Text

2014-11 Final Operating Test
	ML14336A376
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/21/2014
From:	Vincent Gaddy; Operations Branch IV
To:	;
	laura hurley
References
	Download: ML14336A376 (418)
	v • d • e

ES-301 Administrative Topics Outline Revision 0 Form ES-301-1 Facility: ANO-1 Date of Examination: 11-17-2014 Examination Level: RO SRO LI Operating Test Number: 2014-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations Estimate SEP Time to Boil Al 2.1.25 NIR Ability to interpret reference materials, such as (Imp 3.9) graphs, curves, tables, etc.

Al JPM-RO-ADMIN-SFPTTB Conduct of Operations Operate the Plant Computer A2. 2.1.19 D/S Ability to use plant computers to evaluate system (Imp 3.9) or component status.

Al JPM-NRC-ADMIN-PMS3 Equipment Control Perform DG1 Operability Test complete A3. 2.2.12 N/R evaluation of pump based on surveillance results Knowledge of surveillance procedures (Imp 3.7)

Al JPM-RO-SURV3 Radiation Control Review RWP and Survey Map to calculate maximum stay time.

A4. 2.3.7 M/R Ability to comply with radiation work permit (Imp 3.5) requirements during normal or abnormal conditions A1JPM-RO-DOSE-SVY2O14 Emergency Procedures/Plan N/A N/A NCTE A: ;terrs 5 tota are ered for SOs RO appoants rere Oy 4 tems tey are retaRng o iy t a a3nn strative topi s wfler a 5 are equ ea Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 (1) for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1) (3)

(P)revious 2 exams ( 1; randomly selected) (0)

ES-301 Administrative Topics Outline Revision 0 Form ES-301-1 Facility: ANO-1 Date of Examination: 1 1-17-2014 Examination Level: RO SRO Operating Test Number: 2014-1 Administrative Topic (see Type Describe activity to be performed Note) Code*

Conduct of Operations Door Breach requirements, determine need for a firewatch.

A5. 2.1.8 N/R Ability to coordinate personnel activities outside (Imp 4.1) the control room.

Al JPM-SRO-FIREWATCH Conduct of Operations Perform responsibilities & authorities of the SM as required, actions to take on OOS Chemistry Report A6. 2.1.34 DIR Knowledge of primary and secondary plant (Imp 35) chemistry limits Al JPM-SRO-CHEM 1 Equipment Control Utilize procedure deviation A7. 2.2.44 D/R A1JPM-SRO-PROC1 (Imp 4.4)

Radiation Control Potassium Iodine administration determination A8. 2.3 14 M/R Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or (Imp 3 8) emergency conditions or activities.

A1JPM-S RO-KJ Emergency Procedures/Plan Classify an Emergency Event Knowiedge of the emergency action level A9 2 441 N/S thresholds and classifications

( 4 A1JPMSRO EALI NOTE. All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs: 4 (2) for SROs & RO retakes)

N)ew or (Modified from bank ( (3)

P) 2 e arns ra )m se te (0)

ES-301 Control Roomlin-Plant Systems Outline Form ES-301-2 Facility: Arkansas Nuclear One Unit 1 Date of Examination: 11-17-2014 Exam Level: RO SRO-l SRO-U Operating Test No.: 2014-1 Control Room Systems© (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function a.

A1JPM-RO-A0P37 Respond to Continuous Rod 1 Withdrawal AID/LIP/S 001 AA1 .05 (RO 4.3/SRO 4.2) Reactivity Control RO/SRO-UISRO-l b.

A1JPM-RO-PZR01 Equalize Boron Concentrations between the RCS and the PZR A/D/S Reactor 010 A4.02 (RO 3.6/SRO 34) Pressure ROISRO-l Control C.

2 A1JPM-RO-EOP11 Perform Actions Required for an ESAS Actuation (Shift to RB Sump Suction) Reactor Coolant D/EN/L/S System 006 A4.02 (RO 4.0/SRO 3.8)

Inventory ROtS RO-l Control d.

A1JPM-RO-EOPO9 Energize Bus A2 from A4 in a Degraded Power Condition 6 A/D/E N/S 062 Al .01 (RO 34/SRO 3,8) Electrical ROISRO-l AIJPM-RO-A0F27 Respond to Inadvertent ESAS Actuation in A206 (RO 37/SRO 4.0) Contanment ROtS RO-UIS RO-l Integrity A1JPM-RO-E0P24 Reactor Tripped, check all NNI power available (Loss of NNI-X) 7 AID/S B&W APE A02 AAI .3 (RO 3,4/SRO 3.6) Instrumentation RO!SRO-l

g.

A1JPM-RO-A0P28 Respond to Simultaneous Loss of 4 Seal Injection and Seal Cooling N/S Heat Removal 003 A4.08 (RO 3.2ISRO 2.9) From Reactor RO Core (Primary) h.

A1JPM-RO-A0P29 Respond to Loss of Lake 8 Dardanelle Reservoir N/S Plant Service 075 A2.02 (RO 2.5/SRO 2.7)

Systems ROISRO-I In-Plant Systems@ (3 for RO) (3 for SRO-l) (3 or 2 for SRO-U) 4 A1JPM-RO-EFW1O Actions for swapping suction from L41B to T41 Heat Removal A/D/L!E/P/R From Reactor 061 Al .04 (RO 3.9/SRO 3.9)

Core ROISRO-UISRO-I (Secondary)

A1JPM-RO-EDO2O Place Battery Charger D-04A in service 6 D

058 AA1.03 (RO 3.l/SRO 3.3) Electrical ROIS RO-U!S RO-I k.

A1JPM-RO-LRWO2 Commence ThVMT T-16A Release 9 068 A302(RO 3.6/SRO 36) A/N/R Reactivity RO/SRO-U /SRO-I Release All RO and SRO-i control room (and n-plant systems must be different and serve different safety

!unctiins at f SRCJ. SvSte9s i.s seie nf-fecnt afy .n.onc 9 la ztes i0r .

S

1 Type Codes Criteria for RO I SRO-i / CR0-U (A$ternate oats 4-6 (6) / 4-6 (6) / 2-3 (3)

(c:ontrol room (D)irect from bank 9 (7) / 8(7) / 4 (3)

(E)mergency or abnormal n-plant 1 (1) / 1(1) / a 1 (1)

(EN)gineered safety feature (3) / (3) I al (1) (control room system)

(L)ow-Power / Shutdown 1 (3) I a 1(3> / a 1 (2)

(N)ew or (M)odified from bank including 1 (A) a 2 (4) / 2(4) / a 1 (2)

(P)revious 2 exams 3 (2) / 3(2) / 2 (1) (randomly selected)

(R)CA al (2)/a1(2)/1 (2) f65irnuiato

Page 5 of 6 SIM f C PERFORMANCE CHECKLIST STANDARD N/A SAT UNSAT EVALUATOR CUE: After the HPI Block valve is opened with flow and the examinee has started monitoring Pressurizer level, inform examinee that PZR level is in the band of 90 to 110 inches.

7. Operate HPI Block (CV-1220 or CV- Operated HPI Block (CV-1220 or 1285) associated with OP HPI pump CV-1285) associated with OP HPI C to maintain PZR level 90 to 110 pump to maintain PZR level 90 to inches. 110 inches. _____ _____ _____

POSITIVE CUE:

PZR level is ~100 inches.

8. Place RCP Seal INJ Block Momentarily depresses PB-1206 on (CV-1206) in OVRD. C04 and the green OVRD backlight is illuminated.

POSITIVE CUE:

CV-1206 green OVRD light is illuminated.

9. Operate Pressurizer Heater Banks 3, Hand switches HS-1106, HS-1007 4, and 5 in MANUAL as necessary to and HS-1010 placed in MAN as maintain RCS press 2050 to 2250 needed and RCS pressure is C psig. maintained in a band of 2050 to _____ _____ _____

2250.

POSITIVE CUE: (At least one handswitch must be RCS pressure is 2150 psig. placed in HAND for critical step)

END

Page 3 of 5 SIM g JPM ID: A1JPM-RO-AOP28 INITIATING CUE: The CRS/SM directs you to perform actions 1203.031, Exhibit A, RCP Seal Bleedoff Isolation.

C PERFORMANCE CHECKLIST STANDARDS N/A SAT UNSAT

1. Read and Acknowledge CAUTION prior to step 1.0 of Exhibit A.

Reads the CAUTION prior to step one POSITIVE CUE: and marks it as complete CAUTION has been read and marked as complete (place-kept)

2. On C13, place RCP Seal Bleed off (Alternate Path to Quench Tank) in CLOSE:

HS-1273 on C13 is taken from the AUTO

- P-32A ------- SV-1273 (HS-1273A)

C position to the CLOSE position. (valve _____ _____ _____

remains closed)

POSITIVE CUE:

SV-1273 handswitch is in the CLOSE postion.

- P-32B ------- SV-1272 (HS-1272A)

HS-1272 on C13 is taken from the AUTO C POSITIVE CUE: position to the CLOSE position. (valve _____ _____ _____

SV-1272 handswitch is in the CLOSE remains closed) postion.

- P-32C ------- SV-1271 (HS-1271A)

HS-1271 on C13 is taken from the AUTO C POSITIVE CUE: position to the CLOSE position. (valve _____ _____ _____

SV-1271 handswitch is in the CLOSE remains closed) postion.

- P-32D ------- SV-1270 (HS-1270A)

HS-1270 on C13 is taken from the AUTO C POSITIVE CUE: position to the CLOSE position. (valve _____ _____ _____

SV-1270 handswitch is in the CLOSE remains closed) postion.

EVALUATOR NOTE:

- If CV-1274 is closed by the incumbent then CV-1270, CV-1271, CV-1272, & CV-1273 should remain open and those steps will be N/A. Likewise if CV-1270, CV-1271, CV-1272 & CV-1273 are closed, CV-1274 does not need to be closed and will be N/A.

- C* indicates that isolation of seal bleedoff to all RCPs is critical and can be accomplished by performance of step 3 alone. If step 3 is not performed, then steps 4, 5, 6, & 7 must all be performed to isolate seal bleedoff to all RCPs.

Either is acceptable.

3. On C16 perform the following:

- Close RCP Seal Bleedoff (Normal)

On C16, HS-1274 is momentarily placed Return, CV-1274 (HS-1274) in the CLOSE position. CV-1274 C* _____ _____ _____

indicates closed as indicated by its POSITIVE CUE:

Green light ON and Red light OFF.

Green light for CV-1274 is ON and Red light is OFF.

CONTINUED

Page 4 of 6 SIM h JPM ID: A1JPM-RO-AOP29 C PERFORMANCE CHECKLIST STANDARDS N/A SAT UNSAT EVALUATOR CUE:

When the applicant acquires RT-5 for verification of EFW Actuation and Control, inform the incumbent that another operator has performed RT-5 and EFW actuation has been verified.

On the Train A EFIC matrix on C09,

4. Manually actuate EFW and perform depresses both EFW pushbuttons. On RT-5 (C09) the Train B EFIC matrix on C09, depresses both EFW pushbuttons.

C _____ _____ _____

POSITIVE CUE: EFW Pumps P-7A (CV-2613 & CV-P-7A & B are running supplying EFW 2663) & P-7B (HS-2805) start and to both Steam Generators. supply flow to both steam generators (FI-2645, FI-2646, FI-2647, FI-2648).

EVALUATOR NOTE:

- The MFW Pumps can be tripped in any order.

For A MFW Pump, HS-6709 on C02 is

5. WHEN EFW actuation has been momentarily placed in TRIP. Green verified, trip both MFW pumps. (C02) TRIPPED light is ON and Red LATCHED light is OFF above handswitch. Pump speed begins to lower.

For B MFW Pump, HS-6710 on C02 is POSITIVE CUE: momentarily placed in TRIP. Green Green TRIPPED light is on and red TRIPPED light is ON and Red LATCHED light is off for both A and LATCHED light is OFF above B MFW pump handswitch. Pump speed begins to lower.

EVALUATOR NOTE:

- The Atm Dump Isol Valves can be operated in any order.

6. Open Atm Dump Isol Valves (Modulating Valves)

On C09, HS-2676 for CV-2676 is taken

- SGA Atm Dump Isol Valve (CV-to the OPEN position and held until CV-2676) (C09) 2676 indicates open.

C - SGB Atm Dump Isol Valve (CV- _____ _____ _____

2619) (C09) On C09, HS-2619 for CV-2619 is taken to the OPEN position and held until CV-POSITIVE CUE: 2619 indicates open.

Green light OFF and Red light ON for CV-2676 and CV-2619

7. Read and acknowledge NOTE prior to step 5.

Reads the NOTE prior to step 5 and POSITIVE CUE: marks it as complete.

NOTE has been read and marked as complete (place-kept)

CONTINUED

Page 1 of6 Plant I JOB PERFORMANCE MEASURE Unit:

1 Rev 2

Date:

JPM ID: A1JPM-RO-EFW1O System/Duty Area: Emergency Feedwater System Task: Perform Actions for swapping suction from T-41 B to T-41 JTA# ANO1 -WCO-EFW-OFFNORM-36 KA Value RO 3.9 SRO 3.9 KA

Reference:

061 Al .04 Approved For Administration To: RO X SRO X Task Location: Inside CR Outside CR X Both Suggested Testing Environment and Method (Perform or Simulate):

Plant Site: Simulate Simulator: Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Plant Site X Simulator Lab Testing Method: Perform Simulate X Approximate Completion Time in Minutes: 20 Minutes Reference(s): 1203.002 Alternate Shutdown Examinees Name:

Logon ID:

Evaluators Name:

The Examnees performance was evaluated aganst the standards contained in this JPM and is determined to be Unsatisfactory:

StartTime tonTme Total Time Sge] Pate

SUnaftre indicates this JPM ha.s beerfcompared to its applicable procedure by qualified a individual (not the exa ee aa s cae cith bat resn

Page2of6 Plant i JPM ID: A1JPM-RO-EFW-1O THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

Prior to administration, ensure the Examinee has been briefed using Appendix E of NUREG-1021.

JPM INITIAL TASK CONDITIONS:

The plant has been shutdown due to fire in the cable spreading room Alternate Shutdown cooldown is in progress Emergency Feed water CST T-418 level is 29 feet The SM is monitoring T-41 B Q-CST Level TASK STANDARD:

Swap EFW suction to T-41 THIS AN ALTERNATE PATH JPM, success path will be manually aligning Service Water as suction for EFW pump.

TASK PERFORMANCE AIDS:

1203002 Alternate Shutdown Cooldown step 3.6

Page 3 of 6 Plant i JPM ID: Al JPM-RO-EFW-l 0 INITIATING CUE: The CRS/SM directs you to take actions for swapping of EFW pumps suction from T-41B toT-41 per section 3 of 1203.002 Alternate Shutdown Cooldown, step 3.6.

C PERFORMANCE CHECKLIST STANDARD N/A SAT EXAMINER NOTE: Once applicant goes to valve gallery direct the applicant to describe the location of CS-l 9 in the pit (NW of hatch opening). Tell applicant that the stem is UP on CS-i 9.

IF applicant cannot describe location of CS-i 9, have applicant enter the valve gallery to locate the valve.

1. Verify CST T-41 Supp to Cond. Verifies CST T-4i Supp to Cond.

Transfer header (CS-19) open. Transfer header (CS-19) open.

POSITIVE CUE:

CS-i9 stem is UP (see note above)

EXAMINER NOTE: For this JPM the Control Room will be evacuated. The Shift Manager (SM) will be in the Technical Support Center (TSC) and should be contacted report status or get direction.

2. Unlock AND open Condensate Supply Unlocked and attempted to open T-41 to EFW Suction (CS-275). CS-275 by rotating the handwheel in the counter-clockwise direction.

C NEGATIVE CUE: May call the SM in the TSC to make appropriate entry in CAT E CS-275 handwheel will not turn log (not required for SAT performance).

EXAMINER NOTE: If CS-275 failure is reported to the SM. he reports he needs a suction source aligned to maintain operation of EFW.

3. Verify SW Loop 1 and SW loop 2 Contacts the SM to verify SW pressurized Loop I and SW loop 2 are pressurized.

POSIT yE CUE Tue SM reports that SW LOGO I ac SW oon 2 nave 65 psq ressure ManuaUv open EFW SW Loou I ia a creen EF S occ isolation (CV-3850) AND EFW SW I isolahon (CV-3850) AND EFW Loop 2 isolation (CV-3851) SW Loop 2 isolation (CV-3851) by pushing down on the manual lever rotating the handwheel in the C counter-clockwise direction until POSITIVE CUE stem is UP and motion stops,

Page4of6 Plant i JPM ID: A1JPM-RO-EFW-10 C PERFORMANCE CHECKLIST STANDARD N/A SAT

5. Manually open P-7B suction from SW Manually opened P-7B suction (CV-2803) and close P-7B suction from from SW (CV-2803) by pushing CST (CV-2800) down on the manual lever rotating the handwheel in the counter POSITIVE CUE: clockwise direction until stem is UP and motion stops.

C CV-2803 stem is UP AND CV-2800 stem is DOWN. CLOSED P-7B suction from CST (CV-2800) by pushing down on the manual lever and rotating the handwheel in the clockwise direction until stem is DOWN and motion stops.

6. Check P-7B suction pressure rises to Verified P-7B suction pressure approximately SW Loop 1 pressure. rose to approximately SW Loop 1 pressure. May call SM for SW POSITIVE CUE:

pressure PDIS-2806 reads pegged high (point at meter)

OR SM reports P-7B suction pressure is 60 psig

7. Manually open P-7A suction from SW Manually OPENED P-7A suction (CV-2806) and close P-7A suction from from SW (CV-2806) by pushing CST (CV-2802). down on the manual lever rotating the handwheel in the counter-POSITIVE CUE: clockwise direction until stem is UP and motion stops, C CV-28o6isstemisUP AND CV-2802 stem is DOWN CLOSED PJA suction from CST (CV-2802) by pushing down on the manual lever and rotating the handwheel in the clockwise direction until stem is DOWN and motion stops.

8, Verify P7A suction pressrre rises to Verified P7A suction pressure approximately SW Loop 2 pressure. rose to approximately SW Loop 2 pressure. May call SM for SW POSITIVE CUE:

PDIS-2804 reads pegged high (point at

. pressure.

meter)

OR SM reports that P-7A suction pressure is 60 psig CONTINUED

Page 5 of 6 Plant i JPM ID: Al JPM-RO-EFW-i 0 C PERFORMANCE CHECKLIST STANDARD N/A SAT

9. Close SW loop 2 supply to P-7A telltale Closed SW loop 2 supply to P-7A vent (SW-i 085A) and SW loop 1 supply telltale vent (SW-i 085A) and SW to P-7B telltale vent (SW-i 0858) loop 1 supply to P-78 telltale vent POSITIVE CUE (SW-i 0858) by rotating the handwheels in the clockwise SW-i 085A and SW-i 0858 are closed direction until the stems are DOWN and motion stops END

Page 6 of 6 Plant i JPM ID A1JPM-RO-EFW-1O INITIAL CONDITIONS:

The plant has been shutdown due to fire in the cable spreading room Alternate Shutdown cooldown is in progress Emergency Feedwater CST T-41B level is 29 feet The SM is monitoring T-41B Q-CST level.

INITIATING CUE:

The CRSISM directs you to take actIons for swapping of EFW pumps suction from T-41 B to T-41 per section 3 of 1203 002 Alternate Shutdown Cooldown, step 3 6

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE: ALTERNATE SHUTDOWN DOCUMENT NO. CHANGE NO.

1203.002 025 WORK PLAN EXP. DATE REACTIVITY IMPACT N/A DYES DINPR NO SAFETY-RELATED IPTE SET# DYES DNO DYES ZNO TEMP MOD LEVEL OF USE DYES NO 0 CONTINUOUS C REFERENCE C INFORMATIONAL D MULTI-USE PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES ONO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/Interruption Questioning Attitude Multiple Tasks Placekeeping Overconfidence Self Check Vague or Interpretive Guidance Peer Check First Shift/Last Shift Knowledge Peer Pressure Procedures Change/Off Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY I DATE TIME FORM TITLE: FORM NO CHANGE NO VERtFICAIION COVER SHEET 10O0006A 056

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 49 of 80 1203.002 ALTERNATE SHUTDOWN CHANGE: 025 SECTION 3 Page 5 of 10 3.6 Perform the following:

3.6.1 Monitor FEW CST (T-41B) level indication.

3.6.2 WHEN FEW CST is <3, THEN manually alicin FEW sucrion to CST (T41) as follows:

A. In CST valve pit, verify CST T4l Supp to Cond Transfer Header (CSl9) open.

B. Unlock and open Condensate Supply T41 to FEW Suction (CS275)

C. Check FEW Pump suction pressure rises.

3.6.3 IF necessary, THEN align FEW suction to Service Water as follows:

A. Verify SW Loop I arid SW Loop II pressurized.

B. Manually open the following:

EFW SW Loop I Isolation (CV3850)

FEW SW Loop EL isolation (CV3851)

C. Perform the following:

I. Manually open P7B S.UCT from SW (CV2803)

2. ManuaL I y close P7B SUCT from COT çCV28OO)

ID, Check P7P section pressure rIses ro approximately SW Loop I pro F, Perform t.he following:

1. Manua.lI. v oen P7A SOOT from SW (CV2806)

2. Manua.ii.c close P7A SOOT :OT (CV2802i O oO 0 cc

SW oop .J opp!v0o 5 e:aLe cot

SW Loop I Scurly to pnp Telltale Vent 5WlE85B

Appendix D Scenario Outline Form ES-D-1 Facility: ANO-1 Scenario No.: 4-R3 Op-Test No.: 2014-1 Examiners: ____________________________ Operators: _____________________________

Initial Conditions:

- SW Pumps P-4A & P-4C in service

- P-4B MOD selected to A4

- B-55/56 aligned to B6

- SG-3 closed, SG-4 open

- Unit Load Demand is failed. Setpoint cant be changed

- Control Rods Group1 Rod 3 and Group 4 Rod 7 will fail to fully insert on reactor trip

- ADV Isolation CV-2676 will not open electrically Turnover:

- Plant power is at 100%

- 250 EFPD

- Place P-4B Service Water Pump in service on A4 at the earliest opportunity to support scheduled maintenance. OAO has been briefed and is standing by at the intake structure.

Event Event Event Malf. No.

No. Type* Description Swap Service Water pumps per 1104.029, Service Water and N-(BOP) 1 N/A Auxiliary Cooling to support scheduled maintenance. Place P-N-(SRO) 4B in service and stop P-4C.

Power range nuclear instrument NI-5 fails (drifts) high requiring I-(ATC) Reactor Demand and Diamond stations to HAND per 1203.001, 2 NI240 I-(SRO) ICS Abnormal Operation & 1203.021, Loss of Neutron Flux TS Indication.

(Technical Specification - 3.3.1, RPS Instrumentation)

P-4B Service Water Pump trips. Restart P-4C per 1203.012I, C-(BOP)

Annunciator K10 Corrective Action for SERV WATER PUMP 3 CO_P4B4 C-(SRO)

TS TRIP (K10-A3) alarm.

(Technical Specification 3.7.7 - Service Water System)

R-(ATC) Loss of condenser vacuum. Power reduction required per MC088 C-(BOP) 1203.016, Loss of Condenser Vacuum. Unit Load Demand 4 DI_ICC0009L DI_ICC0009R C-(SRO) station does not respond requiring use of SG/RX Demand C-(ATC) station to control power reduction.

~75 gpm tube rupture in the B SG. Perform actions of M-(ALL) 1202.006, Tube Rupture EOP.

5 RC002 TS (Technical Specifications 3.4.13 - RCS Leakage, 3.7.4 - Secondary Activity)

Reactor Trip required due to low condenser vacuum. Perform M-(ALL) reactor trip actions of 1202.006, Tube Rupture EOP. Control RD451 6 C-(ATC) rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the RD455 (CT) core. Emergency boration required per immediate action contingency.

Atmospheric Dump Valve isolation fails closed. To commence a 7 CV2676 (CT) RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 33

Appendix D Scenario Outline Form ES-D-1 SCENARIO 4 OBJECTIVES Evaluate individual ability to swap operating Service Water pumps.

Evaluate individual ability to identify and respond to a Power Range Nuclear Instrument failure (high).

Evaluate individual ability to identify and respond to a Service Water Pump trip.

Evaluate individual ability to identify and respond to a Loss of Condenser Vacuum.

Evaluate individual ability to identify and respond to a failure of the Unit Load Demand to operate.

Evaluate individual ability to identify and respond to a Tube Rupture.

Evaluate individual ability to identify and respond to a Reactor Trip with a Tube Rupture in progress.

Evaluate individual ability to identify and respond to two Control Rods not fully inserting on a reactor trip.

Evaluate individual ability to perform Emergency Boration when required.

Evaluate individual ability to identify and respond to a failure of CV-2676, ADV isolation during SG Tube Rupture.

Evaluate individual ability to recognize when conditions require the entry into technical specifications conditions.

ATTRIBUTES MALFUNCTIONS: (5)

- Event 2 - NI-5 Drifts High

- Event 3 - SW Pump P-4B trip

- Event 4 - Loss of Condenser Vacuum

- Event 4 - ICS ULD station fails to respond

- Event 6 - Two stuck rods on reactor trip requiring Emergency Boration MALFUNCTIONS AFTER EOP ENTRY: (1)

- Event 6 - Two stuck rods on reactor trip requiring Emergency Boration ABNORMAL EVENTS: (3)

- NI-5 Drifts High - 1203.001 ICS Abnormal Operation AOP

- P-4B SW Pump Trip - 1203.030 Loss of Service Water AOP

- Loss of Condenser Vacuum - 1203.016 Loss of Condenser Vacuum AOP MAJOR TRANSIENTS: (2)

- Tube Rupture

- Rx Trip with two stuck rods EOP w/ SUBST. ACTIONS: (1)

- 1202.006 - Tube Rupture EOP w/ CONTINGINCIES: (1)

- 1202.006 - Tube Rupture CRITICAL TASKS: (2)

- Emergency Boration should be directed and started within 15 minutes of the reactor trip.

- Make A SG (good SG) available for steaming prior to reaching 1000 psig RCS pressure. Bad SG should only be steamed if needed to limit level rise due to leakage or assist in maintaining cooldown rate.

Page 2 of 33

Appendix D Scenario Outline Form ES-D-1 SCENARIO 4 NARRATIVE The crew will assume plant responsibility at 100% power.

The SRO will direct placing P-4B Service Water (SW) Pump in service on A4 bus and stopping P-4C SW Pump as directed in 1104.029 Service Water and Auxiliary Cooling Water.

(This will be briefed as part of turnover). (N-BOP), (N-SRO)

After P-4B is in service, power range nuclear instrument will fail (drift) high. This will result in a false signal being sent to the ICS system and will cause control rods to insert. A cross limit developed within the ICS system will cause Feedwater flow to rise. The ICS Reactor Demand must be placed in HAND and Diamond rod control station placed in MANUAL to stabilize the plant. This will release the Feedwater system to control RCS average temperature.

As the instrument fails high, the A RPS channel will trip on high power (104.9%). The alternate signal channel will be selected on HS-509 and the ICS returned to automatic. The SRO should enter and direct actions from 1203.001, ICS Abnormal Operation and 1203.021, Loss of Neutron Flux Indication AOP. Technical Specification 3.3.1, RPS Instrumentation should be referenced for applicability. (I-ATC), (I-SRO), TS When ICS is back in AUTO, P-4B SW pump will trip resulting in only one SW pump running. The SRO will enter 1203.012I, K10 Annunciator Corrective Action or 1203.030, Loss of Service Water AOP. The SRO will direct starting P-4C SW pump to restore system flow and pressure. The SRO should reference Technical Specification 3.7.7, Service Water System for applicability. (C-BOP), (C-SRO), TS An unisolable leak will occur in the main condenser will result in lowering condenser vacuum. The SRO will enter 1203.016, Loss of Condenser Vacuum AOP and will direct a power reduction to attempt to stabilize condenser vacuum. When the ATC attempts to reduce the demand set-point on the Unit Load Demand (ICS) station to lower power, the demand will not change. Due to this failure, the SG/RX Demand station must be placed in HAND to lower plant power. This demand is not rate limited and the ATC must manually control the rate of change of the power reduction. (R-ATC), (C-BOP - Loss of Vacuum), (C-ATC - ULD failure), (C-SRO -

Loss of Vacuum)

Shortly after power deduction begins a Tube Rupture will occur in the B Steam Generator (SG) (approx. 75 gpm). The SRO should enter 1202.006, Tube Rupture EOP and continue with the power reduction. Makeup from the Borated Water Storage Tank (BWST) will be aligned and HPI will be used if necessary to maintain pressurizer level. (Tech Specs: 3.4.13, RCS Operational Leakage - 3.7.4, Secondary Specific Activity. (M-ALL)

When reactor power reaches approximately 75% power, condenser vacuum will reach a value that will require a turbine trip (24.5 Hg if > 180 MW). If the reactor is not tripped manually the Turbine will automatically trip on low vacuum. The reactor will trip on anticipatory trip when the turbine trips with power >43%. When the reactor trips, two control rods will fail to fully insert into the core (Group 1 rod 3 and Group 4 rod 7). The SRO will direct actions for the reactor trip starting at step 11 of 1202.006, Tube Rupture EOP. With more than one rod not fully inserted, emergency boration must be performed as a contingency of the Reactor Trip immediate actions (step 11 of 1203.006, Tube Rupture in this case). The ATC will align boric acid flow to the makeup tank in accordance with RT-12. (M-ALL), (C-ATC)

CT - Emergency Boration should be directed and started within 15 minutes of the reactor trip.

Continued on Next Page Page 3 of 33

Appendix D Scenario Outline Form ES-D-1 Due to the loss of condenser vacuum (< 21 Hg), the Turbine Bypass valves will become unavailable to return steam to the main condenser. The Atmospheric Dump valves (ADV) are used to limit steam pressure and to perform cooldown of the RCS. When the A SG ADV isolation valve (CV-2676) is demanded to open, it will not open electrically. An AO must be dispatched to manually open CV-2676. This will permit the unaffected (good) SG to be used for RCS cooldown. If CV-2676 is not opened, the B (bad) SG must be used for RCS cooldown.

This would result in an additional release to the public and a potential escalation of EAL classification.

CT - Make A SG (good SG) available for steaming prior to reaching 1000 psig RCS pressure. Bad SG should only be steamed if needed to limit level rise due to leakage or assist in maintaining cooldown rate.

END OF NARRATIVE Page 4 of 33

Appendix D Required Operator Actions Form ES-D-2 Simulator Instructions for Scenario 4 Recall IC 123 Verify the following in the director summary:

Insert override DI_ICC0009L to FALSE ------------------------------------------- LOWER,UNIT LOAD DEMAND Insert override DI_ICC0009R to FALSE ------------------------------------------ RAISE,UNIT LOAD DEMAND Insert malfunction RD451 ------------------------------------------------------------- STUCK ROD ON RX TRIP GRP 3 ROD 1 10.7%

Insert malfunction RD455 ------------------------------------------------------------- STUCK ROD ON RX TRIP GRP 4 ROD 7 17.9%

Insert malfunction CV2676 to 0 ----------------------------------------------------- SG-A ATM Dump Isol Insert malfunction NI240 on event 1 ------------------------------------------------ NI-5 DRIFTS HI Insert remote CO_P4B4 to OFF on event 2 -------------------------------------- CO_P4B4 SERVICE WATER PUMP P4B MOD Insert malfunction MC088 from 800 to 1200 in 300 on event 3 ------------- CONDENSER VACUUM LEAK 0-6000 SCFM Insert malfunction RC002 to 0.15 in 300 on event 4 --------------------------- OTSG B TUBE RUPTURE 0-40 TUBES Verify the following initial conditions:

- P-4A & P-4C SW Pumps in service

- P-4B MOD selected to A4

- B-55/56 aligned to B6

- SG-3 CLOSED, SG-4 OPEN

- Operator Adjustable Low Vacuum in service and vacuum alarm setpoint is appropriate.

Event Value/Ramp Time Malf. No. Event Description No. Time Swap Service Water pumps per 1104.029, Service 1 0 N/A N/A Water and Auxiliary Cooling to support scheduled maintenance. Place P-4B in service and stop P-4C.

Power range nuclear instrument NI-5 fails (drifts) high requiring Reactor Demand and Diamond Trigger 1 2 12 N/A stations to HAND per 1203.001, ICS Abnormal NI240 Operation & 1203.021, Loss of Neutron Flux Indication.

Trigger 2 P-4B Service Water Pump trips. Restart P-4C per 3 25 CO_P4B4 OFF 1203.012I, Annunciator K10 Corrective Action for SERV WATER PUMP TRIP (K10-A3) alarm.

Loss of condenser vacuum. Power reduction Trigger 3 required per 1203.016, Loss of Condenser Vacuum.

MC088 800-1500/300 4 30 Unit Load Demand station does not respond DI_ICC0009L FALSE requiring use of SG/RX Demand station to control DI_ICC0009R FALSE power reduction.

Trigger 4 ~75 gpm tube rupture in the B SG. Perform actions 5 37 0.15/300 RC002 of 1202.006, Tube Rupture EOP.

Reactor Trip required due to low condenser vacuum.

Perform reactor trip actions of 1202.006, Tube RD451 N/A 6 Setup Rupture EOP. Control rods group 1 rod 3 and group RD455 N/A 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must 7 Setup CV2676 0 manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

END OF SIMULATOR INSTRUCTIONS

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 1 Event

Description:

Swap Service Water pumps per 1104.029, to support scheduled maintenance.

Place P-4B in service and stop P-4C.

Time Position Applicants Actions or Behavior EXAMINER NOTE:

Swapping of Service Water pumps will be briefed prior to the start of the scenario. The Auxiliary Operator will be standing by in the intake structure to support the activity.

Direct the BOP operator to place P-4B in service and stop P-4C per 0 SRO 1104.029.

BOP Use step 9.0, Pump Rotation section of 1104.029 to perform activity.

EXAMINER NOTE:

In the following action, additional loads that may be placed in service are SW to EDGs or SW to containment coolers.

IF desired to lower SW pressure prior to starting third SW pump for pump rotation, then lower SW loop pressure by opening the following if needed:

BOP - ICW Coolers Loop 1 SW bypass (SW-4026A)

- ICW Coolers Loop 2 SW bypass (SW-4026B)

- If additional loads are required, then list additional loads BOOTH OPERATOR CUE:

If contacted as the AO to adjust SW header pressure, use following remote commands as directed to adjust pressure.

- SW4026B

- SW4026B Determine SW alignment per Table 9.1.4.

- P-4A & B running - SG-3 closed BOP

- P-4B aligned to bus A4 - SG-4 open

- B-55/56 aligned to bus B6 - All crosstie valves open CONTINUED NOTES Page 6 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 1

- CONTINUED Event

Description:

Swap Service Water pumps per 1104.029, to support scheduled maintenance.

Place P-4B in service and stop P-4C.

Time Position Applicants Actions or Behavior BOP Verify P-4B MOD selected to A4. (HS-3608 on C18)

BOP Verify B-55/56 aligned to bus B6. (CST-B56 on C10)

BOP Verify SG-3 is closed and SG-4 is open. (HS-3722 & HS-3723 on C26)

BOP Inform Auxiliary Operator that P-4B will be started.

Make plant announcement for starting P-4B SW pump and stopping P-4C BOP SW pump.

BOP Start P-4B Service Water pump for A4 bus. (HS-3609 on C16)

Direct the Auxiliary Operator to verify there is proper packing leakoff on P-BOP 4B shaft.

BOOTH ROLE PLAY:

- If contacted as the AO verify proper packing leakoff on P-4B SW pump, wait ~ 1 minute and report there is normal packing leakoff on P-4B SW pump.

- If directed to report P-4B discharge pressure and strainer P observe ACW pressure on SPDS and add ~ 3 psig and report that value. For strainer P, report ~ 2 psid.

EXAMINER NOTE:

Per the turnover it will not be desired to obtain shutoff head data.

When proper packing leakoff has been verified, inform the Auxiliary BOP Operator that P-4C SW pump will be stopped.

CONTINUED NOTES Page 7 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 1

- CONTINUED Event

Description:

Swap Service Water pumps per 1104.029, to support scheduled maintenance.

Place P-4B in service and stop P-4C.

Time Position Applicants Actions or Behavior BOP Stop P-4C SW pump. (HS3610 on C16)

BOP Direct the Auxiliary Operator to check for reverse rotation.

BOOTH ROLE PLAY:

If directed as the AO to check for reverse rotation on P-4C SW pump, wait ~ 30 seconds and report that P-4C shaft has stopped, there is no reverse rotation.

Restore any SW loads that were placed in service to lower SW header BOP pressure.

BOOTH OPERATOR CUE:

If contacted the AO to adjust SW header pressure, use following remote commands as directed to adjust pressure.

- SW4026B

- SW4026B ANY Monitor SW bay levels on PMS/PDS/SPDS.

EXAMINER NOTE This event is complete when P-4B Service Water pump is running, AND P-4C Service Water Pump is secured, OR As directed by the Lead Evaluator NOTES Page 8 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 2 Event

Description:

Power range nuclear instrument NI-5 fails (drifts) high requiring Reactor Demand and Diamond stations to HAND Time Position Applicants Actions or Behavior 12 ATC Notice and report unexpected control rod insertion.

ANY Diagnose and report that NI-5 is failing high.

ATC Acknowledge and report SASS MISMATCH alarm. (K07-B4)

EXAMINER NOTE:

1203.001, ICS Abnormal Operations AOP contains a note that allows the operators to take actions to stabilize the plant prior to referencing the AOP. Once the plant is stabilized the AOP should be used to verify that proper actions were performed and complete any additional actions.

Place ICS Reactor Demand station in HAND and Diamond rod control ATC panel in MAN.

ATC Verify that ICS Feedwater Controls stabilize T-ave and RCS pressure.

Enter 1203.001, ICS Abnormal Operations, Section 1 - Neutron Flux SRO High/Low.

ATC Acknowledge and report RPS TROUBLE alarm. (K08-C3)

(This alarm is due to the A RPS Channel tripping on high power as NI-5 fails high)

Refer to 1203.012G Annunciator K08 Corrective Action for K08-C3, RPS ANY TROUBLE.

ANY Observe RPS CHANNEL A light on K1633 (C13) illuminated or flashing.

Diagnose and report that the failed NI has caused A RPS channel to ANY trip.

CONTINUED NOTES Page 9 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 2

- CONTINUED Event

Description:

Power range nuclear instrument NI-5 fails (drifts) high requiring Reactor Demand and Diamond stations to HAND Time Position Applicants Actions or Behavior Select the good Neutron Flux signal for indication.

ATC (HS-509 to Y [NE-511/512] on C03)

SRO Refer to Loss of Neutron Flux indication, 1203.021.

Direct the board operator to return ICS to automatic per the ICS normal SRO operating procedure.

ATC Reference 1105.004, Integrated Control System, section, Section 11.0 -

BOP Reactor Demand Transfer to AUTO.

Select MEAS VAR on Reactor Demand station and check the following:

ATC - T-ave correction is null (on the caret)

- Indicated T-ave is at setpoint (~579 Deg. F on TI-1032 on C03)

EXAMINER NOTE:

For this condition, the feedwater section on ICS maintains T-ave at setpoint.

If T-ave correction is indicated, place both Feedwater Loop Demand ATC stations to HAND and verify correction has been nulled.

ATC Verify that Neutron Error is zero. (NI-515 on C03)

BOP Place Diamond Panel in AUTO.

ATC (AUTO/MANUAL switch on Diamond Panel)

CONTINUED NOTES Page 10 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 2

- CONTINUED Event

Description:

Power range nuclear instrument NI-5 fails (drifts) high requiring Reactor Demand and Diamond stations to HAND Time Position Applicants Actions or Behavior ATC Observe AUTO lamp comes on indicating control inputs from ICS.

BOP (light inside AUTO/MANUAL pushbutton)

When T-ave correction is null and T-ave is at setpoint, place Reactor ATC Demand station in AUTO. (ICC0017 on C03)

ATC If additional stations were placed in HAND, use associated section of BOP 1105.004 to direct returning those stations to AUTO.

Reference Technical Specification 3.3.1 for operability requirements.

SRO (Condition A for one channel inoperable, place channel in bypass or trip within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

TS Since channel trips, condition is already met. Should take action to bypass the failed channel)

EXAMINER NOTE:

Actions related to placing the A RPS channel in bypass may be assessed at the end of the scenario.

SRO Take action to initiate repairs on NI-5.

ANY Take action to bypass the SASS MISMATCH alarm for Neutron Flux.

BOOTH OPERATOR CUE:

If contacted to bypass the SASS alarm for Neutron Flux, wait ~ 5 minutes and use remote SASS01 to BYPASS to clear that SASS alarm.

BOOTH ROLE PLAY:

If contacted to bypass the SASS alarm for Neutron Flux, ~ 1 minute after the alarm is cleared, contact the control room and report that the SASS alarm for RCS pressure has been bypassed.

EXAMINER NOTE This event is complete when all ICS stations have been returned to AUTO OR As directed by the Lead Evaluator NOTES Page 11 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 3 Event

Description:

- P-4B Service Water Pump trips.

- Restart P-4C per 1203.012I, Annunciator K10 Corrective Action for SERV WATER PUMP TRIP (K10-A3) alarm.

Time Position Applicants Actions or Behavior 25 ATC Acknowledge and report SERVICE WATER PUMP TRIP alarm. (K10-A3)

BOP Determine and announce that P-4B SW Pump has tripped.

SRO Refer to 1203.012I, Annunciator K10 Corrective Action.

BOP SRO Determine pump trip was not caused by bus under-voltage.

SRO Determine that pump strainers are not clogged.

BOP Start P-4C Service Water pump.

CONTINUED NOTES Page 12 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 3

- CONTINUED Event

Description:

- P-4B Service Water Pump trips.

- Restart P-4C per 1203.012I, Annunciator K10 Corrective Action for SERV WATER PUMP TRIP (K10-A3) alarm.

Time Position Applicants Actions or Behavior BOOTH ROLE PLAY:

- If directed as the AO to go to the Intake Structure, add ~ 3 minutes to the first item addressed below.

- If directed as the AO to check for reverse rotation on P-4B SW pump, wait ~ 1 minute and report that P-4B shaft has stopped, there is no reverse rotation.

- If directed as the AO verify proper packing leakoff on P-4B SW pump, wait ~ 1 minute and report there is normal packing leakoff on P-4C SW pump.

- If directed as the AO to report P-4A and/or P-4C discharge pressure and strainer P observe ACW pressure on SPDS and add ~ 3 psig and report that value. For strainer P, report ~ 2 psid.

- If directed as the AO to investigate P-4B locally, wait ~ 1 minute and report that there is an acrid odor in the area, but all other indications are normal

- If directed as the AO to investigate the P-4B breaker (A-403), wait ~ 2 minutes and report that P-4B SW Pump breaker A-403 has a drop flag on the instantaneous overcurrent relay.

If only 1 SW pump is running and a second pump cannot be quickly SRO restored, go to Loss of Service Water. (1203.030)

Verify SW parameters and SW/ACW cooled components return to ANY normal.

CONTINUED NOTES Page 13 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 3

- CONTINUED Event

Description:

- P-4B Service Water Pump trips.

- Restart P-4C per 1203.012I, Annunciator K10 Corrective Action for SERV WATER PUMP TRIP (K10-A3) alarm.

Time Position Applicants Actions or Behavior BOOTH OPERATOR CUE:

If directed to rack down A-303 and/or A-403 for P-4B SW pump, use remote commands A303OP to DOWN and A403OP to DOWN as appropriate.

EXAMINER NOTE:

Loop 2 Service Water would be considered inoperable during the time that only one SW pump was running. When P-4C is started, operability is restored.

Reference Technical Specification 3.7.7 for operability requirements.

SRO (Condition A for 1 SWS loop inoperable, 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action to restore operability or be in mode 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and mode 5 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months )

EXAMINERS NOTE:

This event is complete when P-4C Service Water Pump is started AND Technical Specifications have been properly assessed OR As directed by the Lead Evaluator NOTES Page 14 of 33

Appendix D Required Operator Actions Form ES-D-2 Page 15 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 4 Event

Description:

Loss of condenser vacuum. Power reduction required per 1203.016.

Unit Load Demand station does not respond requiring use of SG/RX Demand station to control power reduction.

Time Position Applicants Actions or Behavior 30 ANY Notice and report lowering condenser vacuum.

EXAMINER NOTE:

Different actions may be taken based on the perceived severity of the power rise. The action to lower power may be to attempt to lower the ULD or the first action may be to place the SG/RX Demand station in HAND and lower power. Placing SG/RX Demand in HAND prevents reactor power from rising due to a loss of plant efficiency.

Take action maintain power < 100 %.

ATC (digital indication of reactor power can be read on the left four line florescent display above C03)

ATC If the ULD setpoint is lowered, recognize that it is not responding.

Place the SG/RX Demand station in HAND and maintain reactor power <

ATC 100%.

SRO Enter 1203.016, Loss of Condenser vacuum AOP.

Commence power reduction using the SG/RX Demand at approximate ATC rate designated by the SRO.

BOOTH OPERATOR CUE: Vacuum leak rate may be adjusted if necessary to force plant trip or operator actions Establish trip criteria low condenser vacuum.

SRO (automatic trip at 24.5 inches Hg)

CONTINUED NOTES Page 16 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 4

- CONTINUED Event

Description:

Loss of condenser vacuum. Power reduction required per 1203.016.

Unit Load Demand station does not respond requiring use of SG/RX Demand station to control power reduction.

Time Position Applicants Actions or Behavior SRO Refer to 1203.045, Rapid Plant Shutdown.

Notify outside operators of lowering condenser vacuum and to look for ANY reasons for lowering vacuum.

Direct the Auxiliary Operator to check status of the running vacuum ANY pumps.

BOOTH ROLE PLAY:

- If directed to check status of the condenser vacuum pumps, wait ~ 2 minutes and report that the vacuum pump separator level is normal, ACW outlet temperature is 82 degrees and the vacuum pump is operating normally.

- ~ 10 minutes after being directed to look for vacuum leaks, report as the OAO that there is a loud sound coming from the condenser boot area on the MFW LO Deck.

BOP Set the Transient Low Vacuum alarm on PMS. (Alarm menu)

Verify all Condenser Waterbox Inlet valves open.

BOP (HS-3630, HS-3626, HS-3622 and HS-3618 on C12)

Verify all Circ Water pumps running.

BOP (HS-3629, HS-3625, HS-3621 and HS-3617 on C12)

EXAMINERS NOTE:

This event is complete when a power reduction has commenced to stabilize condenser vacuum OR As directed by the Lead Evaluator NOTES Page 17 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 5 Event

Description:

~75 gpm tube rupture in the B SG. Perform actions of 1202.006, Tube Rupture EOP.

Time Position Applicants Actions or Behavior 35 ATC Acknowledge and report, B OTSG N-16 TROUBLE alarm. (K07-A6)

BOOTH OPERATOR CUE: Raise Vacuum leak rate to 3000 cfm.

ANY Observe rising counts on N16 and condenser offgas detectors. (SPDS)

ANY Observe computer calculated leakrate on PMS. (based on N16 counts)

ANY Observe and report tube leakage > 10 gpm.

SRO Enter 1202.006, Tube Rupture EOP.

Advise the SM to notify Nuclear Chemistry to begin offsite dose SRO projections and implement EAL classification.

EXAMINER NOTE:

Tech Specs for RCS Leakage can be assessed as part of follow-up questioning.

SRO may enter the following Technical Specifications:

3.4.13 - RCS Operational Leakage > 10 gpm identified leakage and 150 gpd primary to secondary leakage through any one SG.

SRO Condition A - If leakage is not within limits, reduce leakage to within limits within 18 TS hours.

Condition B - Required action and completion time of Condition A not met OR Pressure Boundary Leakage exists, OR Primary to Secondary Leakage not within limits, Be in MODE 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND Be in MODE 5 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

CONTINUED NOTES Page 18 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 5

- CONTINUED Event

Description:

~75 gpm tube rupture in the B SG. Perform actions of 1202.006, Tube Rupture EOP.

Time Position Applicants Actions or Behavior Open BWST outlet to the running HPI pump, CV-1407.

BOP (HS-1407 on C18)

Verify Pressurizer Level Control (CV-1235) maintains pressurizer level ATC 200. (LRS-1001 or LIS-1002 on C04)

If pressurizer level is not maintained 200,perform the following:

- Place RCP Seal Injection Block valve, CV-1206 in OVRD (PB-1206 on C04).

BOP - Operate HPI Block valve associated with the operating HPI pump the restore pressurizer level 200 (CV-1220 on C18).

- Isolate letdown by closing Letdown Coolers Outlet valve, CV-1221 (HS-1221 on C16).

Continue with power reduction at approximate rate designated by the ATC SRO. (Using the SG/RX Demand)

SRO Determine bad SG. (alarms indicate B SG is bad)

Verify Control of Secondary Contamination (1203.014) is being SRO performed.

BOOTH ROLE PLAY:

If directed as Auxiliary Operator to perform all or part of 1203.014, Control of Secondary Contamination AOP, acknowledge that you perform it.

EXAMINER NOTE:

If NI power is < 43% and the Turbine trips automatically due to low condenser vacuum, the reactor must be tripped manually to limit offsite release with a tube rupture in progress.

When condenser vacuum approaches 24.5 direct the ATC to trip the SRO reactor and perform immediate actions.

EXAMINERS NOTE:

This event is complete when the Reactor is tripped OR As directed by the Lead Evaluator NOTES Page 19 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 6 & 7 Event

Description:

- Reactor Trip required due to low condenser vacuum. Perform reactor trip actions of 1202.006, Tube Rupture EOP. Control rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

- Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

Time Position Applicants Actions or Behavior 45 SRO Direct actions from step 11 of 1202.006, Tube Rupture EOP.

ATC Depress the Reactor Trip pushbutton. (C03).

Verify all Control Rods are inserted (PI Panel on C13) and that reactor ALL power is lowering. (NI-505 & NI-506 on C03).

ALL Recognize failure of two control rod to fully insert into the core.

BOP Trip the Turbine. (PB-9201 on C01).

ALL Verify Turbine Throttle and Governor Valves are closed. (C32).

Verify Adequate Subcooling Margin. (> 30 Deg. F) (ICC display on C09 ALL or TI-1150A &TI-1150B on C04)

CONTINUED NOTES Page 20 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 6 & 7

- CONTINUED Event

Description:

- Reactor Trip required due to low condenser vacuum. Perform reactor trip actions of 1202.006, Tube Rupture EOP. Control rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

- Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

Time Position Applicants Actions or Behavior Commence Emergency Boration per RT12.

ATC CT CT - Emergency Boration should be directed and started within 15 minutes of the reactor trip.

SRO Verify Immediate actions complete per 1202.001, Reactor Trip EOP.

SRO Determine that the reactor is shut down and continue with the procedure.

EXAMINER NOTE:

The following are the actions for initiating Emergency Boration per RT-12. These are normally performed by the ATC while the SRO and BOP continue with EOP actions.

If both OP and STBY HPI pumps are off or Letdown is isolated THEN go ATC to step 2.

EXAMINER NOTE:

The following are the actions for performance of step 1 of RT-12. This step uses the boric acid pumps to inject boric acid into the Makeup Tank.

If step 2 is required skip down to that section.

Set batch controller for maximum batch size. (9999999)

ATC (Batch controller on C04)

CONTINUED NOTES Page 21 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 6 & 7

- CONTINUED Event

Description:

- Reactor Trip required due to low condenser vacuum. Perform reactor trip actions of 1202.006, Tube Rupture EOP. Control rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

- Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

Time Position Applicants Actions or Behavior Verify Condensate to Batch Controller, CV-1251 closed.

ATC (HS-1251 on C04)

ATC Open Batch Controller Outlet, CV-1250. (HS-1250 on C04)

Verify both Makeup Filters in service:

ATC - F-3A (HS-1246 on C04)

- F-3B (HS-1247 on C04)

ATC Start available Boric Acid Pumps, P-39A or P-39B or BOTH (on C04).

ATC Record initial Boric Acid Addition Tank (BAAT) level. (LI-1604 on C04).

Start Batch Controller by depressing RUN key.

ATC (Green RUN key on Batch Controller)

Adjust Batch Controller Flow control valve to 100%.

ATC (depress VALVE/CE button on Batch Controller)

Verify Batch Controller output rate 5 gpm.

ATC (depress the RATE/8 button on the Batch Controller)

CONTINUED NOTES Page 22 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 6 & 7

- CONTINUED Event

Description:

- Reactor Trip required due to low condenser vacuum. Perform reactor trip actions of 1202.006, Tube Rupture EOP. Control rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

- Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

Time Position Applicants Actions or Behavior ATC Adjust pressurizer level setpoint to 220. (Knob on LIC-1000 on C04)

ATC Verify BWST Outlet valve, CV-1407 open. (HS-1407 on C18)

When pressurizer level is > 100 maximize letdown flow as allowed by ATC cooling capacity and component limitations.

(Knob on FIC-1223 on C04. Monitor flow on FI-1236 on C04)

EXAMINER NOTE:

The following are the actions for performance of step 2 of RT-12.

ATC Initiate HPI per RT-2.

Verify HPI Block valve associated with the running HPI pump, CV-1220 ATC open. (HS-1220 on C18)

If letdown is in service the place the 3-way valve, CV-1248 in BLEED.

ATC (HS-1248 on C04)

When pressurizer level is 100, then establish maximum Letdown flow ATC allowed by cooling capacity and component limitations.

CONTINUED NOTES Page 23 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 6 & 7

- CONTINUED Event

Description:

- Reactor Trip required due to low condenser vacuum. Perform reactor trip actions of 1202.006, Tube Rupture EOP. Control rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

- Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

Time Position Applicants Actions or Behavior Maintain pressurizer level 200 to 220 as follows:

- Verify both HPI pump RECIRC Block valves open:

- CV-1300 (HS-1301 on C16)

ATC

- CV-1301 (HS-1301 on C18)

- Throttle HPI Block valve, CV-1220 as necessary (HS-1220 on C18).

(Last required step for RT-12 Step 2)

EXAMINER NOTE:

The following actions are for Initiating HPI per RT-2.

If HPI initiation is for any reason other than Emergency Boration (RT-12),

THEN isolate Letdown by closing either CV-1221 (C16) or CV-1214 and BOP CV-1216 (C18).

Letdown should not be isolated due to RT-12 being in progress.

Verify BWST outlet CV-1407 open. (C18)

BOP CV-1407 should have already been opened previously based on EOP direction.

Open HPI block valve CV-1220 to maintain PZR level and RCS pressure.

BOP (C18)

Level and pressure band should be provided by the SRO.

CONTINUED NOTES Page 24 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 6 & 7

- CONTINUED Event

Description:

- Reactor Trip required due to low condenser vacuum. Perform reactor trip actions of 1202.006, Tube Rupture EOP. Control rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

- Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

Time Position Applicants Actions or Behavior If PZR level continues to drop, THEN open additional HPI Block valves BOP associated with the OP HPI pump. (CV-1219, CV-1278, CV-1279 on C18)

IF PZR level or RCS press continues to drop, THEN place ES HPI pump BOP in service.

BOP Open BWST outlet, CV-1408. (C16)

Verify both HPI Pump RECIRC Blocks open, (CV-1300 on C16 and CV-BOP 1301 on C18) or HPI Block valve associated with ES HPI pump (CV-1285 on C16) fully open.

Start Aux Lube Oil pump associated with the ES HPI Pump. (P-64C on BOP C16)

CONTINUED NOTES Page 25 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 6 & 7

- CONTINUED Event

Description:

- Reactor Trip required due to low condenser vacuum. Perform reactor trip actions of 1202.006, Tube Rupture EOP. Control rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

- Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

Time Position Applicants Actions or Behavior When BWST outlet (CV-1408) is open, Start the ES HPI pump (P-36C on BOP C16)

Open HPI block valve CV-1285 to maintain PZR level and RCS pressure BOP (C16)

If PZR level continues to drop, THEN open additional HPI Block valves BOP associated with the ES HPI pump. (CV-1227, CV-1228, CV-1284 on C16)

BOP Monitor makeup tank level and control per step 10 as necessary If all HPI block valves are open and additional HPI flow is required, BOP THEN close HPI Pump RECIRC Block (CV-1300 on C16 or CV-1301 on C18)

CONTINUED NOTES Page 26 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 6 & 7

- CONTINUED Event

Description:

- Reactor Trip required due to low condenser vacuum. Perform reactor trip actions of 1202.006, Tube Rupture EOP. Control rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

- Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

Time Position Applicants Actions or Behavior EXAMINER NOTE:

The following are the actions for the Tube Rupture EOP starting at step 14.

BOP Verify header pressure controlling setpoint adjusted to 45.

Check Turbine Bypass valves controlling SG pressure 950 to 990 psig in AUTO.

BOP (Observe SG pressures on C09. PI-2618A or PR2618B for A SG. PR-2667A or PI-2667B for B SG.

EXAMINER NOTE:

At 21 Hg vacuum in the main condenser the Turbine Bypass valves will be interlocked closed and the Atmospheric Dump valve (ADV) isolation valves will open. This allows the ADVs to control SG pressures automatically at 1020 psig. In this case the A SG ADV isolation valve (CV-2676) is failed closed and will not open electrically.

CONTINUED NOTES Page 27 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 6 & 7

- CONTINUED Event

Description:

- Reactor Trip required due to low condenser vacuum. Perform reactor trip actions of 1202.006, Tube Rupture EOP. Control rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

- Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

Time Position Applicants Actions or Behavior If the Turbine Bypass valves are not available, then verify the ADVs BOP control SG pressure 1000 to 1040 psig. (CV-2668 and CV-2618 on C09)

BOP Check MSSV open alarms clear. (K07-C5)

(This alarm should be clear)

Advise the SM to notify Nuclear Chemistry to begin offsite dose SRO projections and implement EAL classification.

BOP Verify Orifice Bypass valve, CV-1223 closed. (FIC-1223 on C04)

(This valve may remain open or be reopened by Emergency Boration)

BOP Verify BWST Outlet valve, CV-1407 open. (HS-1407 on C18)

Check Main Generator and Exciter Field breakers open:

- B5114 (C01)

BOP

- B5118 (C01)

- Exciter Field Breaker (C01)

EXAMINER NOTE:

Pressurizer Cooldown limits do not apply during a Tube Rupture.

ATC Operate pressurizer heaters and spray to maintain RCS pressure low BOP within the limits of figure 3. (normally 40 to 50 deg. F Subcooling Margin)

CONTINUED NOTES Page 28 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 6 & 7

- CONTINUED Event

Description:

- Reactor Trip required due to low condenser vacuum. Perform reactor trip actions of 1202.006, Tube Rupture EOP. Control rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

- Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

Time Position Applicants Actions or Behavior ATC Place all pressurizer heaters in off.

BOP (6 handswitches on C04, Banks 1, 2, 3, 4, 5 and Group 5)

ATC Places the pressurizer spray valve CV-1008 in manual and opens it fully BOP (on C04)

When RCS pressure drops below 1700 psig and Subcooling Margin is adequate (> 30 Deg. F) and RCS pressure is controlled, then bypass ESAS.

ATC - When RCS pressure is < 1700 psig but >1590 psig, momentarily BOP depresses the three (3) yellow ESAS Low RCS pressure trip bypass pushbuttons.

- Verify ES ANALOG LO PRESS BYPASS alarms on K11 in alarm.

(K11-F2, K11-F3, K11-F4)

CONTINUED NOTES Page 29 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 6 & 7

- CONTINUED Event

Description:

- Reactor Trip required due to low condenser vacuum. Perform reactor trip actions of 1202.006, Tube Rupture EOP. Control rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

- Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

Time Position Applicants Actions or Behavior Stabilize pressurizer level as follows:

- Adjust pressurizer level control setpoint to 100 (this should not be done due to emergency boration in progress)

ATC - If HPI is in service, then adjust HPI flow as necessary to maintain BOP pressurizer level 55 and RCS pressure low within the limits of figure 3 (this should be coordinated with emergency boration)

- If pressurizer level is, 55 or pressurizer level is predicted to drop below 55 then initiate HPI (RT-2) (this can be done in addition to emergency boration.)

Verify N16 detector selected to GROSS. (RI-2691 and RI-2692 on C24)

BOP (This is performed by withdrawing the indicator drawer from the panel and checking the status of a slide switch on a circuit board)

ATC Verify bad SG.

BOP (all indications show that B SG is bad)

CONTINUED NOTES Page 30 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 6 & 7

- CONTINUED Event

Description:

- Reactor Trip required due to low condenser vacuum. Perform reactor trip actions of 1202.006, Tube Rupture EOP. Control rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

- Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

Time Position Applicants Actions or Behavior Verify Control of Secondary Contamination, 1203.014 is being SRO performed.

ATC Verify bad SG EFW Pump Turbine steam supply valve, CV-2617 BOP CLOSED. (HS -2617 on C09)

EXAMINER NOTE:

The criteria will not be met to perform an emergency cooldown for this scenario.

If bad SG level is approaching 410 due to leakage or dose rate Alert SRO criteria projected at the site boundary, then establish emergency cooldown rate of 240 deg. F/hr. to 500 deg. T-hot.

If emergency cooldown rate is not required or T-hot is 500 Deg. F then SRO establish RCS cooldown rate of 100 Deg. F/hr.

CONTINUED NOTES Page 31 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 6 & 7

- CONTINUED Event

Description:

- Reactor Trip required due to low condenser vacuum. Perform reactor trip actions of 1202.006, Tube Rupture EOP. Control rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

- Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

Time Position Applicants Actions or Behavior ATC Operate the Atmospheric Dump valve (ADV) for the A SG in HAND to BOP maintain a cooldown rate of 100 Deg. F/hr.

ATC Recognize and report that the A ADV isolation valve, CV-2676 will not BOP open electrically. (this failure may have been identified earlier)

Dispatch an operator to manually open CV-2676.

ANY CT - Make A SG (good SG) available for steaming prior to CT reaching 1000 psig RCS pressure. Bad SG should only be steamed if needed to limit level rise due to leakage or assist in maintaining cooldown rate.

BOOTH OPERATOR CUE:

If directed as the AO to manually open CV-2676, wait ~ 3 minutes open CV-2676 by modifying malfunction CV2676 to 1 over 120 seconds.

BOOTH ROLE PLAY:

When CV-2676 is open, report to the control room that CV-2676 has been manually opened.

ATC Establish RCS cooldown rate 100 Deg. F/hr using the A SG ADV.

BOP (Monitor cooldown rate on SPDS Cooldown Screen)

CONTINUED NOTES Page 32 of 33

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 4 Event No.: 6 & 7

- CONTINUED Event

Description:

- Reactor Trip required due to low condenser vacuum. Perform reactor trip actions of 1202.006, Tube Rupture EOP. Control rods group 1 rod 3 and group 4 rod 7 fail to fully insert into the core. Emergency boration required per immediate action contingency.

- Atmospheric Dump Valve isolation fails closed. To commence a RCS Cooldown, Aux Operator must manually open valve to allow use of unaffected (good) SG to perform RCS cooldown.

Time Position Applicants Actions or Behavior If only one SG is bad, then steam bad SG only as necessary to maintain Exhibit 1 limits.

Exhibit 1 limits are as follows:

- Steam bad SG only as necessary to maintain:

ALL - MSSVs closed

- SG pressure 1040 psig if using ATM Dump Control System

- SG Level 410

- SG Tube-to-Shell T 100 Deg. F (tubes colder) during normal cooldown.

- Desired cooldown rate if good SG TURB BYP Valve or ADV is full open.

Dispatch an operator to open AUX FW Pump RECIRC to E-11A ANY Isolation, FW-1.

BOOTH ROLE PLAY:

If directed as the Auxiliary Operator to open FW-1, wait ~ 2 minutes and report that FW-1 is OPEN.

ATC Verify Feedwater Pumps Discharge cross-tie, CV-2827 open. (C03)

BOP ATC Start P-75 (on C12)

BOP EXAMINERS NOTE:

This scenario may be terminated when a stable RCS cooldown using the A SG ADV OR As directed by the Lead Evaluator END OF SCENARIO NOTES Page 33 of 33

Appendix D Scenario Outline Form ES-D-1 Facility: ANO-1 Scenario No.: 2-R5 Op-Test No.: 2014-1 Examiners: __________________________ Operators: __________________________

Initial Conditions:

- 100% Power

- CV-2670 EFW isolation to A SG from P-7A failed open

- CV-2646 EFW control to A SG from P-7A failed open Turnover:

- Plant at 100% Power

- 250 EFPD

- Need to Drain RB Sump to 40%. This is not the first draining of the month and sampling is not required.

Event Event Event Malf. No.

No. Type* Description N-(BOP) Perform Draining of the Reactor Building Sump per 1 CV4400 N-(SRO) 1104.014.

C-(BOP) 2 ED180 C-(SRO) SU#1 Transformer Lockout (Technical Specification 3.8.1, AC Power Sources, Operating)

TS R-(ATC)

Heater Drain Pump (P-8B) windings heat up and pump 3 FW087 C-(BOP) trips C-(SRO) 4 RD273 TS Group 6 Rod 1 falls into the core. Runback to 40% power (Technical Specification 3.1.4, Control Rod Group Alignments)

I-(ATC) 5 TR631 RCP Seal Injection Flow Transmitter Failure (PDT-1239)

I-(SRO)

C-(ATC) Group 6 Rod 3 falls into the core. Unanalyzed condition 6 RD294 requiring manual reactor trip.

C-(SRO)

(Technical Specification 3.1.4, Control Rod Group Alignments.)

One MSSV fails to reseat resulting in Overcooling event.

M- (ALL) 7 MS141 Use of HPI is required to maintain RCS inventory and (CT) pressure CV2670 C-(ALL) EFW valves, CV-2670 & CV-2646 are failed open and will 8 not close.

CV2646 (CT)

(Technical Specification 3.7.5.B, One EFW train inoperable)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 29

Appendix D Scenario Outline Form ES-D-1 SCENARIO 2- OBJECTIVES Evaluate individual ability to perform Draining of the Reactor Building Sump Evaluate individual ability to identify and respond to a failure of the flow transmitter input to the Reactor Coolant Pump Seal Injection controller Evaluate individual ability to identify and respond to a trip of a Heater Drain Pump Evaluate individual ability to perform a plant power reduction in compliance with station procedures Evaluate individual ability to identify and respond to a lockout of the SU#1 Transformer.

Evaluate individual ability to identify and respond to a single dropped control rod.

Evaluate individual ability to identify and respond to two (2) dropped control rods.

Evaluate individual ability to perform reactor trip immediate actions Evaluate individual ability to identify and respond to an overcooling event as a result of a Main Steam Safety Valve failure to close Evaluate individual ability to perform Main Steam Line Isolation for the affected steam generator Evaluate individual ability to identify and respond to failed open Emergency Feedwater valves to the affected steam generator Evaluate individual ability to recognize when conditions require the entry into technical specifications conditions ATTRIBUTES MALFUNCTIONS: (5)

- Event 2 - SU#1 Transformer Lockout

- Event 3 - Heater Drain Pump Trip (P-8B)

- Event 5 - Seal Injection Flow Transmitter Failure

- Event 6 - 2nd Dropped Control Rod - Manual Reactor Trip

- Event 8 - EFW Valves Fail OPEN MALFUNCTIONS AFTER EOP ENTRY: (1)

- Event 8 - EFW Valves Fail OPEN ABNORMAL EVENTS: (2)

- P-8B Heater Drain Pump trip - 1203.045 Rapid Plant Shutdown AOP

- Dropped Control Rod - 1203.003 Control Rod Drive Malfunction Action AOP MAJOR TRANSIENTS: (1)

- Stuck Open MSSV/Overcooling EOP w/ SUBST. ACTIONS: (1)

- 1202.003 - Overcooling EOP w/ CONTINGENCIES: (0)

- NONE CRITICAL TASKS: (2)

- Initiate HPI per RT-2 prior to ESAS actuation (1590 psig)

- Stop overfeed of faulted SG by placing P-7B in P-T-L prior to isolating feed to both SG.

Page 2 of 29

Appendix D Scenario Outline Form ES-D-1 SCENARIO 2 - NARRATIVE The crew will assume responsibility for the plant at 100% power. The SRO will direct draining of the Reactor Building Sump per 1104.014 (this will be briefed as part of turnover). The RB Sump will be drained to ~ 40% and the evolution will secured.N-(BOP), N-(SRO)

An internal failure of the SU#1 Transformer will result in a lockout of the SU#1 Transformer.

This will render SU#1 Transformer inoperable and entry into Technical Specification 3.8.1 Condition A which requires performance of SR 3.8.1.1 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restore operability of the transformer within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . The corrective actions for K02-A1, SU 1 L.O. RELAY TRIP will direct the operators to use the normal operating procedure, 1107.001 to align SU#2 Transformer for Auto-Transfer. C-(BOP),

C-(SRO), TS The B Heater Drain Pump (P-8B) motor winding temperature will begin to rise. The crew should identify the rise in temperature via the plant computer alarm status or the associated annunciator alarm on K06-E8. The BOP and/or SRO should refer to the Annunciator Corrective Action and the SRO should direct a plant power reduction to ~630 MW (~70 % power) in anticipation of the trip of the heater drain pump in accordance with the Rapid Plant Shutdown AOP, 1203.045. R-(ATC), C-(SRO),C-(BOP)

SU#1 Transformer also feeds redundant power to the CRD system. A CRD programmer malfunction will result in a control rod (group 6 rod1) falling fully into the core. ICS will automatically run the plant back to ~ 40%. 1203.003 Control Rod Drive Malfunction Action AOP should be referenced to address the dropped control rod and 1203.045, Rapid Plant Shutdown AOP will be used to address the plant runback. Power should be stabilized <40% NI Power. TS RCP Seal Injection Flow Transmitter (PDT-1239) will fail low resulting in the RCP seal injection block valve (CV1206) closing and RCP seal injection control valve (CV-1207) opening fully. The SRO should direct the ATC to restore seal injection flow as directed by the Annunciator Corrective Action for RCP Seal Injection Flow Low. The control valve (CV-1207) must remain in HAND since there is no redundant transmitter for this function. l-(ATC) I-(SRO)

A second control rod (group 6 rod 3) will fall fully into the core. Per 1203.003 Control Rod Drive Malfunction Action AOP the reactor will be tripped and 1202.001 Reactor Trip EOP will be entered.

Reactor Trip immediate actions will be performed with no contingencies required. Due to SU#2 Transformer being aligned, automatic load-shedding will occur. This will result in only 2 RCPs (one in each loop) running post reactor trip. C-(ATC) C-(SRO)

When the reactor trips, a main steam safety valve on the A Steam Generator (SG) will fail open and will not reseat. This will result in an overcooling of the RCS. When A SG pressure is <900 psig, the Overcooling EOP, 1203.003 will be entered to address the event. HPI will be aligned if required.

The crew should identify the MSSV Open annunciator remains in alarm and recognize the lowering steam pressure (<900 psig) in the A SG. The SRO should transition to1202.003, the Overcooling EOP.M-(ALL)

Continued on next page Page 3 of 29

Appendix D Scenario Outline Form ES-D-1 Actuation of HPI will be required to maintain RCS pressure and Pressurizer level during Overcooling event. Repetitive task 2 (RT-2) will be utilized to initiate and control HPI flow. The Overcooling EOP directs that HPI be initiated if Pressurizer Level drops below 30 or RCS pressure is

< 1700 psig.

CT - HPI should be initiated prior to reaching the ESAS low RCS pressure of 1590 psig. CT During the isolation process of the A SG, the crew will identify the failure of the EFW valves to the A SG from P7B EFW pump to close. The SRO should direct the ATC/BOP to place the P7B handswitch to Pull - To - Lock and then actuate EFW. Potentially, EFW and MSLI could be actuated which would cause the A SG to be fed from EFW. The ATC/BOP should diagnose this and the SRO should direct placing P-7B in Pull-to-Lock to stop feeding the A SG and terminate the overcooling.

The SRO should reference Technical Specification 3.7.5.B, for One EFW train inoperable. C-(ALL) CT

- Feed to the faulted SG generator should be isolated prior to isolating feed to both SG The scenario can be terminated when EFW has been isolated to the A SG and the SG is dry.

Crew has taken actions to stabilize RCS temperature, pressure and inventory. B Turbine Bypass Valves utilized to stabilize RCS temperature. HPI is secured if initiated to limit RCS pressure and pressurizer level.

END OF NARRATIVE Page 4 of 29

Appendix D Scenario Outline Form ES-D2 Simulator Instructions for Scenario 2 Recall IC 121 Verify the following in the director summary:

malfunction ED180 on event 1 ----------------------------------------------------------- START UP #1 TRANSFORMER FAILURE malfunction FW087 on event 2 ----------------------------------------------------------- P8B MOTOR WINDING HEATUP malfunction RD273 to 0 on event 3 ----------------------------------------------------- DROP ROD GROUP 6 ROD 1 140-0 INCHES malfunction TR631 to 0 in 10 on event 4 ---------------------------------------------- TOTAL RCS SEAL FLOW (PDT1239) 0-80 GPM malfunction RD273 to 0 on event 5 ----------------------------------------------------- DROP ROD GROUP 6 ROD 1 140-0 INCHES malfunction MS141 after 30 to 6.00000 on event 6 --------------------------------- A OTSG SHIFT IN PSV 2696 LIFT&RESET 1-6 SET NO malfunction CV2670 to 1.00000 --------------------------------------------------------- EFW P-7B to SG A ISOL malfunction CV2646 to 1.00000 --------------------------------------------------------- EFW P-7B to SG-A CNTRL Verify RB Sump level ~50% (CAM021 at 16000)

Event Value/

Time Malf. No. Event Description No. Ramp Time Perform Draining of the Reactor Building 1 0 CV4400 N/A Sump per 1104.014.

Trigger 1 2 10 Min SU#1 Transformer Lockout ED180 N/A Trigger 2 Heater Drain Pump (P-8B) windings heat up 3 35 Min FW087 N/A and pump trips Trigger 3 Group 6 Rod 1 falls into the core. Runback to 4 50 Min 40% power RD273 0/0 sec Trigger 4 5 55 Min RCP Seal Injection Flow Failure (PDT-1239)

TR631 0/10 sec Trigger 5 Group 6 Rod 3 falls into the core. Unanalyzed 6 65 RD294 0/0 sec. condition requiring manual reactor trip.

One MSSV fails to reseat resulting in Rx Trip Trigger 6 7 Overcooling event. Use of HPI is required to

+ 30 sec MS141 6/0 sec maintain RCS inventory and pressure CV2670 1 EFW valves, CV-2670 & CV-2646 are failed 8 Initial Setup CV2646 1 open and will not close END OF SIMULATOR INSTRUCTIONS Page 5 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 1 Event

Description:

Perform Draining of the Reactor Building Sump per 1104.014.

Time Position Applicants Actions or Behavior IF in modes 1 - 4 AND this is the first sump drain of the month, THEN GO TO 0 BOP "Sampling RB Sump" section of this procedure.

EXAMINER NOTE:

Based on turnover, this is not the first sump drain of the month, therefore sampling is not required.

BOP Determines that sump sampling is not required.

BOP Notify RP of intent to drain RB sump.

Allow liquid in RB sump to gravity drain to AB sump by performing the following:

BOP - Place RB Sump to AUX Sump CV-4446 handswitch (HS-4446) to OPEN.

- Place RB Sump to AUX Sump CV-4400 handswitch (HS-4400) to OPEN.

Check Aux Building Sump level (LI-4403) goes up while RB Sump level (LI-BOP 1405) goes down.

CONTINUED NOTES Page 6 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 1

- CONTINUED Event

Description:

Perform Draining of the Reactor Building Sump per 1104.014.

Time Position Applicants Actions or Behavior EXAMINER NOTE:

Based on turnover, the desired final RB Sump level is 40%.

WHEN one of the following is met:

- Aux Building Sump (LI-4403) 60%

- Prior to Rx Bldg Sump Level (SPDS L1405) reaching 30.4%

BOP

- Rx Bldg Sump Level (SPDS L1405) at desired level THEN place RB Sump to AUX Sump CV-4400 handswitch (HS-4400) to CLOSE.

When RB sump level reaches desired level (40%), close CV-4400 by placing BOP HS-4400 in the close position.

IF further draining of RB Sump is desired AND Aux Building Sump level shows BOP capacity to receive water, THEN place RB Sump to AUX Sump CV-4400 handswitch (HS-4400) to OPEN AND GO TO step 8.5.

BOP Place RB Sump to AUX Sump CV-4446 handswitch (HS-4446) to CLOSE.

Place RB Sump to AUX Sump CV-4400 handswitch (HS-4400) to OPEN to BOP allow penetration #68 to drain.

After 1 to 2 minutes, place RB Sump to AUX Sump CV-4400 handswitch BOP (HS-4400) to close.

EXAMINER NOTE This event is complete when RB Sump Level is ~ 40%

AND CV-4400 & CV-4446 are closed OR As directed by the Lead Evaluator.

CONTINUED NOTES Page 7 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 2 Event

Description:

SU#1 Transformer Lockout Time Position Applicants Actions or Behavior Acknowledge and report the following alarms:

- SU1 L.O. RELAY TRIP (K02-A1) 10 ANY - SU1 SELECTED NOT AVAIL (K02-B1)

- SU1 TROUBLE (K02-C1)

- CRD MOTOR POWER FAILURE (K08-F2).

SRO Acknowledge that SU1 transformer is de-energized.

BOP Reference 1203.012B, Annunciator K02 Annunciator Corrective Action.

SRO SRO Direct the Auxiliary Operator to investigate SU1 transformer locally.

BOOTH ROLE PLAY:

- If directed as the Auxiliary Operator to investigate the SU1 Transformer locally, wait ~ 2 minutes and report that there is a PRESSURE RELIEF alarm in on SU1 Transformer. All other indications are normal.

- If an operator is sent to A1/A2/H1/H2 busses, wait ~ 2 minutes and report there are no abnormal conditions at A1 & A2 or H1 & H2 busses.

Declare SU1 Transformer inoperable per Technical Specification LCO 3.8.1 SRO Condition A. (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to perform SR 3.8.1.1. to verify operability of SU2 transformer and TS restore transformer operability in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and mode 5 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ).

CONTINUED NOTES Page 8 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 2

- CONTINUED Event

Description:

SU#1 Transformer Lockout Time Position Applicants Actions or Behavior Refer to 1107.001, Electrical System Operations, Section 14.0, Aligning SU2 BOP Feeder Breaksers for Auto-Transfer, Mode 1-4.

BOP Check SU2 considered operable.

SRO Inform Unit 2 CRS/SM of intent to align Unit 1 SU2 Feeder Breakers for Auto-BOP Transfer.

BOOTH ROLE PLAY:

If contacted as Unit 2 CRS/SM of intent to align SU2 Feeder Breakers for Auto-Transfer, acknowledge the communication and also report that Unit 2 is currently aligned for auto-transfer to SU2 on bus 2A1.

Direct the Auxiliary Operator to check Load Shedding Operable lamps BOP illuminated on breakers A-111 and H-13.

BOOTH ROLE PLAY:

If contacted as the Auxiliary Operator to check Load Shedding Operable light status, wait ~ 2 minutes and report that the Load Shedding Operable lamps on A-111 and H-13 are illuminated.

Direct the Auxiliary Operator to check Test Switch covers installed on TS-1 111 BOP (A-111) & TS-1 211 (A-211).

BOOTH ROLE PLAY:

If contacted as the Auxiliary Operator to check Test Switch cover status, wait ~ 1 minute and report that the Test Switch covers are installed on TS-1 111 on A-111 and TS-1 211 on A-211.

CONTINUED NOTES Page 9 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 2

- CONTINUED Event

Description:

SU#1 Transformer Lockout Time Position Applicants Actions or Behavior EXAMINER NOTE:

The 161kV breakers being closed on the C10 switchyard mimic indicates that the following transmission lines are in service.

Check ANO-Russellville East 161kV or Pleasant Hill 161kV transmission lines BOP in-service.

EXAMINER NOTE:

The voltage regulator for the SU2 transformer is in service and the 3% voltage reduction feature is disabled.

Contact the system dispatcher and check SU2 transformer voltage regulator BOP 3% voltage reduction disabled.

BOOTH ROLE PLAY:

- If contacted as the System Dispatcher regarding the status of the SU2 transformer 3% voltage reduction report that 3% voltage reduction feature on the SU2 transformer voltage regulator is disabled.

- If the dispatcher is questioned about the status of the SU2 voltage regulator status report that the SU2 transformer voltage regulator is in-service.

CONTINUED NOTES Page 10 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 2

- CONTINUED Event

Description:

SU#1 Transformer Lockout Time Position Applicants Actions or Behavior Check SU2 voltage on SPDS (EST2R) or PMS (E4013) is between 146 and BOP 175 kV.

Direct Unit 2 to place breaker 2A-111 in Pull-to-Lock and verify breakers 2A-BOP 211, 2H-13 & 2H-23 in Pull-to-Lock.

BOOTH ROLE PLAY:

If directed as Unit 2 to place 2A-111 in P-T-L and verify remaining breakers in P-T-L, wait ~ 3 minutes and contact the control room as Unit 2 CRS and report that breaker 2A-111 has been placed in Pull-to-Lock and 2A-211, 2H-13 & 2H-23 have been verified to be in Pull-to-Lock.

BOP Verify SU2 to A1, A-111 removed from Pull-to-Lock (C10).

Remove the following breakers from Pull-to-Lock:

- SU2 to A2, A-211 (C10)

BOP

- SU2 to H1, H-13 (C10)

- SU2 to H2, H-23 (C10)

BOP Place HS-143-1 & HS-143-2 on C10 to SU#2 position.

EXAMINER NOTE This event is complete when HS-143-1 & HS-143-2 are in the SU#2 position OR As directed by the Lead Evaluator NOTES Page 11 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 3 Event

Description:

Heater Drain Pump (P-8B) windings heat up and pump trips Time Position Applicants Actions or Behavior 35 ATC Acknowledge and report P8A/P8B MTR WDG TEMP HI alarm (K06-E8)

Observe indications on PMS/PDS or TR-2808 (C19) and determine P-8B ANY winding temperature is going up.

(Crew may elect to stop P-8B prior to the pump tripping.)

SRO Reference 1203.012E Annunciator K06 Corrective action for K06-E8.

SRO Initiate steps to determine cause of high temperature alarm.

ANY Direct an Auxiliary Operator to investigate P-8B locally.

BOOTH ROLE PLAY:

If directed as the Auxiliary Operator to check for abnormal conditions at P-8B HD pump, wait ~ 1 minute and report that there is nothing abnormal at P-8B ATC Set ICS rate of change to 10%/min (ICC0012 on C03).

Adjust the Unit Load Demand setpoint to ~ 630 MW (ICC009 on C03).

ATC (The pump may trip before a power reduction can be started.)

CONTINUED NOTES Page 12 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 3

- CONTINUED Event

Description:

Heater Drain Pump (P-8B) windings heat up and pump trips Time Position Applicants Actions or Behavior Enters and directs actions from 1203.045, Rapid Plant Shutdown, Section 1 -

SRO Rapid Plant Shutdown Without Small SG Tube Leak.

ATC Report power at frequency directed by the SRO.

ATC Determine and report proper integrated plant response.

BOP When P-8B trips or is turned off, acknowledge and report P8A/P8B FLOW LOW ATC alarm (K06-A8).

BOP Reference 1203.012E, Annunciator K06 Corrective Action for K06-A8.

Direct chemistry personnel to secure Zinc Injection per Unit 1 Reactor Coolant SRO System (RCS) Zinc Control (1052.036).

CONTINUED NOTES Page 13 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 3

- CONTINUED Event

Description:

Heater Drain Pump (P-8B) windings heat up and pump trips Time Position Applicants Actions or Behavior BOOTH ROLE PLAY:

If directed as a chemist to secure Zinc Injection, wait ~ 5 minutes and report to the Control Room that Zinc Injection has been secured per 1052.036.

BOP Direct the Auxiliary Operator to perform 1203.012E, Exhibit B, Local Actions for SRO Heater Drain Tank T-40B Level Control on High Level Dump.

BOOTH ROLE PLAY:

- If directed as the Auxiliary Operator to perform 1203.012E, Exhibit B, wait ~ 5 minutes and report that 1203.012E Exhibit B is complete and T-40B level is being maintained on the High Level Dump valve.

- If directed as the Auxiliary Operator to maintain monitor polisher flow and P, acknowledge the communication to the affirmative.

- If work management is notified requesting maintenance, report that a Work Order will be generated and given to the Shop.

BOP Verify Low Level Sprays open (HS-2907 on C02).

When plant is stabilized, instruct ATC to refer to Contingency Reactivity Plans SRO AND Exhibit A (Operation of APSR Group) of Power Operation (1102.004).

ATC Refer to Contingency Reactivity Plans and 1102.004 Exhibit A.

SRO Perform transient crew briefing of control room personnel.

EXAMINER NOTE This event is complete when plant power is stabilized within the capacity of the T-40B level control OR As directed by the Lead Evaluator NOTES Page 14 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 4 Event

Description:

Group 6 Rod 1 falls into the core. Runback to 40% power Time Position Applicants Actions or Behavior 50 ANY Acknowledge and report CONTROL ROD ASYMMETRIC alarm (K08-C2).

ANY Identify that control rod Group 6 Rod 1 has fallen into the core.

Enter 1203.003, Control Rod Malfunction Action, Section 2 - Dropped Rod -

SRO Reactor Critical.

SRO Notify ATC that if an additional rod drops, trip the reactor.

ATC Verify ICS runback to 40% (360MW).

BOP EXAMINER CUE:

AMSAC channel 1(ATWS) should be manually bypassed when power is < 45%. The hardware for this feature is not modeled in the simulator. If an operator is directed to bypass AMSAC channel, booth operator will need to bypass it.

BOOTH OPERATOR CUE:

If AMSAC Channel 1 is to be bypassed, use remote command AMSAC1BP to BYPASS to perform the bypass operation.

Enter 1203.045, Rapid Plant Shutdown, Section 1 - Rapid Plant Shutdown SRO Without Small SG Tube Leak and perform in conjunction with 1203.003.

BOP Trip P-8A Heater Drain Pump.

BOP Direct the Auxiliary Operator to perform 1203.012E, Exhibit A, Local Actions for SRO Heater Drain Tank T-40A Level Control on High Level Dump.

BOOTH ROLE PLAY:

If directed as the Auxiliary Operator to perform 1203.012E, Exhibit B, wait ~ 5 minutes and report that 1203.012E Exhibit A is complete and T-40A level is being maintained on the High Level Dump valve.

CONTINUED NOTES Page 15 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 4

- CONTINUED Event

Description:

Group 6 Rod 1 falls into the core. Runback to 40% power Time Position Applicants Actions or Behavior ATC Report power level at frequency specified by the SRO.

ATC Verify integrated plant response.

BOP When plant is stabilized, instruct ATC to refer to Contingency Reactivity Plans SRO AND Exhibit A (Operation of APSR Group) of Power Operation (1102.004).

ATC Refer to Contingency Reactivity Plans and 1102.004 Exhibit A.

EXAMINER NOTE:

Failure to maintain NI Power <40% with an asymmetric control rod will result in a CRD Out Inhbit and will prevent ICS from withdrawing control rods to maintain T-ave. If this is not addressed by the crew, an ICS cross-limit will be developed and ICS will reduce FW flow.

After runback is complete, maintain NI Power < 40% by lowering the ULD ATC setpoint.

ATC Maintain power in the band provided by the SRO.

SRO Perform transient crew briefing.

SRO Declare Group 6 Rod 1 inoperable (Technical Specification 3.1.4, Control Rod Group Alignments, verify shutdown margin within 1 TS hour, restore alignment within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce power to 60%).

EXAMINER NOTE:

This event is complete when power is stabilized <40% (360MW)

OR As directed by the Lead Evaluator NOTES Page 16 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 5 Event

Description:

RCP Seal Injection Flow Transmitter Failure (PDT-1239)

Time Position Applicants Actions or Behavior Acknowledge and report RCP SEAL INJECTION FLOW LO in 55 ANY Alarm. (K08-A7).

ANY Reference Annunciator K08 Corrective Action, 1203.012G for K08-A7.

Determine that there is not a simultaneous loss of both seal injection and seal ATC cooling by observing Seal Cooling Flow Low lights on C13 are not illuminated BOP and that seal temperatures are not rapidly rising on the RCP Seal recorders on C13 (QR-6520, QR-6521, QR-6522 & QR-6523)

(Seal temperatures may rise slowly and stabilize due to the loss of seal injection)

BOOTH ROLE PLAY:

If directed as the WCO to investigate CV-1206 and/or CV-1207 locally, wait ~2 minutes and report that there are no abnormal indications at either valve.

ATC Identify that RCP Seal Total Injection flow is lost.

ATC Identify and announce CV-1206, RCP Seal Injection Block valve has closed.

ATC Verify the Operating HPI Pump is running.

Place RC Pump seals Total INJ Flow (CV-1207) in HAND and close (FIC-ATC 1207on C04).

CONTINUED NOTES Page 17 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 5

- CONTINUED Event

Description:

RCP Seal Injection Flow Transmitter Failure (PDT-1239)

Time Position Applicants Actions or Behavior Place CV-1206 pushbutton in OVRD (OVRD light on for PB-1206 on C04) and ATC open CV-1206 (HS-1206 on C04).

Verify RCP Seal Bleedoff temperatures are < 180 degrees F (RCP seal BOP recorders on C13 or PMS/PDS).

Slowly open CV-1207 until RCP Seals individual flowrates are 8-10 gpm (FIC-ATC 1207).

Identify and announce RCP Seal Total Flow recorder is not functioning (FR-ATC 1239 on C04).

Determine that CV-1207 should not be placed in AUTO and CV-1206 should ANY be left in OVRD.

BOOTH ROLE PLAY:

If work management is notified requesting maintenance, report that a Work Order will be generated and given to the FIN team.

EXAMINER NOTE This event is complete when RCP seal injection flow has been restored OR As directed by the Lead Evaluator NOTES Page 18 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 6, 7 & 8

- CONTINUED Event

Description:

- Group 6 Rod 3 falls into the core. Unanalyzed condition requiring manual reactor trip.

- One MSSV fails to reseat resulting in Overcooling event.

- EFW valves, CV-2670 & CV-2646 are failed open and will not close.

Time Position Applicants Actions or Behavior ANY Diagnose and report second control rod has dropped into the core.

65 TS (Technical Specification 3.1.4, Control Rod Group Alignments.).

BOOTH OPERATOR CUE:

When the reactor is tripped, activate Trigger 6. This trigger has a built-in 30 second delay.

ATC Depress the Reactor Trip pushbutton (C03).

Verify all Control Rods are inserted (PI Panel on C13) and that reactor power is ALL lowering (NI-505 & NI-506 on C03).

BOP Trip the Turbine (PB-9201 on C01).

ALL Verify Turbine Throttle and Governor Valves are closed (C32).

Verify Adequate Subcooling Margin (> 30 Deg. F) (ICC display on C09 or TI-ALL 1150A &TI-1150B on C04).

SRO Enter 1202.001, Reactor Trip EOP.

CONTINUED NOTES Page 19 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 6, 7 & 8

- CONTINUED Event

Description:

- Group 6 Rod 3 falls into the core. Unanalyzed condition requiring manual reactor trip.

- One MSSV fails to reseat resulting in Overcooling event.

- EFW valves, CV-2670 & CV-2646 are failed open and will not close.

Time Position Applicants Actions or Behavior SRO Advise SM to implement Emergency Action Level Classification (1903.010).

Adjust letdown orifice bypass valve, CV-1223 demand adjusted to zero.

ATC (FIC-1223 on C04).

BOP Open BWST Outlet, CV-1407 (HS-1407 on C18).

ATC Adjust pressurizer level control setpoint to 100 (LIC-1000 on C04).

EXAMINER NOTE:

A steam generator pressure < 900 psig is an entry condition for 1203.003, Overcooling EOP.

ANY Recognize and report A SG pressure is < 900 psig.

SRO Enter 1202.003, Overcooling EOP.

CONTINUED NOTES Page 20 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 6, 7 & 8

- CONTINUED Event

Description:

- Group 6 Rod 3 falls into the core. Unanalyzed condition requiring manual reactor trip.

- One MSSV fails to reseat resulting in Overcooling event.

- EFW valves, CV-2670 & CV-2646 are failed open and will not close.

Time Position Applicants Actions or Behavior ATC Check Adequate Subcooling Margin (> 30 Deg. F) (ICC display on C09 or TI-BOP 1150A & TI-1150B on C04).

SRO Direct board operators to monitor floating steps.

If pressurizer level is < 55 inches with no indication of recovery, isolate letdown by closing:

ATC - CV-1221 (HS-1221 on C16)

BOP OR

- CV-1214 (HS-1214 on C18)

- CV-1216 (HS-1216 on C18)

ATC If pressurizer level drops below 55 inches, verify pressurizer heaters off.

If pressurizer level drops below 30 inches or RCS pressure < 1700 psig, then initiate HPI (RT-2).

BOP CT CT - Initiation of HPI should occur prior to ESAS low pressure actuation setpoint of 1590 psig RCS pressure.

CONTINUED NOTES Page 21 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 6, 7 & 8

- CONTINUED Event

Description:

- Group 6 Rod 3 falls into the core. Unanalyzed condition requiring manual reactor trip.

- One MSSV fails to reseat resulting in Overcooling event.

- EFW valves, CV-2670 & CV-2646 are failed open and will not close.

Time Position Applicants Actions or Behavior EXAMINER NOTE:

The following actions are for Initiating HPI per RT-2.

If HPI initiation is for any reason other than Emergency Boration (RT-12), THEN BOP isolate Letdown by closing either CV-1221 (C16) or CV-1214 and CV-1216 (C18).

Verify BWST outlet CV-1407 open. (C18)

BOP CV-1407 should have already been opened previously based on EOP direction.

Open HPI block valve CV-1220 to maintain PZR level and RCS pressure. (C18)

BOP Level and pressure band should be provided by the SRO.

If PZR level continues to drop, THEN open additional HPI Block valves BOP associated with the OP HPI pump. (CV-1219, CV-1278, CV-1279 on C18)

IF PZR level or RCS press continues to drop, THEN place ES HPI pump in BOP service.

BOP Open BWST outlet, CV-1408. (C16)

CONTINUED NOTES Page 22 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 6, 7 & 8

- CONTINUED Event

Description:

- Group 6 Rod 3 falls into the core. Unanalyzed condition requiring manual reactor trip.

- One MSSV fails to reseat resulting in Overcooling event.

- EFW valves, CV-2670 & CV-2646 are failed open and will not close.

Time Position Applicants Actions or Behavior Verify both HPI Pump RECIRC Blocks open, (CV-1300 on C16 and CV-1301 BOP on C18) or HPI Block valve associated with ES HPI pump (CV-1285 on C16) fully open.

BOP Start Aux Lube Oil pump associated with the ES HPI Pump. (P-64C on C16)

BOP When BWST outlet (CV-1408) is open, Start the ES HPI pump (P-36C on C16)

BOP Open HPI block valve CV-1285 to maintain PZR level and RCS pressure (C16)

If PZR level continues to drop, THEN open additional HPI Block valves BOP associated with the ES HPI pump. (CV-1227, CV-1228, CV-1284 on C16)

BOP Monitor makeup tank level and control per step 10 as necessary If all HPI block valves are open and additional HPI flow is required, THEN close BOP HPI Pump RECIRC Block (CV-1300 on C16 or CV-1301 on C18)

EXAMINER NOTE:

This completes RT-2 actions.

CONTINUED NOTES Page 23 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 6, 7 & 8

- CONTINUED Event

Description:

- Group 6 Rod 3 falls into the core. Unanalyzed condition requiring manual reactor trip.

- One MSSV fails to reseat resulting in Overcooling event.

- EFW valves, CV-2670 & CV-2646 are failed open and will not close.

Time Position Applicants Actions or Behavior EXAMINER NOTE:

With seal injection flow control in manual due to previous instrument failure, action must be taken to maintain seal injection flow when HPI flow is established from the operating HPI pump.

Adjust seal injection flow as needed to maintain 8 to 10 gpm per pump.

ATC (FIC-1207 on C04)

BOP If RCS T-cold 465 deg. F, trip one RCP (P-32A or P-32B).

SRO Check ESAS alarms clear on K11 (annunciator panel).

ATC SRO Check MSSV OPEN (K07-C5) alarm clear.

ATC ATC Report the MSSV OPEN annunciator is in alarm.

Determine that one MSSV open on A SG (indicated on ATOG screen on ATC SPDS).

EXAMINER NOTE:

The MSSV will not reseat for this scenario.

If SG A SG pressure is > 700 psig, attempt to reseat the MSSV by using the Turbine Bypass Valves (TBVs) in HAND to lower A SG pressure to 700 psig ATC or until the MSSV OPEN alarm clears then return TBVs to AUTO.

(ICC0014 on C03).

CONTINUED NOTES Page 24 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 6, 7 & 8

- CONTINUED Event

Description:

- Group 6 Rod 3 falls into the core. Unanalyzed condition requiring manual reactor trip.

- One MSSV fails to reseat resulting in Overcooling event.

- EFW valves, CV-2670 & CV-2646 are failed open and will not close.

Time Position Applicants Actions or Behavior SRO Initiate action to gag the stuck open MSSV (contact maintenance).

SRO Check RB pressure, 17 psia and stable.(ATOG screen on SPDS).

ATC SRO Check SG pressure > 600 psig (PI-2618A or PR-2618B on C09) AND MSLI ATC alarms clear on K12 (K12-7 & A8).

SRO Check EFW Off (EFW pushbuttons not backlit on C09 switch matrix).

ATC SRO Check SG levels at or approaching LO LEVEL LIMIT (20 to 40).

ATC SRO Check SG pressure 700 psig.

ATC ATC Close MSIV for SG with the lowest pressure (CV-2691 for A SG on C09).

CONTINUED NOTES Page 25 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 6, 7 & 8

- CONTINUED Event

Description:

- Group 6 Rod 3 falls into the core. Unanalyzed condition requiring manual reactor trip.

- One MSSV fails to reseat resulting in Overcooling event.

- EFW valves, CV-2670 & CV-2646 are failed open and will not close.

Time Position Applicants Actions or Behavior ATC Open Feedwater Pumps discharge cross-tie valve CV-2827 (HS-2827 on C03).

ATC Trip the B MFW pump (HS-6710 on C02).

EXAMINER NOTE:

The A MFW pump should be in service.

SRO Check one MFW pump operating.

ATC EXAMINER NOTE:

The A SG will not re-pressurize.

SRO Check both SGs begin to re-pressurize.

ATC ATC Close B MSIV (CV-2692 on C09).

CONTINUED NOTES Page 26 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 6, 7 & 8

- CONTINUED Event

Description:

- Group 6 Rod 3 falls into the core. Unanalyzed condition requiring manual reactor trip.

- One MSSV fails to reseat resulting in Overcooling event.

- EFW valves, CV-2670 & CV-2646 are failed open and will not close.

Time Position Applicants Actions or Behavior Actuate EFW (depress all four EFW buttons on switch matrix on C09) and verify ATC proper EFW actuation and control (RT-5).

Place EFW Pump Turbine K3 Steam Supply Valve from SG with lowest ATC pressure in MANUAL and CLOSE (CV-2667 on C09).

EXAMINER NOTE:

The A SG will not re-pressurize.

SRO Check both SGs begin to re-pressurize.

ATC ATC Close Main Feedwater Isolation to SG with lowest pressure (CV-2680 on C09).

EXAMINER NOTE:

The EFW isolation valves are modulating valves and the handswitches must be held in the close position until the valves indicate closed (green light on and red light off).

Place bad SG (A) EFW isolation valves in MANUAL and CLOSE (CV-2627 &

ATC CV-2670 on C09).

CONTINUED NOTES Page 27 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 6, 7 & 8

- CONTINUED Event

Description:

- Group 6 Rod 3 falls into the core. Unanalyzed condition requiring manual reactor trip.

- One MSSV fails to reseat resulting in Overcooling event.

- EFW valves, CV-2670 & CV-2646 are failed open and will not close.

Time Position Applicants Actions or Behavior EXAMINER NOTE:

The EFW isolation valve CV-2670 (motor operated) is failed and will not close when taken to close (red light will remain on and green light off). CV-2670 can be operated manually locally.

The EFW control valve, CV-2646 that is in series with CV-2670 is also failed open. This will result in full flow from P-7B electric EFW pump to the A SG (indicated on FI-2646). CV-2646 has a demand meter on its controller (HIC-2646) and an actual valve position meter above the controller. The demand meter will read zero and the position meter will read 100%. CV-2646 cannot be operated manually locally.

Determine and report that EFW isolation valve, CV-2670 and EFW control ATC valve, CV-2646 are failed open causing continuous feed to the A SG.

Perform 1 or both of the following:

- Verify the P-7A EFW pump is operating properly and stop P-7B EFW pump by placing HS-2805 for P-7B in Pull-to-Lock.

ATC

- Direct the WCO close CV-2670 (in upper north piping penetration room CT in the aux building) using the hand-wheel.

CT -Manual isolation of the A SG should occur to prevent need to isolate both SGs and lose primary to secondary heat transfer.

BOOTH OPERATOR CUE:

If directed to close CV-2670 locally, wait ~ 2 minutes and use malfunction CV2670 to 0 in 60.

BOOTH ROLE PLAY:

If directed as the WCO to close CV-2670, when CV-2670 is closed report that EFW isolation valve CV-2670 is closed.

CONTINUED NOTES Page 28 of 29

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 2 Event No.: 6, 7 & 8

- CONTINUED Event

Description:

- Group 6 Rod 3 falls into the core. Unanalyzed condition requiring manual reactor trip.

- One MSSV fails to reseat resulting in Overcooling event.

- EFW valves, CV-2670 & CV-2646 are failed open and will not close.

Time Position Applicants Actions or Behavior When all feed to the A SG is secured, the A SG boils dry and RCS ANY temperature begins to rise, report that Overcooling is Terminated.

SRO Transition to step 25 of 1203.003, Overcooling.

Operate the B SG Atmospheric Dump Control system to stabilize RCS temperature and prevent RCS heatup.

ATC - Verify B SG Atmos. Dump isolation valve open (CV-2619 on C09).

- Operate B SG Atmos. control valve, CV-2618 as necessary to stabilize RCS temperature (HIC-2618 on C09).

SRO P-7B EFW pump inoperable.

(Technical Specification 3.7.5 Condition B, One EFW train inoperable. 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action to restore TS EFW train to operable status or be in mode 4 in 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months ).

EXAMINER NOTE:

Feedwater will not be aligned to the A SG due to the failed open MSSV.

SRO Check feedwater aligned for each SG.

ATC Monitor Tube-to-Shell delta-T and cool down the RCS using 1203.040, Forced ATC Flow Cooldown as needed to maintain Tube-to-Shell delta-T 60 deg. F (tubes hotter).

EXAMINER NOTE:

This scenario is complete when the overcooling is terminated and the RCS pressure/temperature are stable OR As directed by the Lead Evaluator END OF SCENARIO NOTES END OF DOCUMENT Page 29 of 29

Appendix D Scenario Outline Form ES-D-1 Facility: ANO-1 Scenario No.: 1-R4 Op-Test No.: 2014-1 Examiners: ____________________________ Operators: _____________________________

Initial Conditions:

- 80% Power - RPS is failed and will not cause a reactor trip.

- 250 EFPD - Manual Reactor Trip Pushbutton failed

- P-36A MU/HPI pump OOS for seal replacement

- P-36B MU/HPI pump in service Turnover:

- Plant at 80% per load dispatcher request to limit line - P-36A HPI pump tagged out for seal replacement.

loading. - Perform generator field ground test per 1102.004,

- 250 EFPD at earliest opportunity.

Event Event Event Malf. No.

No. Type* Description DO_264A N-(BOP) 1 Perform Generator Field Ground Test K04C6 N-(SRO)

I-(ATC) Controlling RCS pressure transmitter fails causing pressure 2 TR458 I-(SRO) indication to drift high.

(T.S. 3.4.1 Condition A, RCS pressure not within COLR limits)

TS (T.S. 3.3.1 RPS Instrumentation)

K09E3 Pressurizer Heater ground fault alarm due to fault on RUB-14 &

3 DI_HS1007A TS 15 in Group 5, Tech Spec required heaters.

AO_HS1007AG (T.S. 3.4.9 Condition C, ES powered PZR heater capacity)

AO_HS1007AR Operating Makeup/HPI pump, P-36B winding heatup and failure C-(ALL) 4 CV096 causes pump to trip.

TS (T.S. 3.5.2 Condition A, One or more ECCS trains inoperable)

CV018 R-(ATC)

Degraded seal on P-32D RCP meets requirement to reduce 5 CV022 C-(BOP) power and secure the pump.

C-(SRO)

During coast-down of the D RCP, a break in the cold leg occurs that results in RCS leakage requiring reactor trip.

CV026 M-(ALL) Adequate Subcooling Margin is lost requiring running reactor 6

RC005 (CT) coolant pumps stopped within 2 minutes. CT-1, Time Critical Operation Action (2 min)

(T.S. 3.4.13 Condition A, RCS leakage not within limits)

RP246 RPS is failed and the manual trip pushbutton is failed requiring RP247 C-(ATC) use of backup pushbuttons to trip the reactor. CT-23, Time 7 RP248 C-(SRO) Critical Operator Action (1 min)

(T.S. 3.3.1 Condition C, Three or more RPS channels inoperable)

RP249 (CT)

(T.S. 3.3.2 Condition A, Manual Trip function inoperable)

DI_ICC0020 (T.S. 3.3.3 Condition B, Two or more Reactor Trip Modules inoperable)

C-(BOP) Small oil leak on #2 EDG causes fire alarm. CT - Stop #2 EDG 8 FS_B1_5_L_R C-(SRO) within 15 minutes of report of smoke.

(CT) (Technical Specification 3.8.1, AC Sources Operating)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 41

Appendix D Scenario Outline Form ES-D-1 SCENARIO 1 OBJECTIVES Evaluate individual ability to perform a Generator Field Ground Test.

Evaluate individual ability to respond to a failure of the controlling RCS pressure transmitter.

Evaluate individual ability to respond to a Pressurizer Ground Fault alarm.

Evaluate individual ability to respond to a trip of the operating MU/HPI pump with one MU/HPI pump already out of service.

Evaluate individual ability to identify and respond to a degraded Reactor Coolant Pump seal.

Evaluate individual ability to perform a plant power reduction in compliance with station procedures.

Evaluate individual ability to identify and respond to excess RCS leakage inside the reactor building.

Evaluate individual ability to identify and respond to conditions requiring reactor trip based on RCS leakage.

Evaluate individual ability to perform reactor trip immediate actions.

Evaluate individual ability to identify and respond to a loss of subcooling margin.

Evaluate individual ability to respond to a smoke alarm.

Evaluate individual ability to recognize when conditions require the entry into technical specifications conditions.

ATTRIBUTES MALFUNCTIONS: (5)

- Event 2 - Controlling RCS pressure instrument fails high

- Event 4 - Operating HPI pump trips

- Event 5 - RCP P-32D Seal Degradation

- Event 7 - Rx Trip Pushbutton Failed

- Event 8 - Smoke alarm/Oil leak on #2 EDG MALFUNCTIONS AFTER EOP ENTRY: (2)

- Event 7 - Rx Trip Pushbutton Failed

- Event 8 - Smoke alarm/Oil leak on #2 EDG ABNORMAL EVENTS: (3)

- PZR Heater Ground Fault - 1203.015 Pressurizer Systems Failure AOP

- Operating HPI pump trip - 1203.026 Loss of Reactor Coolant Makeup AOP

- P-32D Seal Degradation - 1203.031 Reactor Coolant Pump and Motor Emergencies AOP MAJOR TRANSIENTS: (1)

- Seal Failure/LOCA/LOSM/ESAS EOP w/ SUBST. ACTIONS: (2)

- 1202.002 - Loss of Subcooling Margin

- 1202.010 - ESAS EOP w/ CONTINGENCIES: (1)

- 1202.002 - Loss of Subcooling Margin CRITICAL TASKS: (2)

- Trip Rx using backup pushbuttons within 1 minute

- Trip all running RCPs within 2 minutes of a Loss of Subcooling Margin

- Stop #2 EDG within 15 minutes of report of smoke Page 2 of 41

Appendix D Scenario Outline Form ES-D-1 SCENARIO 1 NARRATIVE The crew will assume plant responsibility at 80% power. The plant will be at 80% per load dispatcher request to limit line loading.

The SRO will direct that BOP perform a generator field ground test (This will be briefed as part of turnover). The BOP operator will utilize 1102.004, Power Operation procedure to perform the task. The BOP will place the GEN FIELD GROUND TEST handswitch in TEST and subsequently the GENERATOR FIELD GROUND alarm (K04-C6) will come in indicating that a ground exists. The BOP will re-perform the test to check that the alarm returns. Actions will be taken to validate that only a single ground exists. Indications will support that only a single ground exists and the plant will be able to operate. (N-BOP), (N-SRO)

The controlling RCS pressure transmitter (PT-1021) will fail causing the pressure indication to drift high. This will cause a SASS MISMATCH (K07-B4) alarm to come in indicating a deviation of the controlling pressure signals. 1203.012F Annunciator K07 Corrective Action (ACA) should be referenced. This will direct the operators to verify that the alternate instrument (PT-1038) is reading as expected and then the ATC operator will select PT-1038 for control on panel C04. This will cause heaters to come on to restore RCS pressure. Heaters may be operated manually by the ATC if directed by the SRO If PT-1038 is not selected before the pressure indication reaches 2205 psig the pressurizer spray valve (CV-1008) will open. This will cause a rapid reduction in actual RCS pressure. The ATC will take manual control of CV-1008 and close the valve to stabilize RCS pressure. After PT-1038 is selected, Pressurizer Spray Valve CV-1008 may be placed back in auto. Crew should verify that RCS recovers to approximately 2155 psig and stabilizes. If the failure is not addressed in a timely manner, it could result in opening of the pressurizer spray valve (CV-1008) and the Electromatic Relief Valve (ERV) (PSV-1000). If the spray valve and ERV are both open, a rapid reduction on RCS pressure will occur. This would be addressed by entering in the Pressurizer Systems Failure AOP, 1203.015. If RCS pressure is <2082.2 psig, TS 3.4.1, Condition A, RCS Pressure, Temperature, and Flow DNB Limits (per COLR) is applicable. When the failed pressure instrument reaches 2355 psig, the A RPS channel will trip on high RCS Pressure. This would require entry into TS 3.3.1 for RPS Instrumentation. The SRO may direct that the A RPS channel be placed in maintenance bypass per 1105 .001, NI & RPS Operating Procedure. (I-ATC), I-SRO), TS A pressurizer heater ground fault alarm will come in due to a ground fault on RUB-14 Group 5 Heaters. This is a vital swing powered, bank of Tech Spec required heaters. The Crew should reference 1203.012H Annunciator K09 Corrective Action (ACA) & 1203.015, Pressurizer Systems Failure AOP, Section 3 - Inoperative Pressurizer Heater(s). The ATC should identify the loss of light indication on RUB-14 and notify the SRO. The ATC should energize additional heaters in Manual if needed to maintain RCS pressure. The AO should be dispatched to investigate the status of the supply breaker B-5663. The AO will report that breaker B-5663 is in the tripped position. If the AO is directed to attempt to reset B-5663, the AO will report that the breaker was reset and taken to close and the breaker immediately tripped back open.

(Resetting a tripped breaker is allowed per a limit and precaution contained in 1107.002, ES Electrical System Operation). The SRO should reference TS 3.4.9 and TRM 3.4.9 and declare RUB-14 heaters inoperable (72hr Action). Work Management personnel should be contacted to direct electrical maintenance personnel to perform the Pressurizer Proportional Heater Checkout to determine KW output. Although not directed by procedure, vital pressurizer heater current values are available on the SPDS computer and could be monitored by the control room operators to aid in determining heater status. TS Continued on Next Page Page 3 of 41

Appendix D Scenario Outline Form ES-D-1 The windings on the operating Makeup/HPI pump (P-36B) will heat up and cause annunciator K10-E7, HPI PUMP MTR WDG TEMP HI alarm to come in when the temperature reaches 260 deg. F. The BOP operator should reference chart recorder TR-6501 or point T1260 on the plant computer to determine the value and trend of the temperature. The SRO/BOP should reference 1203.012I, Annunciator K10 Corrective Action, and take action to stop the Makeup/HPI pump. 1203.026, Loss of Reactor Coolant Makeup AOP, Section 1 - Loss of HPI Pump, will be entered by the SRO to address the loss of normal makeup to the RCS and Seal Injection to the RCP seals. The BOP operator isolates Letdown by closing CV-1221, Letdown Isolation Valve, and verifies that the RCP seals are being cooled by the ICW system by monitoring temperatures on the RCP seal chart recorders and/or Plant Computer. Due to P-36A pump being out of service as part of the initial condition, the WCO operator will be dispatched to perform a manual valve alignment to align the ES HPI pump P-36C to take suction from the Makeup Tank and supply normal makeup and seal injection. This manual alignment will take approximately 10 minutes to perform. If the SRO determines that P-36C will need to be vented, the WCO will be directed to momentarily open P-36C vent valve ABV-9C. Makeup Control Valve CV-1235 and Seal Injection Flow Control Valve CV-1207 will be closed in HAND by the ATC.

The BOP operator will start P-36C and the ATC will restore seal injection by opening block valve CV-1206 and throttling open on CV-1207 to establish 30 to 40 gpm of seal injection and placing CV-1207 back in AUTO. The ATC will then throttle open on CV-1235 to establish on-scale makeup flow and then place CV-1235 into AUTO. The BOP operator will restore letdown using 1202.012 Repetitive Tasks - RT-13. The SRO should reference Tech Spec 3.5.2 and declare 1 train of ECCS inoperable per Condition A (72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action). (C-ALL), TS Reactor Coolant Pump P-32D shaft seal will begin to degrade as evidence by elevated seal cavity pressures and changing seal parameters as monitored on P-32D Seal Recorder QR-6523 and/or the Plant Computer. Annunciator K08-D7, RCP SEAL CAVITY PRESS HI/LO will alarm and will direct the SRO to perform 1203.031 Reactor Coolant Pump and Motor Emergencies AOP, Section 1 - Seal Degradation. The ATC/BOP will verify that seal bleed-off and seal injection are aligned properly. The BOP operator will be directed to monitor seal parameters and will be provided an attachment that provides criteria that if met would require performance of particular steps or sections of the AOP. Delta-P across a single seal stage will exceed 2/3 of system pressure that will require that power be reduced to 70% power and P-32D stopped using the normal operating procedure 1103.006 Reactor Coolant Pump Operation.

(R-ATC), (C-BOP) (C-SRO)

During coast-down of P-32D, the cold leg associated with P-32D will experience failure which will result in a significant loss of reactor coolant. The RCS leakrate will be large enough to warrant a reactor trip. The SRO should direct the ATC to trip the reactor. RPS is failed and will not cause a reactor trip. The manual reactor trip pushbutton is failed so when the ATC pushes the button, the reactor will not trip. The ATC should depress both backup pushbuttons beside the reactor trip button within 1 minute of depressing the reactor trip pushbuttion Continued on Next Page Page 4 of 41

Appendix D Scenario Outline Form ES-D-1 Failure to manually trip the reactor in a timely manner could result in exceeding a safety limit. (CT) Reactor tripped prior to 1700# RCS Pressure. (CT) Backup pushbuttons should be depressed within 1 minute of pushing the manual reactor trip pushbutton (Time Critical Operator Action). These backup buttons remove power from the CRD system allowing the control rods to drop into the core. Once the reactor is tripped, the ATC and BOP operators will continue performing the remainder of the immediate actions. The Turbine will be verified to be tripped and the status of Subcooling margin determined. The SRO will enter 1202.001 Reactor Trip EOP. The following Tech Specs are applicable to this event: T.S. 3.3.1 Condition C, Three or more RPS channels inoperable; T.S. 3.3.2 Condition A, Manual Trip function inoperable; T.S. 3.3.3 Condition B, Two or more Reactor Trip Modules inoperable.

(M-ALL), (CT)

When RCS pressure reaches 1590# ESAS channels 1, 2, 3, and 4 will actuate. The BOP operator will perform repetitive task RT-10, Verify Proper ESAS Actuation to ensure components actuated and positioned as required. When ESAS actuates the SRO will transition to 1202.010, ESAS EOP unless Subcooling Margin has been lost. If Subcooling Margin has been lost the SRO can remain in the Loss of Subcooling Margin EOP as long as RCS pressure is >150#. The BOP will perform RT-10 to verify proper actuation of the Engineered Safeguards System.

Adequate Subcooling Margin (SCM) (30 deg. F) will not be maintained and per the Reactor Trip EOP, all running RCPs will be tripped. (CT) The RCPs should be tripped within two minutes of a Loss of Subcooling Margin (Time Critical Operator Action). Failure to stop all reactor coolant pumps within 2 minutes could result in core uncovery and fuel cladding failure. When all RCPs are tripped, the EFIC system will automatically actuate the Emergency Feedwater System and feed both Steam Generators (SG) based on a pre-programmed rate based on SG pressure. The SRO will enter 1202.002 Loss of Subcooling Margin EOP. Only one train of HPI will be available due to the previous failure of P-36B and P-36A OOS for maintenance. Reflux Boiling setpoint will be selected for EFW control. (C-ATC), (C-SRO), (CT)

Approximately 10 minutes after ESAS actuates a fire (smoke) alarm will be received in the control room from the #2 EDG room (Both EDGs will start when ESAS actuates). The AO will be dispatched and should be directed to investigate the smoke alarm. The AO will report an oil leak on the turbocharger for the #2 EDG and that some oil is on the exhaust manifold. He will report that there is heavy black smoke at this time but no fire. Since the EDG is not being used to power equipment the #2 EDG should be secured or Locked Out (CT) - #2 EDG stopped within 15 minutes of report of smoke. (C-BOP), (C-SRO)

The scenario may be concluded when One Train of HPI is in service, verification of ESAS Actuation RT-10 is complete and the #2 EDG has been secured END OF NARRATIVE Page 5 of 41

Appendix D Required Operator Actions Form ES-D-2 Simulator Instructions for Scenario 1 Recall IC 120 Verify the following in the director summary:

override DO_264A to On on event 1 ---------------------------------------------- AMB LP,GROUND malfunction K04C6 to ON on event 1 --------------------------------------------- K04 GENERATOR FIELD GROUND override DO_264A to Off on event 2 ---------------------------------------------- AMB LP,GROUND malfunction K04C6 to NORMAL on event 2 ------------------------------------ K04 GENERATOR FIELD GROUND override DO_264A to On on event 3 ---------------------------------------------- AMB LP,GROUND malfunction K04C6 to ON on event 3 --------------------------------------------- K04 GENERATOR FIELD GROUND override DO_264A to Off on event 4 ---------------------------------------------- AMB LP,GROUND malfunction K04C6 to OFF on event 4 -------------------------------------------- K04 GENERATOR FIELD GROUND malfunction TR458 to 2500.00000 in 90 on event 5 --------------------------- RCS PRESSURE (PT1021) {NNIX} 1700-2500 PSIG malfunction K09E3 to ON on event 6 --------------------------------------------- K09 PZR HEATER GROUND FAULT override DI_HS1007A to FALSE on event 6 ------------------------------------ ON,RUB 13/14,GP5,HS-1007A override DO_HS1007AG1 to Off on event 6 ------------------------------------ GRN LP,RUB E-13,HS-1007A override DO_HS1007AR1 to Off on event 6 ------------------------------------ RED LP,RUB E-13,HS-1007A malfunction CV096 on event 7 ------------------------------------------------------ P36B MOTOR WINDING HEATUP malfunction CV018 to 100.00000 in 120 on event 8 -------------------------- 1ST STAGE SEAL FAILURE P32D 0-100%

malfunction CV022 to 60.00000 in 180 on event 8 --------------------------- 2ND STAGE SEAL FAILURE P32D 0-100%

malfunction CV026 to 80.00000 in 10 on event 9 ----------------------------- 3RD STAGE SEAL FAILURE P32D 0-100%

malfunction RC005 to 0.10000 in 10 on event 9 ------------------------------- COLD LEG LEAK(LOOP A) 0-8.55 SQ. FT.

malfunction RP247 -------------------------------------------------------------------- REACTOR TRIP RELAY KE2 FAILS malfunction RP248 -------------------------------------------------------------------- REACTOR TRIP RELAY KE3 FAILS malfunction RP249 -------------------------------------------------------------------- REACTOR TRIP RELAY KE4 FAILS override DI_ICC0020 to FALSE --------------------------------------------------- REACTOR TRIP,PB override DO_HS1291G to OFF ---------------------------------------------------- GRN LP,HPI,P36A,AUX L.O.,P64A override DO_HS1291R to OFF ---------------------------------------------------- RED LP,HPI,P36A,AUX L.O.,P64A malfunction FS_B1_5_L_R on event 10 ----------------------------------------- FIRE #2 EDG RM SMOKE DET ZONE 86-G Verify the following remotes are as indicated:

remote MU14 after 300 to 1.00000 in 120 on event 11 --------------------- MU14 P36C TO P36B SUCTION XCONN remote MU23 after 420 to 1.00000 in 120 on event 11 --------------------- MU23 P36C TO P36B DSCH XCONN remote MU25 after 900 to 0 in 120 on event 11 ------------------------------ MU25 P36A TO P36B DSCH XCONN remote MU16 after 1020 to 0 in 120 on event 11 ---------------------------- MU16 P36A TO P36B SUCTION XCONN remote A307OP after 480 to DOW N on event 12 --------------------------- A307OP RACK DOWN A307 P36B HPI PUMP remote A407OP after 480 to DOW N on event 12 --------------------------- A407OP RACK DOWN A307 P36B HPI PUMP remote A306OP to DOW N --------------------------------------------------------- A306OP RACK DOWN A306 P36A HPI PUMP remote CO_P64A to OFF____________________________________CO-P64A / MAKEUP PUMP P36A AUX LO Event Value/Ramp Time Malf. No. Event Description No. Time Trigger 1 1 0 (DO_264A) ON Perform Generator Field Ground Test (K04C6) ON Trigger 5 Controlling RCS pressure transmitter fails 2 10 (TR458) 2500/90 sec. causing pressure indication to drift high Trigger 6 ON Pressurizer Heater ground fault alarm due to (K09E3) 3 25 FALSE fault on RUB-14 & 15 in Group 5, Tech Spec (DI_HS1007A)

(AO_HS1007AG) OFF required heaters.

(AO_HS1007AR) OFF Trigger 7 Operating Makeup/HPI pump, P-36B winding 4 45 (CV096) TRUE heatup and failure causes pump to trip.

Trigger 8 Degraded seal on P-32D RCP meets 5 65 (CV018) 100/120 sec. requirement to reduce power and secure the (CV022) 60/180 sec. pump.

CONTINUED ON NEXT PAGE

Appendix D Required Operator Actions Form ES-D-2 Simulator Instructions for Scenario 1 - CONTINUED Event Value/Ramp Time Malf. No. Event Description No. Time Trigger 9 During coast-down of the D RCP, a break in RCP (CV026) 80/10 the cold leg occurs that results in RCS leakage trip (RC005) 0.1/10 requiring reactor trip.

+ 30 6&7 RP246 TRUE sec. TRUE RPS is failed and the manual trip pushbutton is RP247 OR TRUE failed requiring use of backup pushbuttons to RP248 75 TRUE trip the reactor RP249 DI_ICC0020 FALSE ESAS

+10 Trigger 10 8 min TRUE Small oil leak on #1 EDG causes fire alarm.

(FS_B1_5_L_R)

OR 80 END OF SIMULATOR INSTRUCTIONS Page 7 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 1 Event

Description:

Perform Generator Field Ground test - Generator Field Ground alarm -

Time Position Applicants Actions or Behavior Direct performance of the generator field ground test per 1102.004 Step 0 SRO 12.0 BOOTH OPERATOR CUE:

When the Gen Field Ground Test Switch is taken to test, activate TRIGGER 1 BOP Momentarily place Gen Field Ground Test Switch in Test and release.

Verify the following:

BOP Test Brush Solenoid Actuated Lamp illuminates.

Generator Field Ground (K04-C6) does not alarm.

ATC Acknowledge and report Generator Field Ground alarm (K04-C6)

BOP BOP References 1203.012C, Annunciator K04 Corrective Action for K04-C6.

SRO EXAMINER NOTE:

The following actions are for K04-C6 corrective actions.

BOP Notify the Shift Manager SRO BOOTH ROLE PLAY:

If contacted as System Engineering, inform the caller that system engineering will commence an immediate evaluation of the field ground alarm.

BOP Notify System Engineering SRO CONTINUED NOTES Page 8 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 1

- CONTINUED Event

Description:

Perform Generator Field Ground test - Generator Field Ground alarm -

Time Position Applicants Actions or Behavior BOOTH ROLE PLAY:

If contacted as Auxiliary Operator to check the DGC alarm panel, wait ~ 2 minutes and report that there are no alarms on the DGC alarm screen.

Direct an Auxiliary Operator to check the Digital Generator Controller (DGC)

BOP alarm panel graphical display.

Validate Generator Field Ground alarm by performing the following:

BOP 1. Clear alarm by placing Gen Field Ground Test handswitch to RESET and release.

BOOTH OPERATOR CUE:

- When the Ground Test handswitch is taken to RESET the first time, activate TRIGGER 2 to turn off the GROUND light and clear the annunciator.

- When switch is taken back to TEST, activate TRIGGER 3.

- When switch is taken back to RESET, activate TRIGGER 4.

2. Test for Generator Field Ground by placing Gen Field Ground Test handswitch in TEST and release.

BOP 3. Check GENERATOR FIELD GROUND alarm returns.

1) Clear alarm by placing Gen Field Ground Test handswitch to RESET and release BOOTH ROLE PLAY:

If contacted as the Auxiliary Operator to report the status of the Generator Condition Monitor and/or the Radio Frequency Monitor, wait ~ 1 minute and report that there are no alarms on either monitor.

CONTINUED NOTES Page 9 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 1

- CONTINUED Event

Description:

Perform Generator Field Ground test - Generator Field Ground alarm -

Time Position Applicants Actions or Behavior EXAMINER NOTE:

The Governor/Exciter screen on PDS can be used to help monitor parameters on the Main Generator.

Determine if multiple grounds exist by checking whether 2 or more of the following unexpected or unexplained conditions exist:

A. A rise in generator bearing 7 or 8 vibration, available at any of the following:

Main Turbine TSIS or BOP

PMS points VB6640X, VB6640Y for Bearing #7 SRO

PMS points VB6650X, VB6650Y for Bearing #8 B. Rise in exciter current or voltage.

C. Reduction in MVARs.

D. Rise in Hydrogen Hot Gas or Cold Gas Temperatures.

E. Generator Condition Monitor alarm.

F. Radio Frequency Monitor alarm.

Determines that multiple grounds do not exist and rapid power reduction is SRO not required.

BOOTH ROLE PLAY:

If contacted to have relay determine excessive ground current, report that a crew will be assembled and will talk to the Shift Manager prior to any work.

BOP Contact Relay to determine if excessive ground current (>4.6 mA DC)

SRO exists.

BOOTH ROLE PLAY:

If the Ops Manager is contacted, direct to continue with power operations. If System Engineering is contacted, report that a system engineer will report to the shift manager.

SRO Contact Ops Manager and System Engineering for further guidance.

EXAMINER NOTE This event is complete when the second ground test is performed OR As directed by the Lead Evaluator NOTES Page 10 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 2 Event

Description:

Controlling RCS pressure transmitter fails causing pressure indication to drift high Time Position Applicants Actions or Behavior 10 ATC Acknowledge and report SASS MISMATCH annunciator (K07-B4)

Observe SASS indications on C03, C04 and C13 and determine white ATC SASS ENBL not illuminated on C04 for Narrow Range RCS Pressure.

EXAMINER NOTE :

If the failed pressure instrument is not addressed in a timely manner, it could result in opening of the pressurizer spray valve and the Electromatic Relief Valve (ERV). The crew may elect to address the opening of the pressurizer spray valve and ERV prior to addressing the SASS MISMATCH ALARM. IF so, this would be addressed in the Pressurizer Systems Failure AOP, 1203.015. With pressurizer spray and the ERV open, RCS pressure will be lowering rapidly.

EXAMINER NOTE:

The following actions are for the SASS MISMATCH corrective actions.

Diagnose and report deviation on narrow range RCS pressure recorder ATC PR-1023.

Refer to 1203.012F Annunciator K07 Corrective Action for K07-B4, SASS ANY MISMATCH.

ATC Determine that a transfer from the X source (PT-1021) has not occurred.

EXAMINER NOTE:

There are various independent indications of RCS pressure on the panels including the Y parameter that should be selected. Crew might not observe parameters on the Plant Computer.

Compare indication on PR-1038 (Y signal) to other RCS pressure ATC indications and determine that the Y signal is valid.

Determine that pressure signal will not cause a pressure transient and ATC select HS-1038 to the Y position (PT-1038). Verify that green X light goes out and blue Y light comes on above the handswitch.

Verify the pressurizer heaters are energized and RCS pressure is ATC recovering. (setpoint - 2155psig)

CONTINUED NOTES Page 11 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 2

- CONTINUED Event

Description:

Controlling RCS pressure transmitter fails causing pressure indication to drift high Time Position Applicants Actions or Behavior EXAMINER NOTE:

- The following actions are for the Pressurizer Systems Failure AOP.

- These actions will be N/A if the alternate instrument is selected quickly.

SRO Enter 1203.015, Pressurizer Systems Failure AOP.

SRO Refer to Section 1 of 1203.015 for ERV System Failure.

Close ERV isolation valve CV-1000 by momentarily placing HS-1000 in the ATC CLOSE position.

SRO Refer to Section 6 of 1203.015 for Pressurizer Spray Valve Failure.

ATC Place the Pressurizer Spray Valve, CV-1008 in HAND (HS-1003).

Close Pressurizer Spray Valve, CV-1008 by holding HS-1008 in CLOSE ATC until CV-1008 indicates closed (green light on, red light off).

If in MANUAL, place the Pressurizer Spray Valve, CV-1008 in AUTO ATC (HS-1003). Check that CV-1008 remains closed.

If CLOSED, OPEN the ERV Isolation, CV-1000 by momentarily placing ATC HS-1000 in the OPEN position.

SRO Perform transient brief.

CONTINUED NOTES Page 12 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 2

- CONTINUED Event

Description:

Controlling RCS pressure transmitter fails causing pressure indication to drift high Time Position Applicants Actions or Behavior BOOTH ROLE PLAY:

If contacted to initiate repairs on PT-1021, report that a Condition Report and Work Request will be generated for the failure of PT-1021.

SRO Take actions to initiate repairs on PT-1021.

ANY Take actions to bypass the SASS MISMATCH alarm for RCS Pressure.

BOOTH OPERATOR CUE:

If contacted to bypass the SASS alarm for RCS pressure, wait ~ 5 minutes and use remote SASS06 to BYPASS to clear that SASS alarm.

BOOTH ROLE PLAY:

If contacted to bypass the SASS alarm for RCS pressure, ~ 1 minute after the alarm is cleared, contact the control room and report that the SASS alarm for RCS pressure has been bypassed.

Reference Technical Specification 3.4.1 for RCS Pressure, Temperature SRO and DNB Limits. (ref. COLR RCS Pressure, Temperature and Flow Limits).

TS Minimum Hot Leg Pressure w/ 4 RCPs is 2082.2psig.

2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months action to restore parameter within limits or be in mode 2 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

If RCS pressure is 2082.2 psig, declare TS 3.4.1 in affect with 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to SRO restore RCS pressure above the limit.

If TS 3.4.1 was entered, when RCS pressure is > 2082.2 psig, exit the SRO specification.

CONTINUED NOTES Page 13 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 2

- CONTINUED Event

Description:

Controlling RCS pressure transmitter fails causing pressure indication to drift high Time Position Applicants Actions or Behavior EXAMINER NOTE:

- The following actions are related to the tripped A RPS channel.

- Actions related to placing the A RPS channel in bypass may be assessed at the end of the scenario.

ATC Acknowledge and report RPS TROUBLE alarm (K08-C3)

Refer to 1203.012G Annunciator K08 Corrective Action for K08-C3, RPS ANY TROUBLE.

ANY Observe RPS CHANNEL A light on K1633 (C13) illuminated or flashing.

Diagnose and report that the failed pressure transmitter has caused A ANY RPS channel to trip.

SRO Reference Technical Specification 3.3.1 for RPS Instrumentation.

(Condition A for one channel inoperable, place channel in bypass or trip or bypass TS within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The channel is already tripped but may be placed in bypass.)

EXAMINER NOTE This event is complete when, HS-1038 is selected to Y (PT-1038)

AND Tech Specs have been assessed OR As directed by the Lead Evaluator NOTES Page 14 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 3 Event

Description:

Pressurizer Heater ground fault alarm due to fault on RUB-14 & 15 in Group 5, Tech Spec required heaters.

Time Position Applicants Actions or Behavior Acknowledge and report PZR HEATER GROUND FAULT annunciator 25 ATC (K09-E3).

Refer to 1203.012H Annunciator K09 Corrective Action for K09-E3, PZR ANY HEATER GROUND FAULT.

BOOTH ROLE PLAY:

- If contacted as the Auxiliary Operator to check the status of ground flags on the SCR cabinets, wait ~ 4 minutes and report that there are no ground flags at the either SCR cabinet.

- If directed to report current values at the SCR cabinets use SPDS points A1PZRHTR1 (Bank 1) and A1PZRHTR2 (Bank2) and report value to the control room for respective SCR bank.

Direct Auxiliary Operator to check status of ground flags and SCR cabinets ANY in the LSEPR and UNEPR.

Enter 1203.015 Pressurizer Systems Failure AOP, Section 3 - Inoperative SRO Pressurizer Heaters.

ATC Diagnose and report loss of indication on Group 5 heaters, RUB 14 & 15.

BOOTH ROLE PLAY:

- If contacted as the Auxiliary Operator to investigate the status of B-5663, wait ~ 2 minutes will report that B-5663 is tripped.

- If directed to open the breaker cubicle to check for damage, wait ~ 1 minute and report that there is not damage indicated internally to the breaker cubicle.

- If the operator is directed to attempt to reclose the breaker, it will not re-close.

- If Work Management is contacted to perform the Pressurizer Proportional Heater Checkout (1307.009), report that a Work Order will be issued and provided to the FIN team.

CONTINUED NOTES Page 15 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 3

- CONTINUED Event

Description:

Pressurizer Heater ground fault alarm due to fault on RUB-14 & 15 in Group 5, Tech Spec required heaters.

Time Position Applicants Actions or Behavior Direct an Auxiliary Operator to check status of the supply breaker for ANY RUB 14 & 15 (B-5663)

Reference 1107.001, Electrical System Operations - Reclosing Tripped BOP Individual Load Supply Breakers, section.

ATC Consider placing Group 5 hand switch in OFF.

BOP (HS-1007A on C04)

Does not give permission to reclose B-5663 as there is no emergency SRO condition and the cause of the trip is not known and corrected.

EXAMINER NOTE:

RUB-14 & 15 must be operable to provide the required 126 KW required by Tech Specs.

Reference Technical Specification 3.4.9 for Pressurizer Operability SRO Requirements.

TS Minimum 126 KW of ES Powered pressurizer heaters Operable.

72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months action to restore pressurizer heater capacity or be in mode 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and mode 4 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Declare RUB 14 & 15 pressurizer heaters inoperable and enter 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months SRO completion time.

EXAMINERS NOTE:

This event is complete when RUB 14 & 15 pressurizer heaters have been declared inoperable, OR As directed by the Lead Evaluator NOTES Page 16 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 4 Event

Description:

Operating Makeup/HPI pump, P-36B winding heatup and failure causes pump to trip Time Position Applicants Actions or Behavior Acknowledge and report HPI PUMP MTR WDG TEMP HI annunciator 45 ATC (K10-E7)

Determine and report value and trend of P-36B winding temperature by BOP observing value on PMS/PDS (process computer) or on recorder TR-6501 on C13.

ANY Reference 1203.012I, Annunciator K10 Corrective Action for K10-E7.

BOOTH ROLE PLAY:

- If contacted as the Waste Control Operator to investigate P-36B locally, wait ~3 minutes and report that there is an acrid smell in the area and P-36B motor is very hot to the touch.

- If directed as the AO to investigate the P-36B breaker (A-307) locally, wait ~ 2 min and report that the Timed Overcurrent Relay on A-307 has a drop flag on it.

ANY Direct the Waste Control Operator to investigate the pump locally.

EXAMINER NOTE:

P-36B may trip automatically prior to being manually tripped.

Determine that P-36B Winding Temperature will exceed 311 Deg. F and ANY trip P-36B.

Enter 1203.026, Loss of Reactor Coolant Makeup, Section1 - Loss of HPI SRO Pump.

BOP Isolate letdown by closing CV-1221(HS-1221) on C16.

ATC Verify RCP seal cooled by ICW (Nuclear ICW pump running, low seal cooling flow alarm clear and seal temperatures BOP stabilizing)

CONTINUED NOTES Page 17 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 4

- CONTINUED Event

Description:

Operating Makeup/HPI pump, P-36B winding heatup and failure causes pump to trip Time Position Applicants Actions or Behavior BOOTH ROLE PLAY:

If contacted as the Waste Control Operator to realign the ES HPI pump per Att. A of 1203.026, report that you will obtain a copy of Att. A of 1203.026 and perform it immediately.

BOOTH OPERATOR CUE:

When the WCO is directed to perform Att. A, activate TRIGGER 11 EXAMINER NOTE:

The crew may direct an AO to provide the attachment to the WCO.

Dispatch Waste Control Operator (WCO) to realign the ES HPI pump per SRO Attachment A of 1203.026.

Place Seal Injection flow control valve CV-1207 in HAND and close. (FIC-ATC 1207 on C04)

Place Pressurizer Level Control valve CV-1235 in HAND and close. (LIC-ATC 1000 on C04).

Verify that RCP Seal Injection block valve CV-1206 indicates closed on ATC C04.

Select Safety System Diagnostic instrument display on SPDS for the OP ANY HPI pump and evaluate suction pressure and flow stability prior to event.

CONTINUED NOTES Page 18 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 4

- CONTINUED Event

Description:

Operating Makeup/HPI pump, P-36B winding heatup and failure causes pump to trip Time Position Applicants Actions or Behavior ANY Determine that loss of suction is not indicated.

BOP Start aux oil pump for P-36C (ES HPI pump), P-64C (HS-1294 on C18).

SRO Determine that it is not necessary to vent P-36C HPI pump.

Verify HPI pump suction pressure > 10 psig (use SPDS diagnostic ANY screen).

BOOTH ROLE PLAY:

- After ~ 10 minutes from being directed to perform Att. A, contact the control room as the WCO and ask if HPI pump venting is required.

- If directed to vent P-36C, wait ~ 2 minutes and report that P-36C has been vented and ABV-9C vent valve is closed.

- If venting is not required or is complete, report to the control room that steps 1 through 6 of Att. A are complete and the ES HPI pump (P-36C) is ready for start.

- If directed the WCO will report that P-36C pre-start checks are complete and all personnel are clear of the room.

When the WCO reports that steps 1 through 6 of Attachment A is BOP complete, start P-36C HPI pump (HS-1243 on C18).

BOP Stop the aux oil pump, P-64C (HS-1294 on C18).

CONTINUED NOTES Page 19 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 4

- CONTINUED Event

Description:

Operating Makeup/HPI pump, P-36B winding heatup and failure causes pump to trip Time Position Applicants Actions or Behavior Place Seal Injection Block valve, CV-1206 in override. (OVRD light ON on ATC PB-1206 on C04)

ATC Open CV-1206 (HS-1206 on C04)

ANY Determine RCP seal bleedoff temperatures are < 180 Deg. F.

Slowly open CV-1207 (FIC-1207 on C04) to obtain 30 to 40 gpm total seal ATC injection flow (FR-1239 on C04) and place CV-1207 in AUTO (FIC-1207).

ATC Place CV-1206 in normal (not in override) (PB-1206 OVRD light OFF)

Slowly open Pressurizer Level Control Valve, CV-1235 (LIC-1000 on C04)

ATC until makeup flow indication is on scale (FI-1238 on C04 > 10 gpm) and place CV-1235 in AUTO (LIC-1000 on C04).

SRO Direct letdown to be restored per 1202.012 (RT-13).

CONTINUED NOTES Page 20 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 4

- CONTINUED Event

Description:

Operating Makeup/HPI pump, P-36B winding heatup and failure causes pump to trip Time Position Applicants Actions or Behavior EXAMINER NOTE:

The following are actions for restoring letdown using RT-13.

BOP Verify ICW pump supplying Nuclear loop. (P-33C on C09)

BOP Verify 3-way valve, CV-1248 aligned to LETDOWN. (HS-1248 on C04)

Verify Orifice Bypass, CV-1223 demand adjusted to zero.

BOP (FIC-1223 on C04, knob adjusted to zero, demand is zero)

Verify the following:

- Makeup Filter Inlet valve open (CV-1246 or CV-1247 on C04)

- PURIF Demineralizer Inlet open (CV-1244 or CV-1245 on C04)

BOP - Either or both RC and ICW to Letdown coolers open

- CV-1213 and CV-2216

- CV-1215 and CV-2217

- Orifice Block open (CV1222 on C04)

Check Nuclear ICW RB inlet and outlet valve OPEN

- CV-2214 (on C18)

BOP

- CV-2233 (on C16 or C18)

- CV-2215 (on C16)

CONTINUED NOTES Page 21 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 4

- CONTINUED Event

Description:

Operating Makeup/HPI pump, P-36B winding heatup and failure causes pump to trip Time Position Applicants Actions or Behavior Verify Letdown Cooler outlet valve OPEN.

BOP (CV-1214 and CV-1216 on C18)

BOP Open Letdown Coolers Outlet valve. (CV-1221 on C16)

BOP Establish desired letdown flow using Orifice Bypass (CV-1223 on C04)

ATC BOOTH OPERATOR CUE:

If contacted to rack down the P-36B supply breakers activate TRIGGER 12.

BOOTH ROLE PLAY:

If contacted to rack down the P-36B supply breakers wait 10 minutes, verify breakers indicated racked down and contact the control room (phone) and report the P-36B supply breakers A-307

& A-407 are racked down.

CONTINUED NOTES Page 22 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 4

- CONTINUED Event

Description:

Operating Makeup/HPI pump, P-36B winding heatup and failure causes pump to trip Time Position Applicants Actions or Behavior BOOTH ROLE PLAY:

- If contacted regarding repairs to the HPI pumps, acknowledge the report and state that a team will be assembled to address the problem.

- When MU-16 & MU-25 indicate closed on the director summary screen, notify the control room as the WCO that P-36A to P-36B cross-tie valves MU-16 and MU-25 are closed. 1203.26 Att. A is complete.

SRO Initiate repairs for failed components SRO Refer to TS 3.5.2 for LCO (Emergency Core Cooling Systems).

(Technical Specification 3.5.4 Condition A, One or more trains inoperable - Restore TS train(s) to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months )

EXAMINERS NOTE:

This event is complete when Letdown has been restored OR As directed by the Lead Evaluator NOTES Page 23 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 5 Event

Description:

Degraded seal on P-32D RCP meets requirement to reduce power and secure the pump Time Position Applicants Actions or Behavior Acknowledge and report RCP BLEEDOFF FLOW HI (K08-B7) and RCP 65 ATC SEAL CAVITY PRESS HI/LO (K08-D7)

Observe seal parameters on RCS seal recorders on C13 and/or RCP seal ANY indication on PDS (process computer).

ANY Determine that seal pressures associated with P-32D RCP are changing.

Reference 1203.012G, Annunciator K08 Corrective Action for K08-B7 and ANY K08-D7.

Enter 1203.031 Reactor Coolant Pump and Motor Emergencies, SRO Section 1 - Seal Degradation.

EXAMINER NOTE:

The degradation of the P-32D RCP seal will result in a differential pressure across one stage exceeding 2/3 of system pressure. This requires power to be reduced to 70% power and P-32D stopped using normal procedures (3 pump operation).

Verify the following seal bleedoff valves open on C16 & C18:

CV-1274 (C16)

BOP CV-1270 (C18)

ATC CV-1271 (C18)

CV-1272 (C18)

CV-1273 (C18)

CONTINUED NOTES Page 24 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 5

- CONTINUED Event

Description:

Degraded seal on P-32D RCP meets requirement to reduce power and secure the pump Time Position Applicants Actions or Behavior ATC Verify RCP Seal Injection Block valve CV-1206 is OPEN (C04).

ATC Verify CV-1207 is maintaining 30 to 40 gpm (FR-1239 on C04)

Verify individual seal injection flow rates 8 to 10 gpm ATC (FI-1280, FI-1281, FI-1282, FI-1283 on C04)

Provide a copy of Attachment A of 1203.031 to a Control Board Operator SRO to aid in monitoring seal parameters.

Determine that delta-p across the upper stage of the P-32D seal exceeds ANY 2/3 of system pressure.

Enter 1203.045, Rapid Plant Shutdown, Section 1 - Rapid Plant Shutdown SRO Without Small SG Tube Leak.

ATC Set ICS rate of change setpoint as directed by the SRO (ICC0012 on C03).

EXAMINER NOTE: A value of 630MW equates to approximately 70% power Adjust the Unit Load Demand setpoint to value provided by the SRO ATC (ICC009 on C03)

ATC Report power at frequency directed by the SRO.

ATC Determine and report proper integrated plant response.

BOP CONTINUED NOTES Page 25 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 5

- CONTINUED Event

Description:

Degraded seal on P-32D RCP meets requirement to reduce power and secure the pump Time Position Applicants Actions or Behavior EXAMINER NOTE:

As the power reduction is completed, P-32D seal parameters will degrade further resulting in a differential pressure across one stage equal to RCS pressure. This will require entry into the Seal Failure section of 1203.031 and tripping of P-32D RCP.

BOOTH OPERATOR CUE:

When power is ~ 75%, modify malfunction CV002 to 100 over 60 seconds. This will make the D RCP seal meet seal failure criteria.

Determine and report that P-32D seal delta-P is equal to RCS pressure ANY across one stage.

Enter 1203.031, Reactor Coolant Pump and Motor Emergencies, SRO Section 2 - Seal Failure.

Trip P-32D Reactor Coolant Pump by momentarily placing HS-1021(C13)

BOP in STOP.

Verify proper ICS response (re-ratio of feedwater flow)

ATC (FI-2628 & 2678 or FR-2632 & 2682 on C03).

EXAMINERS NOTE:

This event is complete when P-32D has been tripped OR As directed by the Lead Evaluator NOTES Page 26 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 6 & 7 Event

Description:

- During coast-down of the D RCP, a break in the cold leg occurs that results in RCS leakage requiring reactor trip.

- RPS is failed and the manual trip pushbutton is failed requiring use of backup pushbuttons to trip the reactor Time Position Applicants Actions or Behavior RCP trip

+ 30 ANY Report lowering RCS pressure and pressurizer level.

sec.

OR 75 ANY Determine need to trip the reactor based on RCS leakage.

EXAMINER NOTE:

Reactor Trip immediate actions are pre-scripted and normally there is no verbal communication from the crew until all immediate actions have been performed. In the event of the inability to perform an immediate action in a normal manner, the operator should announce the malfunction and that he is performing the contingency.

ATC Depress the Reactor Trip pushbutton (C03).

Determine and report failure of the reactor to trip and depress the CRD ATC Power Supply Trip pushbuttons (PB-0140 & PB-0141 on C03)

CT CT - Reactor tripped within 1 minute of valid trip signal (manual or automatic)

The SRO may enter the following Technical Specifications:

(T.S. 3.4.13 Condition A, RCS leakage not within limits)

SRO (T.S. 3.3.1 Condition C, Three or more RPS channels inoperable)

(T.S. 3.3.2 Condition A, Manual Trip function inoperable)

(T.S. 3.3.3 Condition B, Two or more Reactor Trip Modules inoperable)

CONTINUED NOTES Page 27 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 6 & 7

- CONTINUED Event

Description:

- During coast-down of the D RCP, a break in the cold leg occurs that results in RCS leakage requiring reactor trip.

- RPS is failed and the manual trip pushbutton is failed requiring use of backup pushbuttons to trip the reactor Time Position Applicants Actions or Behavior Verify all Control Rods are inserted (PI Panel on C13) and that reactor ALL power is lowering (NI-505 & NI-506 on C03).

BOP Trip the Turbine (PB-9201 on C01).

ALL Verify Turbine Throttle and Governor Valves are closed (C32).

Verify Adequate Subcooling Margin (> 30 Deg. F) (ICC display on C09 or ALL TI-1150A &TI-1150B on C04)

ANY Report that Subcooling Margin is inadequate.

Enter 1202.001, Reactor Trip EOP and verify Immediate actions SRO performed.

EXAMINER NOTE: At this point the SRO may enter 1202.002, Loss of Subcooling Margin EOP or 1202.010, ESAS EOP. Either is acceptable.

CONTINUED NOTES Page 28 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 6 & 7

- CONTINUED Event

Description:

- During coast-down of the D RCP, a break in the cold leg occurs that results in RCS leakage requiring reactor trip.

- RPS is failed and the manual trip pushbutton is failed requiring use of backup pushbuttons to trip the reactor Time Position Applicants Actions or Behavior EXAMINER NOTE: The following are the actions when entering 1202.010, ESAS EXAMINER NOTE: When Subcooling Margin is not adequate, a timer will appear on the bottom of the ICCMDS display at the top C19 displaying time since LOSM.

SRO Enter 1202.010, ESAS EOP.

If 2 minutes has elapsed since subcooling margin has been lost, trip all BOP running Reactor Coolant Pumps (HS-1020, HS-1022, & HS-1023 on C13).

CT CT - RCPs tripped within 2 minutes of a Loss of Adequate Subcooling Margin.

ATC Select Reflux Boiling setpoint for both EFW trains (Pushbuttons on C09)

BOP Verify proper ESAS actuation (RT-10)

CONTINUED NOTES Page 29 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 6 & 7

- CONTINUED Event

Description:

- During coast-down of the D RCP, a break in the cold leg occurs that results in RCS leakage requiring reactor trip.

- RPS is failed and the manual trip pushbutton is failed requiring use of backup pushbuttons to trip the reactor Time Position Applicants Actions or Behavior IF Makeup Tank level drops below 18, THEN close Makeup Tank Outlet ATC CV-1275. (HS-1275 on C04)

SRO Determine that ESAS did NOT actuate on high RB pressure alone.

Place the Pressurizer Spray valve CV-1008 in MAN and verify closed. HS-ATC 1003 & HS-1008 on C04).

ATC Close Pressurizer Spray Isolation, CV-1009 (HS-1009 on C04).

ATC Close ERV isolation, CV-1000 (HS-1000 on C04).

ATC Check Nuclear Loop ICW process monitor (RI-2236) alarm clear (can be BOP verified on PMS/PDS)

ATC Check SG tube integrity (RT-18)

SRO Determine that RCS Pressure is > 150 psig and go to step 13.

CONTINUED NOTES Page 30 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 6 & 7

- CONTINUED Event

Description:

- During coast-down of the D RCP, a break in the cold leg occurs that results in RCS leakage requiring reactor trip.

- RPS is failed and the manual trip pushbutton is failed requiring use of backup pushbuttons to trip the reactor Time Position Applicants Actions or Behavior SRO Transition to the Loss of Subcooling Margin procedure.

EXAMINER NOTE:

The following are the actions when entering 1202.002, Loss of Subcooling Margin.

SRO Enter 1202.002, Loss of Subcooling Margin.

EXAMINER NOTE:

When Subcooling Margin is not adequate, a timer will appear on the bottom of the ICCMDS display at the top C19 displaying time since LOSM.

If 2 minutes has elapsed since subcooling margin has been lost, trip all BOP running Reactor Coolant Pumps (HS-1020, HS-1022, & HS-1023 on C13).

EXAMINER NOTE:

HPI will automatically actuate when ESAS actuates. RT-3 to actuate Full HPI will not need to be performed but it should be verified that Full HPI is in service. For this scenario, only 1 train of HPI is available.

BOP Initiate Full HPI (RT-3).

CONTINUED NOTES Page 31 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 6 & 7

- CONTINUED Event

Description:

- During coast-down of the D RCP, a break in the cold leg occurs that results in RCS leakage requiring reactor trip.

- RPS is failed and the manual trip pushbutton is failed requiring use of backup pushbuttons to trip the reactor Time Position Applicants Actions or Behavior IF Makeup Tank level drops below 18, THEN close Makeup Tank Outlet ATC CV-1275. (HS-1275 on C04)

ATC Verify proper EFW actuation and control (RT-5)

ATC Trip both MFW Pumps (HS-6709 & HS-6710 on C02).

BOP Verify proper ESAS actuation (RT10).

EXAMINER NOTE:

The actions for RT-10 are later in this section.

Check RCS pressure 150 psig and stay in the Loss of Subcooling Margin SRO procedure.

Place the Pressurizer Spray valve CV-1008 in MAN and verify closed. HS-ATC 1003 & HS-1008 on C04).

ATC Close Pressurizer Spray Isolation, CV-1009 (HS-1009 on C04).

ATC Close ERV isolation, CV-1000 (HS-1000 on C04).

CONTINUED NOTES Page 32 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 6 & 7

- CONTINUED Event

Description:

- During coast-down of the D RCP, a break in the cold leg occurs that results in RCS leakage requiring reactor trip.

- RPS is failed and the manual trip pushbutton is failed requiring use of backup pushbuttons to trip the reactor Time Position Applicants Actions or Behavior ATC Check Nuclear Loop ICW process monitor (RI-2236) alarm clear. (can be BOP verified on PMS/PDS)

Determine the CETs are NOT superheated and moving away from the SRO saturation line (average CET temps can be read on the ICCMDS display at the top of C19).

ATC Check SG tube integrity (RT-18).

ATC Check SG levels at of approaching 370 to 410.

EXAMINER NOTE:

- When the Hot Legs are voided and HPI is in service during a loss of subcooling margin event, indications of primary to secondary heat transfer are usually not observed. The PSHT screen on SPDS is used to monitor these indications.

- If the SRO does not perform contingency column for step 16, follow-up with the applicant at the end of the scenario to ensure understanding of the event.

Check primary to secondary heat transfer in progress indicated by all of the following:

ATC T-cold tracking associated SG T-sat T-hot tracking CET temps T-hot/T-cold delta-T stable or dropping CONTINUED NOTES Page 33 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 6 & 7

- CONTINUED Event

Description:

- During coast-down of the D RCP, a break in the cold leg occurs that results in RCS leakage requiring reactor trip.

- RPS is failed and the manual trip pushbutton is failed requiring use of backup pushbuttons to trip the reactor Time Position Applicants Actions or Behavior ATC Raise primary to secondary delta-T to 40 to 60 Deg F.

Bypass MSLI (4 channels) by placing the SG bypass toggle switch in bypass and releasing:

ATC C37-1 BOP C37-2 C37-3 C37-4 Place EFW isolation valves in Vector Override:

CV-2627 ATC CV-2670 CV-2620 CV-2626 ADJUST turbine bypass or atmospheric dump control system to establish ATC SG pressures within the limits of Figure 5.

If primary to secondary heat transfer is established, adjust turbine bypass ATC or atmospheric dump control system to stabilize RCS temperature.

CONTINUED NOTES Page 34 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 6 & 7

- CONTINUED Event

Description:

- During coast-down of the D RCP, a break in the cold leg occurs that results in RCS leakage requiring reactor trip.

- RPS is failed and the manual trip pushbutton is failed requiring use of backup pushbuttons to trip the reactor Time Position Applicants Actions or Behavior EXAMINER NOTE:

The following are the actions for RT-10, Verify Proper ESAS Actuation.

Verify BWST Outlets OPEN:

BOP - CV-1407 (C18)

- CV-1408 (C16)

Verify Service Water to DG1 and DG2 coolers OPEN:

BOP - CV-3806 (C19)

- CV-3807 (C19)

Verify proper ESAS Channels TRIPPED:

- RCS Pressure 1550 psig - Channels 1, 2, 3 & 4 BOP

- RB Pressure 18.7 psia - Channels 1, 2. 3, 4, 5 & 6

- RB Pressure 44.7 psia - Channels 7, 8, 9, 10 EXAMINER NOTE:

Proper component actuation for ESAS is accomplished by matching light indications for the component with black tape adjacent to the light.

BOP Verify each component properly actuated on C16 and C18 CONTINUED NOTES Page 35 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 6 & 7

- CONTINUED Event

Description:

- During coast-down of the D RCP, a break in the cold leg occurs that results in RCS leakage requiring reactor trip.

- RPS is failed and the manual trip pushbutton is failed requiring use of backup pushbuttons to trip the reactor Time Position Applicants Actions or Behavior BOP Verify proper ES system flow rates.

If any ES Flow alarms exist, use associated Annunciate Corrective action BOP to clear unexpected alarms.

If only 1 Train of HPI is available and RCS pressure is > 600 psig, then throttle HPI Block valve with highest flow within 20gpm of the next highest BOP flow.

(flows should be approximately equal for this scenario)

Verify DGs operating within normal limits (C10):

- 4100 to 4200 V BOP

- 59.5 to 60.5 Hz

- 2750 kW Verify the following breakers OPEN (C10):

- A-310 - A-410 BOP

- B-513 - B-613

- A-112 - A-212 Verify the following breakers CLOSED:

BOP - A-301 - B-512

- A-401 - B-612 CONTINUED NOTES Page 36 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 6 & 7

- CONTINUED Event

Description:

- During coast-down of the D RCP, a break in the cold leg occurs that results in RCS leakage requiring reactor trip.

- RPS is failed and the manual trip pushbutton is failed requiring use of backup pushbuttons to trip the reactor Time Position Applicants Actions or Behavior On C09 perform the following:

BOP - Check Aux Cooling Water header DEPRESSURIZED

- If not already performed, verify EFW actuation and control per RT-5 On C19 perform the following:

- LPI pump room coolers RUNNING

- VUC-1A or 1B BOP - VUC-1C or 1D

- If Spray is actuated, then verify SW to LO coolers OPEN

- CV-3804

- CV-3805 If RCPs are off and Seal Injection Block, CV-1206 is closed then place RCP seal bleedoff (Alt. Path to Quench Tank) controls to CLOSE (C13):

- SV-1271 BOP

- SV-1270

- SV-1273

- SV-1272 CONTINUED NOTES Page 37 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 6 & 7

- CONTINUED Event

Description:

- During coast-down of the D RCP, a break in the cold leg occurs that results in RCS leakage requiring reactor trip.

- RPS is failed and the manual trip pushbutton is failed requiring use of backup pushbuttons to trip the reactor Time Position Applicants Actions or Behavior If leakage into the RB is indicated then verify RB cooling maximized:

- Verify all four RB Cooling Fans RUNNING:

- VSF-1A

- VSF-1B

- VSF-1C

- VSF-1D

- Verify RB Cooling Coils Service Water Inlet/Outlet valves OPEN:

BOP

- CV-3812/CV-3814

- CV-3813/CV-3815

- Verify key-locked Chiller Bypass Dampers UNLATCHED:

- SV-7410

- SV-7411

- SV-7412

- SV-7413 Initiate RB H2 sampling using Containment Hydrogen Control (1104.031)

BOP Exhibit A.

BOP Verify each component properly actuated on C26.

CONTINUED NOTES Page 38 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 6 & 7

- CONTINUED Event

Description:

- During coast-down of the D RCP, a break in the cold leg occurs that results in RCS leakage requiring reactor trip.

- RPS is failed and the manual trip pushbutton is failed requiring use of backup pushbuttons to trip the reactor Time Position Applicants Actions or Behavior Verify sample valves CLOSED on C26:

- Pressurizer Steam Space Sample Valve (CV-1814)

BOP

- Pressurizer Water Space Sample Valve (CV01816)

- Hot Leg Sample (SV-1840)

Verify the following High Point Vents CLOSED:

A Loop B Loop Rx Vessel Pressurizer BOP - SV-1081 - SV-1091 - SV-1071 - SV-1077

- SV-1082 - SV-1092 - SV-1072 - SV-1079

- SV-1083 - SV-1093 - SV-1073

- SV-1084 - SV-1094 - SV-1074 If AUX Lube Oil pump for running HPI pump fails to stop after 20 second BOP time delay, then within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of ESAS actuation dispatch an operator to stop AUX Lube Oil pump locally at breaker while continuing.

Place running Low Pressure Injection (Decay Heat) pump hand switches in NORMAL-AFTER-START to enable DECAY HEAT PUMP TRIP alarm:

BOP

- P-34A

- P-34B Monitor ENGINEERED SAFEGUARDS ACTUATION SYSTEM alarms on BOP K11.

EXAMINER NOTE:

The last two steps of RT-10 are follow-up type steps (18 & 19) and are not required to be performed verify ESAS actuation.

EXAMINERS NOTE:

This event is complete when RT-10 has been completed through step 17, OR As directed by the Lead Evaluator NOTES Page 39 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 8 Event

Description:

Small oil leak on #1 EDG causes fire alarm.

Time Position Applicants Actions or Behavior ESAS

+10 min ATC Acknowledge and report reflash on FIRE alarm (K12-A1).

OR 80 BOP Check and Acknowledge red alarm LEDs on C463 per 1203.009 Exhibit A.

ATC BOP Determine on fire panel (Blue Panel C463-2) that smoke detector for #2 ATC EDG (zone 86-G) in alarm.

Reference 1203.009, Fire Protection System Annunciator Corrective Action SRO for K01-A1.

ANY Dispatch an Auxiliary Operator to investigate at the #2 EDG.

BOOTH ROLE PLAY:

- If the Auxiliary Operator is dispatched, wait ~ 2 minutes and report that there is a oil leak on the turbocharger of the #2 EDG and that oil is getting on the exhaust manifold. There is thick black smoke in the room. There currently is no fire.

- If the #2 EDG is not stopped after 15 minutes of the initial report of smoke, contact the control room as the AO and report that there are now flames present on the exhaust manifold.

CONTINUED NOTES Page 40 of 41

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2014-1 Scenario No.: 1 Event No.: 8 Event

Description:

Small oil leak on #1 EDG causes fire alarm.

Time Position Applicants Actions or Behavior SRO Determine that it is acceptable to turn off the #2 EDG.

Stop the #2 EDG by placing HS-0141 on C10 in LOCKOUT.

BOP CT - #2 EDG stopped within 15 minutes of report of smoke.

BOOTH ROLE PLAY:

After the EDG is stopped, if directed to report conditions at the #2 EDG, report that the oil leak has stopped and that there is still a lot of smoke in the EDG room.

The SRO may enter the following Technical Specification:

(TS 3.8.1 Condition B, verify offsite circuits operable within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , declare required SRO features inoperable if redundant feature is inoperable within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , determine inoperability is not common cause within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months & restore DG operability within 7 days).

EXAMINERS NOTE:

This scenario may be terminated when #2 EDG has been stopped AND All required actions have been completed OR As directed by the Lead Evaluator END OF SCENARIO NOTES END OF DOCUMENT Page 41 of 41

ES-301 Transient and Event Checklist Form ES-301-5 Facility: ANO Date of Exam: 11/17/2014 Operating Test No.: 2014-1 A E Scenarios P V T M 1 2 4 P E O I L N CREW POSITION CREW POSITION CREW POSITION T N I T S A B S A B S A B I A

M C R T O R T O R T O L U A T O C P O C P O C P M(*)

N Y R I U T P E

RX 0 1 1 0 NOR 1 1 2 1 1 1 SRO-U I/C 2, 4, 5, 7, 8 2, 3, 4 8 4 4 2 U1, U2 MAJ 6 5, 6 3 2 2 1 TS 2, 3, 4 2, 3, 5 6 0 2 2 RX 0 1 1 0 NOR 1 1 2 1 1 1 SRO-U I/C 2, 3, 5, 2, 3, 4 8 4 4 2 U3 6, 8 MAJ 7 5, 6 3 2 2 1 TS 2, 4 2, 3, 5 5 0 2 2 RX 4 1 1 1 0 NOR 1 1 1 1 1 SRO-I I/C 2, 3, 5, 6, 8 2, 4, 6 8 4 4 2 S1, S2 MAJ 7 5, 6 3 2 2 1 TS 2, 4 2 0 2 2 RX 3 1 1 1 0 NOR 1 1 2 1 1 1 SRO-I I/C 2, 4, 5, 5, 6, 8 2, 3, 4 11 4 4 2 S3 7, 8 MAJ 6 7 5, 6 4 2 2 1 TS 2, 3, 4 2, 3, 5 6 0 2 2 RX 4 1 1 1 0 NOR 1 1 2 1 1 1 SRO-I I/C 2, 3, 5, 4, 5, 8 2, 4, 6 11 4 4 2 S4 6, 8 MAJ 6 7 5, 6 4 2 2 1 TS 2, 4 2 0 2 2 Page 1 of 2

ES-301 Transient and Event Checklist Form ES-301-5 RX 3 1 1 1 0 NOR 1 1 2 1 1 1 RO I/C 4, 5, 8 5, 6, 8 3, 4 8 4 4 2 R1, R3 MAJ 6 7 5, 6 4 2 2 1 TS 0 0 2 2 RX 5 1 1 1 0 NOR 1 1 1 1 1 RO I/C 2, 4, 7 2, 3, 8 6 4 4 2 R2, R4 MAJ 6 7 2 2 2 1 TS 0 0 2 2 RX 5 1 1 1 0 NOR 1 1 2 1 1 1 RO I/C 2, 4, 7 2, 3, 8 3, 4 8 4 4 2 R5 MAJ 6 7 5, 6 4 2 2 1 TS 0 0 2 2 RX 4 1 1 1 0 NOR 1 1 1 1 1 RO I/C 2, 3, 8 2, 4, 6 6 4 4 2 R6 MAJ 7 5, 6 3 2 2 1 TS 0 0 2 2 RX 3 1 1 1 0 NOR 1 1 1 1 1 RO I/C 5, 6, 8 3, 4 5 4 4 2 R7 MAJ 7 5, 6 3 2 2 1 TS 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

Page 2 of 2

ES-301 Competencies Checklist Form ES-301-6 Facility: ANO Date of Examination: 11-17-2014 Operating Test No.: 2014-1 APPLICANTS RO RO R1, R3 R2, R4 SCENARIO SCENARIO Competencies 1 2 4 1 2 4 BOP ATC BOP ATC BOP Interpret/Diagnose Events 1, 2, 3, 4, 5, 2, 3, 4, 5, 6, 1, 3, 4, 5, 6 2, 3, 4, 5, 6, 1, 2, 3, 4, 5, N/A and Conditions 6, 8 7, 8 7, 8 6, 7, 8 Comply With and 1, 2, 4, 5, 6, 3, 4, 5, 6, 7, 2, 3, 4, 5, 6, 1, 3, 4, 5, 6 1, 2, 3, 6, 7 N/A Use Procedures (1) 8 8 7 Operate Control 3, 4, 5, 6, 7, 1, 4, 5, 6, 8 1, 3, 4, 5, 6 2, 4, 5, 6, 7 1, 2, 3, 6, 7 N/A Boards (2) 8 Communicate 1, 2, 3, 4, 5, 1, 2, 3, 4, 5, 1, 2, 3, 4, 5, 1, 2, 3, 4, 5, 1, 2, 3, 4, 5, N/A and Interact 6, 7, 8 6, 7, 8 6, 7 6, 7, 8 6, 7, 8 Demonstrate Supervisory N/A N/A N/A N/A N/A N/A Ability (3)

Comply With and N/A N/A N/A N/A N/A N/A Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

CONTINUED Page 1 of 4

ES-301 Competencies Checklist Form ES-301-6 Facility: ANO Date of Examination: 11-17-2014 Operating Test No.: 2014-1 APPLICANTS RO RO RO R5 R6 R7 SCENARIO SCENARIO SCENARIO Competencies 1 2 4 1 2 4 1 2 4 ATC BOP BOP BOP ATC ATC BOP 2, 3, 4, 1, 2, 3, 1, 2, 3, 2, 3, 4, Interpret/Diagnose Events 1, 3, 4, 2, 3, 4, 1, 3, 4, 5, 6, 7, 4, 5, 6, N/A 4, 5, 6, N/A 5, 6, 7, and Conditions 5, 6 5, 6, 7 5, 6 8 7, 8 7, 8 8 Comply With and 2, 3, 4, 1, 2, 3, 1, 3, 4, 1, 2, 3, 2, 3, 4, 3, 4, 5, 1, 3, 4, N/A N/A Use Procedures (1) 5, 6, 7 6, 7 5, 6 6, 7 5, 6, 7 6, 7, 8 5, 6 Operate Control 2, 4, 5, 1, 2, 3, 1, 3, 4, 1, 2, 3, 2, 4, 5, 3, 4, 5, 1, 3, 4, N/A N/A Boards (2) 6, 7 6, 7 5, 6 6, 7 6, 7 6, 7, 8 5, 6 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, Communicate 4, 5, 6, 4, 5, 6, 4, 5, 6, N/A 4, 5, 6, 4, 5, 6, N/A 4, 5, 6, 4, 5, 6, and Interact 7, 8 7, 8 7 7, 8 7 7, 8 7 Demonstrate Supervisory N/A N/A N/A N/A N/A N/A N/A N/A N/A Ability (3)

Comply With and N/A N/A N/A N/A N/A N/A N/A N/A N/A Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

CONTINUED Page 2 of 4

ES-301 Competencies Checklist Form ES-301-6 Facility: ANO Date of Examination: 11-17-2014 Operating Test No.: 2014-1 APPLICANTS SRO-U SRO-U U1, U2 U3 SCENARIO SCENARIO Competencies 1 2 4 1 2 4 SRO SRO SRO SRO Interpret/Diagnose Events 1, 2, 3, 4, 5, N/A 1, 2, 3, 4, 5, N/A 1, 2, 3, 4, 5, 1, 2, 3, 4, 5, and Conditions 6, 7, 8 6, 7 6, 7, 8 6, 7 Comply With and 1, 2, 3, 4, 5, 2, 3, 4, 5, 6, 2, 3, 4, 5, 6, 2, 3, 4, 5, 6, N/A N/A Use Procedures (1) 6, 7, 8 7 7, 8 7 Operate Control N/A N/A N/A N/A N/A N/A Boards (2)

Communicate 1, 2, 3, 4, 5, 1, 2, 3, 4, 5, 1, 2, 3, 4, 5, 1, 2, 3, 4, 5, N/A N/A and Interact 6, 7, 8 6, 7 6, 7, 8 6, 7 Demonstrate Supervisory 1, 2, 3, 4, 5, N/A 1, 2, 3, 4, 5, N/A 1, 2, 3, 4, 5, 1, 2, 3, 4, 5, Ability (3) 6, 7, 8 6, 7 6, 7, 8 6, 7 Comply With and 2, 3, 4 N/A 2, 3, 5 N/A 2, 4 2, 3, 5 Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

CONTINUED Page 3 of 4

ES-301 Competencies Checklist Form ES-301-6 Facility: ANO Date of Examination: 11-17-2014 Operating Test No.: 2014-1 APPLICANTS SRO-I SRO-I SRO-I S1, S2 S3 S4 SCENARIO SCENARIO SCENARIO Competencies 1 2 4 1 2 4 1 2 4 SRO ATC SRO ATC SRO BOP SRO ATC 1, 2, 3, 1, 2, 3, 2, 3, 4, 1, 2, 3, 1, 2, 3, 1, 2, 3, 2, 3, 4, Interpret/Diagnose Events 2, 3, 4, N/A 4, 5, 6, 4, 5, 6, 5, 6, 7, 4, 5, 6, 4, 5, 6, 4, 5, 6, 5, 6, 7, and Conditions 5, 6, 7 7, 8 7, 8 8 7 8 7, 8 8 2, 3, 4, 1, 2, 3, 2, 3, 4, Comply With and 2, 3, 4, 3, 4, 5, 2, 3, 4, 1, 2, 4, 2, 3, 4, N/A 5, 6, 7, 4, 5, 6, 5, 6, 7, Use Procedures (1) 5, 6, 7 6, 7, 8 5, 6, 7 5, 6, 8 5, 6, 7 8 7, 8 8 Operate Control 2, 4, 5, 3, 4, 5, 1, 4, 5, 2, 4, 5, N/A N/A N/A N/A N/A Boards (2) 6, 7 6, 7, 8 6, 8 6, 7 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, Communicate N/A 4, 5, 6, 4, 5, 6, 4, 5, 6, 4, 5, 6, 4, 5, 6, 4, 5, 6, 4, 5, 6, 4, 5, 6, and Interact 7, 8 7 7, 8 7, 8 7 7, 8 7, 8 7 1, 2, 3, 1, 2, 3, 1, 2, 3, 1, 2, 3, Demonstrate Supervisory N/A 4, 5, 6, N/A 4, 5, 6, N/A 4, 5, 6, N/A 4, 5, 6, N/A Ability (3) 7, 8 7, 8 7 7, 8 Comply With and N/A 2, 4 N/A 2, 3, 4 N/A 2, 3, 5 N/A 2, 4 N/A Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

Page 4 of 4

ML14336A376

Text

Reference:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description:

Description: