ML031210780

Final - Section C Operating

ML031210780
Person / Time
Site:	Indian Point
Issue date:	04/01/2003
From:	Wilson F Entergy Nuclear Northeast
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-286/03-301 50-286/03-301
Download: ML031210780 (64)

Text

Appendix D Scenario Outline Form ES-D-1 Facility:

IP3 Scenario No.:

3 Op Test No.:

1 Examiners:

Candidates:

CRS RO PO Initial Conditions:

45% power BOL 32 Charging Pump OOS 32 Heater Drain Pump OOS Small SG Tube Leak < 25 GPD Turnover:

Reduce Power and remove Main Turbine and Generator from service Critical Tasks:

Restore AC Power Stop ECCS pumps Event Malf.

Event No.

No.

Type*

Event Description 1

R (RO)

Reduce power.

N (BOP)

N (CRS) 2 NIS7D I (ALL)

PR NI failure high 3

MSS4D C

Steam Flow transmitter fails low (ROICRS) 4 EPS4F C

Loss of 6.9 KV bus 6 (BOP/CRS)

DG output breaker fail to auto close 5

EPS6 M (ALL)

Loss of Off Site power.

EPS4C Loss of 6.9 KV bus 3. Reactor trip.

6 DSG1B C (ALL)

Two Running DGs trip. 480 volt bus 3A tie breaker trips open.

lSGIC OVR EPS29 7

SIS7A C (ALL)

Inadvertent SI

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 3 The crew will assume the shift and commence a load reduction IAW POP-3. 1.

Shortly after the power reduction is underway, power range channel N44 will fail high. The RO will take manual control of rods IAW ONOP-NI-1. The BOP will defeat the failed channel inputs.

The CRS will determine appropriate Technical Specification action.

A Steam Flow transmitter failure will cause the associated Feedwater Regulating valve to fail in the closed direction. The crew will swap steam flow inputs IAW ONOP-RPC-1.

When the plant is stabilized, 6.9KV bus 6 will de-energize. The crew will check equipment operation IAW ONOP-EL-7. The standby Charging Pump will be started manually.

Subsequently, a loss of off-site power and a loss of 6.9KV bus 3 will require reactor trip.

Subsequent to the reactor trip, 32 and 33 DGs will trip, and the tie breaker to 480V bus 3A will fail to close, requiring entry to ECA-0.0, Loss of All AC Power.

An inadvertent SI actuation will occur subsequent to the trip. 480V bus 5A will be restored by local emergency diesel start, allowing exit from ECA-0.0. The crew will then perform the action required to terminate SI.

EOP flow path: E-O - ECA-0.0 - E-O - ES-1.1 Indian Point Unit 3 2003 NRC Initial License Examination Simulator Scenario Setup Scenario 3 RESET TO IC-38 32 Charging Pump OOS:

32 HDP Pump OOS:

EDG 32 Breaker fail to AUTO close:

OVR CVC47A 2 OVR CVC47C 2 OVR CVC47D 1 OVR CVC47F 2 OVR CVC47G 2 OVR FWH2A 2 OVR FWH2C 2 OVR FWH2D 1 OVR FWH2F 2 OVR FWH2G 2 OVR DSG6A 1 OVR DSG6C 2 OVR DSG6D 1 OVR DSG6E 2 OVR DSG6F 2 EDG trip on reactor trip:

Bus 3A Tie Breaker fail to close:

MAL DSG1C ACT,QC,JPPLP4 MAL DSG 1 B ACT,0,C,JPPLP4 OVR EPS29D 1 OVR EPS29F 2 Materials needed for scenario:

POP-3.1 Graph Book Tags for tagged equipment OA-99-29 (Operator Aid)

Daily Reactivity Sheet Allow crew to begin scenario brief approximately 30 minutes prior to entering simulator Note: Simulator IC data sheet has Condensate Booster Pumps in Trip Pullout Scenario built from IC 19 Indian Point Unit 3 2003 NRC Initial License Examination Simulator Scenario Turnover Information Scenario 3 The plant is at 45% power, steady state conditions exist.

Beginning of Life, Cbis 1581 ppm.

Burnup = 150 MWD/MTU Control Bank D = 166 steps Tavg = 5561F RCS Pressure = 2235 psig Pressurizer Level on program (33%)

The following equipment is out of service:

31 Charging Pump. Return expected in approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

32 Component Cooling Water Pump. Return to service in approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Crew instructions:

The plant has been at 45% power for 2 days due to Main Generator abnormalities at higher power levels In accordance with POP-3. 1, reduce power to 20% at 100 MWe per hour in preparation for removing the Turbine Generator from service for material inspection.

The STA will perform 3PT-V053B, Power Reduction Surveillance Requirements Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

3 Event #

1 Page 5

of 35 Event

Description:

Reduce Power.

Time E Position l

Applicant's Actions or Behavior CRS Refers to POP-3.1, step 4.1 CRS CONDUCT a brief using Attachment 7, POP-3.1 Briefing Guide INITIATE performance of the following attachments as required:

CRS o Attachment 1, Watch Routines/Operating Limits o Attachment 6, POP-3.1 Expected Alarms CRS ENTER starting power level and desired ending power level CRS N/A, initial, and date all inappropriate steps Obtain Shift Manager permission to reduce load and continue CRS performance of this attachment.

CRS Notify Entergy system operator of load reduction

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

3 Event #

1 Page 6

of 35 Event

Description:

Reduce Power.

Time Position l

Applicant's Actions or Behavior Commence performance of 3PT-V053B, Power Reduction CRS Surveillance Requirements.

Note: STA will perform Initiate generator load decrease to desired generator load at desired rate using any of the following:

BOP o

Governor (preferred) o Load Limit 1 o

Load Limit 2 Adjust Feedwater Regulators manual setpoint to null manual-auto deviation:

BOP o Maintain FW Regulators nulled while continuing with this attachment WHEN Turbine power is approximately 40%, THEN VERIFY RO Power Below C-20 lamp illuminates RO Initiates boration IAW SOP-CVCS-3 NOTE Reactivity changes shall be closely monitored by observation of different parameters such as Nis, MWs, Tavg, Tref, Control Rods, and AT RO Determine required increase in boron concentration

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

3 Event #

1 Page 7

of 35 Event

Description:

Reduce Power.

Time Position j

Applicant's Actions or Behavior Determine the volume of boric acid required for boration by using any of the following:

o CCR Reactivity Summary Sheet RO o CCR Computer program o

CVCS-5, Boration Nomograph Hot RCS o

CVCS-6, Boration Nomograph Cold RCS o

The Boration/Dilution book from Westinghouse (Operator Aid)

Set YIC-1 10, Boric Acid Flow Integrator, for required volume of RO boron Set FCV-1 1 OA, Boric Acid Flow Control Blender, controller to RO desired flow rate RO Ensure Boric Acid Trans Pump speed switches are in slow RO Ensure in-service Boric Acid Transfer Pump is in AUTO RO Place RCS Makeup Mode Selector switch in BORATE Turn RCS Makeup Control switch to START and return switch RO to NORM

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

3 Event#

1 Page 8

of 35 Event

Description:

Reduce Power.

Time Position Applicant's Actions or Behavior Observe the following as applicable:

RO o IF RX critical, THEN Tavg o

IF rods in AUTO, THEN control bank position o

IF RX subcritical, THEN count rate IF any of the following occurs, THEN immediately STOP boration:

o Rod motion is in wrong direction or becomes blocked o

Subcritical count rate increases AND a deliberate RO approach to criticality is NOT in progress o

Tavg increases o Axial flux target band is exceeded o

RCP seal injection flow becomes erratic NOTE WHEN boric acid integrator reaches preset value, THEN boration will automatically terminate IF performing additional boration without flushing of lines, THEN DEPRESS Integrator Reset P.B.

RO o Return to Step 4.4.8 (Turn RCS Makeup control switch to START and RETURN switch to NORM)

WHEN boration operation is complete, THEN FLUSH makeup RO lines with a minimum of 20 gallons of blended makeup per Step Rc t4.2 Proceed to Event 2 at Lead Evaluator's discretion

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

3 Event #

2 Page 9

of 35 Event

Description:

PR NI Failure Time ll Position 1

Applicant's Actions or Behavior Booth Instructor: When directed, insert the following command:

MAL NIS7D ACT,200,480,0 CRS Refers to ONOP-NI-1 RO May place rod control in MANUAL CRS Go to attachment 3 RO Place rod control in MANUAL Maintain Tave on program with Tref RO o Adjust control rods in manual o Adjust turbine load or boron concentration as necessary CAUTION If core operating above 75% power with one excore nuclear channel out of service, Technical Specifications require that a core quadrant power balance be determined (PER RA-1 1.1) at least once per day using movable incore instrumentation NOTE Refer to Tech Specs Table 3.3.1-1 (Completion times associated with Function 17 have 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> completion times)

I

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

3 Event #

2 Page 10 of 35 Event

Description:

PR NI Failure Time Position Applicant's Actions or Behavior CREW Verify only 1 Power Range Channel inoperable Remove affected channel from service as per SOP-NI-1 BOP (Evaluator Note: Procedure for removing N-44 from service is attached to back of scenario guide)

CRS Refers to Tech Specs 3.2.3, 3.2.4, 3.3.1 Proceed to Event 3 when directed by the Lead Evaluator or upon instruction to place rods in AUTO

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

3 Event#

3 Page 11 of 35 Event

Description:

Steam Flow Transmitter fails low Time ll Position L Applicant's Actions or Behavior Booth Instructor: When directed, insert the following command:

MAL MSS4D ACT,0,180,0 CRS Refers to ONOP-RPC-1, Instrument Failures.

Verify the following controls:

o Turbine load - STABLE o

Rod Control - STABLE CREW o

PRZR pressure control - NORMAL o

PRZR level control - NORMAL o

MBFP Speed - NORMAL o

SG levels - NORMAL(NO)

PERFORM the following:

o If affected instrument has caused a turbine runback, then perform the following:

o OPEN 31 DC Distribution panel, circuit 16 o

OPEN 32 DC Distribution panel, circuit 16 o

If SG control is affected, then place affected SG transfer CREW switches to non-affected channel (Flight Panel) o STM GEN NO 32 STM FL CONT TRANSFER o STM GEN NO 32 FW FL CONT TRANSFER o

If automatic control has failed, then perform the following:

o Place affected control system in MANUAL o

Control affected system to stabilize plant conditions

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

3 Event #

3 Page 12 of 35 Event

Description:

Steam Flow Transmitter fails low Time Position Applicant's Actions or Behavior NOTE o

Positive reactivity additions using control rods require CRS or SM approval and shall be made slowly and incrementally o

Substeps of step 2 may be performed in any order o

If a bistable failure is suspected with no other indications, then entry into the appropriate attachment is permitted Check the following instrumentation:

o RCS loop temperatures normal o

Check AT setpoints RO o Power Range channels o

Overpower AT o

Overtemperature AT o

RCS coolant loop flow channels o

PRZR instrumentation Check SG Instrumentation - NORMAL o SG Levels RO o

SG Pressures o SG Feedwater Flow o SG Steam Flow (NO)

CRS Go to Attachment 11, SG Steam Flow Channel Failures Perform Attachment 11 BOP (Evaluator note: Attachment 11 is attached to the back of this scenario guide)

Refer to Technical Specification 3.3.2 Condition D for failure of CRS FI-429B

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

3 Event #

3 Page 13 of 35 Event

Description:

Steam Flow Transmitter fails low Time Position 1

Applicant's Actions or Behavior I

I When Attachment 11 is complete or at the discretion of the Lead Evaluator, proceed to Event 4

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

3 Event#

4 Page 14 of 35 Event

Description:

Loss of 6.9 KV Bus 6; DG Output Breaker Fail to Auto Close Time Position E

Applicant's Actions or Behavior Booth Instructor: When directed, insert the following command:

MAL EPS4F ACT Refers to ONOP-EL-7, Loss of a 480 Volt Bus Above Cold CRS Shutdown Check RCP seal cooling o Check charging pumps -ANY RUNNING RO o

Start Charging pump o

Control speed to maintain 6-12 gpm seal injection Check Service Water Header Pressure - GREATER THAN 60 psig BOP o Non-Essential Header o Essential Header o Start 34 Service Water Pump Check status of Circ Pumps o

At least one per condenser running BOP o All running o

Reduce load as necessary to maintain greater than 25.5" vacuum Refer to ONOP-RW-2 if necessary

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

3 Event #

4 Page 15 of 35 Event

Description:

Loss of 6.9 KV Bus 6; DG Output Breaker Fail to Auto Close Time Position Applicant's Actions or Behavior NOTE o TSB 3.8.9 states the cross-tie between bus 5A and 2A, and the cross-tie between bus 3A and 6A shall be open above Mode 5 o Rod bottom lights and rod position indicators will only indicate correctly if Bus 2A and MCC-36C are energized o

It is acceptable for FCV-1 1 1A to be in AUTO and closed RO Check in-service Boric Acid Transfer Pump running Check EDG status BOP o Check EDG for affected 480V bus - energized by EDG (NO)

Check ABFP status RO/BOP o

Check ABFPs - ANY RUNNING (NO)

CREW Check any waste release in progress (NO)

Check Service Water Headers - Between 60 psig and 97.5 psig BOP o

Non-Essential o

Essential

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

3 Event #

4 Page 16 of 35 Event

Description:

Loss of 6.9 KV Bus 6; DG Output Breaker Fail to Auto Close Time Position plicant's Actions or Behavior CAUTION Different CCW pump combinations could result in surge tank levels changes Check Component Cooling Water status:

o Check CCW low pressure alarms on panel SGF -

CLEAR BOP o

Check CCW pumps - 3 running o Verify Thermal Barrier cooling established Thermal Barrier CCW Header Low flow alarm on panel SGF - CLEAR RO Verify Seal Injection flows - BETWEEN 6 and 12 gpm BOP Check IA header pressure greater than 90 psig Check 480V busses energized by 6.9 KV busses BOP o

Check bus 6A - ENERGIZED BY 6.9 KV Bus (NO)

CRS Go to Attachment 2 Performs Attachment 2 BOP (Evaluator note: Attachment 2 is attached to the back of this scenario guide)

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

3 Event#

4 Page 17 of 35 Event

Description:

Loss of 6.9 KV Bus 6; DG Output Breaker Fail to Auto Close Time Position Applicant's Actions or Behavior Evaluate Tech Spec impact CRS o

LCO 3.8.1 o

LCO 3.8.9 When NPO is directed to shut down 32 EDG or at discretion of Lead Evaluator, proceed to Event 5

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

3 Event #

5, 6, 7 Page 18 of 35 Event

Description:

Loss of Off-Site Power. Running DGs Trip. Inadvertent SI Time lPosition 1

Applicant's Actions or Behavior Booth Instructor: When directed, insert the following command:

MAL EPS6 ACT (Station Aux Transformer failure)

MAL EPS4C ACT (Loss of 6.9 KV Bus 3)

Determine Loss of Off-Site power has occurred. Loss of 6.9 KV CREW Bus 3 has occurred. Reactor Trip.

Opens E-0, Reactor Trip or Safety Injection CRS (May go directly to ECA-0.0)

Verify Reactor Trip o

Reactor trip and Bypass breakers open RO o Rod bottom lights lit o

Rod position indication less than 20 steps o

Neutron flux decreasing Verify turbine trip RO o All turbine stop valves closed BOP Verify all 480V AC Busses energized by offsite power (NO)

CRS Directs transition to ECA-0.0, Loss of All AC Power

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

3 Event #

5,6,7 Page 19 of 35 Event

Description:

Loss of Off-Site Power. Running DGs Trip. Inadvertent SI Time Position Applicant's Actions or Behavior NOTE o

CSF Status Trees should be monitored for information only. FRPs should NOT be implemented.

o Normal communication channels may be unavailable without AC power. Radios should be used by watch personnel outside the control room Verify Reactor Trip RO o Reactor trip and Bypass breakers open o Neutron flux decreasing Isolate Main Steam RO o Manually close all MSIVs o Check MSIV Bypass valves closed Booth Instructor:

If request has been made to restore EDG Power Supply to 480 volt busses, Start 33 EDG NOW by inserting the following commands, THEN report that 33 EDG is RUNNING:

MAL DSG1C CLR LOA DSG30 T If request has NOT been made yet, be prepared to start 33 EDG IMMEDIATELY when requested in step 6.a of ECA-0.0 using the commands above

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

3 Event #

5, 6, 7 Page 20 of 35 Event

Description:

Loss of Off-Site Power. Running DGs Trip. Inadvertent SI Time Position A

licant's Actions or Behavior Check if RCS is isolated:

o Check PRZR PORVs closed o Close Letdown Isolation Valves o

459 o

460 o

200A-C o

Check Excess Letdown stop valves closed RO o

CH-AOV-213A o CH-AOV-213B o

Check Resid HR LP Bypass To Demin closed o

CH-HCV-133 o

Close sample isolation valves o

SP-AOV-956A,C,E,G o

SP-AOV-956B,D,F,H o Secure any radwaste release in progress Maintain SG levels using Turbine driven AFW pump o

Check 32 AFW pump running o

Maintain 32 AFW pump discharge pressure greater than or equal to 150 psi above highest SG pressure o

Adjust HC-1 18, ABFP Turb Speed control BOP o

Check SG levels - ANY greater than 9% (NO) o Maintain AFW flow greater than 365 gpm until 1 NR SG level is >9%

o Preferentially restore level to 32 or 33 SG first o Establish level in 1 SG at a time and maintain feed flow to other SGs less than 100 gpm

Appendix D Operator Action Form ES-D-2 Op Test No.:

I Scenario #

3 Event #

5,6,7 Page 21 of 35 Event

Description:

Loss of Off-Site Power. Running DGs Trip. Inadvertent SI Time I

Position I

Applicant's Actions or Behavior CAUTION An Essential Service Water pump should be kept available to automatically load on its 480V bus to provide diesel generator cooling Determine status of Bus 2A and 3A o

Check bus 2A and 3A - EITHER energized (YES) o Attempt to close Bus no. 2A to 3A tie BOP/ RO o Check Bus 2A energized o Check the following equipment running o

32 CCW pump o

32 Service Water pump CAUTION Use extreme caution whenever attempting AC power restoration from multiple sources simultaneously Booth Instructor: When requested, and prior to procedure step 6.d, immediately Emergency start 33 EDG:

MAL DSG1C CLR (Clears malfunction)

LOA DSG30 T (Resets the trip)

Report that 33 EDG is RUNNING and that 32 EDG 86 relay would NOT reset CRITICAL Try to restore power to any 480V AC safeguards bus TASK o

Dispatch NPO to emergency start all EDGs and energize any 480V bus per SOP-EL-1 o

Contact and inform CON ED D.O. of urgent need for CRS AC power o

Attempt to energize any 480V AC bus using any of the following:

o EDGs per SOP-EL-1 o

Offsite power per SOP-EL-5 Check 480V AC Safeguards busses - ANY Energized CRS o

2A and 5A - (YES)

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

3 Event #

5, 6, 7 Page 22 of 35 Event

Description:

Loss of Off-Site Power. Running DGs Trip. Inadvertent Si Time l

Position

]

Applicant's Actions or Behavior Booth Instructor: When BOP verifies 2 ESW pumps running, insert the following command:

MAL SIS7A ACT CRS Check ECA-0.0, entered directly (YES OR NO)

CRS Go to E-0, Reactor Trip or Safety Injection (Step 1 or 3)

Verify reactor trip:

o Reactor trip and bypass breakers open RO o Rod bottom lights lit o

Rod position indicators less than 20 steps o

Neutron flux decreasing Verify Turbine Trip:

RO o Verify all turbine stop valves closed BOP Verify 480V AC Busses - All energized by offsite power

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

3 Event #

5, 6, 7 Page 23 of 35 Event

Description:

Loss of Off-Site Power. Running DGs Trip. Inadvertent SI Time Position Applicant's Actions or Behavior Determine if SI is actuated o

Any SI annunciator lit Crew OR o

Sl pumps -ANY RUNNING (YES) o Manually actuate SI o Close MSIVs Check AFW status:

BOP o Verify total AFW flow - greater than 365 gpm o Control feed flow to maintain SG NR levels between 9%(14%) and 50%

CAUTION Starting of equipment must be coordinated with all control room operators to ensure that two components are NOT started at the same time on the same power supply CRS Direct BOP operator to perform RO-1, BOP operator actions during use of EOPs (steps begin on page 27 of this guide) 4 4

+

4 Verify Feedwater Isolation:

o Verify MBFPs tripped o Verify MBFP discharge valves closed o BFD-MOV-2-31 o

BFD-MOV-2-32 o Verify Main and Bypass feedwater isolated o

Main and Bypass FW MOVs closed OR o

Main (SNF panel) and Bypass FW FRVs closed RO l

I

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

3 Event #

5, 6, 7 Page 24 of 35 Event

Description:

Loss of Off-Site Power. Running DGs Trip. Inadvertent SI Time Position

]

Applicant's Actions or Behavior Check SG Blowdown:

RO o SG Blowdown isolation valves closed o

SG Sample isolation valves closed Verify SI flow:

o Check RCS pressure less than 1650 psig (2000 psig)(NO)

RO o

Check HHSI pump flow indicators - Flow indicated o

Check RCS pressure less than 325 psig (650 psig) (NO)

Verify Containment Spray NOT required:

RO o Check containment pressure has remained less than 22 psig Check RCP seal cooling:

o Verify CCW flow to RCP thermal barriers o

RCP BEARING COOLANT LOW FLOW alarm RO on panel SGF clear o

THERMAL BARRIER CCW HEADER LOW FLOW alarm on panel SGF clear o

Trip RCPs Booth Instructor: When directed to open CH-288, immediately insert the following command:

LOA CVC34 I ow

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

3 Event#

5, 6, 7 Page 25 of 35 Event

Description:

Loss of Off-Site Power. Running DGs Trip. Inadvertent SI Time Position Applicant's Actions or Behavior RO Check RCS Tcold temperature stable at or trending to 5470F Check if RCPs should be stopped RO o

Already tripped Check PRZR PORVs, Safety Valves, and Spray Valves o

Check both PRZR PORVs - CLOSED o

Check PRZR Safety Valves - CLOSED RO o

Tailpipe temperatures normal o Acoustic monitors normal o

Check normal PRZR Spray Valves closed o

Check CH-AOV-212 closed Determine if SGs are faulted:

RO o Check SG pressures:

o ANY DECREASING IN AN UNCONTROLLED MANNER (NO)

Determine if SG tubes are ruptured:

o Condenser Air ejector radiation recorder trends -

CREW NORMAL o

SG Blowdown Radiation recorder trends - NORMAL o

Main Steam Line radiation recorder trends - NORMAL o

All intact SG level response - NORMAL Determine if RCS is intact:

CREW o

Containment pressure - NORMAL o

Containment sump level - NORMAL a

Containment radiation - NORMAL

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

3 Event #

5, 6, 7 Page 26 of 35 Event

Description:

Loss of Off-Site Power. Running DGs Trip. Inadvertent SI Time Position Applicant's Actions or Behavior Determine if SI should be terminated:

o Check RCS subcooling based on qualified CETs greater than 400F o Check secondary heat sink o Total AFW to intact SGs greater than 365 psig available, OR Crew o Intact SG NR levels - ANY greater than 9%

(14%)

o RCS pressure o

Greater than 1650 psig (2000 psig) o Stable or increasing o

Pressurizer level greater than 14%

CRS Go to ES-1.1, SI Termination Reset SI as follows:

o Check verification of SI automatic actions of steps 2 -

12 of RO-1 is complete RO/BOP o Press BOTH SI RESET pushbuttons on Panel SBF-2:

a. Train 1 SI Reset

b. Train 2 SI Reset o

Check SI - RESET

a. SI ACTUATED light - EXTINGUISHED

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

3 Event#

5, 6, 7 Page 27 of 35 Event

Description:

Loss of Off-Site Power. Running DGs Trip. Inadvertent SI Time Position Applicant's Actions or Behavior Reset Containment Isolation Phase A and Phase B as follows:

o Place switches for letdown orifice isolation valves to close:

o 200A RO/BOP o 2008 o 200C o

Reset Phase A o

Reset Phase B, if required (NO)

Direct BOP operator to initiate performance of attachment 3, CRS Re-establishing operator control of valves following phase A CRS reset Establish Instrument Air to containment:

o Check INST AIR LOW PRESS alarm on panel SJF RO clear o

Press Instr. Air Reset PB 28 on panel SMF o

Open IA-PCV-1 228, Inst Air to Cont.

Critical Stop SI pumps and place in AUTO task RO o SI pumps o RHR pumps Terminate scenario when SI pumps are off

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

All Event #

Page 28 of 35 Event

Description:

RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Monitor Control Room Annunciators:

a. Acknowledge all Supervisory Panel Alarms as time permits

b. Report all unusual alarms affecting accident BOP response to CRS

c. Monitor status of the following alarms:

HIGH CONT ATMOS TEMP/RTD FAILURE - CLEAR 480 V SAFEGUARDS UNDERVOLTAGE

- CLEAR Caution Starting of equipment must be coordinated with the CRS to ensure that two components are not started at the same time on the same power supply.

Verify Si Pumps - RUNNING BOP

a. THREE Si pumps

b. TWO RHR pumps Verify Containment FCU status:

a. Check FCUs -ALL RUNNING

b. Place FCU Damper control switch in -

INCIDENT MODE position

c. Check FCU dampers for all FCUs - IN INCIDENT MODE POSITION BOP Dampers A/B - CLOSED (inlet)

Damper C - CLOSED (bypass)

Damper D - OPEN (outlet)

d. Place control switches for 1104 and 1105 to OPEN

e. Check Service Water Cooling Valves - OPEN 1104 1105 BOP Verify SI Valve alignment - Proper Emergency Alignment

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

All Event #

Page 29 of 35 Event

Description:

RO-1, BOP Operator Actions During EOPs Time ll Position Applicanfts Actions or Behavior

a. Verify Safeguard Valve Off Normal Position alarm on panel SBF CLEAR

b. Ensure BIT Discharge valves 1835A, 1835B -

OPEN

c. Ensure BIT Inlet valves 1852A, 1852B -

OPEN

d. Ensure High Head Stop valves 856J, 856H, 856C, 856E - OPEN

e. If RWST purification loop in service, then secure system per SOP-SI-3 Verify ABFP status:

BOP

a. Check Motor Driven Pumps - BOTH RUNNING

b. Check Turbine Driven Pump - RUNNING Verify ABFP valve alignment:

a. If Motor Driven AFW pump(s) are running, ensure SG Aux FW Reg valve controllers -

Set to 0% (full open)

BOP FCV-406A FCV-406B FCV-406C FCV-406D

b. Check SG Blowdown Isolation Valves -

CLOSED

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

All Event #

Page 30 of 35 Event

Description:

RO-1, BOP Operator Actions During EOPs Time Position 1 Applicant's Actions or Behavior Verify CCW Pump status:

BOP

a. Check CCW pumps - ALL RUNNING

b. Check RHR HX CCW Shutoff valve - OPEN BOP Verify Essential Service Water Pumps - Three Running Verify Containment Isolation Phase A:

a. Check Phase A - ACTUATED BOP

b. Check Phase A valves - CLOSED Refer to Attachment 2, Phase A valve closure list Verify Containment Ventilation Isolation:

a. Check Purge Valves - CLOSED FCV-1170 FCV-1171 FCV-1 172 FCV-1 173

b. Check Pressure Relief valves - CLOSED PCV-1190 BOP PCV-1191 PCV-1192

c. Check WCCPP low pressure zone alarm -

NOT LIT

d. Verify IVSW Valves - OPEN IV-AOV-1410 IV-AOV-1413 IV-SOV-6200 IV-SOV-6201 BOP Verify Emergency Diesel Generator status:

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

All Event #

Page 31 of 35 Event

Description:

RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior

a. Check EDGs-ALL RUNNING

b. Check Both EDG SWS Outlet Flow Control Valves - OPEN SWN-FCV-1 176 SWN-FCV-I 176A

c. Dispatch NPO to set switches for both EDG SWS Outlet Flow Control Valves to OPEN:

SWN-FCV-1176 SWN-FCV-i 176A Verify Control Room Ventilation:

a. SET Control Room ventilation control switch to - 10% INCIDENT MODE (switch position 3)

b. Check Damper status Dampers A, B, F1, F2

• A-DIM B - BRIGHT BOP Either F1 OR F2 - BRIGHT Dampers D1 and D2 - BRIGHT

c. Verify AC Compressors and fans - ALL RUNNING ACC 31A ON - BRIGHT ACC 31 B ON-BRIGHT ACC 32A ON - BRIGHT ACC 32B ON - BRIGHT ACF 31 ON - BRIGHT ACF 32 ON - BRIGHT

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

All Event #

Page 32 of 35 Event

Description:

RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Verify Emergency DC Oil Pumps status:

Main turbine emergency bearing oil pump -

BOP RUNNING Dispatch NPO to verify main generator air side seal oil backup pump - RUNNING MBFP DC emergency oil pump - RUNNING Reset SI as follows:

a. Press BOTH SI RESET pushbuttons on Panel SBF-2:

BOP Train 1 SI Reset Train 2 SI Reset

b. Check SI - RESET SI ACTUATED light-EXTINGUISHED Reset MCCs as follows:

a. Dispatch NPO to secure VC sump pumps and BOP RCDT pumps on Waste Disposal panel

b. Dispatch NPO to align and reset MCCs per SOP-EL-15 Note to examiner:

The following step is designed to stop actions of RO-1 IF the CRS has transitioned to ES-1.1. The BOP will continue in RO-1 if there is transition to other procedures, but any time ES-1.1 is entered, the BOP will inform the CRS of automatic action verification and RO-1 will be suspended.

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

All Event #

Page 33 of 35 Event

Description:

RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Check if additional SI actions should be performed:

a. Check if the CRS has transitioned to - ES-1.1

b. Perform the following:

Inform the CRS of the status of automatic BOP action verification If E-0 has been exited, THEN continue with step 17 If E-0 has NOT been exited, then wait until E-0 is exited. When E-0 is exited, then recheck this step Perform the following:

a. Dispatch NPO to perform the following:

Close SWN-FCV-I 111 and SWN-FCV-1112 BOP

b. Check Condensate Pumps - ONLY ONE RUNNING.

c. SECURE all but one Condensate Pump

d. Initiate the following section of SOP-EL-15 Alignment of City water Cooling Reset Containment isolation Phase A and Phase B as follows:

a. PLACE switches for letdown orifice isolation valves to CLOSE:

BOP 200A 200B 200C

b. RESET Phase A

c. RESET Phase B, if actuated

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

All Event #

Page 34 of 35 Event

Description:

RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Establish Instrument Air and Nitrogen to containment:

a. Establish IA to containment:

Check INST AIR LOW PRESS alarm on panel SJF - CLEAR DEPRESS Inst Air reset pushbutton 28 BOP CHECK IA-PCV-1228, Inst Air to Cont. -

BOP OPEN

b. ESTABLISH PRZR PORV N2 supply:

PRESS Accumulator N2 Supply Reset pushbutton 44 Check 863, Accumulator N2 Supply Valve

- OPEN Check if one non-essential Service Water pump should be started:

a. Check Off-Site power to at least one Non-BOP Essential service Water Pump - AVAILABLE

b. Check SWN-FCV-1 1 1 1 and SWN-FCV-1 1 12

-CLOSED

c. START one Non-Essential Service Water pump Check status of off-site power:

a. VERIFY all AC Busses:

BOP Energized by off-site power AND All 480V tie breakers open

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

All Event #

Page 35 of 35 Event

Description:

RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior NOTE It is permissible for operators to perform board clean-up actions (steps 22-29 of ROI, BOP OPERATOR ACTIONS DURING USE OF EOPs) while performing actions of other EOPs; provided this does not interfere with other EOPs in progress.

EVALUATOR NOTE: The remainder of the steps in this attachment are highlighted (High Level) action only.

BOP Re-align secondary plant BOP Check secondary valve position BOP Check Heater Drain Pumps 31 and 32 Tripped BOP Check plant equipment status BOP Determine if Source Range detectors should be energized BOP Start AC Oil Pumps and Stop DC Oil pumps as follows BOP Check Long Term Plant status BOP Inform CRS that RO-1 is complete and advise on the status Iof actions

Appendix D Scenario Outline Form ES-D-1 Facility:

IP3 Scenario No.:

4 Op Test No.:

1 Examiners:

Candidates:

CRS RO I

~PO I

Initial Conditions:

94% power EOL 32 Charging Pump OOS 31 AFW Pump OOS Small SG Tube Leak < 25 GPD Turnover:

Main Condenser rupture disc is leaking. Reduce Power to 50 MWe at 200 MWe per hour and remove Main Turbine and Generator from service Critical Tasks:

Manual Turbine Trip Initiate Emergency Boration Event l

Malf.

Event No.

No.

Type*

Event Description 1

R (RO)

Reduce load N (BOP)

N (CRS) 2 TUR10B (CRS)

First Stage Sheil Pressure PT-412B fails low 3

MSS3 I (RO)

Steam Pressure transmitter 404 fails high I (CRS) 4 CCW1A CCW Pump Trip.

5 RCS10C C (ALL)

RCP TBHX leak. RCP vibration RCS7C 6

XMT38 M (ALL)

RCP sheared shaft; ATWS XMT39 XMT40 7

TUR2A C (RO)

Turbine Trip failure TUR2B 8

CVC16 C (ALL)

Boration failure

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 4 The crew will assume the shift and initiate a load decrease in accordance with POP-2.1.

First Stage Shell Pressure transmitter PT-412B will fail low. The crew will place steam dumps in Pressure Control Mode and will bypass AMSAC IAW ONOP-RPC-1. The CRS will refer to Technical Specifications.

When actions are complete, Steam pressure transmitter PT-404 will fail high, causing Feed Pump speed to increase and Feed Regulating Valves to throttle closed. The crew will respond by placing Feed Pump Speed Control and steam dumps in manual IAW ONOP-FW-1.

A running CCW pump will trip. The standby pump will automatically start. The crew will respond IAW ONOP-CC-1. A TBHX leak will develop, and manual action to isolate the TBHX will be taken IAW ONOP-CC-2.

During the TBHX tube leak, RCP vibration will rise, eventually resulting in failure of the RCP shaft. The crew will refer to ARP-13 and ONOP-RCS-5. A reactor trip will be required based on Low RCS Loop Flow, but will not automatically occur.

The RO will attempt to manually trip the reactor, but the reactor will not trip. The turbine must be manually tripped, and emergency boration will fail, requiring an alternate method to be used for emergency boration.

EOP flow path: E FR-S.1 - E ES-0.1 Indian Point Unit 3 2003 NRC Initial License Examination Simulator Scenario Setup Scenario 4 RESET TO IC-39 32 Charging Pump OOS:

31 ABFP OOS:

ATWS:

OVR CVC47A 2 OVR CVC47C 2 OVR CVC47D 1 OVR CVC47F 2 OVR AFW9A 2 OVR AFW9C 2 OVR AFW9D I OVR AFW9F 2 MAL RPS2A ACT MAL RPS2B ACT OVR EPS24D,2,0 OVR EPS24G,2,0 OVR EPS17D,2,0 OVR EPS17G,2,0 Boration failure:

Materials needed for scenario:

POP-2.1 Graph Book Tags for tagged equipment OA-99-29 (Operator Aid)

Daily Reactivity Sheet OVR CVC16A 1 OVR CVC16C I OVR CVC16D 2 OVR CVC16B 2 Allow crew to begin scenario brief approximately 30 minutes prior to entering simulator Note: Simulator IC data sheet has Condensate Booster Pumps in Trip Pullout Scenario built from IC 12 Indian Point Unit 3 2003 NRC Initial License Examination Simulator Scenario Turnover Information Scenario 4 The plant is at 94% power, steady state conditions exist.

End of Life, Cb is 14 ppm.

Burnup = 23135 MWD/MTU Control Bank D = 213 steps Tavg = 565.31F RCS Pressure = 2235 psig A small Steam Generator Tube Leak exists on 33 SG, less than 5 gallons per day.

The following equipment is out of service:

32 Charging Pump. Return expected in approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

31 Auxiliary Boiler Feed Pump. Return to service in approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Action of ITS 3.7.5.b entered 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago.

Crew instructions:

One LP Turbine Main Condenser Rupture Disc is leaking.

In accordance with POP-2.1, reduce generator load to 50 MWe at a rate of 200 MWe per hour and remove the Main Turbine and Generator from service to facilitate rupture disc repair.

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

4 Event #

1 Page 5

of 29 Event

Description:

Reduce Load Time Position Applicant's Actions or Behavior Refers to POP-2.1, step 4.3.1 CRS o

Refer to Attachment 1, Watch Routines/Operating Requirements Refers to POP-2.1, step 4.3.2 CRS o Go to Attachment 3, Reactor Power Reduction Checklist, for lowering plant load CRS Enter starting power level and desired ending power level CRS Record reason for load reduction Ensure a reactivity calculation for power reduction is CRS performed. (Attachment 5 may be used as necessary)

If reactor power is less than 100%, then N/A, initial, and date all CRS inappropriate steps Obtain Shift Manager permission to reduce load and continue CRS performance of this attachment.

CRS Notify Entergy system operator of load reduction

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

4 Event #

1 Page 6

of 29 Event

Description:

Reduce Load Tie Position Applicant's Actions or Behavior Commence performance of 3PT-V053B, Power Reduction CRS Surveillance Requirements.

CRS Perform a reactivity briefing for pending load change If RCS boron concentration will be changed by 10 ppm or RO greater, then energize all PRZR backup heaters Initiate generator load decrease to desired generator load at desired rate using any of the following:

BOP o Governor (preferred) o Load Limit 1 o

Load Limit 2 Adjust Feedwater Regulators manual setpoint to null manual-auto deviation:

BOP o Maintain FW Regulators nulled while continuing with this attachment RO Initiates boration IAW SOP-CVCS-3 NOTE Reactivity changes shall be closely monitored by observation of different parameters such as Nis, MWs, Tavg, Tref, Control Rods, and AT RO Determine required increase in boron concentration

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

4 Event #

1 Page 7

of 29 Event

Description:

Reduce Load Time Position Applicant's Actions or Behavior Determine the volume of boric acid required for boration by using any of the following:

o CCR Reactivity Summary Sheet RO o CCR Computer program o

CVCS-5, Boration Nomograph Hot RCS o

CVCS-6, Boration Nomograph Cold RCS o

The Boration/Dilution book from Westinghouse (Operator Aid)

Set YIC-1 10, Boric Acid Flow Integrator, for required volume of RO boron Set FCV-1 1 OA, Boric Acid Flow Control Blender, controller to RO desired flow rate RO Ensure Boric Acid Trans Pump speed switches are in slow RO Ensure in-service Boric Acid Transfer Pump is in AUTO RO Place RCS Makeup Mode Selector switch in BORATE Turn RCS Makeup Control switch to START and return switch RO to NORM

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

4 Event #

1 Page 8

of 29 Event

Description:

Reduce Load Time

]Position Applicant's Actions or Behavior Observe the following as applicable:

RO o IF RX critical, THEN Tavg o

IF rods in AUTO, THEN control bank position o

IF RX subcritical, THEN count rate IF any of the following occurs, THEN immediately STOP boration:

o Rod motion is in wrong direction or becomes blocked RO o Subcritical count rate increases AND a deliberate approach to criticality is NOT in progress o

Tavg increases o

Axial flux target band is exceeded o

RCP seal injection flow becomes erratic NOTE WHEN boric acid integrator reaches preset value, THEN boration will automatically terminate IF performing additional boration without flushing of lines, THEN DEPRESS Integrator Reset P.B.

RO o Return to Step 4.4.8 (Turn RCS Makeup control switch to START and RETURN switch to NORM)

WHEN boration operation is complete, THEN FLUSH makeup RO lines with a minimum of 20 gallons of blended makeup per Step Rc o4.2 Proceed to Event 2 at Lead Evaluator's discretion

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

4 Event #

2 Page 9

of 29 Event

Description:

First Stage Shell Pressure PT-412B Fails Low Time Position 1

Applicant's Actions or Behavior Booth Instructor: When directed, insert the following command:

MAL TUR10B ACT,0,120,0 CRS Refers to ONOP-RPC-1, Instrument Failures Verify the following controls:

o Turbine load - STABLE o

Rod Control - STABLE CREW o

PRZR pressure control - NORMAL o

PRZR level control - NORMAL o

MBFP Speed - NORMAL o

SG levels - NORMAL NOTE o

Positive reactivity additions using control rods require CRS or SM approval and shall be made slowly and incrementally o

Substeps of step 2 may be performed in any order o

If a bistable failure is suspected with no other indications, then entry into the appropriate attachment is permitted Check the following instrumentation:

o RCS loop temperatures normal o

Check AT setpoints RO o

Power Range channels o

Overpower AT o

Overtemperature AT o

RCS coolant loop flow channels a PRZR instrumentation

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

4 Event #

2 Page 10 of 29 Event

Description:

First Stage Shell Pressure PT-412B Fails Low Time P

Applicant's Actions or Behavior Check SG Instrumentation - NORMAL o

SG Levels RO o SG Pressures o

SG Feedwater Flow o

SG Steam Flow CREW Check Turbine first stage pressure - NORMAL (NO)

Go to attachment 12, Turbine First Stage Pressure Channel CRS Failures Performs attachment 12 RO/BOP (Evaluator note: Att. 12 procedure is attached to the end of this scenario guide)

CRS Refer to Technical Requirements Manual 3.1.A for AMSAC I _I I

When Steam Dumps are in Pressure Control Mode in accordance with attachment 12, proceed to Event 3

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

4 Event#

3 Page 11 of 29 Event

Description:

Steam Pressure Transmitter 404 Fails High Time Position F

Applicant's Actions or Behavior Booth Instructor: When directed, insert the following command:

MAL MSS3 ACT,1050,480,0 CREW Determines that MBFP speed is increasing CRS May refer to ONOP-FW-1 due to feed transient RO Check MBFPs - BOTH RUNNING Verify the following controls:

RO o MBFP Speed control stable (NO) o All SG levels stable If automatic control has failed, then perform the following:

o Place affected control system in manual RO o Control affected system to stabilize plant conditions o

Refer to attachment 2, Main Feedwater Regulating valves program DP

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

4 Event #

3 Page 12 of 29 Event

Description:

Steam Pressure Transmitter 404 Fails High Tie Position I

-Applicant's Actions or Behavior Check the following conditions - NORMAL FOR PRESENT POWER LEVEL:

o Both MBFPs - RUNNING o

Heater Drain Pumps - RUNNING o

Condensate Pumps - RUNNING o

Check MBFP operation o

MBFP instrumentation - NORMAL RO P1-404, Main Steam Header Pressure RO (NO)

PI-408A, Feed Pump Discharge Pressure PI-408B, Feed Pump Suction Pressure o

MBFP Speed Control - OPERATING PROPERLY o

Main Feedwater Regulating valves - MAINTAINING SG PROGRAM LEVEL CRS Go to attachment 4, Loss of MBFP speed control Perform attachment 4 RO/BOP (Evaluator note: Attachment 4 procedure steps are attached to the end of this scenario guide)

_ I __

_ I I__

When steam dump control is placed in manual or at Lead Evaluator's discretion, proceed to Event 4

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

4 Event#

4 Page 13 of 29 Event

Description:

CCW Pump Trip.

Time D Position 1

Applicant's Actions or Behavior Booth Instructor: When directed, insert the following command:

MAL CCWIA ACT,0,0 (31 CCW trip)

MAL RCS10C ACT,40,180,300 (TBHX tube leak)

MAL RCS7C ACT,10,600,300 (RCP vibration)

CRS Refer to ONOP-CC-1 Note: Next event initiation is on time delay from initiation of this event.

If one or both of the previously operating CCW pumps have tripped, then verify that the standby pump has started BOP automatically o 32 CCW pump NOTE o

If a tripped CCW pump is required to maintain the plant in a safe condition, then one breaker re-closure attempt (without investigation) is allowed o

Step 5.1.1 through step 5.3.3.2 actions to split CCW headers may be initiated at any time CCW surge tank level can't be maintained, while continuing with this procedure If levels in the CCW surge tanks are decreasing, then initiate BOP primary water makeup to the respective surge tank(s). (NIA)

CAUTION If RCP seal cooling has been lost and the RCS temperature is greater than 3500F then seal injection shall not be re-established and the reactor shall be brought to Mode 5 to minimize any further seal degradation If surge tank levels decrease to less than 5% level in BOTH BOP tanks then trip all CCW pumps (NIA)

+/-

+

Op Test No.:

1 Scenario #

5 Event #

4, 5, 6 Page 14 of 29 Event

Description:

SGTR, Atmospheric Dump Valve on ruptured SG fails open; Train "B" RTB fails closed. Manual action to stop ECCS pumps.

Time Position Applicant's Actions or Behavior Check AFW status:

o Verify total AFW flow - greater than 365 gpm BOP o

Control feed flow to maintain SG NR levels between 9%(14%) and 50%

o May stop feed to 33 SG based on SG level CAUTION Starting of equipment must be coordinated with all control room operators to ensure that two components are NOT started at the same time on the same power supply Direct BOP operator to perform RO-1, BOP operator actions during use of EOPs (steps begin on page 22 of this guide)

Verify Feedwater Isolation:

o Verify MBFPs tripped o

Verify MBFP discharge valves closed o

BFD-MOV-2-31 o

BFD-MOV-2-32 o

Verify Main and Bypass feedwater isolated o

Main and Bypass FW MOVs closed OR o

Main (SNF panel) and Bypass FW FRVs closed Booth Instructor: Approximately 5 minutes after call to open 'B' Reactor Trip Breaker, report that it will NOT open Check SG Blowdown:

RO o

SG Blowdown isolation valves closed o

SG Sample isolation valves closed

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

4 Event#

6, 7, 8, Page 15 of 29 Event

Description:

RCP Sheared Shaft; ATWS; Turbine Trip Failure; Boration Failure I

Time Position Applicant's Actions or Behavior l This event was initiated via time delay on the previous eventI NOTE AC-FCV-625, RCP Thermal Barrier Return Isolation, may close following the start of a CCW pump due to momentary flow surge Verify AC-FCV-625 is open BOP o

If AC-FCV-625 is closed, then an RCP Thermal Barrier leak may exist Observe the following for abnormal indication:

o CCW surge tank level o

Letdown flow rate o

Charging flow rate CREW o

Thermal barrier Delta P o

RCP seal injection flows o

Pressurizer level trend o

RCP thermal barrier return flow (Local) o WHUT levels BOP Close AC-FCV-625 Investigate RCP vibration alarm (ARP-13) (ONOP-RCS-5 also RO applies but unlikely action will be taken prior to RCP failure)

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

4 Event #

6, 7, 8, Page 16 of 29 Event

Description:

RCP Sheared Shaft; ATWS; Turbine Trip Failure; Boration Failure Time Position Applicant's Actions or Behavior Booth Instructor: When RO is checking RCP vibration, insert the following commands:

FILE RCSFLOW2 (OVR XMT RCS38 85,40,0)

(OVR XMT RCS39 85,40,0)

(OVR XMT RCS40 85,40,0)

CREW Recognize requirement for reactor trip on Low RCS flow CRS Enter E-0, Reactor Trip or Safety Injection. Direct reactor trip.

RO Attempt to manually trip reactor.

De-energize busses with an energized MG set for at least 5 BOP seconds then re-energize o

Bus 2A and 6A Critical RO Manually Trip the turbine Task CRS Go to FR-S. 1, Response to Nuclear Power Generation/ATWS CRS Dispatch NPO to trip reactor using posted operator aid Verify reactor trip o

Reactor trip and bypass breakers open RO o

Rod bottom lights lit o

Rod position indicators less than 20 steps a

Neutron flux decreasing

__I I

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

4 Event #

6, 7, 8, Page 17 of 29 Event

Description:

RCP Sheared Shaft; ATWS; Turbine Trip Failure; Boration Failure Tim Position 1Applicant's Actions or Behavior Manually trip reactor RO o Insert control rods in manual o Dispatch NPO to trip reactor using posted operator aid

_ ~I.

I NOTE If at any time reactor power decreases to less than 5% with a zero or negative startup rate, then go to step 15, page 13 I

I Verify turbine trip RO (Should have been tripped manually)

Check Auxiliary Feedwater pumps running BOP o

Motor Driven Both running o Total AFW flow greater than 730 gpm Initiate Emergency Boration of RCS RO/BOP o

Check charging pumps - ANY RUNNING o

Open CH-MOV-333, Emergency Boration valve (Will NOT open)

Critical Emergency Borate using one of the following methods in order Task of preference:

o (Normal boration)

RO/BOP o Attachment 2 (RWST) a (Failing air to FCV-11 0A)

Evaluator note: Attachment I is included at the end of this scenario guide

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

4 Event#

6, 7, 8, Page 18 of 29 Event

Description:

RCP Sheared Shaft; ATWS; Turbine Trip Failure; Boration Failure Time Position Applicant's Actions or Behavior Verify containment ventilation isolation o

Check Purge valves closed BOP o Check pressure relief valves closed o

Check WCCPP low pressure zone alarms NOT lit Check Si actuated RO o If required, then actuate Si (NO)

Determine if the following trips have occurred:

RO o

Reactor trip o Turbine trip Check SG NR levels - ANY greater than 9%

RO/BOP o Verify AFW flow greater than 730 gpm until SG NR level is greater than 9%

Verify all dilution paths isolated RO a

FCV-111Aclosed o CH-330, Boric acid blender primary water bypass isolation closed

Appendix D Operator Action Form ES-D-2 Op Test No.:

I Scenario#

4 Event#

6, 7, 8, Page 19 of 29 Event

Description:

RCP Sheared Shaft; ATWS; Turbine Trip Failure; Boration Failure Time Position Applicant's Actions or Behavior Check for uncontrolled reactivity insertion from uncontrolled RCS cooldown RO/BOP o RCS temperatures decreasing in an uncontrolled manner o

Any SG pressure decreasing in an uncontrolled manner o STOP any CONTROLLED Cooldown Booth Instructor:

Delete RTB malfunctions and report as NPO that reactor trip breakers are open MAL RPS2A CLR MAL RPS2B CLR RO Check CETs less than 12001F Verify reactor subcritical RO o Power range less than 5%

o Intermediate range SUR zero or negative RO Check all rods less than 20 steps Secure any emergency boration in progress RO o

Turn makeup control switch to stop o

Establish Auto makeup per SOP-CVCS-3 RO Place both boric acid transfer pumps to slow speed RO Open BAST recirc control valves to approximately 25% open

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

4 Event #

6, 7, 8, Page 20 of 29 Event

Description:

RCP Sheared Shaft; ATWS; Turbine Trip Failure; Boration Failure

[ime Position I

Applicant's Actions or Behavior Check RCP seal cooling RO/BOP o Seal Injection established o Thermal Barrier Cooling established Check charging pump status RO o CCW available o Any charging pump running o

Control speed to maintain 6-12 gpm seal injection Verify adequate Shutdown Margin o

Verify all control rods less than 20 steps CREW o Direct watch chemist to sample RCS o

Check boron concentration greater than required for cold shutdown o

Refer to graph 4A, 4B CRS Return to E-0 Verify reactor trip o

Reactor trip and Bypass breakers open RO o Rod bottom lights lit a

Rod position indication less than 20 steps a

Neutron flux decreasing Verify turbine trip RO o All turbine stop valves closed

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

4 Event #

6, 7, 8, Page 21 of 29 Event

Description:

RCP Sheared Shaft; ATWS; Turbine Trip Failure; Boration Failure T__imrne D1 Position Applicant's Actions or Behavior BOP Verify all 480V AC Busses energized by offsite power Determine if SI is actuated RO o Any SI annunciator lit OR o Sl pumps-ANY RUNNING Determine if SI required using posted operator aid RO o

Determines SI NOT required Start Both Motor Driven ABFPs BOP o

Starts 31 and 32 ABFP manually CRS Direct transition to ES-0.1, Reactor Trip Response Terminate scenario upon transition to ES-O. 1

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

Al Event #

Attachment I Page 22 of 29 Event

Description:

RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Monitor Control Room Annunciators:

a. Acknowledge all Supervisory Panel Alarms as time permits

b. Report all unusual alarms affecting accident BOP response to CRS

c. Monitor status of the following alarms:

HIGH CONT ATMOS TEMP/RTD FAILURE - CLEAR 480 V SAFEGUARDS UNDERVOLTAGE

-CLEAR Caution Starting of equipment must be coordinated with the CRS to ensure that two components are not started at the same time on the same power supply.

Verify SI Pumps - RUNNING BOP

a. THREE SI pumps

b. TWO RHR pumps Verify Containment FCU status:

a. Check FCUs - ALL RUNNING

b. Place FCU Damper control switch in -

INCIDENT MODE position

c. Check FCU dampers for all FCUs - IN INCIDENT MODE POSITION BOP Dampers A/B - CLOSED (inlet)

Damper C - CLOSED (bypass)

Damper D - OPEN (outlet)

d. Place control switches for 1104 and 1105 to OPEN

e. Check Service Water Cooling Valves - OPEN 1104 1105 BOP Verify SI Valve alignment - Proper Emergency Alignment

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

All Event #

Page 23 of 29 Event

Description:

RO-1, BOP Operator Actions During EOPs Time Position j

Applicant's Actions or Behavior

a. Verify Safeguard Valve Off Normal Position alarm on panel SBF CLEAR

b. Ensure BIT Discharge valves 1835A, 1835B -

OPEN

c. Ensure BIT Inlet valves 1852A, 1852B -

OPEN

d. Ensure High Head Stop valves 856J, 856H, 856C, 856E - OPEN

e. If RWST purification loop in service, then secure system per SOP-SI-3 Verify ABFP status:

BOP

a. Check Motor Driven Pumps - BOTH RUNNING

b. Check Turbine Driven Pump - RUNNING Verify ABFP valve alignment:

a. If Motor Driven AFW pump(s) are running, ensure SG Aux FW Reg valve controllers -

Set to 0% (full open)

BOP FCV-406A FCV-406B FCV-406C FCV-406D

b. Check SG Blowdown Isolation Valves -

CLOSED

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

All Event #

Page 24 of 29 Event

Description:

RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Verify CCW Pump status:

BOP

a. Check CCW pumps - ALL RUNNING

b. Check RHR HX CCW Shutoff valve - OPEN BOP Verify Essential Service Water Pumps - Three Running Verify Containment Isolation Phase A:

a. Check Phase A - ACTUATED BOP

b. Check Phase A valves - CLOSED Refer to Attachment 2, Phase A valve closure list Verify Containment Ventilation Isolation:

a. Check Purge Valves - CLOSED FCV-1170 FCV-1171 FCV-1172 FCV-1173

b. Check Pressure Relief valves - CLOSED PCV-1190 BOP PCV-1191 PCV-1192

c. Check WCCPP low pressure zone alarm -

NOT LIT

d. Verify IVSW Valves - OPEN IV-AOV-1410 IV-AOV-1413 IV-SOV-6200 IV-SOV-6201 BOP Verify Emergency Diesel Generator status:

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

All Event#

Page 25 of 29 Event

Description:

RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior

a. Check EDGs -ALL RUNNING

b. Check Both EDG SWS Outlet Flow Control Valves - OPEN SWN-FCV-1176 SWN-FCV-1 176A

c. Dispatch NPO to set switches for both EDG SWS Outlet Flow Control Valves to OPEN:

SWN-FCV-1 176 SWN-FCV-1I176A Verify Control Room Ventilation:

a. SET Control Room ventilation control switch to-10% INCIDENT MODE (switch position 3)

b. Check Damper status Dampers A, B, F1, F2

• A-DIM B - BRIGHT Either F1 OR F2 - BRIGHT BOP Dampers D1 and D2 - BRIGHT

c. Verify AC Compressors and fans - ALL RUNNING ACC 31A ON - BRIGHT ACC 31 B ON - BRIGHT ACC 32A ON - BRIGHT ACC 32B ON - BRIGHT ACF 31 ON - BRIGHT ACF 32 ON - BRIGHT

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario#

All Event#

Page 26 of 29 Event

Description:

RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Verify Emergency DC Oil Pumps status:

Main turbine emergency bearing oil pump -

BOP RUNNING Dispatch NPO to verify main generator air side seal oil backup pump - RUNNING MBFP DC emergency oil pump - RUNNING Reset SI as follows:

a. Press BOTH SI RESET pushbuttons on Panel SBF-2:

BOP Train 1 SI Reset Train 2 SI Reset

b. Check SI - RESET SI ACTUATED light - EXTINGUISHED Reset MCCs as follows:

a. Dispatch NPO to secure VC sump pumps and BOP RCDT pumps on Waste Disposal panel

b. Dispatch NPO to align and reset MCCs per SOP-EL-15 Note to examiner:

The following step is designed to stop actions of RO-1 IF the CRS has transitioned to ES-1.1. The BOP will continue in RO-1 if there is transition to other procedures, but any time ES-1.1 is entered, the BOP will inform the CRS of automatic action verification and RO-1 will be suspended.

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

All Event #

Page 27 of 29 Event

Description:

RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Check if additional SI actions should be performed:

a. Check if the CRS has transitioned to - ES-1.1

b. Perform the following:

Inform the CRS of the status of automatic BOP action verification If E-0 has been exited, THEN continue with step 17 If E-0 has NOT been exited, then wait until E-0 is exited. When E-0 is exited, then recheck this step Perform the following:

a. Dispatch NPO to perform the following:

Close SWN-FCV-i 111 and SWN-FCV-1112 BOP

b. Check Condensate Pumps - ONLY ONE RUNNING.

c. SECURE all but one Condensate Pump

d. Initiate the following section of SOP-EL-1 5

• Alignment of City water Cooling Reset Containment isolation Phase A and Phase B as follows:

a. PLACE switches for letdown orifice isolation valves to CLOSE:

BOP 200A 200B 200C

b. RESET Phase A

c. RESET Phase B, if actuated

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

All Event #

Page 28 of 29 Event

Description:

RO-1, BOP Operator Actions During EOPs Time Position

..Applicant's Actions or Behavior Establish Instrument Air and Nitrogen to containment:

a. Establish IA to containment:

Check INST AIR LOW PRESS alarm on panel SJF - CLEAR DEPRESS Inst Air reset pushbutton 28 BOP CHECK IA-PCV-1228, Inst Air to Cont. -

OPEN

b. ESTABLISH PRZR PORV N2 supply:

PRESS Accumulator N2 Supply Reset pushbutton 44 Check 863, Accumulator N2 Supply Valve

- OPEN

_ t I

BOP Check if one non-essential Service Water pump should be started:

a. Check Off-Site power to at least one Non-Essential service Water Pump -AVAILABLE

b. Check SWN-FCV-I 111 and SWN-FCV-I 112

-CLOSED

c. START one Non-Essential Service Water pump Check status of off-site power:

a. VERIFY all AC Busses:

Energized by off-site power AND All 480V tie breakers open

Appendix D Operator Action Form ES-D-2 Op Test No.:

1 Scenario #

All Event #

Page 29 of 29 Event

Description:

RO-1, BOP Operator Actions During EOPs l

Time Position

]

Applicant's Actions or Behavior NOTE It is permissible for operators to perform board clean-up actions (steps 22-29 of ROI, BOP OPERATOR ACTIONS DURING USE OF EOPs) while performing actions of other EOPs; provided this does not interfere with other EOPs in progress.

EVALUATOR NOTE: The remainder of the steps in this attachment are highlighted (High Level) action only.

BOP Re-align secondary plant BOP Check secondary valve position BOP Check Heater Drain Pumps 31 and 32 Tripped BOP Check plant equipment status BOP Determine if Source Range detectors should be energized BOP Start AC Oil Pumps and Stop DC Oil pumps as follows BOP Check Long Term Plant status BOP Inform CRS that RO-1 is complete and advise on the status of actions