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.

Event Event Type* D e s c r l p t i o n N Raise reactor power SRO/BOP R

RO 2 XMT- I Pressurizer Level Channel 2 (LT-460) Fails Low (TS RCS020A ALL SRO) 3 MAL- C 22 SG Tube Leak (5 gpm) (TS SRO)

RCSO14B ALL 4 MAL- C 21 Main Boiler Feed Pump Trip (Manual reactor trip ATS007A SRO/RO required)

M SGTR ALL with subsequent Loss of Offsite Power C 21 SI Pump Fails to Auto Start SRO/BOP (N)ormal (R)eac 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 Loss of Offsite Power when manual SI pushed TRGSET 29 "xaoi6lOa.eq.1" TRG 29 "IMF MAL-EPSOO1 (-1 0) TRUE" A SGTR 22 SG gets big when reactor trips TRGSET 30 "JBKRTA.EQ.0" TRG 30 "IMFMAL-RCS014B (-1 0) 5.00000 0 0.050000" Verify that the following commands appear in the Instructor Station Summary:

Pg-*<;:;!;i';< ' - 10Ix I DescnpbOn Oeley Ramp Event Value Find InsertTime 000000 000000 Elnne nla mCi5 onnooo

-RCSOZWFIXED OUTPUT LT-460 PZ 000000 000000 1 43 E803 0 000000 HCS0148 S T E W G E N E M l O R Z Z n J B E LEAK 00000[I 000000 t 005 000000

-ATSOO7A tABFrZ1 TtiRUSTBEARING FAILUR 000000 000000 3 FALSE FALSE 000000 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 Available 17 Available 18 Available 19 Avai Iable 20 Avai I ab le 21 Avai I ab le 22 Avail able 23 Avai I ab le 24 Avai I able 25 Avail able 26 Avai I ab le 27 Avail able 28 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.

Event

Description:

Raise Reactor Power from 3% reactor power Position SRO 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

Appendix D Required Operator Actions Form ES-D-2 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 Applicants Actions or Behavior RO Diagnose Pressurizer Level Channel 2 failed low BOP 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 SRO Directs RO to perform immediate operator actions (from memory) of 2-AOP-INST-1, InstrumenVController Malfunctions RO 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)

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

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

- Verifies a charging pump is in service

- Verifies HCV-142, Charging Line Flow Controller is I throttled open

- 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 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 Applicants Actions or Behavior RO 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 SRO Direct actions to restore backup heaters to pre-failure configuration (21 AUTO, 22 and 23 ON) (or as desired by SRO)

RO 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 SRO Direct actions to reset modulating heaters RO 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 SRO 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 o f 3 Event

Description:

Pressurizer Level Channel 2 (LT-460) Fails Low

-Time Position Applicants Actions or Behavior RO 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 SRO 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 SRO 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.

BOP Place bistable LC-460A (LOOP 2) Hi Level Trip in the White Foxboro Rack A-12 to TRIP SI MULATOR 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 Page1 o f 3 Event

Description:

22 SG Tube Leak (5 GPM)

Time Position Applicant's Actions or Behavior BOP 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)

TEAM Diagnose steam generator tube leak SRO Enter 2-AOP-SG-1, "Steam Generator Tube Leak" SRO/RO 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 SRO 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.

TEAM 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.

RO/BOP Check R-45 operable 8of 18 NUREG-1021, Draft Revision 9

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

Description:

22 SG Tube Leak (5 GPM)

Position 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 BOP Calculates leak rate of approximately 5 gpm SRO 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 SRO Notify Health Physics of SGTL

_ _ _ _ _ _ ~ -

BOP Initiate Attachment 2, SG Leak Rate Data Sheet TEAM Determine primary to secondary leak rate using

- N-16

- Chemistry grab sample results

- Attachment 1 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 SRO Determine that leak rate is >lo0 gpd SRO 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 Event No.: 3 Page3 of 3 Event

Description:

22 SG Tube Leak (5GPM)

P Position 1 SRO Initiate notifications per SAO-124, Oral Reporting of Non-Emergency Events and Items of Interest and Significant Occurrence Reporting SRO 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 SRO 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 /> SRO 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:

- Checks any Main Boiler Feed Pump operating (no)

- Checks Reactor power greater than 4% (yes)

- Manually trip the reactor 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 o f 5 Event

Description:

Steam Generator Tube Rupture with subsequent Loss of Offsite Power

~~

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

__ __ ~~~ ~

RO Verifies Turbine Trip (from memory)

BOP 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 RO Checks status of SI: (from memory)

- Determines pressurizer pressure and level are lowering

- Manually actuates S I

- 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.

TEAM Perform immediate actions steps again (using the procedure)

SRO 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 RO Verify AFW Pumps Running RO 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 Event

Description:

Steam Generator Tube Rupture with subsequent Loss of Offsite Power

-Position - Applicants Actions or Behavior RO Verify SI System Flow

- Checks RCS Pressure < 1160 psig (no)

- Places one RHR pump in pullout RO 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 RO Check cold leg temperatures stable at or trending to 547°F RO Check PRZR Porvs and Spray Valves Closed RO Check RCPS stopped (yes- loss of offsite power)

~~~~ ~~

RO Check if any SG is faulted (no)

RO 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

~~

SRO Transitions to EOP E-3, Steam Generator Tube Rupture 130f 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 Check 22 SG pressure > 440 PSlG Determine required core exit temperature:

NOTE: 510°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 Amlicant's Actions or Behavior BOP Check Intact SG Levels

- Maintain total feed flow > 400 gpm until narrow range level >lo% in at least one SG RO Check PORVs and Block Valves BOP Reset SI and CI Phase A BOP Check RCS pressure greater than 320 PSlG and then stop RHR pumps and place in AUTO RO Establish maximum charging flow RO Check 22 SG pressure stable or increasing RO Check RCS subcooling > value from table (>39"F expected)

RO 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 RO Checks RCS pressure increasing TEAM Checks if SI flow can be terminated

- Checks subcooling greater than value from table

- AFW flow > 400 GPM

- RCS Pressure stable or increasing

- PRZR Level > 14%

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

- Checks Subcooling greater than value from table

- PRZR Level > 14%

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)

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 F7-9Open

- 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 I BOP Verify RN Isolation Check if MSlVs should be isolated Check SW system operation

~

BOP Check Three SI Pumps running

- Manually starts 21 S I pump

- OPEN851B

- Check RHR pumps running Check SI system valve aligment Verifv Containment Fan Coolers in service 1 BOP 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: TODAY Condition: Power Ops RCS Temp: 549 O F  % Power: 3%

RCS Press: 2235 psig MW Gross: 0 PZR Level: 38 % River Water: 63 O F RCS Total Leakage: 0.1 gpm Boron Conc: 1530 ppm RCS Unidentified 0.1 gpm Control Rods 105 CBD Leakage:

Xenon: Increasing Condenser Air leakage 6 SCFM EFPD: 30 RCS Gas activity 2.5E-3 pCi/cc PZR Press Control: Channel 1 PZR Level Control: Channel 2 Service Water: 3 Header Ops Risk Assessment: Green 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 />.

Event Descrlptlon 1 Raise main generator reactive load (MVARS)

TS (SRO) due to surveillance failure.

1 3 CVCOl9A MOT- C VCT Level Transmitter fails low 23 Condensate Pump trips CFW003A BOP/SRO Reduce steam flow<Feed Flow R Reduce Tave using boration and rod insertion RO 4 MAL- M Faulted Steam Generator SGN002B ALL Reactor auto and manual trips fail to actuate Bat FailRxTripsbat C AFW Flow Control Valve will not close from CCR ALL C PORV Fails Open. Block valve used to isolate it.

RO/SRO

• (N)ormal (R)eactivity, (1)nstrume t , (C)omponent, (M)ajor 1 of 11

Simulator Setup

1. Reset to IC-2, 100% MOL

2. 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 HC-406B SET DOWN SWITCH MOTOR DRIVEN AUX FEEDWATER FLOW 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-AFWOI9L (-1 0) 1 SWI-AFWOI9M HC-406B C SWITCH MOTOR DRIVEN AUX FEEDWATER FLOW TO S/G IOR SWI-AFWOI9M (-1 0) 1 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 MG22 INPUT BREAKER (480)

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 C 22 480V BKR RACK OUT/RACK IN IRF LOA-EPSOl1 (-1 0) OUT A XMT-CVCO19A FIXED OUTPUT: LT-112 VCT LEVEL IMF XMT-CVCO19A (1 0) 0.000000 0 34.159801 A MOT-CFWOO3A CP23 CONDENSATE PUMP 23 MTR 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 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. Place CS for 21 EDG in Pullout

4. Place 23 Charging pump in auto operation.

5. Place CS for 22 Charging Pump in Pullout

6. Put a copy of SOP 26.4 MVARs section on RO clipboard.

2of 11

Simulator Setup 000000 000000 None Ilia fa1 ELSlS 00 00 00 000000 000000 None n/a fail (ISIS 00 00 00 oonooo ooonoo Nnnp nla fall no 00 00 IXEDOUTPUT LT-112 VC 000000 000000 1 31 1583 0 00 00 00 CW3 MNOENSATE P-IMP23 111100 no 00 00 110 1 nla wnding short 00 00 00 STM HDfi LK INSIDE CNThiT S/G 2 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'XBF F FOXEOROC 000000 000000 None AUTOSIGN AUTO SIGN 00 0000

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

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

-Mwnig~ H C - ~ O E BSWITCHMOTORDWENAWFE I 00 00 00 00 00 00 None OFF OFF 000000 Verify that conditional trigger 30 appears as follows:

2 .'p*

11.

.' 'I4,,

- A Event# Event Action I

1. Action 7 1 Einish I r I 16 Available 18 Available 21 Available 24 Available 26 Available 27 Available I

TRUE FALSE 3 o f 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 Applicants Actions or Behavior CRS 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.

~

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

RO Adjust Main Generator Voltage using the AC Raise switch to obtain desired VARS BOP When VARs adjustment is complete, verify UAT voltage 7.0 to 7.2 KV BOP 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 CRS 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 Page 1 of 1 Event

Description:

VCT Level Transmitter fails low Time Position -Applicant's Actions or Behavior RO Diagnoses VCT Level Transmitter failure SRO Enters 2-AOP-CVCS-1, Chemical and Volume Control System Malfunctions, and directs the operator's actions BOP Holds LCV-112C Control Switch in OPEN When LCV-112C indicates open, then CLOSES LCV-112B RO 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 BOP Monitors VCT Pressure. Controls VCT pressure 2-5 psig above pre-malfunction (19-20 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 SIMULATOR OPERATOR:

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

Diagnoses trip of 23 Condensate Pump SRO Directs RO to perform immediate actions of 2-AOP-FW-1, Loss of Main Feedwater RO Verifies Main Feedwater Pumps running SRO Directs team actions using 2-AOP-FW-1, Loss of Main Feedwater RO 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 > 310 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 I I Direct team to perform immediate actions of EOP FR-S.l, Response to Nuclear Power GeneratiodATWS 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 I Bop I Maintain total feed flow > 800 gpm until NR level in at least one SG > 10%

RO Verify all dilution paths isolated:

- Check FCV-111A demin water flow control valve CLOSED

- Check no flow indicated on FI-111 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 o f 2 Event

Description:

PORV Fails Open. Block valve used to isolate it.

Time P

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

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

- Dispatches NPO to reset all lighting and MCCs 24A, 27A, 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 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 o f 2 Event

Description:

PORV Fails Open. Block valve used to isolate it.

d p l i c a n t ' s Actions or Behavior I Ro 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

• I 1

I Ro Ro TEAM CRS EXAMINER NOTE:

Lead Examiner 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 10 of 11 NUREG-1021, Draft Revision 9

Shift Turnaver Watch Team Turnover Sheet:

Dateflime: TODAY Condition: Power Ops RCS Temp: 562 O F  % Power: 100%

RCS Press: 2235 psig MW Gross: 1017 PZR Level: 48 % River Water: 78 O F RCS Total Leakage: 0.1 gpm Boron Conc: 972 ppm RCS Unidentified 0.1 gpm Control Rods 214 CBD Leakage:

Xenon: Equilibrium Condenser Air leakage 6 SCFM EFPD: 340 RCS Gas activity 2.54e-2 PCilcc PZR Press Control: Channel 1 PZR Level Control: Channel 2 Service Water: 3 Header Ops Risk Assessment: 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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