ML043270601

Final - Section C Operating (Folder 3), Indian Point 2

ML043270601
Person / Time
Site:	Indian Point
Issue date:	10/22/2004
From:	Christman R Entergy Nuclear Indian Point 2
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
Download: ML043270601 (29)

Text

Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 2 Scenario No.: NRC#I Op-Test No.: 1 Examiners:

Operators:

Initial Conditions: 3% Rated Thermal Power, MOL Turnover: Unit 2 is at 3% power, recovering from a 7 day forced outage to repair body tc bonnet leak on PRZR Spray Loop 23 Bypass Valve 524. Shift orders are to continue the startup in accordance with Pop 1.3 Plant Startup, Mode 2 to Mode 1. The previous shift completed POP 1.3 though step 4.23. Shift Manager has directed you to baseload the HP Steam Dumps to approximately 8% prior to placing the unit on line per POP-2.1.

The Operations Manager, Reactor Engineering and Power Marketing have authorized a rate of power increase of 200 MWe per hour to 100% RTP.

2 XMT-RCS020A 3

MAL-RCSO14B 4

MAL-ATS007A (N)ormal (R)eac Event N

SRO/BOP R

RO Type*

I ALL C

ALL C

SRO/RO M

ALL C

SRO/BOP Event D

e s

c r

l p

t i

o n

Raise reactor power Pressurizer Level Channel 2 (LT-460) Fails Low (TS SRO) 22 SG Tube Leak (5 gpm) (TS SRO) 21 Main Boiler Feed Pump Trip (Manual reactor trip required)

SGTR with subsequent Loss of Offsite Power 21 SI Pump Fails to Auto Start rity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Draft Revision 9 1 of 18

Simulator Setup Reset to IC-124 Validation time = 105 minutes.

Execute batch file Bat "NRC#l.bat" from Ph.D Expert window:

MOC-SISOO1 SI1 SAFETY INJECTION PUMP 21 MOTOR IMF MOC-SISOO1 (-1 0) 4 A XMT-RCS020A FIXED OUTPUT: LT-460 PZR LEVEL CH.2 IMF XMT-RCS020A (1 0) 0.000000 0 40.412601 A MAL-RCSO14B STEAM GENERATOR 22 TUBE LEAK (NR)

IMF MAL-RCS014B (2 0) 0.050000 0 0.000000 MAL-ATS007A MBFP 21 THRUST BEARING FAILURE (NR)

IMF MAL-ATS007A (3 0) TRUE TRGSET 29 "xaoi6lOa.eq. 1" A SGTR 22 SG gets big when reactor trips TRGSET 30 "JBKRTA.EQ.0" Loss of Offsite Power when manual SI pushed TRG 29 "IMF MAL-EPSOO1 (-1 0) TRUE" TRG 30 "IMF MAL-RCS014B (-1 0) 5.00000 0 0.050000" Verify that the following commands appear in the Instructor Station Summary:

Pg-*<;:;!;i';< ' - 10 I x I Oeley Ramp Event Value Find InsertTime 000000 000000 Elnne DescnpbOn nla m C i 5 onnooo 0

000000 00000[I 000000 t

005 000000 000000 000000 3

FALSE FALSE 000000

-RCSOZWFIXED OUTPUT LT-460 PZ 000000 000000 1

43 E803 HCS0148 STEWGENEMlORZZnJBE LEAK

-ATSOO7A tABFrZ1 TtiRUSTBEARING FAILUR I

2of 18

Simulator Setup Verifv that Conditional Tripper 29 & 30 amears on Event Trigger 29 and 30 as follows:

1 Event#

Event Action IJBKRTA.EQ.0 16 17 18 19 20 21 22 23 24 25 26 27 28 Available Available Available Avai I able Avai I ab le Avai I ab le Avail able Avai I ab le Avai I able Avail able Avai I ab le Avail able Avail able 3of 18

Appendix D Required Operator Actions Form ES-D-2 Prior to start of scenario, brief team on power escalation orders. Allow them to formulate a reactivity plan and do their brief outside the simulator. Provide them required graphs and NUPOP, and turnover sheet.

Position SRO Event

Description:

Raise Reactor Power from 3% reactor power Directs activities associated with power increase per 2-POP-1.3, Plant Startup, Mode 2 to Mode 1:

Rod Motion RO Adds Positive reactivity Rod Motion Dilution SRO Initiates Turbine Generator startup operations per 2-SOP-26.4, Turbine Generator Startup, Synchronizing, Voltage Control and Shutdown SIMULATOR OPERATOR:

Activate trigger 1 to start the next event Pressurizer Level Channel 2 (LT-460) Fails Low (TS SRO) when directed by the Lead Evaluator.

4of 18 NUREG-1021, Draft Revision 9

Required Operator Actions Form ES-D-2 Appendix D 3p-Test No.: 1 Scenario No.: 1 Event No.: 2 Page 1 of 3 Event

Description:

Pressurizer Level Channel 2 (LT-460) Fails Low Time Position RO BOP SRO RO SRO BOP SRO RO Applicants Actions or Behavior Diagnose Pressurizer Level Channel 2 failed low Refers to Alarm response Procedure SAF 3-3 Pressurizer Low Level 18% 5%

SAF 4-3 Pressurizer Lo Lo Level Channel Trip 5%

SGF 2-9 RCS Reduced Inventory SFF 1-7 PRZR Heater Group Tripped Directs RO to perform immediate operator actions (from memory) of 2-AOP-I NST-1, I nstrumenVController Malfunctions Places 22 Charging Pump speed controller in manual and adjusts charging flow as necessary to maintain Pressurizer Level on program (per Graph RCS-2, Pressurizer Level vs. Tave)

Directs actions to select operable channels for control and alarm Defeats controlling PRZR Level Channel by placing U460A (Pressurizer Level Defeat Transfer Switch) in DEFEAT CH2 (located in Foxboro rack B-6)

Directs initiation of actions to restore letdown using SOP-3.1, Charging Seal Water and Letdown Control Restores letdown:

Verifies a charging pump is in service Verifies HCV-142, Charging Line Flow Controller is Verifies Charging flow established with 204A 22 Hot Leg Alternate Charging Stop is OPEN Verifies letdown orifice stops CLOSED (200 A, B, C)

Verifies that switch Letdown Flow Control Valves ABC in REMOTE Verifies Letdown Line Isolation Stops 200A and 2008 are OPEN I

throttled open 5of 18 NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Page2 of 3 Event

Description:

Pressurizer Level Channel 2 (LT-460) Fails Low Time -

Position RO SRO RO SRO RO SRO Applicants Actions or Behavior Restores letdown (continued):

OPENS LCV 459 Letdown Stop and places control switch to AUTO Places PCV-135, Low Pressure Letdown Line Controller to manual and adjusts to 50%

OPENS desired letdown orifice stop to obtain desired letdown flow (200A or 200C excepted to obtain 75 gpm letdown flow)

ADJUSTS PCV-135 to maintain 225-275 psig Letdown Pressure Return PCV-135 to AUTO Direct actions to restore backup heaters to pre-failure configuration (21 AUTO, 22 and 23 ON) (or as desired by SRO)

Reset PRZR Backup heaters by taking control switches for each group (21,22, and 23) to OFF and then returning to AUTO or ON as directed by SRO Direct actions to reset modulating heaters Resets Modulating Heaters:

Place Modulating Heaters control switch in TRIP and then back to neutral.

Place control switch in CLOSE and then back to neutral Direct actions to place 22 Charging Pump in AUTO (if desired) 6of 18 NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Page3 of3 Event

Description:

Pressurizer Level Channel 2 (LT-460) Fails Low Time -

Position RO SRO SRO BOP Applicants Actions or Behavior Places 22 Charging Pump to AUTO:

Place speed control to MAN-BAL Adjust bias knob until deviation meter indicates zero Place speed controller to AUTO Slowly return bias knob to zero Verify RCP Seal Injection Flow 6-12 GPM Monitor automatic Przr level control per Graph RCS-2, Pressurizer Level vs Tave Refer to Technical Specification 3.3 Instrumentation and Table 3.3.1 -1 Reactor Protection System Instrumentation for required actions:

Determine that TS 3.3.1 Condition A applies Determine from table 3.3.1 -1 function 8 directs that Condition K applies Determine form TS 3.3.1 Condition K that the bistable must be placed in trip within 72 Direct actions to trip bistable LC-460A (LOOP 2) Hi Level Trip in the White Foxboro Rack A-12 CUE: IF the SM is asked if Bistables should be tripped, direct the team to trip the appropriate bistables.

Place bistable LC-460A (LOOP 2) Hi Level Trip in the White Foxboro Rack A-12 to TRIP SI MU LATO R OPERATOR:

Activate Trigger 2 to start the next event (22 SG Tube Leak) when directed by the lead evaluator. (Wait until PRZR level is stable from previous event, else team will have to wait in AOP-SG-1 to determine leak rate) 7of 18 NUREG-1021, Draft Revision 9

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

Description:

22 SG Tube Leak (5 GPM)

Page1 of3 Time Position BOP TEAM SRO SRO/RO SRO TEAM RO/BO P Applicant's Actions or Behavior Acknowledge alarms and perform ARPs SA-1 (3-7) R49 Steam Generator Blowdown Hi Rad/Trouble (WARN SETPOINT(after about 1 minute))

SA-1 (3-9) R-45 Air Ejector Radiogas Hi Ramrouble (after about 6 minutes)

Diagnose steam generator tube leak Enter 2-AOP-SG-1, "Steam Generator Tube Leak" Verify that Pressurizer level is being maintained by charging flow:

Checks PRZR level able to be maintained with two charging pumps Checks PRZR level > 11%

Checks RCS Pressure and Subcooling Directs RO to evaluate plant conditions for indication of Gross TubeLeakage EVALUATOR NOTE: The team will not have clear indication of Gross Tube Leakage at this point.

Initiate determination of affected SG. Checks:

N-16 Monitor Steam Line surveys Chemistry results BOOTH OPERATOWCOMMUNICATOR: When chemistry or the NPO are contacted, report back that 22 SG is affected.

Check R-45 operable 8of 18 NUREG-1 021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Position BOP SRO SRO BOP TEAM SRO Applicants Actions or Behavior Initiate attachment 1, R-45 Estimated Leak Rate NOTE: If chemistry is requested, provide the following information:

Condenser air in leakage = 6 SCFM RCS total gaseous activity = 2.5 e-3 uCi/cc Calculates leak rate of approximately 5 gpm Directs Chemistry to perform Primary to Secondary Leak Rate determination BOOTH OPERATOWCOMMUNICATOR: After about 10 minutes, report that Pri to Sec leakrate is 4.3 GPM Event

Description:

22 SG Tube Leak (5 GPM)

SRO Notify Health Physics of SGTL

_ _ _ _ _ _ ~ -

Initiate Attachment 2, SG Leak Rate Data Sheet Determine primary to secondary leak rate using N-16 Chemistry grab sample results EVALUATOR NOTE: N-16 data is not valid b w w 30% power.

Team should use Chemistry results and Attachment 1 calculation to determine that leak rate is 3-5 gpm Determine that leak rate is >lo0 gpd Direct chemistry to draw backup samples and re-perform Primary to Secondary Leak Rate calculation.

BOOTH OPERATOWCOMMUNICATOR: When Chemistry is contacted, report that additional samples have been obtained and that the leak rate has been verified at 4.3 gpm 9of 18 NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Scenario No.: 1 22 SG Tube Leak (5 Event GPM)

No.: 3 Page3 of 3 Position SRO P

SRO Event

Description:

SRO SRO 1

Initiate notifications per SAO-124, Oral Reporting of Non-Emergency Events and Items of Interest and Significant Occurrence Reporting Direct Chemistry to calculate leak rate every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> while shutting down Evaluate attachment 3 and Technical Specification 3.4.1 3 to determine Shutdown Requirements:

TS 3.4.13 Condition A - reduce leak rate to allowable in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (cannot be met)

Be in mode 3 in additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Be in mode 5 in additional 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Initiate plant shutdown IAW POP-3.1, Plant Shutdown Mode 1 to Mode 3.

SIMULATOR OPERATOR:

Activate trigger 3 when directed by Lead Evaluator to proceed to the next event (21 MBFP trips) 10 of 18 NUREG-1021, Draft Revision 9

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

Description:

21 Main Boiler Feed Pump Trips Diagnose trip of 21 Main Boiler Feed Pump Diagnose Loss of Feedwater:

Direct RO to perform immediate operator actions of 2-AOP-FW-1 Loss of Main Feedwater Performed from memory:

Manually trip the reactor Checks any Main Boiler Feed Pump operating (no)

Checks Reactor power greater than 4% (yes)

Directs team to perform immediate operator actions of EOP E-0, Reactor Trip or Safety Injection

1. The SGTL will increase in size to a SG Tube Rupture (600 gpm) when the reactor is tripped (from conditional trigger 30 which actuates from condition of reactor trip breakers open)

2. A loss of offsite power will occur when SI is manually actuated (from conditional trigger 29 which actuates from condition of manual SI buttons pushed) 11 of 18 NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Page 1 of5 Event

Description:

Steam Generator Tube Rupture with subsequent Loss of Offsite Power Time

~~

Position SRO RO RO BOP RO TEAM SRO RO RO Direct Operators to perform immediate operator actions of EOP-E-0, Reactor Trip or Safety Injection Verifies Reactor Trip (from memory)

~~~

~

Verifies Turbine Trip (from memory)

Checks status of 480V ac buses (from memory)

NOTE: Following SI actuation, offsite power will be lost and all 480V buses will be powered from the EDGs Checks status of SI: (from memory)

Manually actuates SI Determines pressurizer pressure and level are lowering Checks both trains of SI actuated EVALUATOR NOTE: The team may go to ES-0.1 and then manually actuate SI from the foldout. Also, the team may use AOP-SG-1 IAAT step 4.1 to actuate SI.

Perform immediate actions steps again (using the procedure)

Directs BOP to perform E-0 Attachment 1, Automatic Action Verification EVALUATOR NOTE: See required operator actions for event 7 for BOP E-0 Attachment 1, Automatic Action Verification Verify AFW Pumps Running Verify total AFW flow > 400 GPM 12 of 18 NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Scenario No.: 1 Event No.: 6 Page2 of 5 Steam Generator Tube Rupture with subsequent Loss of Offsite Power Position RO RO RO Event

Description:

RO RO RO RO SRO Applicants Actions or Behavior Verify SI System Flow Checks RCS Pressure < 1160 psig (no)

Places one RHR pump in pullout Check RCP Seal Cooling Dispatch an NPO to align backup cooling to the Charging Pumps, RHR pumps, and SI pumps Dispatch an NPO to locally close SWN-4 and SWN-5 in the zurn strainer pit Check cold leg temperatures stable at or trending to 547°F Check PRZR Porvs and Spray Valves Closed Check RCPS stopped (yes-loss of offsite power)

~~~~

~~

Check if any SG is faulted (no)

Check if SG tubes are intact (no, 22 SG is Ruptured)

Main Steam Line radiation recorder Condenser air ejector radiation recorder SG Blow down radiation recorder No SG Level increasing in an uncontrolled manner

~~

Transitions to EOP E-3, Steam Generator Tube Rupture 130f 18 NUREG-1021, Draft Revision 9

Required Operator Actions Form ES-D-2 Appendix D Event

Description:

Steam Generator Tube Rupture with subsequent Loss of Offsite Check 22 SG pressure > 440 PSlG Determine required core exit temperature:

NOTE: 51 0°F expected with 22 SG pressure > 1025 PSlG 14 of 18 NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Position BOP RO BOP BOP RO RO RO RO RO TEAM Amlicant's Actions or Behavior Check Intact SG Levels Maintain total feed flow > 400 gpm until narrow range level >lo% in at least one SG Check PORVs and Block Valves Reset SI and CI Phase A Check RCS pressure greater than 320 PSlG and then stop RHR pumps and place in AUTO Establish maximum charging flow Check 22 SG pressure stable or increasing Check RCS subcooling > value from table (>39"F expected)

Depressurize RCS using PORV Opens one PORV Monitors RCS Pressure, 22 SG Pressure, PRZR Level, and RCS subcooling Closes PORV when RCS pressure < 22 SG Pressure, or PRZR Level > 71%, or subcooling e value from table Checks RCS pressure increasing Checks if SI flow can be terminated PRZR Level > 14%

Checks subcooling greater than value from table AFW flow > 400 GPM RCS Pressure stable or increasing 15of 18 NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

Steam Generator Tube Rupture with subsequent Loss of Offsite Power PRZR Level > 14%

Checks Subcooling greater than value from table EVALUATOR NOTE:

Terminate scenario after SI pumps stopped, or at the discretion of the lead evaluator.

16 of 18 NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Page1 of 1 Event

Description:

21 SI Pump Fails to Auto Start (E-0, Attachment 1 Automatic Action Verification)

I BOP

~

BOP 1

BOP Verify charging system operation Starts one charging pump in manual at maximum speed Align charging system to the RWST (opens LCV-1128, Closes LC-l12C, place Makeup Control Switch to STOP)

Check 345 KV MO Disc Switch F7-9 Open verifes BKR 7 and 9 open Check status of 480 V buses Determines all are powered from EDGs Direct personnel to align lighting to TSC bus Verify RN Isolation Check if MSlVs should be isolated Check SW system operation Check Three SI Pumps running Manually starts 21 SI pump Check RHR pumps running OPEN851B Check SI system valve aligment Verifv Containment Fan Coolers in service Verify AFW Flow to all SGs NOTE: The team may use prudent operator action to isolate ARN flow to 22 SG when NR Level is > 10%

Verify Containment Ventilation Isolation Verifv Containment Isolation Phase A Check if CS should be actuated Verify CCR Air Conditioner status Notify SRO Attachment 1 complete 170f 18 NUREG-1021, Draft Revision 9

Shift Turnmw Watch Team Turnover Sheet:

Datemime:

RCS Temp:

RCS Press:

PZR Level:

RCS Total Leakage:

RCS Unidentified Leakage:

Xenon:

EFPD:

PZR Press Control:

PZR Level Control:

Service Water:

Risk Assessment:

TODAY 549 O F 2235 psig 38 %

0.1 gpm 0.1 gpm Increasing 30 Channel 1 Channel 2 3 Header Ops Green Condition:

Power Ops

% Power:

3%

MW Gross:

0 River Water:

63 O F Boron Conc:

1530 ppm Control Rods 105 CBD Condenser Air leakage 6 SCFM RCS Gas activity 2.5E-3 pCi/cc Daily Risk Factor:

0.78 Plant Equipment Status:

No equipment out of service Instructions to the Shift:

Continue plant startup LAW POP-1.3. Unit 2 is at 3% power, recovering from a 7 day forced outage to repair body to bonnet leak on PRZR Spray Loop 23 Bypass Valve 524. Shift orders are to continue the startup in accordance with Pop 1.3 Plant Startup, Mode 2 to Mode 1. The previous shift completed POP 1.3 though step 4.23.

Shift Manager has directed you to baseload the HP Steam Dumps to approximately 8% prior to placing the unit on line per POP-2.1 The Operations Manager, Reactor Engineering and Power Marketing have authorized a rate of power increase of 200 MWe per hour to 100% RTP.

Page 18 of 18

Appendix D Scenario Outline Form ES-D-1

-Facility: Indian Point 2 Scenario No.: NRC#4 Op-Test No.: 1 Examiners:

Operators:

Initial Conditions: 100% Rated Thermal Power, MOL. 21 EDG is out of Service. 22 Charging Pump is out of service.

Turnover: Unit 2 is at 100% Power steady state conditions 340 EFPD. 21 EDG is out of service and has been inoperable for 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />. Maintenance is currently performing repairs.

In addition, 22 Charging Pump was removed from service for corrective maintenance 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> ago. Expected return to service in 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />.

1 1 CVCOl9A Event Descrlptlon Raise main generator reactive load (MVARS)

TS (SRO) due to surveillance failure.

VCT Level Transmitter fails low 3

MOT-CFW003A 4

MAL-SGN002B Bat FailRxTripsbat

• (N)ormal (R)eactivity, C

BOP/SRO R

RO M

ALL C

ALL C

RO/SRO (1)nstrume 23 Condensate Pump trips Reduce steam flow<Feed Flow Reduce Tave using boration and rod insertion Faulted Steam Generator Reactor auto and manual trips fail to actuate AFW Flow Control Valve will not close from CCR PORV Fails Open. Block valve used to isolate it.

t, (C)omponent, (M)ajor 1 of 11

Simulator Setup

1.

2.

Reset to IC-2, 100% MOL Execute batch file Bat NRC4.bat from Ph.D Expert window:

A SWI-AFWOl9G HC-406B MANUAL SWITCH MOTOR DRIVEN AUX FEEDWATER FLOW TO IOR SWI-AFWO19G (-1 0) 1 A SWI-AFWOI9J IOR SWI-AFWO19J (-1 0) 1 A SWI-AFW001A PC-406A PC-406A AUX B.F.P. FOXBORO CONTROLLER (B5)

IOR SWI-AFW001A (-1 0) 5 A SWI-AFWO19L HC-406B D SWITCH MOTOR DRIVEN AUX FEEDWATER FLOW TO S/G IOR SWI-AFWOI 9L (-1 0) 1 SWI-AFWOI9M IOR SWI-AFWOI9M (-1 0) 1 HC-406B SET DOWN SWITCH MOTOR DRIVEN AUX FEEDWATER FLOW HC-406B C SWITCH MOTOR DRIVEN AUX FEEDWATER FLOW TO S/G SWI-AFWO19K HC-406B I SWITCH MOTOR DRIVEN AUX FEEDWATER FLOW TO S/G IOR SWI-ARNOI9K (-1 0) 1 A BKR-PPL003 52/RTA REACTOR TRIP BKR IMF BKR-PPL003 (-1 0) 5 A BKR-PPL004 52/RTB REACTOR TRIP BKR IMF BKR-PPL004 (-1 0) 5 A BKR-EPSO31 52/MG1 MG21 INPUT BREAKER (480)

IMF BKR-EPS031 (-1 0) 5 A BKR-EPS032 52/MG2 IMF BKR-EPS032 (-1 0) 5 A LOA-DSG055 DSG-NT-89 DG-21 MANUAL-OFF-AUTO (ECS)

IRF LOA-DSG055 (-1 0) OFF A LOA-DSG032 DSG-NT-110 BKR 52/EG1 RACK-OUT/RACK-IN IRF LOA-DSG032 (-1 0) OUT A LOA-EPSOI 1 52-C2 IRF LOA-EPSOl1 (-1 0) OUT A XMT-CVCO19A FIXED OUTPUT:

LT-112 VCT LEVEL IMF XMT-CVCO19A (1 0) 0.000000 0 34.1 59801 A MOT-CFWOO3A CP23 IMF MOT-CFW003A (2 0) 3 A MAL-SGN002B STM HDR LK INSIDE CNTMT S/G 22 (NR)

IMF MAL-SGN002B (3 0) 25.000000 360 0.000000 MG22 INPUT BREAKER (480)

C 22 480V BKR RACK OUT/RACK IN CONDENSATE PUMP 23 MTR A set up conditional trigger 30 to actuate when PORV opens TRGSET 30 xeoo325r.eq.l I A Fails open PORV 455C four minutes after it auto opens TRG 30 IMF AOV-RCS002A (-1 240) 1

3.

4.

5.

6.

Place CS for 21 EDG in Pullout Place 23 Charging pump in auto operation.

Place CS for 22 Charging Pump in Pullout Put a copy of SOP 26.4 MVARs section on RO clipboard.

2of 11

Simulator Setup IXEDOUTPUT LT-112 VC CW3 MNOENSATE P-IMP23 STM HDfi LK INSIDE CNThiT S/G 2 000000 000000 None Ilia fa1 ELSlS 00 00 00 fail (ISIS 00 00 00 000000 000000 None n/a oonooo ooonoo Nnnp nla fall no 00 00 000000 000000 1

31 1583 0

00 00 00 1111 00 no 00 00 110 1

nla wnding short 00 00 00 000000 000G00 3

0 25 000000 OA-DSG032 DSENT-110 BKR 52/EG1 PACK-0 000000 000000 None in out 000000 OA-EPSfliI 52-C2 C72480VHKRR4C 000000 OODUOO None in out 000000

- A M O l A FC-40GAPC-40GAAU'XB F F FOXEOROC 000000 000000 None AUTOSIGN AUTO SIGN 00 0000

-AI-MlSL H0406BD SWITCHMOTOHOPNENAUXFE 000000 000000 None OFF OFF 000000

-AFJiol9M HC-406B C SMTCH MOTOR DRNEN A W FE 00 00 00 00 00 00 None OFF OFF 000000

-Mwnig~

HC-~OEBI SWITCHMOTORDWENAWFE 00 00 00 00 00 00 None OFF OFF 000000 Verify that conditional trigger 30 appears as follows:

Event#

Event Action 2.'p*

' 'I4, - A

11..,

I 7

1 Einish I

Action r

I 16 Available 18 Available 21 Available 24 Available 26 Available 27 Available I

TRUE FALSE 3of 11

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 1 Page4 of 3 Event

Description:

Raise Main Generator Reactive Load (MVARS), TS (SRO) Due to surveillance failure.

SIMULATOR OPERATOR: Telephone the CCR from the System Operator. Request Indian Point Unit 2 raise VARs 100 MVARs OUT.

Time P Position CRS

~

RO BOP RO BOP BOP CRS Applicants Actions or Behavior Receives VAR request from SO. (Jim Armstrong)

Directs RO to increase lagging MVARs by 100 Directs BOP to monitor UAT voltage during main generator voltage adjustment.

Refers to 2-SOP-26.4 Place Unit Aux Transformer tap changer in Manual and adjust UAT voltage to 7.0 to 7.1 KV while adjusting Main Generator Voltage.

Adjust Main Generator Voltage using the AC Raise switch to obtain desired VARS When VARs adjustment is complete, verify UAT voltage 7.0 to 7.2 KV Return the UAT Tap Changer to AUTO SIMULATOR OPERATOR: Telephone the CCR fro the Field Support Supervisor. Surveillance 2-PT-W020, Electrical Verification-Inverters and DC Distribution In Modes 1-4 step 4.5.2 is UNSAT. Static Inverter 24 Output Frequency is 60.6 Hz.

Allowable band is 59.5 to 60.5 Hz. This surveillance references TS SR3.8.7.1 References TS SR 3.8.7.1.

Determines that 24 Static Inverter is inoperable per LCO 3.8.7.A with required action A.l and A.2 SIMULATOR OPERATOR: Activate trigger 1 when directed by the Lead Examiner to proceed to event 2: VCT Level Transmitter fails low 4of 11 NUREG-1021, Draft Revision 9

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

Description:

VCT Level Transmitter fails low Page 1 of 1 Time -

Position RO SRO BOP RO BOP

-Applicant's Actions or Behavior Diagnoses VCT Level Transmitter failure Enters 2-AOP-CVCS-1, Chemical and Volume Control System Malfunctions, and directs the operator's actions Holds LCV-112C Control Switch in OPEN When LCV-112C indicates open, then CLOSES LCV-112B Places Makeup Control Switch in STOP If necessary, reduces turbine load to keep Tave on program When necessary to raise VCT pressure, initiates manual VCT makeup per SOP-3.2, Reactor Coolant System Boron Concentration Control Monitors VCT Pressure. Controls VCT pressure 2-5 psig above pre-malfunction (1 9-20 psig) pressure as follows:

Coordinates with RO to raise VCT Pressure by manual makeup to VCT per SOP-3.2, Reactor Coolant System Boron Concentration Control Lowers VCT Pressure by manually diverting letdown via LCV-112A SIMULATOR OPERATOR:

When directed by the Lead Examiner, actuate trigger 2 to cause Condensate Pump Trip 5of 11 NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 3 Page1 of 1 Event

Description:

23 Condensate Pump trips, Reduce Steam flow<Feed Flow, Reduce Tave using boration and rod insertion SI MU LATO R OPE RATOR:

Activate Trigger 1 when directed by Lead Examiner to start event.

Diagnoses trip of 23 Condensate Pump SRO RO Directs RO to perform immediate actions of 2-AOP-FW-1, Loss of Main Feedwater Verifies Main Feedwater Pumps running SRO RO Directs team actions using 2-AOP-FW-1, Loss of Main Feedwater Reduces turbine load as necessary to maintain Feed Flow 2 Steam Flow Adds negative reactivity using boration and/or control rods to maintain Tave on program Monitors delta-flux during reactivity addition and uses control rods when required to maintain delta-flux within the target band BOP Monitors MBFP suction pressure and if suction pressure cutback actuates, then places MBFP Master Speed Controller in MANUAL and slowly lowers MBFP speed to maintain suction pressure > 31 0 psig EXAMINER NOTE: Suction pressure will not immediately respond after manual action is taken: Suction pressure will respond after Feed Flow is > Steam Flow AND the Main Feed Regulating Valves begin to throttle closed.

RO Places Main Feed Regulating Valve controllers to manual as necessary and controls feed flow when level in SG > 60% or when controller windup is to be removed.

Places Main Boiler Feed Pump Master Controller back to automatic using SOP 21.1 SIMULATOR OPERATOR:

When directed by the Lead Examiner, actuate trigger 3 to cause Faulted Steam Generator, Reactor auto and manual trips fail to actuate 6of 11 NUREG-1021, Draft Revision 9

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

Event No.: 4 Page 1 of 2 Event

Description:

Faulted Steam Generator, Reactor auto and manual trips fail to actuate Diagnose steam leak Manually actuate Reactor Trip Diagnose failure of reactor to trip Direct team to perform immediate actions of EOP FR-S.l, Response to Nuclear Power GeneratiodATWS I

I SIMULATOR OPERATOR: Trip both Rod Drive MG set Output Breakers to insert control rods at this time.

I I

I 7of 11 NUREG-1021, Draft Revision 9

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

Event No.: 4 Page2 of 2 Event

Description:

Faulted Steam Generator, Reactor auto and manual trips fail to actuate Verify Containment Ventilation Isolation Check reactor trip and turbine trip have occurred Maintain total feed flow > 800 gpm until NR level in at least one I

Bop I SG > 10%

RO Verify all dilution paths isolated:

Check FCV-111 A demin water flow control valve CLOSED Check no flow indicated on FI-1 1 1 Primary Water Flow Check for Reactivity Insertion from Uncontrolled RCS Cooldown BOOTH OPERATOR: When NPO is dispatched to close FCV-406B, use CVH-AFWOOGB set to 0 to close the valve.

RO Check CETs c 1200°F Verify Reactor Subcritical Return to EOP E-0, Reactor Trip or Safety Injection 8of 11 NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page1 of2 Event

Description:

PORV Fails Open. Block valve used to isolate it.

Time P Position RO BOP RO BOP Applicants Actions or Behavior Verify Reactor Trip Verify Turbine Trip Verify power to 480V Buses Verify SI Status Performs Attachment 1 while SRO and RO continue in E-0:

Verify charging system operation Closes LC-l12C, place Makeup Control Switch to STOP)

Check 345 KV MO Disc Switch F7-9 Open Check status of 480 V buses and 29A Stops all Condensate Pumps Verify FW Isolation Check if MSlVs should be isolated Check SW system operation Check SI System Operation Check SI system valve aligment Verify Containment Fan Coolers in service Verify AFW Flow to all SGs Verify Containment Ventilation Isolation Verify Containment Isolation Phase A Check if CS status Verify CCR Air Conditioner status Starts one charging pump in manual at maximum speed Align charging system to the RWST (opens LCV-1128, verifes BKR 7 and 9 open Dispatches NPO to reset all lighting and MCCs 24A, 27A, Notify SRO Attachment 1 complete 9of 11 NUREG-1021, Draft Revision 9

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page2 of2 Event

Description:

PORV Fails Open. Block valve used to isolate it.

I Ro I

Ro 1

Ro

• TEAM I

CRS EXAMINER NOTE:

d p

l i

c a

n t

s Actions or Behavior Verifies ARN Pumps running and supplying > 400 GPM ARN flow to the SGs Verifies SI Pump flow and RHR pump flow Checks RCP seal cooling Starts 22 SWP Controls RCS Cool-Down by verifying not dumping steam, reducing ARN flow to >400gpm and closing MSlVs Check if RCPs should be stopped Checks for any faulted SG Transitions to E-2, Faulted SG Isolation Verify all actions to isolate 22 SG have been completed Transition to E-1, Loss of Reactor or Secondary Coolant Verify that SI Termination Criteria are met Transition to ES-1.l, SI Termination Terminate the scenario when transition to ES-1.1 is made, or at the discretion of the Lead Examiner 10 of 11 NUREG-1021, Draft Revision 9

Shift Turnaver Watch Team Turnover Sheet:

Dateflime:

RCS Temp:

RCS Press:

PZR Level:

RCS Total Leakage:

RCS Unidentified Leakage:

Xenon:

EFPD:

PZR Press Control:

PZR Level Control:

Service Water:

Risk Assessment:

TODAY 562 O F 2235 psig 48 %

0.1 gpm 0.1 gpm Equilibrium 340 Channel 1 Channel 2 3 Header Ops Condition:

Power Ops

% Power:

100%

MW Gross:

1017 River Water:

78 O F Boron Conc:

972 ppm Control Rods 214 CBD Condenser Air leakage 6 SCFM RCS Gas activity 2.54e-2 PCilcc Yellow Daily Risk Factor:

3.45 Plant Equipment Status:

1. EDG 21 is out of service for bearing replacement. It was removed from service 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> ago and is due back in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Maintenance is currently performing repairs. TS 3.8.1.B surveillance requirement last performed 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago.

2. 22 and 23 EDGs are protected equipment.

3. 22 Charging Pump was removed from service for corrective maintenance 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> ago.

Expected return to service in 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />.

Instructions to the Shift:

Maintain current plant conditions.

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