or equal to 60% recirculation flow, alarms and automatic trips are initiated upon detection of THI. Pump operations are governed by the limits of the applicable Power Flow Map, as specified in the COLR. {8. 1 .9} C

Entry into the 5% Buffer Region warrants increased monitoring of reactor instrumentation for signs of Thermal Hydraulic Instability. Time in the 5% Buffer Region presents additional risk and is rninimtzed.{8. 1.9) C

Wfth core flow less than 57.5 x 108 lbslhr, jet pump loop tlows are required within 10% (maximum indicated difference 6.0 x 108 lbslhr). With core flow greater than or equal to 57.5 x 10 lbsThr. jet pump loop flows are required within 5% (maximum indicated difference 3.0 x 108 lbs/br) C

When Recirc Pump speeds are less than 40%, decreasing speed using a Lower Fast pushbutton can result in a Speed Hold condition due to exceeding the regen torque limit C BEGIN R.M. LEVEL R21R3 REACTIVITY EVOLUTION

3. IF desired to lower the speed of both recirculation pumps simultaneously.

THEN depress Recirc Master Control Lower (Slow Medium Fast) pushbutton

4. IF desired to lower the speed of an individual recitculaon pump, THEN depress the Recirc VFD AC B) Lower (Slow Medium Fast) pushbutton

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 16 of 80 REACTOR RECIRCULATION SYSTEM OPERATING 20P-02 PROCEDURE Rev. 168 Page 47 ot 250 6.2.1 Lowering SpeediPower Using individual Recirculation Pump Control Or Recirc Master Control (continued)

5. Confirm the following, as applicable:

Recirc Pump A(B) Speed Demand, Calculated Speed, and Actual Speed have lowered

Reactor power lowers

632-R617(R613) [Recirc Pump A(B) Discharge Flowl lowers

B32-VFD-IDS-003A(B) [Recirc VFD 2A(B) Output Wattmeter]

lowers

832-VFD-IDS-OQ1A(B)]Recirc VFD 2A(B) Output Frequency Meter] lowers END R.M. LEVEL R21R3 REACTIVITY EVOLUTION Date/Time Completed Perrormed By (Print) Initials Reviewed By:

Unit CRS/SRO

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 17of80 EVENT 2: ISOLATE 230 KV DELCO WEST LINE 30 Simulator Operator Actions Simulator Operator Role Play If contacted as the Load Dispatcher acknowledge report.

Evaluator Notes Plant Response: 230 kV Delco West line is isolated Objectives: SRO - Direct 230kV Delco West Line isolated ATC Plant monitoring BOP Performs 20P-50 Section 6.2.6 for isolating ONLY the Delco West Line Success Path: 230 kV Delco West (Line 30) isolated Event Termination: Go to Event 3 at the direction of the Lead Evaluator.

2016 NRC SCENARIO LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 18 of 80 EVENT 2: ISOLATE 230 KV DELCO WEST LINE 30 Time Pos EXPECTED Operator Response Comments Directs 230kV Delco West Line isolated lAW SRO marked up version of 2OP-50, Section 6.2.6.

BOP Performs 20P-50, Section 6.2.6 RO Monitors the plant.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Pagel9of8O PLANT ELECTRIC SYSTEM OPERATING 20P-50 PROCEDURE Rev. 147 Page 58 of 281 6.2.6 De-energizing The 230 kV Switchyard

1. Ensure the Unit 2 230 kV switchyard is ENERGIZED AD

2. Ensure the 4kV Auxihary Electrical Systems are DE-ENERGIZED in accordance with Section 6,2.3 N-i SRO

3. Ensure the SAT is DE-ENERGIZED in accordance with Section 6.2.4 N-i SRO

4. Ensure Caswefl Beach Pumptng Station is DE-ENERGIZED in accordance with Section 6.2.5 N-i SRO

5. Ensure required LCOs for Technical Specification Sections 3.8.1, 3.8.2, 3.8.7 and 3.6.8 are initiated cRO

6. Obtain Load Dispatchets permission to de-energize the 230 kV switcrlyard AD A Powers the Delco West Line ONLY Person Contacted

7. Place Auto Reclose switches for the following PCBs in MAN:

31 B (Bus 26 Whitevifle 230 kV Breaker) N-i SRO

31 A (Bus 2A Wtiitevdle 230 kV Breaker) N-i SRO

SOB (Bus 26 Delco West Line 230 KV Breaker)

30A (Bus 2A Delco West Line 230 kV Breaker)

286 (Bus 26 Wallace 230 kV Breaker) N-i SRO

28A (Bus 2A Wallace 230 kV Breaker) N-i SRI)

278 (Bus 28 Town Creek 230 kV Breaker) N-I SRO

27A (Bus 2A Town Creek 230 kV Breaker) N-i SRI)

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 20 of 80 PLANT ELECTRIC SYSTEM OPERATING 20P-50 PROCEDURE Rev. 137 Page 59 of 281 6.2.6 De-energizing The 230 kV Switchyard (continued)

CAUTION PC8 Supervisory switch must be in LOCAI. before the associated PCB fs operated from Panel XU-5 13

8. Place Supervisory switches for the following PCBs in LOCAL:

31 B (Bus 28 Whitevifle 230 kV Breaker) N-I SRO

308 (Bus 2B Delco West Line 230 kV Breaker)

288 (Bus 26 Wallace 230 kV Breaker) N-i SRO

278 (Bus 26 Town Creek 230 kV Breaker) N-i SRO

31A (Bus 2A Whiteville 230 kV Breaker) N-i SRO

30A (Bus 2A Delco West Line 230 kV Breaker)

28A (Bus 2A Wallace 230 kV Breaker) N-I SRO

27A (Bus 2A Town Creek 230 kV Breaker) N-i SRO

9. Open 316 (Bus 26 Whiteville 230 kV PCB) N-i SRO

10. Confirm 3iB (Bus 28 Whiteville 230 kV PCB) is OPEN by observing the indicating lights N-i SRO 11 Open 31A(Bus 2A Whiteville 230kV PCB) N-i SRO 12 Confirm 3iA (Bus 2A Wheville 230 kV PCB) is OPEN by observing the indicating lights N-i SRO

13. Open 306 (Bus 28 Delco West Line 230 kV PCB) 14 Confirm 306 (Bus 26 Delco West Line 230 Ky PCB) is OPEN by observing the indicating lights

15. Open 30A (Bus 2A Delco West Line 230 kV PCB) 16 Confirm 30A (Bus 2A Delco West Line 230 kV PCB) is OPEN by observing the indicating lights 17 Open 288 (Bus 26 Wallace 230 kV PCB) N-i SRO

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 21 of8O PLANT ELECTRIC SYSTEM OPERATiNG 20P-50 PROCEDURE Rev. 147 Page 60 of 281 6.2.6 De-energizing The 230 kV Switchyard (continued)

18. Confirm 286 (Bus 26 Wallace 230 kV PCB) is OPEN by observing N-i SRO the indicating ligrns

19. Open 28A (Bus 2A Wallace 230 Ky PCB) N-i SRO

20. Confirm 28A (Bus 2A Wallace 230 kV PCB) is OPEN by observing NI SRO the indicating lights

21. Open 276 (Bus 26 Town Creek 230 kV PCB) N-i SRO

22. Confirm 27B (Bus 28 Towli Creek 230 kV PCB) is OPEN by N-i SRO observing the indicating lights

23. Open 27A (Bus 2A Town Creek 230 kV PCB) N-i SRO

24. Confirm 27A (Bus 2ATown Creek 230 kV PCB) is OPEN by observing the indicating lights N-i SRO NOTE IT work is to be performed on a 230 kV bus, the manual disconnects are to be opened C

25. Place Supervisory switches for the following PCBs in REMOTE;

316 (Bus 28 Wtiiteville 230 kV Breaker) N-I SRO

306 (Bus 28 Delco West Line 230 kV Breaker)

286 (Bus 26 Wallace 230 kV Breaker) N-i SRO

278 (Bus 26 Town Creek 230 kV Breaker N-i SRO

3 JA (Bus 2A Whiteville 230 kV Breaker) N-i SRO

30A (Bus 2A Delco West Line 230 kV Breaker)

28A (Bus 2A Wallace 230 kV Breaker) N-i SRO

27A (Bus 2A Town Creek 230 kV Breaker) N-i SRO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 22 of 80 PLANT ELECTRIC SYSTEM OPERATING 20P-50 PROCEDURE Rev, 147 Page 61 01281 6.2.6 De-energizing The 230 KV Switchyard (continued)

Daterflme Completed Performed By (Print) Initials Reviewed By Unit CRSISRO N-i, Partial usage to isolate only the Delco West 230 kV Line (Line 30)

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 23 of 80 EVENT 3: ROD DRIFT Simulator Operator Actions At the direction of the Lead Evaluator, Initiate Trigger I to drift CR 26-1 1 into the core.

When CR 26-1 1 is inserted to 00, Initiate Trigger 2 to activate CRD High Temperature alarm.

Two minutes after control rod is disarmed or scrammed, delete CRD HYD TEMP HIGH alarm.

If asked to disarm CRD 26-1 1 Initiate Trigger 4.

Simulator Operator Role Play If contacted as the RE to address thermal limits, acknowledge the request.

When contacted for scramming control rod 26-1 1, report that Thermal Limits will NOT be exceeded by this single rod scram.

If asked as the RBAO to investigate HCU for control 26-1 1, report that the HCU scram outlet riser is hot to the touch.

When contacted as the RBAO and after high temperature alarm has been actuated, report that the CRD temperature is 390° F and slowly rising.

When contacted as the System Engineer report that based on past history of this rod (26-11) scram times cannot be guaranteed.

If contacted as the WCC to perform the single rod scram, report that there are no operators available to perform the task.

If asked as the RBAO to disarm control rod, coordinate with Sim Operator after 5 minutes.

If requested, close/reopen the 1 13 valve (Charging Header Isolation Valve) as necessary As RBAO, Report Accumulator pressure 980# after rod has been scrammed.

Evaluator Notes Plant Response: Control Rod 26-1 1 will drift full in. Crew should enter AOP-02.0 and take action lAW 2APP-A-05 (3-2). When the high temperature alarm is received, Engineering will report that scram times cannot be assured based on past history of the control rod. Determine TS 3.1.3 condition Cl in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and C2 within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Objectives: SRO - Direct actions in response to a drifting control rod and evaluate Tech Specs.

RO - Respond to a drifting control rod.

Success Path: The drifting control rod is fully inserted, determined that the control rod must be placed under clearance and electrically disarmed.

Event Termination: Go to Event 4 at the direction of the Lead Evaluator.

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 24 of 80]

EVENT 3: ROD DRIFT Time Pos EXPECTED Operator Response Comments SRO Direct actions of 2APP-A-05 (3-2) ROD DRIFT Direct entry into OAOP-02.0, Control Rod SRO Malfunction/Misposition.

After System Engineer reports that the scram times cannot be guaranteed, according to Note 2 in TS Table 3.1.4-1 the rod must be declared inoperable.

Tech Spec 3.1.3 Control Rod Operability SRO Condition C. One or more control rods inoperable for reasons other than Condition A or B Required Action C.1 Fully insert inoperable control rod (3 hrs)

C.2 Disarm the associated CRD (4 hrs)

Contact System Engineer on high temperature condition of control rod.

SRO Contact RE to inform of rod drift and to evaluate thermal limits May direct the control rod to be scrammed to attempt to reseat the leaking outlet valve SRO lAW A-05 (3-2) ROD DRIFT May conduct a brief (See Enclosure 1, page 62 for format of the brief.

Monitor reactor plant parameters during evolution.

BOP May read APP actions for the OATC to perform

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 25 of 80 EVENT 3: ROD DRIFT Time Pos EXPECTED Operator Response Comments Acknowledge alarms:

A-05 (5-2) Rod Block RWM/RMCS Sys Trouble ATC A-05 (3-2) Rod Drift Announce and enter OAOP-02.0, Control Rod Malfunction/Misposition.

Perform the actions of APP-A-05 (3-2) ROD DRIFT as follows:

D Determine which control rod is drifting.

Select the drifting control rod and determine direction of drift.

Attempt to arrest the drift by giving a withdraw signal.

0 If rod continues to drift in, apply an RMCS insert signal and fully insert to position 00.

ATC U Attempt to locate and correct the cause of the rod malfunction as follows:

U Check and adjust cooling water header pressure if required.

U Direct AO to check for leaking scram valve.

U May direct an AO to check HCU temperature on R018 temperature recorder_(in_the_Rx_Bldg.)

Monitor core parameters, main steam line ATC radiation and off-gas activity.

Perform 20P-07 Section 6.3.17, Single Rod The examiner will prompt the Scram from RPS Test Panel. performer that the blue light is ON ATC and indication is 00 when step CRS will NA appropriate steps.

6.3.17.11 is performed.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 26 of 80 REACTOR MANUAL CONTROL SYSTEM OPERATING 20P-O1 PROCEDURE Rev. 105 Page 94 of 162 6.3.17 Single Rod Scram From RPS Test Panel Confirm the following initial conditions are met:

All applicable prerequisites in Section 5.0 are met

Attachment 1 has been reviewed

Communications are estabLished beeen RPS Test Panel and the Control Room

Reactor Engineer recommends performance of this section and has determined Technical Spedtication Thermal Limits will NOT be exceeded by this single rod scram Reador Engineer

2. IF AT ANY TIME it becomes necessary to sciarn a single control rod for operability concerns THEN perform OPT-14.2.1, Single Rod Scram Insertion Times Test for that control rod

3. Obtain permission from the Unit CR5 to perform this section CRS

4. Document applicable control rod to be scrammed in the space provided Control Rod

5. IF recommended by Reactor Engineering to support diagnostic data.

THEN record the following

Reactor pressure:

psig

Applicable accumulator pressure psig

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 27 of 80 REACTOR MANUAL CONTROL SYSTEM OPERA1YNG 20P-0? I PROCEDURE Rev. 105 Page 95 of 16j 6.3.1 7 Single Rod Scram From RPS Test Panel (continued)

BEGiN R.M. LEVEL R21R3 REACTIVITY EVOLUTION 6 Select applicable control rod at P603 Cv

7. Close C 12-1 13 (Charging Water Riser Isolation Valve) for the applicable control rod . - -

8. IF RWM scram time recording is recommended by Reactor Enginoenng, THEN perform the fdlowng

a. Have Reactor Enqineenng connect temporary scram time test cable to single rod scram interface box (located on terminal strip GM in P616-RMCS cabinet) and route cable up to RPS Test Panel P610 in accordance with Attachment 12. (Reference Use) -Test Cable Arranqement For RWM Scram Recordtng Reatar Engrneor (1) Insert black load into N[UTRAL socket on the P610 test panel IV (2) Insert red lead into socket corresponding to control rod to be tested at P610 IV

9. Monitor control rod position 10 IF AT ANY TIME the control rod does NOT fully scram after lovring the scram test switch.

THEN immediately notify the Unit CRS to determine operability of the rod (Technical Specificaton 3.1.3)

11. Using a currently licensed ROISRO, perform the following:

a. Scram the applicable control rod by lowering the scram test switch on RPS Test Panel P610 to the scram (down) position CV

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 28 of 80 REACTOR MANUAI CONTROL SYSTEM OPERATING 20P-0/

PROCEDURE Rev. 105 Page 96 of 162 6.3.17 Single Rod Scram From RPS Test Panel (continued)

b. WHEN the scrammed control rod is fully inserted OR 10 seconds have elapsed (whichever ours first).

THEN return applicable scram test switch to the normal (up) position .-

IV

12. Confirm rod position display indicates O0 for scrammed rod and the GREEN Full In light is ON

13. IF control rod U NOT fully insert, THEN reference Technical Specifications for OPERABILITY - -

CR5 NOTE Holding Emergency Rod In Notch Override switch in EMERGENCY ROD IN position for a period of time will flush any ingested crud from the drive to help prevent double notching LI

14. Hold the Emergency Rod In Notch Override switch in EMERGENCY ROD IN position for at least 15 seconds and record insert stall flow.

stall tbw stall flow stall flow 1: 2: 3:

15 Repeat Seion 6.3.17 Step 14 two additional times END RM. LEVEL R21R3 REACTIVITY EVOLUTION

16. Slowly open applicable C12-.11 3 (Charging Water Riser Isolation Valve) _J..

IV

17. Confirm associated accumulator pressure is greater than 955 psig

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 29 of 80 REACTOR MANUAL CONTROL SYSTEM OPERATiNG 20P-0f PROCEDURE nov. los Page 97 of 162 6.3.17 Single Rod Scram From RPS Test Panel (continued) 1& IF RWM scram time was recorded.

THEN perform the folowing:..

a- Contact Reactor Engineering to upload Reador Enaineer

b. Remove temporary scram timing cables from P616 and P610 ............

lv

c. Perform the following to delete RWM scram data buffers:

(1) Select SCRAM DATA screen on RWM Operator Display n the Control Room (2) Press DELETE softkcy to delete scram data (3) Confirm SCRAM DATA screen displa - -

ROD SCRA-1 TIMING FUNCTION: READY

ROD SCRAM TIMING DATA: NOT TRANSFERRED

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 L Page 30 of 80 EVENT 4: ADHR SECONDARY PUMP TRIP Simulator Operator Actions At the direction of the Lead Evaluator, Initiate Trigger 5 to trip the running ADHR Pump.

When informed to align 2A RCC pump to ADHR mode Initiate Trigger 6 If asked to throttle closed the RCC-V51 14, Initiate Trigger 7.

When asked to re-open the RCC-V51 14, then adjust the remote to 1.0.

Simulator Operator Role Play If directed to investigate the trip of RCC Pump D, report the pump is tripped on overcurrent.

When directed to align RBCCW Pump 2A to ADHR mode lAW 20P-21 Section 6.3.16 (steps 2b through 2i) have Sim Op align pump to ADHR mode and inform BOP Op that the steps are complete.

When contacted as RBAO report radiation monitor is aligned per 2OP-21 Section 6.3.18 step 4.

RCC-V5154 (Rad Monitor Bypass Standby Isolation Valve) is CLOSED RCC-V5116 (Rad Monitor Bypass ADHR Isolation Valve) is OPEN RCC-V5115 (Rad Monitor Bypass Common Mode Isolation Valve) is OPEN When contacted report RCC-V51 14 (RBCCW Pump 2A ADHR Mode Discharge Valve) is throttled 90% closed. (2OP-21 Section 6.3.18 Step 5a)

When contacted report RCC-V51 14 (RBCCW Pump 2A ADHR Mode Discharge Valve) is full open. (2OP-21 Section 6.3.18 Step 5c)

Evaluator Notes Plant Response: The running ADHR Secondary Loop Pump (RCC Pump D) will trip. The crew will have to start RCC Pump C. Shutdown RCC Pump A. Re-align RCC Pump A for ADHR mode and then start the pump for ADHR. (AOP-38.0 will be entered).

Objectives: SRO Direct swapping of RCC pumps and then direct starting of RCC Pump in ADHR Mode.

RO - Swap RCC pumps, Place RCC Pump in ADHR Mode.

Success Path: Standby ADHR Pump placed in service.

Event Termination: Go to Event 5 at the direction of the Lead Evaluator.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 31 of 80]

EVENT 4: ADHR SECONDARY PUMP TRIP Time Pos EXPECTED Operator Response Comments Direct entry into OAOP-38.0, Loss of Fuel Pool SRO Cooling Direct swapping of RBCCW pumps Start RBCCW Pump C, secure A.

Direct alignment of RBCCW Pump A to ADHR Mode.

Direct starting RBCCW Pump 2A in ADHR Mode.

Direct I/C to investigate trip of RBCCW Pump 2D.

May conduct a brief (see Enclosure 1 on page 62 for format)

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 32 of 80 EVENT 4: ADHR SECONDARY PUMP TRIP Time Pos EXPECTED Operator Response Comments RO Plant Monitoring Report trip of RBCCW Pump 2D (running in ADHR Mode)

SOP UA-01 3-3, ADHR SECONDARY LOOP TROUBLE May secure the primary pump lAW this APP Announce and enter AOP-38.0, Loss of Fuel Pool Cooling Perform 20P-21, Section 6.3.10 (page 33) to swap RBCCW pumps. (Start C and secure A)

Plant announcement for the start of 2C RCC Pump and securing of 2A RCC Pump.

Perform 2OP-21, Section 6.3.16 (page 34) to align RBCCW Pump A into ADHR Mode.

Direct RB AO to perform steps 2b through 2i.

Step 3 is N/A Perform 2OP-21, Section 6.3.18 (page 37) to start RBCCW Pump A in ADHR Mode.

Notifies E&C, starting ADHR pump Step 2 is N/A Step 3 is N/A Direct the RB AO to perform step 4 and 5a.

Announce starting of RCC Pump 2A.

Direct the RB AO to perform step 5c.

May direct AO to ensure primary loop is operating lAW 2OP-1 3.1.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 33 of 80 REACTOR BUILDING CLOSED COOLING WATER 20P.21 SYSTEM OPERATING PROCEDURE Rev. 93 Page 47 of 149 6.3.10 Transferring to the Standby RBCCW Pump RBCCW Mode-Ensure the following initaI conditions are met:

Applicable prerequisites listed in Section 5.0, Prerequisites are met

RBCCW System in operation with two pumps aligned for RBCCW Mode in service

2. Start the standby RBCCW pump by placing the associated pump control switch in ON:

RBCCWPUMP2A

RBCCW PUMP 26

RBCCWPUMP2C

RBCCW PUMP 2D

3. Secure the desired RBCCW pump by placing the associated pump control switch in OFF:

RBCCW PUMP 2A

RBCCW PUMP 26

RBCCWPUMP2C

RBCCWPUMP2D

4. lEa third RBCCW pump is aligned to RBCCW Mode, 4p RBCCW discharge header pressure has stabilized, THEN place the pump control switch in AUTO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 34 of 80 REACTOR BUILDING CLOSED COOLING WATER 20P-21 SYSTEM OPERATING PROCEDURE Rev. 93 Page 68 of 149 6.3.16 Alignment of RBCCW Pump from RBCCW Mode to ADHR Mode

1. Ensure the following initial condition is met:

One RBCCW Heat Exchanger is aligned to ADHR Mode per Section6.3.14

Key for RBCCW/ADHR Mode Selectot Switch has been obtained from one of the following:

O Control Rm Key Locket key 98 O WCC Key Locker key 167 or 168 NOTE RBCCW Pump 2A and RBCCW Pump 2D can support either RGCCW Mode or ADHR Mode. A Mode Selector Switch Is located on the pump breaker and a white ADHR Mode indicating light is on the RTGB. This switch determines which of the two header pressures (RBCCW or ADHR) wilt be monitored for the pump auto start on low header pressure when the pump control switch is placed in AUTO. When the Mode Selector Switch is placed in the ADHR Mode position, the white light is ON on the RTGB C

2. IF aligning RBCCW Pump 2A to ADHR Mode.

THEN perform the following

a. Ensure RBCCW Pump 2A control switch is in OFF

b. Close RCC-V32 (RBCCW Pump 2A RBCCW Suction)

c. Close RCC-V38 (RBCCW Pump 2A RBCCW Mode Discharge Valve)

U. Open RCC-V5105 (RBCCW Pump 2A ADHR Mode Suction Valve)

e. Open RCC-V51 14 (RBCCW Pump 2A ADHR Mode Discharge Valve)

f. Open RCC-V303 (RBCCW Pump 2A Casing Vent Valve)

g. WHEN a steady stream of water is present.

THEN close RCC-V303 (RBCCW Pump 24 Casing Vent Valve)

h. Ensure 2-RCC-SS-7667 (Pump 24 RBCCW,ADHR Mode Selector Switch) located at MCC 2XE. in ADHR

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 35 of 80 REACTOR BUILDING CLOSED COOLING WATER 20P-2i SYSTEM OPERATING PROCEDURE Rev. 93 Page 69of 149 6.3.16 Alignment of RBCCW Pump from RBCCW Mode to ADHR Mode (continued)

i. Remove key from 2-RCC-SS-7667 (Pump 2A RBCCW/ADHR Mode Selector Swxtch)

j. Confirm the ADHR white indicating light on the RTGB for RBCCW Pump 2A is ON

3. IF aligning RBCCW Pump 2D to ADHR Mode, THEN perform the following

a. Ensure RBCCW Pump 2D control switch is m OFF

b. Close RCC-V5 107 (RBCCW Pump 20 RBCCW Mode Suction Valve)

c. Close RCC-V51 11 <RBCCW Pump 20 RBCCW Mode Discharge Valve) d Open RCC-V5104 (R5CCW Pump 2D ADHR Mode Suction Valve)

e. Open RCC-V51 13 (RBCCW Pump 20 ADHR Mode Discharge Valve)

1. Open RCC-V5139 (RBCCW Pump 2D Casing Vent Valve)

g. WHEN a steady stream of water is present.

THEN close RCC-V5 139 (RBCCW Pump 20 Casing Vent Valve)

h. Ensure 2-RCC-SS-7668 (Pump 2D RBCCWIADHR Mode Selector Switch) located at MCC 2XD, in ADHR

i. Remove key from 2-RCC-SS-7668 (Pump 2D RBCCW1ADHR Mode Selector Switch)

j. Confirm the ADHR white indicating light on the RTGB for RBCCW Pump 2D is ON

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 36 of 80 REACTOR BUILDING CLOSED COOLING WATER 2OP2 1 SYSTEM OPERATING PROCEDURE Rev. 93 Page 70 of 149 6.3.16 Alignment of RBCCW Pump from RBCCW Mode to ADHR Mode (continued)

NOTE ADHR Mode piping is placed either in Standby Mode or in service to ensure RBCCW circulation and proper chemistry control wtien NOT undergoing maintenance D

4. Place ADHR in service per Section 63.18, Starting an RBCCW Pump-ADHR Mode Date/Time Completed Performed By (Pnnt) Initials Reviewed By Unit CRS/SRO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 37 of 80 REACTOR BUILDING CLOSED COOLING WATER 20P-2 1 SYSTEM OPERATING PROCEDURE Rev. 93 Page 74 of 149 6.3.18 Starting an RBCCW Pump ADHR Mode

1. Ensure the following initial conditions are met

Designated RBCCW Pump is aligned to ADHR Mode per Section 6.3.16

RBCCW pump is operating in ADHR Mode, THEN E&C notified commencing startup of ADHR t1ode Person Notified NOTE RBCCW Pump 2A and RBCCW Pump 2D can support either RBCCW Mode or ADHR Mode. A Mode Selector Switch is located on the pump breaker and a white ADHR Mode indicating light is on the RTGB. This switch determines which of the two header pressures (RBCCW or ADHR) wilt be monitored for the pump auto start on low header pressure wtien the pump control switch is placed in AUTO. When the Mode Selector Switch is placed in the ADHR Mode position, the wtite light is ON on the RTGB 0 RBCCW Pump 2D will NOT auto re-start wtien power returns after a LOOP or bus under voltage condition with the control switch in ON or AUTO. The control switch must be placed in OFF/RESET prior to restarting the pump 0 CAUTION Two pump operation in ADHR Mode subjects RCC-V37 (RBCCW Pump IA Discharge Check Valve) and RCC-V51 10 (RBCCW Pump 1D Discharge Check Valve) to accelerated wear. This lineup is expected to be utilized only when maximum ADHR capacity is required. [8.7.2] 0

2. IF desired to start a second pump aligned to ADHR Mode, THEN perform the following a Obtain concurrence from Engineering to start a second pump in the ADHR Mode Person Coitacted

b. Go to Step 5.b

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 38 of 8]

REACTOR BUILDING CLOSED COOLING WATER 20P-2 SYSTEM OPERATING PROCEDURE Rev. 93 Page 75 of 149 6.318 Starting an RBCCW Pump ADHR Mode (continued)

3. IF the ADHR Mode has been shutdown for greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR maintenance has been petfomied, THEN fill and vent the ADHR piping per Section 63.13

4. Ensure the following valve alignment for system radiation monitoring:

RCC-V51 54 fRau Monitor Bypass Standby Isolation Valve) is CLOSED

RCC-V5i 16 (Rad Monitor Bypass ADHR Isolation Valve) is OPEN

RCC-V51 15 fRad Monitor Bypass Common Mode Isolation Valve) is OPEN

5. For the RBCCW pump aligned to ADHR Mode to be started, perform the following

a. Throttle 80% to 95% dosed the associated pump discharge valve:

RCC-V51 14 (RBCCW Pump 2A ADHR Mode Discharge Valve)

RCC-V51 13 (RBCW Pump 20 ADHR Mode Discharge Valve)

b. Start an RBCCW pump aligned to ADHR Mode by placing the associated pump control switch in ON:

RBCCWPUMP2A

RBCCWPUMP2D

c. IF throttled in Step 5.a, THEN slowly open the associated pump discharge valve

RCC-V51 14 (RBCCW Pump 2A ADHR Mode Discharge Valve)

RCC-V5 113 (RBCCW Pump 20 ADHR Mode Discharge Valve)

. 2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 39 of 80 REACTOR BUILDING CLOSED COOLING WATER 20P-21 I SYSTEM OPERATING PROCEDURE Rev1 Page 76 of 149 6.3.18 Starting an RBCCW Pump -ADHR Mode (continued)

d. Ensure a log entry is made stating RBCCW pumps are in service in the ADHR Mode and Engineering has been notified NOTE The normal parameters for Supplemental Spent Fuel Pool Cooling are provided in Attachment 1, Normal System Operation Parameters. Equipment manipulations to maintain these parameters are performed per 20-13.1, Alternate Decay Heat Removal System Primary Loop Operating Procedure C

6. IF a Primary Loop pump is operating, THEN maintain Primary Loop flow per 20-13.1, Alternate Decay Heat Removal System Primary Loop Opemhng Procedure

7. Ensure Plant Process Computer setup as follows per OOP-55, Plant Process and ERFIS Computer Systems Operating Procedure

PPC U2RCCM 11 point ENABLED

PPC U2RCCAO95 Value Monitoring setup with the nominal flow values per Attachment 1 Section 2.5 for the number of RBCCW Pumps in ADHR Mode to provide audible alarms for ADHR secondary flow changes Date/Time Completed Performed By (Print) Initials Reviewed By Unit CRSISRO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 40 of 80 EVENT 5: RECIRC LOOP B FLOW TRANSMITTER FAILURE Simulator Operator Actions At the direction of the Lead Evaluator, Initiate Trigger 8 to activate Recirc Loop B Flow failure.

Simulator Operator Role Play If contacted as l&C to investigate, acknowledge the request.

After LCD entries have been determined and SRO is waiting for l&C, call as WCCSRO and request APRM 4 be placed in tripped condition to support l&C trouble shooting. The WCC will hang the status control tag paperwork.

If asked to pull fuses (for TRM 3.3 actions, 2-C12A-F1 Labeled ROD OUT BLOCK RELAYS CI2A in P616 panel) acknowledge the request Evaluator Notes Plant Response: Flow reference off normal alarm, rod block and scram signal to all 4 voters Flow transmitter signals are displayed on PC display 845, and on individual NUMACs by selecting Input Status.

Objectives: SRO - Determine LCO for APRM 4 inoperability and direct placing channel in trip.

RD Respond To A Flow Unit/Transmitter Failure Per APP A-06 5-7.

Success Path: APRM 4 TS 3.3.1.1 declaration and placed in trip condition lAW 001-18.

Event Termination: Go to Event 6 at the direction of the Lead Evaluator.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 41 of8O EVENT 5: RECIRC LOOP B FLOW TRANSMITTER FAILURE Time Pos EXPECTED Operator Response Comments Direct actions of APPs SRO Direct I&C to investigate Evaluate Tech Spec 3.3.1.1 Reactor Protection System Instrumentation TS 3.3.11, Function 2b, Required Action Al.

With one or more required channels inoperable, place in trip condition in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Evaluate TRM 3.3 Control Rod Block Instrumentation TRM 3.3, Function Ia, Required Condition Al.

With one of the required channels not operable -

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to restore to operable.

Refers to 001-18 for actions to place APRM 4 in a tripped condition.

Direct APRM 4 mode selector switch placed in INOP to allow I&C troubleshooting.

May conduct a brief (see Enclosure I on page 62 for format)

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 42 of 80 EVENT 5: RECIRC LOOP B FLOW TRANSMITTER FAILURE Time Pos EXPECTED Operator Response Comments BOP Monitors the plant.

May check back panel APRM indications.

Acknowledges, refers to & reports annunciators A-6 2-8 APRM UPSCALE 3-8 APRM UPSCALE TRIP/INOP ATC 5-7 FLOW REF OFF NORMAL A-5 2-2 ROD OUT BLOCK 4-8 OPRM TRIP ENABLED Diagnose and report failure of APRM 4 Flow Transmitter Obtains key number 1 14 from the SRO key locker to place APRM 4 in trip.

Places APRM mode selector switch in INOP lAW 001-18.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 L Page 43 of 80 EVENT 6: HEATER DRAIN DEAERATOR PUMP TRIP Simulator Operator Actions At the direction of the Lead Evaluator, Initiate Trigger 9 to trip a Heater Drain Pump.

Simulator Operator Role Play If contacted as AC to investigate, wait until pump is tripped and report over-current flags for all phases of 2A HDP 4KV breaker on Bus 2D If contacted as RE for reduced EW Temp, acknowledge any requests.

If asked as I&C to investigate, acknowledge the request Evaluator Notes Plant Response: Heater Drain Pump 2A shaft seizes and trips on overcurrent. Heater Drain tank level will rise and the crew will throttle HD-V57 to stabilize HD Tank level. If the standby HDP is not started, REP suction pressure will lower during the transient requiring power reduction to stabilize Condensate/feedwater.

Objectives: SRO Directs OAOP-23, Condensate/Feedwater System Failures, and possible OAOP-03.0, Positive Reactivity Addition, entry.

RO Diagnose HDP pump trip and start the standby HDP.

Success Path: 2C HDP started with HDD level recovered in the normal band.

Event Termination: Go to Event 7 at the direction of the Lead Evaluator.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 44 0180]

EVENT 6: HEATER DRAIN DEAERATOR PUMP TRIP Time Pos EXPECTED Operator Response Comments Direct annunciator response for UA-04:

4-10 HD PUMP A TRIP 2-10 HD DEAERATOR LEVEL HIGH-LOW 3-10 HD DEAERATOR LEVEL HIGH TRIP SRO Direct entry into OAOP-23, Condensate/Feedwater System Failures Direct starting standby HDP.

May direct 2AOP-3.0, Positive Reactivity Addition, entry if power rises due to the HDD Ext Trip.

May direct monitoring of final feedwater temperature.

May direct maintenance to investigate trip May conduct a brief (see Enclosure I on page 62 forformat)

RO Plant Monitoring May reduce power lAW OAOP-23 to stabilize reactor water level.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 45 of 80 EVENT 6: HEATER DRAIN DEAERATOR PUMP TRIP SOP Recognize and report annunciators UA-04 4-10 HO PUMP A TRIP 2-10 HD DEAERATOR LEVEL HIGH-LOW 3-10 HD DEAERATOR LEVEL HIGH TRIP UA-06 1-7 BUS 204 KV MOTOR OVLD Manually starts 2C HDP lAW APP or AOP.

Enter and announce OAOP-23, Condensate/Feedwater System Failures.

Monitors final feedwater temperature (FFWT) lAW 20 1-03.2 May open the HD-V57 to assist in HDD level recovery.

Directs an A0 to 4.16 Ky Switchgear Bus 2D to investigate 2A HDP trip Verifies auto actions for HD DEAERATOR LEVEL HIGH TRIP, if it occurs.

1. Non-return valves (EX-VI I and EX-Vi 2) to deaerator close. (Only close if turbine load is below 500 MWe)

2. HDD Extraction Line B moisture removal valves (MVD-LV-266 and MVD-LV-267) open.

May reference 20P-35 to recover MRVs following HDD level restoration.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 46 of 80]

EVENTS 7/819: STEAM LEAK IN DW ATWS I SLC SWITCH FAILURE I ARt RESET FAILURE Simulator Operator Actions At the direction of the Lead Evaluator, Initiate Trigger IOta activate small steam leak in DW.

If requested to defeat Group I LL3, wait 2 minutes, and install jumpers (Trigger II)

If requested to install LEP-02, Section 2.3 jumpers, wait 5 minutes, and inform the SRO that the jumpers are installed (RPOO5F already active).

Simulator Operator Role Play Acknowledge request as l&C to investigate failure of SLC switch.

If requested as I&C to investigate the failure of the ARt reset failure, acknowledge the request.

Acknowledge request to perform LEP-03 actions.

Evaluator Notes Plant Response: Most control rods will fail to insert on the scram. The crew will respond to the ATWS per EOP-01-ATWS. When SLC initiation is attempted, the switch positions will not work. The crew will enter LEP-03 and align for alternate boron injection using CRD.

The scram cannot be reset due to failure of the ARI to reset.

Objectives: SRO - Direct actions to control reactor power per EOP-01-ATWS..

RD - Perform actions for an ATWS per EOP-01-ATWS.

Success Path: Lower level to control power, inject SLC, insert control rods.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 47 of 80 EVENTS 71819: STEAM LEAK IN DW ATWS I SLC SWITCH FAILURE I ARI RESET FAILURE Time Pos EXPECTED Operator Response Comments Enter RSP and transition to ATWS.

Direct mode switch to shutdown when steam flow < 3 Mlbs/hr.

Direct ARI initiation.

Direct Recirc Pumps Tripped. CRITICAL TASK #2 SRO Direct SLC initiation, then LEP-03, Alternate Boron Injection.

Direct ADS inhibited. CRITICAL TASK #1 Direct RWCU isolation verification.

Direct LEP-02, Alternate Rod Insertion CRITICAL TASK #2 Direct Group 10 switches to override reset.

Direct terminate and prevent HPCUFeedwater (CS/RHR when LOCA signal received) to CRITICAL TASK #2 lower level to 90 inches.

When level reaches 90 inches, evaluate Table Q-2:

If not met, establishes a level band of LL4 to +90 inches.

If met, directs RPV injection to remain terminated.

Enters POOP Directs Torus cooling when Torus temperature is greater than 95° F, (See Enclosure 5, page 68)

Directs Torus Sprays before torus pressure reaches 11.5 psig (See Enclosure 8, page 77)

Directs Drywell Sprays when torus pressure exceeds 11.5 psig (See Enclosure 7, page 71)

Direct injection established to maintain RPV level LL4 to TAF (or the level at which APRMs indicate downscale)

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 48 of 80 EVENTS 7/819: STEAM LEAK IN OW ATWS I SLC SWITCH FAILURE I ARI RESET FAILURE Time Pos EXPECTED Operator Response Comments Place mode switch to shutdown when steam RO flow < 3x106 lb/hr.

Initiates ARI.

Trips Recirc Pumps. CRITICAL TASK #2 Initiates SLC.

Determines SLC switch failure.

Directs LEP-03, Alternate Boron Injection Recognizes failure of SLC switch and reports to CRS.

Monitor APRMs for downscale.

Performs LEP-02, Alternate Rod Insertion.

Section 2.1, Initial Actions (see page 48)

Section 2.3, Reset RPS and Initiate a Manual CRITICAL TASK #2 Scram (see page 51)

Section 2.4, Reactor Manual Control System (RMCS) (see page 54)

May also perform Section 2.5, Increasing Cooling Water Header Pressure (see page 56).

Recognizes failure of ARI to reset, informs CRS

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 49 of 8p]

EVENTS 7/819: STEAM LEAK IN OW ATWS I SLC SWITCH FAILURE I ARI RESET FAILURE Time Pos EXPECTED Operator Response Comments BOP Places ADS in inhibit. CRITICAL TASK #1 Places Group 10 switches to override I reset Terminate and prevent injection to RPV. CRITICAL TASK #2 Terminates and prevents HPCI lAW Hard Card. (Enclosure 2, page 63)

Terminates and Prevents Feedwater lAW Hard Card. (Enclosure 3, page 64)

May place HPCI in service for level control during ATWS when directed by the SRO.

(Enclosure 6, page 70)

Restart RFP to maintain level as directed by SRO. (Enclosure 4, page 65)

When Torus temperature is greater than 95° F, places Torus Cooling in service.

(Enclosure 5, page 68)

When directed, places Torus Sprays in service.

(Enclosure 8, page 77)

When directed, places Drywell Sprays in service.

(Enclosure 7, page 71)

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 50 of 80 ALTERNATE CONTROL ROD INSERTION OEOP-01-LEP-02 Rev. 029 R3ge4of37 1.0 ENTRY CONDITIONS

As dwected by Emergency Operating Procedures fEOPs)

As directed by Severe Accident Management GudeIine (SAMGs) 2.0 OPERATOR ACTIONS 2.1 Initial Actions 2.1.7 Manpower Required

1 Reactor Operator

1 Auxiliary Operator 2.1.2 Special Equipment None NOTE

Two-handed operation is allowed during implementation of this procedure in order to minimize delay in control rod insertion D

Section 2.1.3 Step 1 through Step 6 may be performed concurrently with the test of this procedure C

The system designation Cii is for Unit 1 and C12 for Unit 2 C 2.1.3 Operator Actions

1. Monitor reactor power on APRMs until IRM recorders on scale C RO

2. Insert IRMs and monitor reactor power on IRM recorders C RO

3. Downrange IRMs to bring them on scale C RO

4. WHEN IRM5 on Range 3 OR below.

THEN insert SRMs C RO

5. Monitor reactor period C RO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 51 of8O ALTERNATE CONTROL ROD INSERTION OEOP-01-LEP-02 I Rev. 029 Page 5 otT]

2.1.3 Operator Actions (continued)

6. Monitor control rod position using:

Process computer RO

SPDS D RO

RWM C RO

Four rod [3 RO

Full core display C RO

7. WHEN either:

All control rods in C RO

Qy one control rod I4Q[ fully inserted C RO

NO more than 10 control rods withdrawn to position 02 NO control rod withdrawn beyond position 02 C RO

Reactor engineering has determined the reactor ill remain shutdovai under all conditions without boron C RO THEN perform Section 2.2, Control Rod Insertion Verification on Page7 C RO

. 2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 52 of 80 ALTERNATE CONTROL ROD INSERTION OEOP-01-LEP-02 Rev. 029 Page 6 of 37 2.1.3 Operator Actions (continued)

8. Insert control rods by one or more methods:

Section 2.3, Reset RPS and Initiate a Manual Scram on Page 15 D RO

Section 2.4, Reactor Manual Control System (RMCS) on Page 18 C RO

Section 2.5, Increasing Cooling Water Header Pressure on Page 20 C RO

Section 2.6. Scram Individual Control Rods on Page 22 C RO

Section 2.7, De-energize Scram Solenoids and Vent Scram Air Header on Page 26 C RO

Section 2,8, Venting Over Piston Area on Page 32 C RO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 53 of 80 ALTERNATE CONTROL ROD INSERTION OEOP-0 1 -LEP-02 Rev. 029 Page 15 of 37 2.3 Reset RPS and Initiate a Manual Scram 2.3.1 Manpower Required

1 Reactor Operator 2.3.2 Special Equipment

RO Desk Locked Drawer 0 4 jumpers (15, 16, 17 and 18) C]

2.3.3 Manual Scram Actions NOTE Section 2.3.3 Step 1 and Step 2 may be performed concurrently C]

IF an automatic scram signal present AND power available to RPS bus.

THEN install jumpers to bypass reactor scram:

Jumper 15 in Panel H 12-P609, Terminal Board DD, from right side of Fuse C71A(C72A)-F 14A to Terminal 4 of Relay C7JA(C72A)-K12E C]

RO

Jumper 16 in Panel Hi 2-P609, Terminal Board 88, from left side of Fuse C71A(C72A)-F14C to Terminal 4 of Relay C71A(C72A)-K12G C]

RO

Jumper 17 in Panel H12-P611, Terminal Board DD, from right side of Fuse C7IAfC72A)-F 148 to Terminal 4 of Relay C71A(C72A)-KI2F C]

RO

Jumper 18 in Panel H12-P611, Terminal Board BB, from left side of Fuse C7 1Af C72A)-F 14D to Terminal 4 of Relay C71A(C72A)-K12H C]

RO

2. Inhibit ARI:

a. Place CII (Cl 2)-CS-5560 (ARI Auto/Manual Initiation Switch) t0INOP C]

RO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 54 of 80 ALTERNATE CONTROL ROD INSERTION OEOP-O1-LEP-02 Rev. 029 Page 16 of 37 2.3.3 Manual Scram Actions (continued)

b. Place and hold Cli (C12)-CS-5562 (ARI Reset) switch in RESET 0 RO

c. WHEN 5 seconds have elapsed.

THEN release 0 RO

d. Confirm ted TRIP light located above CI 1(C12)-CS-556 1 (ARI Initiation) OFF 0 RO

3. Ensure Disch Vol Vent & Drain Test switch in ISOLATE 0 RO

4. Conhrm CLOSED:

C1i(CI2)-V139(DischVolVentVlv) 0 RO

Cl 1fC 12)-CV-F0 10 (Disch Vol Vent VIv) 0 RO

Cl 1(C12)-V 140 fDisch Vol Drain Vlv) 0 RO Cl 1fCI2)-CV-F0i 1 fDisch Vol Drain VIv) 0 RO

5. Reset RPS 0 RO

6. IF either RPS A OR B can be RESET, THEN go to Section 2.3.3 Step 8 0 RO

7. IF RPS CANNOT be RESET, THEN return to Section 2.1.3 Step 7 0 RO

8. Place Disch Vol Vent & Drain Test switch to NORMAL 0 RO

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 55 of 80 ALTERNATE CONTROL ROD INSERTION OEOP-01-LEP-02 Rev. 029 Page 17 of 37 2.3.3 Manual Scram Actions (continued)

9. Confirm OPEN:

Ci i(C12)-V 139 (Disch Vol Vent Vlv) C]

RO

Ci l(C12)-CV-F0l0 (Disch Vol Vent Vlv) C]

RO

Ci 1fC12)-V140 (Disch Vol Drain Vtv) C]

RO

Cl i(C12-CV-F0i 1 fDisch Vol Drain Vlv) C]

RO

10. WHEN the scram discharge volume has drained for approximately 2 minutes OR A-05 1-6, SDV Hi-Hi Level RPS Thp clears, THEN continue C]

RO ii. IF venting control rod over piston area per Section 2.8, THEN notify AO to secure venting prior to inserting a manual scram C]

RO

12. Manually scram the reactor C]

RO 13 IF control rods moved inward AND ll control rods NOT inserted to

.Q.. beyond Position 00, THEN return to Section 2.3.3 Step 3 C]

RO

14. IF.II control rods inserted to OR beyond Position 00 9 control rods did NOT move inward, THEN return to Section 2.1.3 Step 7 C]

RO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 56 of 80 ALTERNATE CONTROL ROD INSER11ON OEOP-01-LEP-02 Rev. 029 Page 180137 2.4 Reactor Manual Control System (RMCS) 2.4.7 Manpower Required I Reactor Operator 2.4.2 Special Equipment RO Desk Locked Dravr Unit 1 Only: 1 5450 key for RWM D 0 Unit 2 Only: 1 5451 key ror RWM 0 2.4.3 RMCS Actions

1. IF a reactor scram sealed in, THEN ensure available CR0 pumps operating 0 RO

2. Ensure Ci1(C12)-FC-R600fCRD Flow Control) in MAN 0 RO

3. IF a CRD pump NOT operating, THEN:

a. Close the in-service Cl 1(C12)-FOO2A(F0028) (Flow Control Vlv) 0 RO

b. Start one CR0 pump 0 RO c, Adjust CI 1fC 12)-FC-R600 (CRD Flow Control) to greater than or equal to 30 gpm 0 RO

d. IF avalabte, THEN start the second CRD pump 0 RO

4. IFNO CR0 pump can be started, THEN return to Section 21.3 Step 7 0 RO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 57 of 80 ALTERNATE CONTROL ROD INSERTION OEOP-01-LEP-02 Rev. 029 Page 19 of 37 2.4.3 RMCS Actions (continued)

5. Insert control rods with RMCS:

a Throttle open ci 1(C12)-EOO2A(E0026)fFIow Control Vlv) until drive water differential pressure greater than or equal to 26opsid D RO

b. IF drive water differential pressure less than 260 psid, THEN throttle closed Cli (Cl 2)-PC V-F003 (Drive Pressure Vlv) until drive water differential pressure greater than or equal to 260 psid C RO

c. Bypass RWM C RO d Insert control rods with Emergency Rod In Notch Override switch C RO

6. WHEN fl control rods inserted to beyond Position 00 .Q CANNOT be inserted with RMCS.

THEN return to Section 2.7.3 Step 7 C RO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 58 of 80 ALTERNATE CONTROL ROD INSERTION OEOP-0 1 -LEP-02 Rev. 029 Page 20 of 37 2.5 Increasing Cooling Water Header Pressure 2.5.1 Manpower Required

1 Reactor Operator 2.5.2 Special Equipment None 2.5.3 Cooling Water Header Actions

1. IF a reactor scram sealed in, THEN ensure available CRD pumps operating D RO

2. JE a CR0 pump QI operating, THEN:

a. Ensure Cl 7fC12)-FC-R600 (CRD Flow Control) in MAN D RO

b. Close the in-service Cl 1fC12)-FOO2AfFOO2B) (Flow Control Vlv) D RO

c. Start one CRD pump D RO ci. Adjust Cl i(Ci2-FC-R600 (CRD Flow Control) to greater than or equal to 30 gpm C RO

e. IF available, THEN start the second CRD pump C RO

3. IFNO CRD pump can be started, THEN return to Section 2.1.3 Step 7 C RO t

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 59 of 80 OEOP-01-LEP-02 I ALTERNATE CONTROL ROD INSERTION Rev. 029 I Page2lof37 L

2.5.3 Cooling Water Header Actions (continued)

4. IF a reactor scram NOT sealed in, THEN maximize cooling water header pressure:

a. Ensure Cl 1fC12)-FC-R600 (CRD flow Control) in MAN and fully open the in service Cl 1(C12).-FOO2A(F0026)fFlow Control Vlv) D RO b Fully open Cii (C12)-PCV-F003 (Drive Pressure VIv) D RO

5. WHEN jj control rods inserted to beyond Position 00 control rods NOT moving inward, THEN return to Section 2.1.3 Step 7 0 RO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 60 of 80 TERMINATION Simulator Operator Actions When directed by the Lead Evaluator, delete the following commands:

Malfunction K2624A, ARI Reset Malfunction K2625A, ARI INOP Malfunction RPOI 1 F, ATWS 4 (Make sure RPS is reset and scram air header pressurized before deleting)

When directed by the Lead Evaluator, place the simulator in FREEZE DO NOT RESET THE SIMULATOR PRIOR TO RECEIPT OF CONCURRENCE TO DO SO FROM THE LEAD EXAMINER Simulator Operator Role Play After Sim Operator has deleted SDV malfunction, Inform the CRS that a loose wire was found on ARI switch and it has been repaired.

Evaluator Notes Plant Response: When actions are taken to control reactor water level during the ATWS after terminating and preventing, ARt will be repaired and rods can be inserted.

Objectives: SRO - Directs actions for an ATWS.

RO Insert control rods lAW LEP-02.

Success Path: Rods inserted with LEP-02, Alternate Rod Insertion.

Scenario Termination: When all rods are inserted and level is being controlled above TAF with injection established, the scenario may be terminated.

Remind students not to erase any charts and not to discuss the scenario until told to do so by the evaluatorlinstructor.

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 61 of 80 TERMINATION Time Pos EXPECTED Operator Response Comments Exit ATWS and enter RVCP when all rods are SRO in.

Direct level restored to 170 200 inches after rods are all in.

RO Confirms ARI reset when reported fixed.

Inserts a scram after discharge volume has drained for 2 minutes.

Reports all rods in.

Maintains reactor pressure as determined by the BOP CRS.

Maintains level as directed by the SCO.

Restores level to 170 200 inches after all rod inserted. (Enclosure 4, page 65, contains actions for restart of Condensate and Feedwater)

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 62 of 80 ENCLOSURE I Page 1 of I CONDUCT OF OPERATIONS AD-OP-ALL-i 000 Rev. 6 Page 90 of go AUACHMENT $

Page 1 of 1

<< Crew Brief Template>>

1] Announce Crew Brief Begin Brie?

D NI crew members acknowledge announcement (AZ Required)

I] Updatetflecrewas needed:

D Descnbe what happened and major actions taken D Procedures in-progress D Notifications:

Recap 0 Maintenance 0 Engineering 0 Others tDispatcher, Station Management. etc.)

0 Future Direction and pnonties C Discuss any contingency plans (AZ Required)

C Solicit questionstoncerns from each crew member:

DROs Input 0 CRS C STA 0 Are there any alarms unexpected for the plant conditions?

C What is the status of Cnticat Parameters?

(AZ Required)

EAt.

C Provide EAL and potential escalation criteria C Restore normal alarm announcement7 fYesNo)

Flnl:h Brief C Announce End of Bnet

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 63 of 80 ENCLOSURE 2 Page 1 of 1 SECURING HPCI INJECTION 1.0 INITIAL CONDITIONS WHEN DIRECTED BY 2EOP-O1-LPC TO TERMINAIE AND PREVENT HPCI INJECTION, OR D

2. WHEN DIRECTED BY OEOP-Oi-RXFP TO TERMINATE AND PREVENT HPCI INJECTION. OR C

3. WHEN PERMISSION GIVEN DY THE UNIT CRS TO SECURE HPCI INJECTION WITH A HPCI AUTO START SIGNAL PRESENT C 2.0 PROCEDURAL STEPS

1. IF HPCI IS NOT OPERATING. PERFORM THE TOLLOWING:

a PLACE HPCI AUXILIARY OIL PUMP CONTROL SWITCH IN PULL-TO-LOCK C

2. IF HPC( IS OPERATING. PERFORM THE FOLLOWING:

b. DEPRESS AND HOLD THE HPCI TURBINE TRIP PUSHBUTTON C

c. WHEN HPCI TURBINE SPEED IS 0 RPM. AND HPCI TURBINE CONTROL VALVE, E41-V9 IS CLOSED. THEN PLACE HPCI AUXILIARY OIL PUMP CONTROL SWITCH IN PULL-TO-LOCK C U. WHEN HPCI TURD BRG OIL PRESS LO.

A-01 4- 2. IS SEALED IN. THEN RELEASE THE HPCI TURBINE TRIP PUSHBUTTON C

e. ENSURE HPCI TURBINE STOP VALVE, [41-VS.

AND HPCI TURBINE CONTROL VALVE. E41-V9.

REMAIN CLOSED, AND HPCI DOES NOT RESTART C 1 2)1368 Sf1369

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 64 of 8_Qj ENCLOSURE 3 Page 1 of 1 Terminating and Preventing Injection From Condensate and Feedwater During EOPs (20P-32)

1. IF desired TRIP all operating REPs. []

2. IF one or more REPS are in service IDLE one REP as tollows

a. IF two RFPs are operating THEN TRIP one E

b. PERFORM either of the following for the operating REP

1. PLACE MANIDFCS control switch to MAN.

2, RAPIDLY REDUCE speed to approximately 1000 rpm with the LOWERJRAISE speed control switch.

OR 1 PLACE REPT Speed Control in M (MANUAL)

2. SELECT DEM and RAPIDLY REDUCE speed to approximately 2550 rpm.

3. CLOSE the following valves

- FW HTR 5A OUTLET VLVS, FW-V6

- FW HTR 55 OUTLET VLVS, FW-V8 OR

- FW HTR 4A INLET VLV, EW-Vi 1$

- FW HTR 45 INLET VLV, FW-Vi 19

4. ENSURE the SULCV is dosed by performing the following

a. PLACE SULCV, in M (Manual),

b. SELECT DEM and DECREASE signal until VALVE DEM E indicates 0%

5. ENSURE EW-V120. is closed.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 L Page 65 of 80 ENCLOSURE 4 Page 1 of 3 Aligning Condensate and Feedwater After Terminating and Preventing Ensure FW.FV-177 (Feedwater Recwc to Condenser Vlv) CLOSED .......El

2. Ensure FW Control Mode Select in 1 ELEM El

3. Ensure at least one valve OPEN El

B21-E032A (Feedwater Isol Vtv) El

821-F0325 (Feedwater Isol Vlv) El 4 IFNO REP operating, THEN: El

a. Ensure REPT A(S) Sp CD.

(1) lnM(manual) El (2) Pmp A(S) Dern at 0.0 PCT El

b. Place EW-FV-46f47) tREP (NB) Recirc Vlv] in OPEN El

c. Ensure El

FW-V3(V4) [RFP (A/B) Disch Vlv] OPEN El

REP A(S) ManuatIDFCS control switch in MANUAL El d Depress: El (1) Reactor Water Level High Reset A El (2) Reactor Water Level High Reset B El (3) Reactor Water Level High Reset C El (4) REP A(S) Reset El

e. Confirm OPEN El

REP A(S) LP Stop Vlvs El

REP A(S) HP Stop Vlvs El f Depress REP A(S) REPT Start El

g. WHEN at 1000 rpm.

THEN raise REP A(S) to at least 2550 rpm El

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 66 of 80 ENCLOSURE 4 Page 2 of 3 Aligning Condensate and Feedwater After Terminating and Preventing (continued)

5. IE desired to transier REP Af 5) to DFCS, THEN D

a. Ensure speed at least 2550 rpm D

b. Depress DFCS Ctfl Reset D c Place Manual/DFCS control switch in DFCS D

6. Raise RFP A(S) speed until discharge pressure approximately 100 psig above RPV pressure band D 011550 S/I 372

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 67 of 80 ENCLOSURE 4 Page 3 of 3 Injection After Terminating and Preventing Condensate and Fe.dwater WHEN RPV injection directed.

THEN as needed C

Adjust SULCV Valve Dem C

Throttle FW-V 120 (FW Htrs 4&5 Byp VIv) C

2. WHEN automatic control desired, THEN: C

a. Confirm RPV level greater than + 170 inches C

b. Ensure FW-V 120 (FW Htrs 4&5 Byp VIv) CLOSED C c Open FW-V 10 (FW Recirc To Cond Isol VIv) C

d. Adjust SULCV to between 25 PCT and 55 PCI using C

SULCV Valve Dem C

FW-FV-177 (Feedwater Recirc To Condenser Vlv) C

e. Ensure Mstr RFPT Sp/Rx LVI Ctl: C (1) lnM(manual) C (2) Level Setpoint at current RPV level C

1. Place SULCV in A (automatic) C

g. Adjust as needed to control RPV level C

Mstr RFPT SpIRx Lvi CtI Level Setpoint C

FW-FV-i 77 (Feedwater Recirc To Condenser VIv) C 0/1551 511552

, 2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0

. Page 68 of 80 ENCLOSURE 5 Page 1 of 2 ATTACHMENT 8A Page 1 of 1 Emergency Suppression Pool Cooling Using Loop A f20P-17)

NOTE: Ths attachment is NOT to be used for nomaI system operations START RHR SW A LOOP CCONV) START RHR SW A LOOP fNUC)

OPEN SW-ViOl OPEN SW-V105 CLOSE SW-V143 U OPEN SW-V102 START CSW PUMPS AS NEEDED CLOSE SW-V143 IF LOCA SIGNAL IS PRESENT THEN START PUMPS ON NSW HDR AS NEEDED PLACE RHR SW BOOSTER PUMPS IF LOCA SIGNAL IS PRESENT THEN PLACE A & C LOCA OVERRIDE SWITCH RHR SW BOOSTER PUMPS A & C LOCA TO MANUAL OVERRIDE OVERRIDE SWITCH TO MANUAL OVERRIDE START RHR SW PMP START RHR SW PMP ADJUST Eli-PD V-F068A ADJUST El f-PDV-F068A ESTABLISH CLG WIR TO VITAL HDR ESTABLISH CLG WTR TO VITAL HDR START ADDITIONAL RHR SW PUMP START ADDITIONAL RHR SW PUMP AND ADJUST FLOW AS NEEDED AND ADJUST FLOW AS NEEDED START RHR LOOP A IF LOCA SIGNAL IS PRESENT, THEN VERIFY COOLING LOGIC IS MADE UP IF El 1-FOI5A IS OPEN, THEN CLOSE Elf-FO17A START LOOP A RHR PMP E OPEN Eil-F028A E THROTTLE Ell-F024A THROTTLE EI1-F018A START ADDITIONAL LOOP A RHR PMP AND ADJUST FLOW AS NEEDED 2 2/1061 2 S1062

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 69 of 80 ENCLOSURE 5 Page 2 of 2 ATTACHMENT 8B Page 1 of 1 Emergency Suppression Pool Cooling Using Loop B (20P-i7)

NOTE This attachment is NOT to be used for normal system operabons START RHR SW B LOOP CNUC) START RHR SW B LOOP (CONV)

OPEN SW-V105 OPEN SW-Viol CLOSE SW-V143 OPEN SW-V 1 02 START PMPS ON NSW HDR AS NEEDED CLOSE SW-V743 IF LOCA SIGNAL IS PRESENT THEN START CSW PUMPS AS NEEDED PLACE RHR SW BOOSTER PUMPS IF LOCA SIGNAL IS PRESENT THEN PLACE B & D LOCA OVERRIDE SWITCH RHR SW BOOSTER PUMPS B & 0 LOCA TO MANUAL OVERRIDE OVERRIDE SWITCH TO MANUAL OVERRIDE STARTRHRSWPMP START RHR SW PMP ADJUST Elf-PD V-F0688 ADJUST Eli-PD V-F0688 ESTABLISH CLG WTR TO VITAL HDR ESTABLISH CLG WTR TO VITAL HDR START ADDITIONAL RHR SW PUMP START ADDITIONAL RHR SW PUMP AND ADJUST FLOW AS NEEDED AND ADJUST FLOW AS NEEDED START RHR LOOP B IF LOCA SIGNAL IS PRESENT. THEN VERIFY COOLING LOGIC IS MADE UP IF Ell-F0f58 IS OPEN. THEN CLOSE Ell-F0178 START LOOP B RHR PMP OPEN E11-F0288 THROTTLE E1l-F024B THROTTLE E1l-F048B START ADDITIONAL LOOP B RHR PMP AND ADJUST FLOW AS NEEDED 2 21063 2 S. 1064

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 70 of 80 ENCLOSURE 6 Page 1 of 1 HPCI INJECTION IN EOPs

1. IF HPCI IS TRIPPED ON HIGH WATER LEVEL, DEPRESS HIGH E WATER LEVEL SIGNAL RESET, E41-S25. PUSH BUTTON, AND ENSURE THE INDICATING LIGHT IS OFF

2. ENSURE AUXILIARY OIL PUMP IS NOT RUNNiNG E

3. ENSURE E41-V9 AND E$1-V8 ARE CLOSED

4. OPEN E41-F059

5. PLACE HPCI FLOW CONTROL. E41-FIC-R600, IN MANUAL fM),

AND ADJUST OUTPUT DEMAND TO APPROXIMATELY MIDSCALE, USING THE MANUAL LEVER.

6. START VACUUM PUMP AND LEAVE IN START

7. OPEN E41-F001

8. START AUXILIARY OIL PUMP AND LEAVE IN START

9. OPEN E41-F006, IMMEDIATELY AFTER E41-V8 HAS DUAL INDICATION

10. ENSURE E4i-V9 AND E41-V8 ARE OPEN E ii. WHEN SPEED STOPS INCREASING, THEN ADJUST SPEED TO APPROXIMATELY 2100 RPM

12. ADJUST HPCI FLOW CONTROL, E41-FIC-R600, TO OBTAIN DESIRED FLOW RATE

13. ENSURE E41-F0 12 IS CLOSED WHEN FLOW IS GREATER THAN 1400 GPM

14. ADJUST HPCI FLOW CONTROL, E41-FIC-R600, SETPOINT TO MATCH SYSTEM FLOW, AND THEN PLACE E41-FIC-R600 IN AUTO (A)

15. ENSURE E41-F025 AND E41-F026 ARE CLOSED

16. START SBGT (OP-b)

17. ENSURE BAROMETRIC CNDSR CONDENSATE PUMP IS OPERATING

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0

. Page7lofSO ENCLOSURE 7 Page 1 016 DRWIELL SPRAY PROCEDURE OEOP-0i -SEP-02 Rev. 18 Page 4 of 18 1.0 ENTRY CONDITIONS As directed by Emergency Operating Procedures (EOPs) 2.0 INSTRUCTIONS 2.1 Drywell Spray Initiation 2.1.1 Manpower Required

1 Reactor Operator 2.1.2 Special Equipment

RO Desk Locked Drawer 0 23095keys C]

2.1.3 Drywell Spray Actions

1. Ensure reactor recirculation pumps tripped C RO

2. if E-bus load stripping has occurred.

THEN:

a. Confirm electrical power has been aligned per EOP-0 1-SBO-i4 C]

RD

b. Secure drywell coolers per Attachment 1 and continue at Section 2.1.3 Step 2.c C]

RO c IF RHR Loop A will be used for sprays, THEN go to Section 2.1.3 Step 9 C]

RO U. IF RHR Loop B will be used for spras, THEN go to Section 2.1.3 Step 10 C]

RD 3 Place afl drywell cooler control switches to OFF (LID) C]

RO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 72 of 80 ENCLOSURE 7 Page 2 of 6 DRTWELL SPRAY PROCEDURE OEOP-0 1-SEP-02 Rev. 78 Page 50118 2.1.3 Dryweli Spray Actions (continued)

4. Unit 1 Only: IF drywell coolers continue to run, THEN:

in Panel XU-27. west side, place VA-CS-5993 (01W Cit A&D Override Switch) in STOP C RO

In Panel XU-28, west side, place VA-CS-5993 (01W Cit B&C Override Switch) in STOP C RO

5. Unit 2 Only: IF drwelI coolers continue to run, THEN:

In Panel XU-27, west side, place VA-CS-5993 (DNI Cit A&D Override Switch) in STOP C RO

in Panel XU-28, east side, place VA-CS-5994 (DM dr B&C Override Switch) in STOP C RO

6. iF drwelI coolers continue to run, THEN secure drwell coolers per Attachment 1 and continue at Section 2.7.3 Step 7 C RO

7. Ensure SW-V 141 fWell Water to Vital Header Vlv) CLOSED C RO

8. Ensure one valve OPEN

SW-Vt Ii (Cony SW To Vital Header Vlv) C RD

SW-Vt 17 (Nuc SW To Vital Header Viv) C RD

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 73 of 80 ENCLOSURE 7 Page 3 of 6 DRWIELL SPRAY PROCEDURE OEOP-Oi-SEP-02 Rev. 16 Page 6 of 18 2.1.3 Drywell Spray Actions (continued)

9. if Loop A RHR will be used for drywell spray.

THEN:

NOTE El l-FO17A will remain OPEN for five minutes following a LOCA signal [1

a. IF El 1-FO 15A (Inboard Injection Vlv) OPEN, THEN close El 1-FO17A (Outboard Injection VIv) I]

RD

b. Place El 1-CS-S 18A (213 Core Height LPCI Initiation Ovemde Switch) to MANUAL OVERRD C RO c Momentarily place El 1-CS-S 17A (Containment Spray Valve Control Switch) to MANUAL C RD d Ensure El 1-F024A (Torus Cooling Isol Vlv) CLOSED C RD e Ensure one Loop A RHR Pump running C RD

f. Confirm requirements for Drywell Spray Initiation met

Safe region of Drywell Spray Initiation Limit C RO

Torus level below +21 inches C RD

g. Open El 1-FO21A (Drywell Spray lnbd Isol Vlv) C RO Ii Throttle open El l-FO16A(Drywell Spray Otbd Isol Vlv)to obtain between 8,000 gpm and 10000 gpm flow C RO

i. IF E-bus load stripping has occurred, THEN go to Section 2.1.3 Step 11 C RD

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 74 of 80 ENCLOSURE 7 Page 4 of 6 DRWJELL SPRAY PROCEDURE OEOP-Ol.-SEP-02 Rev. 18 Page 7 c 18 2.1.3 Drywell Spray Actions (continued)

j. IF additional flow required.

THEN start the other RHR pump and limit flow to less than orequaltoil,500gpm C RO

k. Ensure RHRSW Loop A operating:

(1) Place El i-S19A (RHR SW Booster Pumps A & C LOCA Override Switch) in IANUAL OVERRD C RO (2) Align RHRSW to the heat exchanger fOP-43) C RO Est3blish RHR flow through the heat exchanger:

(1) Ensure El 1-F047A fHx A Inlet Vlv) OPEN C RO (2) Ensure El l-FQO3A(HxA Outlet Vlv) OPEN 0 RO NOTE El l-F048A will remain OPEN for three minutes following a LOCA signal C]

(3) Close Eli-F048A(HxABypassVlv) C RO

10. IF Loop B RHR will be used for drywell spray, THEN:

NOTE El i-F0l78 will remain OPEN for five minutes following a LOCA signal C

a. IF E 1 l-F0l58 (Inboard Injection Vlv) OPEN.

THEN close El l-FO 178 (Outboard Injection Vlv) C]

RO

b. Place El 1-CS-S 188 f2f3 Core Height LPCI Initiation Override Switch) to MANUAL OVERRD 0 RO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 75 of 80 ENCLOSURE 7 Page 5 of 6 DRYWELL SPRAY PROCEDURE OEOP-0 1-SEP-02 Rev. 18 Page8ot 18 2.1.3 Drywell Spray Actions (continued)

c. Momentarily place El 1-CS-S 17B (Containment Spray Valve Control Switch) to MANUAL D RO U. Ensure Eii-F024B (Torus Cooling lsd Vlv) CLOSED ID RO

e. Ensure one Loop B RHR Pump wnning ID RO

f. Confirm requirements for Drywell Spray Initiation are met:

Safe region of the Drywell Spray Initiation Limit ID RO

Torus level below +21 inches ID RO

g. Open El 1-FO21B (Drwell Spray lnbd Isol Vlv) ID RO Ii. Throttle open El i-FO16B fDrvwell Spray Otbd lsol Vlv) to obtain between 8,000 gpm and 10,000 gpm flow ID RO I. IF. E-bus load stripping has occurred, THEN go to Section 2.1.3 Step 11 ID RO

j. if additional flow required, THEN start the other RHR pump and limit flow to less than or equal to 11,500 gpm ID RO k Ensure RHRSW Loop B operating.

(1) Place Eil-S19B (RHR SW Booster Pumps B & D LOCA Override Switch) in MANUAL OVERRD U RO (2) Align RHRSW to the heat exchanger (OP-43) ID RO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 76 of 80 ENCLOSURE 7 Page 6 of 6 DRWIELL SPRAY PROCEDURE OEOP.-O 1-SEP-02 Rev. 16 Page9ot 18 2.1.3 Drywell Spray Actions (continued)

I. Establish RHR llc through the heat exchanger:

(1) Ensure El l-EcM7B (Hx B Inlet Vlv) OPEN D RO (2) Ensure El l-E0036 fHx B Outlet Vlv) OPEN . D RO NOTE El l-E048B will remain OPEN for three minutes foHoving a LOCA signal C (3) Close E1i-FO48BfHxB BpassVlv) C RO

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 77 of 80 ENCLOSURE 8 Page 1 of2 TORUS SPRAY PROCEDURE OEOP-O 1-SEP-03 Rev. 012 Page 4 of?

1.0 ENTRY CONDITIONS

As directed by Emergency Operating Procedures fEOPs) 2.0 INSTRUCTIONS 2.1 Torus Spray 2.1.1 Manpower Required

. 1 Reactor Operator 11.2 Special Equipment None 2.1.3 Torus Spray Actions

1. Confirm tows pressure above 2.5 pstg . C RO

2. IF Loop A RHR Il be used.

THEN:

NOTE

[1 1-tO 1 1A will remain OPEN for live minutes fdlowinq a LOCA signal C

a. IF RPV injection NOT needed, THEN ensure at least one valve CLOSED:

El l-FO15A (Inboard Injection Vlv) C RO

El l.FOl?A (Outboard Injection Vlv) C RO

b. Place El 1-CS-S 1$A (2/3 Core Height LPCI Initiation Override Stch) to MANUAL OVERRD C RO c Momentarily place [11-CS-Si ZA (Containment Spray Valve Control Switch) to MANUAL C RO

d. Ensure one Loop A RHR Pump running C RO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 78 of 80 ENCLOSURE 8 Page 2 of 2 TORUS SPRAY PROCEDURE 0EOP-01SEP-03 Rev. 012 Page 5 of?

2.1.3 Tows Spray Actions (continued)

e. Ensure El 1-F028A (Torus Discharge Isol Vlv) OPEN C]

RO

1. OpenE1l-tO2?AtIonsSprayIsoIVlv) C]

RO g Ensure operation ii LPCI. Torus Cooling or Drywelt Spray mode C]

RO

3. IE Loop B RHR wiU be used.

THEN:

NOTE El 1-TO 1 /B will remain OPEN for five minutes following a LOCA signal C]

a IF RPV intection NOT needed.

THEN ensure at least one valve CLOSED:

Li 1-FO5B (Inboard Inlection Vlv) ....._ C]

RO

El 1 -FOl /B (Outboard Injection Vlv) . C]

RO

b. Place ElI-CS-S 186 (2/3 Core Height LPCI Initiation Override Switch) to MANUAL OVERRD C]

RO

c. Momentarily place Eli-CS-SuB (Containment Spray Valve Control Switch) to MANUAL C]

RO U. Ensure one Loop B RHR Pump running C]

RO

e. Ensure Eli-T028B (Torus Discharge Isol VIv) OPEN C]

RO

1. Open El 1-F0216 (Torus Spray lsol Vlv) C]

RO

g. Ensure operation ii LPCI, Torus Cooling OR Dry.vell Spray mode .. C]

RO

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 L Page 79 of 80 ATTACHMENT I - Scenario Quantitative Attribute Assessment NUREG 1021 Scenario Content Category Rev. 2 Supp. I Req.

Total Malfunctions 5-8 7 Malfunctions after EOP 1-2 2 Entry Abnormal Events 2-4 2 Major Transients 1-2 1 EOPs Used 1-2 2 EOP Contingency 0-2 2 Run Time 60-90 mm 90 Crew Critical Tasks 2-3 3 Tech Specs 2 2 Instrument I Component 2 OATC Failures before Major 2 - BOP Instrument I Component 2 2 Failures after Major Normal Operations 1 1 Reactivity manipulation 1 1

LOl SIMULATOR EVALUATION GUIDE Page 80 of 80 ATTACHMENT 2 Shift Turnover Brunswick Unit 2 Plant Status Station Duty Workweek B. Craig E. Neal Manager:

Manager:

Mode: I Rx Power: 100% Gross*INet MWe*: 977 / 951 Plant Risk:

. Green Current EOOS Risk Assessment is:

SEP Time to Days Online: 82 days 49.7 hrs 200 Deg F:

Turnover:

Protected 2A FPC Pump/Hx, 2D RCC Pump, and 2C Demin Transfer Pump for Equipment: Fuel Pool Decay Heat Removal and inventory makeup.

2A/B NSW Pumps due to IA NSW pump maintenance.

1A NSW Pump is under clearance for planned maintenance.

Comments: APRM 2 has failed downscale and is bypassed.

2C TCC Pump is in service on Unit One.

The Load Dispatcher has called to perform the following as soon as possible due to an emergent repairs required on the Delco West Line:

Shft

. The OATC is to reduce power to 850 MWe Gross Activities The BOP operator will then Isolate 230 kV Delco West (Line 30) lAW the marked up of 20P-50, Section 6.2.6.

DUKE ENERGY. Run 2 BRUNSWICK TRAINING SECTION OPERATIONS TRAINING INITIAL LICENSED OPERATOR SIMULATOR EVALUATION GUIDE 2016 NRC SCENARIO 2 LOWER POWER, REMOVE 230KV LINE FROM SERVICE, ROD DRIFT, ADHR PP TRIP, RECIRC LOOP FLOW FAILURE, HDD PP TRIP, ATWS, SLC MODE SWITCH FAILURE, ARI FAIL TO RESET REVISION 0 Developer: Date: e7/t7/2O!6 Technical Review: Va% Date: 91/2120/6 Validators: Date: 09/06/16 4a Te Facility Representative: tâe Date: 09/221/6

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 2 of 80 REVISION

SUMMARY

o Scenario developed for 2016 NRC Exam.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev.0 Page 3 of 80 TABLE OF CONTENTS 1.0 SCENARIO OUTLINE 4 2.0 SCENARIO DESCRIPTION

SUMMARY

5 3.0 CREW CRITICAL TASKS 6 4.0 TERMINATION CRITERIA 6 5.0 IMPLEMENTING REFERENCES 7 6.0 SETUP INSTRUCTIONS 8 7.0 INTERVENTIONS 10 8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES 12 ATTACHMENT 1 - Scenario Quantitative Attribute Assessment 49 ATTACHMENT 2 Shift Turnover 80

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 L Page4of8o 1.0 SCENARIO OUTLINE Event MaIf. No. Type* Event Description 1 R ATC

- Lower power to 850 MWe to remove 230 kV Line 30 2 N - BOP Remove 230 kV Line 30 from service RDOOIM C-ATC RodDrift 3 (26-11)

C CRS (TS)

K4526A C BOP

- ADHR Secondary pump trip 4

C-CRS (AOP)

C ATC

- Recirc Loop B Flow transmitter Failure 5

C-CRS (TS)

CFO89F C BOP

- Heater Drain Deaerator Pump Trip 6

C-CRS (AOP)

Small steam leak in DW results in an ATWS requiring 7 CAOO8F M terminate and prevent actions (RSP)(ATWS) 8 K2119A C SLC Mode Switch Failure 9 K2624A C Alternate Rod Insertion reset failure

(N)ormal (R)eactivity, (C)omponent or Instrument, (M)ajor

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev.0

. Page5of8O]

2.0 SCENARIO DESCRIPTION

SUMMARY

Event Description 1 After taking the watch the CRS will direct power reduced to 850 MWe.

2 The BOP will isolate 230 kV Line 30.

F Control Rod -.4l start to drift in. The crew will enter OAOP-02.0 and take action lAW 2APP-A-05 (3-2). When the high temperature alarm is received Engineering will erCu fl (3 report that scram times cannot be assured based on past history of the control rod.

L Determine TS 3.1.3 condition Cl to insert the control rod in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and 02 to disarm the control rod within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

After Tech Specs are addressed the Alternate Decay Heat Removal (ADHR)

Seconday pump will trip. AOP-38.0 will be entered The Recirc Loop B flow transmitter to APRM Channel 4 will fail wiiscale resulting in a rod block and a trip input to each voter. The crew will respond per APPs and bypass 5 APRM 4. The APRM will be declared Inoperable per TS 3.3.1.1, Condition A and placed in trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . APRM TS Actions to be taken requires the APRM mode selector switch to be place in INOP lAW 001-18 A motor overload will occur on Heater Drain Pump 2A. The crew will reference APP

. 6 UA-06 1-7, Bus 2D 4KV Motor OvId and determine which pump has the overload condition. The crew should start HDP 20 and secure HDP 2A. The crew may reference AOP-23.0.

A small steam leak in the DW results in rising Drywell pressure requiring a reactor 7 scram. An ATWS will occur, conditions will require terminate and prevent actions to be performed.

When SLO is initiated, the mode switch will fail and the pumps will not start. LEP-03 8

will be executed to inject the boron into the core.

Alternate Rod Insertion (ARI) will not reset, the crew will perform LEP-02 to drive 9 control rods into the core. When level is stabilized after terminating and preventing ARI will be repaired to allow the rods to be manually scrammed.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 6 of 80 3.0 CREW CRITICAL TASKS Critical Task #1 Prevent the automatic actuation of ADS (LL3) to prevent low pressure ECCS injection to the reactor.

Critical Task #2 Reduce reactor power/pressure to prevent exceeding Heat Capacity Temperature Limit (HCTL) 220

..i....r i1.1tt1iIi 210 4 - -- - UNSAFE ABOVE U

0 Lj SELECTED LINE w

200 zi:ETzJ 1.

190 D f::

180 Lii a 170 :L. f-) 025 FT

(-)1.2SFT U 160 %%

I. . :-

(-) 2.50 FT 150 f-)3.25 FT 140 j SAFE BELOW (- ) 4.25 FT 130 ELECTED LINE

(-)5.5OFT 120 4.-

110 : -

100

..+/- 1 1,150 100 300 500 700 900 1,100 0 200 400 600 800 1,000 RPV PRESSURE (PSIG) 4.0 TERMINATION CRITERIA When all rods are inserted and level is being controlled above TAF the scenario may be terminated.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page_7_of 80 5.0 IMPLEMENTING REFERENCES NOTE: Refer to the most current revision of each Implementing Reference.

Number Title A-05, 3-2 ROD DRIFT OAOP-02.0 CONTROL ROD MALFUNCTION/MISPOSITION UA-18, 6-1 BUS E4 4KV MOTOR OVLD.

UA-01, 2-3 ADHR PRIMARY LOOP TROUBLE UA-01, 3-3 ADHR SECONDARY LOOP TROUBLE OAOP-38.O LOSS OF FUEL POOL COOLING A-06, 2-8 APRM UPSCALE A-06, 3-8 APRM UPSCALE TRIP/INOP A-06, 5-7 FLOW REF OFF NORMAL A-05, 2-2 ROD OUT BLOCK A-05, 4-8 OPRM TRIP ENABLED UA-5, 3-5 SBGT SYS B FAILURE UA-5, 4-6 SBGT SYS A FAILURE

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 8 of 80 6.0 SETUP INSTRUCTIONS list for

1. PERFORM TAP-409, Miscellaneous Simulator Training Guidelines, Attachment 5, Check Simulator Exam Security.

2. RESET the Simulator to IC-il.

3. ENSURE the RWM is set up as required for the selected IC.

4. ENSURE appropriate keys have blanks in switches.

5. RESET alarms on SJAE, MSL, and RWM NUMACs.

6. ENSURE no rods are bypassed in the RWM.

7. PLACE all SPDS displays to the Critical Plant Variable display (#100).

8. ENSURE hard cards and flow charts are cleaned up

9. TAKE the SIMULATOR OUT OF FREEZE

10. LOAD Scenario File.

II. ALIGN the plant as follows:

Manipulation Ensure 20 TCC pump is in service on Unit One.

Bypass APRM 2 RCC Pump D in service for ADHR RCC Pump A in service for RBCCW

12. IF desired, take a SNAPSHOT and save into an available IC for later use.

13. PLACE a clearance on the following equipment.

Component Position APRM 2 Blue tag

14. INSTALL Protected Equipment sign age and UPDATE RTGB placard as follows:

Protected Equipment

1. 2A and 2B NSW pumps

2. 2A FPC Pump/Hx, 2D ROC Pump, and 20 Demin Transfer Pump.

2016 NRC SCENARIO 2 LOt SIMULATOR EVALUATION GUIDE Rev. 0 Page 9 of 80

15. VERIFY OENP 24.5 Form 2 (Immediate Power Reduction Form) for IC-Il is in place.

16. ENSURE each Implementing References listed in Section 7 is intact and free of marks.

17. ENSURE all materials in the table below are in place and marked-up to the step identified.

Required Materials Marked up of 20P-50, Section 6.2.6

18. ADVANCE the recorders to prevent examinees from seeing relevant scenario details.

19. PROVIDE Shift Briefing sheet for the CRS.

20. VERIFY all actions contained in TAP-409, Miscellaneous Simulator Training Guidelines, Attachment 4, Simulator Training Instructor Checklist, are complete.

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page lOof8O 7.0 INTERVENTIONS TRIGGERS Trig Type ID 1 Malfunction RD0O1M [CONTROL ROD SLOW INSERTION DRIFT]

2 j Annunciator ZA512 [CRD HYD TEMP HIGH]

3 Trigger Command MFD:RD001M,26-11 4 Remote Function RD_RDELDIS [ELECTRICAL DISARM OF ROD]

5 DI Override K4526A [RBCCW PMP D AUTO]

5 DO Override Q4526AMW [RBCCW PMP D ADHR MODE]

5 DO Override Q4526LG4 [RBCCW PMP D OFF GJ Malfunction RPO11F [ATWS 4]

6 Remote Function CC_MODE [RBCCW/ADHR VALVE LINEUPS]

6 Remote Function CCMSS [RBCCW/ADHR PUMP MODE SELECTOR SWITCH]

7 Remote Function CC_PDV [RBCCW PUMP DISCHARGE VALVE]

8 Malfunction N1063F [RECIRC LOOP B XMIUER FAILURE]

9 Malfunction CF089F [HEATER DRAIN PUMP MOTOR WINDING FAULT]

10 Malfunction NBOO6F [MSL BRK BEFORE FLOW RESIRICTORJ 11 Remote Function EP_IAEOPJP - [BYPASS LL-3 GROUP I ISOL (SEP-10)]

Trig # Trigger Text 3 KM118EDN - [SCRAM TEST SWITCH 26-11] true deletes RDOO1M ANNUNCIATORS Override OVal AVaI Actime Dactime Trig Window Description Tagname 1-2 CRD HYD TEMP HIGH ZA512 ON ON OFF 2

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 11 of 80 MALFUNCTIONS taif Mult CUrreflt Thret Actime Dactime Trig Description CONTROL ROD SLOW INSERTION 1 RDOO1M 26-11 False True N1063F APRM 4 RECIRC LOOP B XMIUER FAILURE 0.00 125.00 8 NBOO6F A MSL BRK BEFORE FLOW RESTRICTOR 0.00 1.Oe-1 0:03:00 10 HEATER DRAIN PUMP MOTOR 9 CFO89F A False True WINDING FAULT RPO11F ATWS 4 False True 5 RPO0SF AUTO SCRAM DEFEAT True True NIO32F APRM 2 APRM FAILS LO ] True True REMOTES CUITeflt ThTt Actime Trig Remf Id Mult Id Description RD_RDELDIS 26-11 ELECTRICAL. DISARM OF ROD ARM DISARM 4 6

CC_MODE PUMP-A

[ RBCCW/ADHR VALVE LINEUPS RBCCW/ADHR PUMP MODE RBCCW ADHR CC MSS A RBCCW ADHR 6 SELECTOR SWITCH CC_PDV A_V38_V5114 RBCCW PUMP DISCHARGE VALVE 1.0000 1.Oe-01 7 CC_IACW4518 2CTBCCW PUMP UNIT ALIGNMENT 1 1 EP_IAEOP]P1 BYPASS LL-3 GROUP I SOC (SEP-10) OFF ON 11 PANEL OVERRIDES Position I Actual Override Actime Dactime Trig Tag ID Description K4526A RBCCW PUMP D OFF OFF/RESEST OFF ON 5 K4526A RBCCW PMP D AUTO AUTO OFF OFF 5 K4526A RBCCW PMP 0 ON ON ON OFF 5 Q4526LG4 RBCCW PMP D OFF G ON/OFF OFF OFF 5 Q4526AMW RBCCW PMP D ADHR MODE ON/OFF ON OFF 5 K2119A S/B LIQ PUMP A & B_______ PUMP_A OFF OFF K2119A S/BLIQPUMPA&B PUMP_A&B OFF OFF K2119A S/B CIQ PUMP A & B PUMP_B OFF OFF

K2624A CS-5562 ARI RESET OFF OFF K2625A CS-5560 ARI INOP OFF OFF

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 12of80 8.0 OPERATOR RESPONSE AND INSTRUCTIONAL STRATEGIES EVENT 1: LOWER POWER TO 850 MWE Simulator Operator Actions Ensure Monitored Parameters is open and Scenario Based Testing Variables are loaded.

Simulator Operator Role Play If asked as the NE, report that reactivity plan is to reduce power with recirc flow.

If asked as the NE, report that 850 MWe gross is 86% power and 65 Mlb/hr core flow Evaluator Notes Plant Response:

Objectives: SRO Directs power to be reduced to 850 MWe BOP Monitor the Plant RO Reduces power to 850 MWe.

Success Path: Power is lowered to 850 MWe Event Termination: When directed by the Lead Evaluator, go to Event 2.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 13 of 80 EVENT 1: LOWER POWER TO 850 MWE Time Pos EXPECTED Operator Response NOTES SRO Conduct shift turnover shift briefing.

Direct power to be reduced using recirc flow to

-850 MWe. (20P-02, Section 6.21)

Contacts chemistry for samples due to 15%

power change.

May contact Load dispatcher to inform of power decrease.

May conduct a brief (See Enclosure 1, page 62 for format of the brief.

Reduces reactor power using recirc lAW 20P-RO 02 Section 6.2.1 May null the DVM meter.

BOP Monitors the plant

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 14 of 80 REACTOR RECIRCULATION SYSTEM OPERATING 20P-02 PROCEDURE Rev 166 Page 45 ot 250 6.2 Shutdown 6.2.1 Lowering SpeedlPower Using Individual Recirculation Pump Control Or Recirc Master Control

1. Contirm reactor recirculation pump in operation in accordance with Section 6.1.2 NOTE Recirculation Pump speed changes ate performed when directed by OGP-05.

Unit Shutdown, and OGP-12, Power Changes. Other operating procedures are used simultaneously with this procedure as directed by OGP-05, Unit Shutdown, and OGP-12, Power Changes C Speed changes are accomplished by depressing Lower Slow. Lower Medium, or Lower Fast pushbuttons The Lower Slow pushbutton changes Recfrc pump speed at 0.06%/decrement at 1 rpm/second The Lower Medium pushbutton changes Recirc pump speed at 0,28%/decrement at 5 rpm/second The Lower Fast pushbutton changes Recirc pump speed at 2.8%/decrement at 100rpm/second C

2. IF AT ANY TIME any ot the following conditions exist.

THEN enter 1AOP-04.0. Low Core Flow.{8.1.9}

Entry into Region A of Power to Flow Map

OPRM INOPERABLE AND any of the following O Entry into Region B of Power to Flow Map O Entry into 5% Buffer Region of Power to Flow Map O Entry into OPRM Enabled Region and indications of THI (Thermal Hydraulic Instability) exist

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 J Pagel5of8O REACTOR RECIRCULATION SYSTEM OPERATING 20P-02 PROCEDURE Rev. 168 Page 46 of 250 6.2.1 Lowering SpeedlPower Using Individual Recirculation Pump Control Or Recirc Master Control (continued)

CAUTION

The OPRM System monitors LPRM5 for indication of thermal hydraulic instability (THI). When greater than or equal to 25% power and less than or equal to 60% recirculation flow, alarms and automatic trips are initiated upon detection of THI. Pump operations are governed by the limits of the applicable Power Flow Map, as specified in the COLR. {8. 1 .9} C

Entry into the 5% Buffer Region warrants increased monitoring of reactor instrumentation for signs of Thermal Hydraulic Instability. Time in the 5% Buffer Region presents additional risk and is rninimtzed.{8. 1.9) C

Wfth core flow less than 57.5 x 108 lbslhr, jet pump loop tlows are required within 10% (maximum indicated difference 6.0 x 108 lbslhr). With core flow greater than or equal to 57.5 x 10 lbsThr. jet pump loop flows are required within 5% (maximum indicated difference 3.0 x 108 lbs/br) C

When Recirc Pump speeds are less than 40%, decreasing speed using a Lower Fast pushbutton can result in a Speed Hold condition due to exceeding the regen torque limit C BEGIN R.M. LEVEL R21R3 REACTIVITY EVOLUTION

3. IF desired to lower the speed of both recirculation pumps simultaneously.

THEN depress Recirc Master Control Lower (Slow Medium Fast) pushbutton

4. IF desired to lower the speed of an individual recitculaon pump, THEN depress the Recirc VFD AC B) Lower (Slow Medium Fast) pushbutton

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 16 of 80 REACTOR RECIRCULATION SYSTEM OPERATING 20P-02 PROCEDURE Rev. 168 Page 47 ot 250 6.2.1 Lowering SpeediPower Using individual Recirculation Pump Control Or Recirc Master Control (continued)

5. Confirm the following, as applicable:

Recirc Pump A(B) Speed Demand, Calculated Speed, and Actual Speed have lowered

Reactor power lowers

632-R617(R613) [Recirc Pump A(B) Discharge Flowl lowers

B32-VFD-IDS-003A(B) [Recirc VFD 2A(B) Output Wattmeter]

lowers

832-VFD-IDS-OQ1A(B)]Recirc VFD 2A(B) Output Frequency Meter] lowers END R.M. LEVEL R21R3 REACTIVITY EVOLUTION Date/Time Completed Perrormed By (Print) Initials Reviewed By:

Unit CRS/SRO

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 17of80 EVENT 2: ISOLATE 230 KV DELCO WEST LINE 30 Simulator Operator Actions Simulator Operator Role Play If contacted as the Load Dispatcher acknowledge report.

Evaluator Notes Plant Response: 230 kV Delco West line is isolated Objectives: SRO - Direct 230kV Delco West Line isolated ATC Plant monitoring BOP Performs 20P-50 Section 6.2.6 for isolating ONLY the Delco West Line Success Path: 230 kV Delco West (Line 30) isolated Event Termination: Go to Event 3 at the direction of the Lead Evaluator.

2016 NRC SCENARIO LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 18 of 80 EVENT 2: ISOLATE 230 KV DELCO WEST LINE 30 Time Pos EXPECTED Operator Response Comments Directs 230kV Delco West Line isolated lAW SRO marked up version of 2OP-50, Section 6.2.6.

BOP Performs 20P-50, Section 6.2.6 RO Monitors the plant.

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Pagel9of8O PLANT ELECTRIC SYSTEM OPERATING 20P-50 PROCEDURE Rev. 147 Page 58 of 281 6.2.6 De-energizing The 230 kV Switchyard

1. Ensure the Unit 2 230 kV switchyard is ENERGIZED AD

2. Ensure the 4kV Auxihary Electrical Systems are DE-ENERGIZED in accordance with Section 6,2.3 N-i SRO

3. Ensure the SAT is DE-ENERGIZED in accordance with Section 6.2.4 N-i SRO

4. Ensure Caswefl Beach Pumptng Station is DE-ENERGIZED in accordance with Section 6.2.5 N-i SRO

5. Ensure required LCOs for Technical Specification Sections 3.8.1, 3.8.2, 3.8.7 and 3.6.8 are initiated cRO

6. Obtain Load Dispatchets permission to de-energize the 230 kV switcrlyard AD A Powers the Delco West Line ONLY Person Contacted

7. Place Auto Reclose switches for the following PCBs in MAN:

31 B (Bus 26 Whitevifle 230 kV Breaker) N-i SRO

31 A (Bus 2A Wtiitevdle 230 kV Breaker) N-i SRO

SOB (Bus 26 Delco West Line 230 KV Breaker)

30A (Bus 2A Delco West Line 230 kV Breaker)

286 (Bus 26 Wallace 230 kV Breaker) N-i SRO

28A (Bus 2A Wallace 230 kV Breaker) N-i SRI)

278 (Bus 28 Town Creek 230 kV Breaker) N-I SRO

27A (Bus 2A Town Creek 230 kV Breaker) N-i SRI)

2016 NRC SCENARIO 2 LOl SIMULATOR EVALUATION GUIDE Rev. 0 Page 20 of 80 PLANT ELECTRIC SYSTEM OPERATING 20P-50 PROCEDURE Rev. 137 Page 59 of 281 6.2.6 De-energizing The 230 kV Switchyard (continued)

CAUTION PC8 Supervisory switch must be in LOCAI. before the associated PCB fs operated from Panel XU-5 13

8. Place Supervisory switches for the following PCBs in LOCAL:

31 B (Bus 28 Whitevifle 230 kV Breaker) N-I SRO

308 (Bus 2B Delco West Line 230 kV Breaker)

288 (Bus 26 Wallace 230 kV Breaker) N-i SRO

278 (Bus 26 Town Creek 230 kV Breaker) N-i SRO

31A (Bus 2A Whiteville 230 kV Breaker) N-i SRO

30A (Bus 2A Delco West Line 230 kV Breaker)

28A (Bus 2A Wallace 230 kV Breaker) N-I SRO

27A (Bus 2A Town Creek 230 kV Breaker) N-i SRO

9. Open 316 (Bus 26 Whiteville 230 kV PCB) N-i SRO

10. Confirm 3iB (Bus 28 Whiteville 230 kV PCB) is OPEN by observing the indicating lights N-i SRO 11 Open 31A(Bus 2A Whiteville 230kV PCB) N-i SRO 12 Confirm 3iA (Bus 2A Wheville 230 kV PCB) is OPEN by observing the indicating lights N-i SRO

13. Open 306 (Bus 28 Delco West Line 230 kV PCB) 14 Confirm 306 (Bus 26 Delco West Line 230 Ky PCB) is OPEN by observing the indicating lights

15. Open 30A (Bus 2A Delco West Line 230 kV PCB) 16 Confirm 30A (Bus 2A Delco West Line 230 kV PCB) is OPEN by observing the indicating lights 17 Open 288 (Bus 26 Wallace 230 kV PCB) N-i SRO

2016 NRC SCENARIO 2 LOI SIMULATOR EVALUATION GUIDE Rev. 0 Page 21 of8O PLANT ELECTRIC SYSTEM OPERATiNG 20P-50 PROCEDURE Rev. 147 Page 60 of 281 6.2.6 De-energizing The 230 kV Switchyard (continued)

18. Confirm 286 (Bus 26 Wallace 230 kV PCB) is OPEN by observing N-i SRO the indicating ligrns

19. Open 28A (Bus 2A Wallace 230 Ky PCB) N-i SRO

20. Confirm 28A (Bus 2A Wallace 230 kV PCB) is OPEN by observing NI SRO the indicating lights

21. Open 276 (Bus 26 Town Creek 230 kV PCB) N-i SRO

22. Confirm 27B (Bus 28 Towli Creek 230 kV PCB) is OPEN by N-i SRO observing the indicating lights

23. Open 27A (Bus 2A Town Creek 230 kV PCB) N-i SRO

24. Confirm 27A (Bus 2ATown Creek 230 kV PCB) is OPEN by observing the indicating lights N-i SRO NOTE IT work is to be performed on a 230 kV bus, the manual disconnects are to be opened C

25. Place Supervisory switches for the following PCBs in REMOTE;

316 (Bus 28 Wtiiteville 230 kV Breaker) N-I SRO

306 (Bus 28 Delco West Line 230 kV Breaker)

286 (Bus 26 Wallace 230 kV Breaker) N-i SRO

278 (Bus 26 Town Creek 230 kV Breaker N-i SRO

3 JA (Bus 2A Whiteville 230 kV Breaker) N-i SRO

30A (Bus 2A Delco West Line 230 kV Breaker)

28A (Bus 2A Wallace 230 kV Breaker) N-i SRO

27A (Bus 2A Town Creek 230 kV Breaker) N-i SRO