ML031210663
| ML031210663 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  (DPR-064) |
| 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 | |
| Download: ML031210663 (170) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility:
IP3 Scenario No.:
1 Op Test No.:
1 Examiners:
Candidates:
100% power EOL 31 Charging Pump OOS 32 CCW Pump OOS Small SG Tube Leak < 25 GPD Turnover:
Reduce load to 800 MWe to remove 33 Condensate Pump from service within 60 minutes Critical Tasks:
Manual reactor trip Initiate Condensate flow Event Malf.
Event No.
No.
Type*
Event Description 1
R (RO)
Reduce power N (BOP)
MFRV fails closed slowly 3
PRS6B I (RO)
Pressurizer level channel fails high I (BO0P) 4 ATS4B C (ALL)
Feedwater Pump trip requiring rapid load decrease to 700 MWe 5
ATS4A M (ALL)
Feedwater pump trip. Reactor trip required.
6 RPS2A C (RO)
Auto reactor trip failure. Manual trip required 7
ATS2 C (BOP)
TDAFW trips 8
CFW1A C (BOP)
MDAFW fails to start 9
CFW1C C (BOP)
MDAFW trips CFW1A (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 1 The crew assumes the shift and initiates a power reduction. The RO will commence RCS boration and the BOP will slowly reduce generator load.
33MFRV controller fails in automatic. The controller must be placed in manual lAW ONOP-FW-1, and 33 SG level restored to the normal control band.
Pressurizer level channel 460 (controlling channel) will fail high. The crew will respond lAW ONOP-RPC-1. The RO will operate charging pumps and pressurizer heaters manually while the BOP defeats the failed channel inputs and the CRS refers to Technical Specifications.
Subsequently, 32 MBFP will trip, requiring a plant runback to 700 MWe. Normal boration will be performed for AFD control. If Rod Insertion Limits are exceeded, the RO will commence Emergency Boration.
When the plant is stabilized, 31 MBFP will trip, requiring a reactor trip. The reactor must be tripped manually lAW ONOP-FW-1, because automatic reactor trip is not functional.
Subsequent AFW failures result in the requirement to transition to FR-H.1, and restore Secondary Heat Sink using Condensate flow or Bleed and Feed.
EOP flow path:
E ES-0.1 - FR-H.1 Indian Point Unit 3 2003 NRC Initial License Examination Simulator Scenario Setup Scenario 1 RESET TO IC-36 31 Charging Pump OOS:
32 CCW Pump OOS:
AUTO reactor trip failure:
31 ABFP fail to auto start:
33 ABFP trips upon starting:
32 ABFP Overspeed:
OVR CVC46A 2 OVR CVC46C 2 OVR CVC46D 1 OVR CVC46F 2 OVR CVC46G 2 OVR CCW3A 2 OVR CCW3C 2 OVR CCW3D 1 OVR CCW3F 2 OVR CCW3G 2 MAL RPS2A ACT MAL CFW1A ACT,1,0 MAL CFW1C ACT,0,0 MAL ATS2 ACT 60,C,JPPLP4 Materials needed for scenario:
POP-2.1 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-12 Indian Point Unit 3 2003 NRC Initial License Examination Simulator Scenario Turnover Information Scenario 1 The plant is at 100% power, steady state conditions exist.
End of Life, Cb is 3 ppm.
Burnup = 23135 MWD/MTU Control Bank D = 224 steps Tavg = 566.90F RCS Pressure = 2235 psig A small Steam Generator Tube Leak exists on 33 SG, less than 5 gallons per day.
33 Condensate Pump has high vibration.
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:
In accordance with POP-2.1, reduce generator load to 800 MWe at a rate of 200 MWe per hour and remove 33 Condensate Pump from service.
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
I Event #
1 Page 5
of 39 Event
Description:
Reduce Power 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 #
1 Event #
1 Page 6
of 39 Event
Description:
Reduce Power Time 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 1 Oppm 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 I 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
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
1 Event#
1 Page 7 of 39 Event
Description:
Reduce Power Time Position E 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-11 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 #
1 Event #
1 Page 8
of 39 Event
Description:
Reduce Power Time Position A
licant'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 #
1 Event #
2 Page 9
of 39 Event
Description:
MFRV Fails Closed Slowly Time Position Applicant's Actions or Behavior Booth Instructor: When directed, insert the following command:
MAL CFW13E ACT,0,120,0 Refers to ONOP-FW-1 CRS (May refer to RPC-1 to place control in manual)
RO Check MBFPs - Both Running Verify the Following Controls:
RO o
MBFP Speed Control - Stable o
All S/G levels - Stable (33 SG level is trending down)
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 AP.
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
1 Event#
2 Page 10 of 39 Event
Description:
MFRV Fails Closed Slowly Time Position 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 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 (NO)
CRS Got to ONOP-FW-1, Step 6, Page 12 Check Main Feedwater Regulating Valves:
CREW o
MFRVs - OPERATING PROPERLY IN AUTO (NO)
PLACE affected SG main feedwater regulating valve in CREW MANUAL (33 SG)
CREW Manually control affected SG NR levels between 40% and 50%
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
1 Event #
2 Page 11 of 39 Event
Description:
MFRV Fails Closed Slowly Time Position Applicant's Actions or Behavior IF main feedwater regulating valves are NOT functioning properly, THEN CONTROL affected SG NR level using any of the following: (Should be N/A) o Manually adjust MBFP speed CREW o Reduce unit load o
Use SG low flow bypass valves o
Continue efforts to regain control of main feedwater regulating valve o
Continue unit load reduction until auxiliary feedwater is capable of maintaining level DETERMINE cause of main feedwater regulating valve malfunction CRS o
If a main feedwater regulating valve cannot be fully closed and auxiliary feedwater is capable of maintaining level, then close its associated motor operated isolation valve IF the cause of the feedwater regulating valve malfunction is CRS due to an instrument failure, then go to ONOP-RPC-1, Instrument Failures. (Should be N/A)
CRS Initiate repairs of affected main feedwater regulating valve Check Feedwater and steam systems integrity:
CREW o
AMSAC ALERT alarm - CLEAR o
Containment parameters - NORMAL a
Plant noise levels - NORMAL
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
1 Event #
2 Page 12 of 39 Event
Description:
MFRV Fails Closed Slowly Time Position Applicant's Actions or Behavior Determine if MBFPs should be placed in AUTO:
CRS o
Check reactor power - greater than 25%
o Check both MBFPs - IN AUTO CRS Return to Plant Operating Procedure Proceed to Event 3 at Lead Evaluator's discretion
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
1 Event #
3 Page 13 of 39 Event
Description:
Pressurizer Level Channel Fails High Time ll Position A
Applicant's Actions or Behavior Booth Instructor: When directed, insert the following command:
MAL PRS6B ACT,100,180,0 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 (NO) o MBFP Speed - NORMAL o
SG levels - NORMAL 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 If automatic control has failed, then perform the following:
o Place affected control system in MANUAL (PRZR level control) o Control affected system to stabilize plant conditions (Place Charging Pump Speed to MANUAL)
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
1 Event #
3 Page 14 of 39 Event
Description:
Pressurizer Level Channel Fails High Time Position II Applicant's Actions or Behavior
... E 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 permuited Check the fclowing instrumentation:
o RCS loop temperatures normal o Check AT setpoints o
Power Range channels RO o
Overpower AT o
Overtemperature AT o
RCS coolant loop flow channels o
PRZR instrumentation o Level is NOT normal CR&
Go to attachment 6, PRZR level channel failures (pg 49)
IF actual PRZR level decreases to less than 19%, then perform the following: (Has NOT gone below 19%)
o ENSURE Letdown has isolated o PLACE PRZR heater control group in STOP PULLOUT o PLACE PRZR heater backup groups in OFF RO I
r
_,1 NOTE Letdow flow shall be limited to 120 gpm l Il
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
1 Event#
3 Page 15 of 39 Event
Description:
Pressurizer Level Channel Fails High Time Position Applicant's Actions or Behavior If LCV-459 or LCV-460 is closed, then perform the following:
(Have NOT closed. Proceed to next action) o ENSURE the following Letdown isolation valves are closed:
o CH-LCV-459, Letdown Isolation Valve o
CH-LCV-460, Letdown Isolation Valve o
ENSURE running charging pump speed control is in MAN BOP a REDUCE charging pump speed to maintain minimum seal injection o 6-12 gpm per RCP o
Ensure the following charging valves are closed:
o CH-HCV-142, Charging Line flow Control valve o
CH-AOV-204A, 32 Loop Hot Leg Alternate Charging Isolation o
CH-AOV-204B, 31 Loop Cold Leg Normal Charging Isolation If affected channel has failed high, then OPERATE PRZR RO heaters as necessary to maintain PRZR between 2205 psig and 2260 psig. (Action required)
If affected channel is used for PRZR level control, then perform the following: (Action required)
RO 0
Ensure charging pump speed controller in MANUAL o CONTROL PRZR level to maintain program level Place L/460A, LEVEL DEFEAT switch, for the failed instrument to the required position: (Foxboro Rack B-6)
BOP o LI-460, Channel 2 (White), DFT CH II
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
1 Event #
3 Page 16 of 39 Event
Description:
Pressurizer Level Channel Fails High Time Position l
Applicant's Actions or Behavior Check CVCS system:
o If letdown is secured, then re-establish charging, seal injection, and letdown per ONOP-CVCS-1, Loss of Charging Or Letdown (NOT required) o If running charging pump speed controller is in MANUAL, then transfer to AUTO per SOP-CVCS-2, Charging, Seal Water, and Letdown Control (Action RO required) o ENSURE controller bias dial is set to zero o
PLACE in MAN BAL o
ADJUST to null deviation meter o
PLACE in AUTO o
MONITOR the following to verify proper automatic operation:
PRZR level on program Seal injection between 6 and 12 gpm RESET PRZR heaters as follows:
o PLACE modulating heater control switch to STOP, then PLACE to START RO o
Leave Modulating heater control switch in AUTO o
PLACE one backup heater control switch to ON o
PLACE two backup heater control switches to OFF, then place in AUTO If affected loop was selected for the PRZR level recorder, then RO PLACE PRZR level recorder transfer switch to a functioning channel (Flight Panel)
Appendix D Operator Action Form ES-D-2 Op Test No.:
I Scenario#
1 Event #
3 Page 17 of 39 Event
Description:
Pressurizer Level Channel Fails High Time Position Applicant's Actions or Behavior CAUTION IF THE REDUNDANT CHANNELS BISTABLE LIGHTS ARE NOT EXTINGUISHED, THEN A REACTOR TRIP MAY OCCUR IN STEP 11 Check all redundant BISTABLE STATUS lights listed for the failed instrument are EXTINGUISHED:
BOP o PRZR Hi LEVEL LC459A o
PRZR HI LEVEL LC461A Evaluator Note:
Step 10 of attachment will not be performed because BISTABLE TRIP STATUS LIGHTS for redundant channels are extinguished PLACE the BISTABLE TRIP SWITCHES for the failed instrument to the TRIPPED (UP) position:
BOP o
Protection Rack A-10, Loop 2, High Level Trip Ensure the BISTABLE STATUS LIGHTS listed for the failed instrument are illuminated:
BOP o
PRZR Hi LEVEL LC460A ENSURE the PRESSURIZER HIGH LEVEL CHANNEL TRIP CREW annunciator is LIT.
RO ENSURE automatic PRZR level control is restored Booth Instructor: Prior to proceeding to the next event, inform the control room that 33 Feed Reg valve controller had a loose fitting and has been satisfactorily repaired.
Automatic operation of the valve may be restored. Also, remove the FRV malfunction:
MAL CFW13E CLR
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
1 Event #
3 Page 18 of 39 Event
Description:
Pressurizer Level Channel Fails High Time Position Applicant's Actions or Behavior DIRECT I&C to troubleshoot and repair failed PRZR level CRS instrumentation IAW annunciator response on Panel SAF for PRZR HIGH LEVEL, CRS may refer to ITS 3.4.9 and determine it does not apply to the listed instrument failure.
CRS Although not directed by procedure, ITS 3.3.1 will apply to failed instrument, but placing in tripped condition fulfills the intended function.
Proceed to Event 4 at Lead Evaluator's discretion
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
1 Event #
4 Page 19 of 39 Event
Description:
Feedwater Pump Trip Requiring Rapid Load Decrease to 700 MWe Time I
Position Fl Applicant's Actions or Behavior Booth Instructor: When directed, insert the following command:
MAL ATS4B ACT CRS Refers to ONOP-FW-1 CREW Check MBFPs - Both Running (NO)
Reduce unit load as necessary to maintain SG levels (Refer to )
CREW o
Att. 1 indicates load will have to be reduced to approximately 700 MWe for available Feed configuration ADJUST running MBFP speed as necessary to:
BOP o Match steam flow and feedwater flow o Maintain MBFP suction pressure greater than 300 psig If control rods are in MANUAL, then insert rods as necessary to RO prevent high PRZR pressure trip Verify the following controls:
CREW o
MBFP Speed control - STABLE o
All SG levels - STABLE
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
I Event #
4 Page 20 of 39 Event
Description:
Feedwater Pump Trip Requiring Rapid Load Decrease to 700 MWe Time Position Applicant's Actions or Behavior Check the following conditions - NORMAL FOR PRESENT POWER LEVEL:
CREW o
Both MBFPs RUNNING (NO)
If one of the operating MBFPs has tripped, then go to CRS attachment 3, MAIN BOILER FEEDWATER PUMP MALFUNCTION, Page 17 Check ABFPs - RUNNING BOP o
Start 31 and 33 ABFPs RO Check steam flow and feedwater flow - MATCHED RO Check Al - WITHIN NORMAL CONTROL BAND Borate to restore Al. (See boration activity in event 1)
RO If RIL exceeded, emergency boration will be performed using MOV-350 Check condenser steam dump system RO o
All steam dump valves closed o Steam dumps reset CREW Check plant conditions stable
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
Event#
4 Page 21 of 39 Event
Description:
Feedwater Pump Trip Requiring Rapid Load Decrease to 700 MWe Time Position Applicant's Actions or Behavior BOP Check operating MBFP - IN AUTO AND STABLE Verify MBFP High Discharge Pressure Limiting Circuit 'D' CREW Curve - RESET Check SG Blowdown Containment Isolation Valve Control BOP Switches - IN CLOSED POSITION Place tripped MBFP Turbine Trip Reset Control Switch to -
RO TRIP Check ABFPs NOT REQUIRED o
STOP ABFPs o
Place Motor Driven ABFP control switches in AUTO BOP o Check 31 and 33 ABFP regulating valves controller setpoint dials - SET TO 0% (FULL OPEN) o Check 32 ABFP regulating valves controller setpoint dials - SET TO 100% (FULL CLOSED)
BOP Check Condensate Booster Pumps Running (NO)
CRS Determine cause of MBFP trip Determine if SG Blowdown should be established:
CRS o CRS may contact Chemistry or SM to request direction.
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
1 Event #
4 Page 22 of 39 Event
Description:
Feedwater Pump Trip Requiring Rapid Load Decrease to 700 MWe Time Position Applicant's Actions or Behavior I
Go to appropriate POP as directed by CRS or SM CRS o POP-2.1 still in effect Proceed to event 5 at Lead Evaluator's discretion
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
1 Event #
5, 6, 7, 8, 9 Page 23 of 39 Event
Description:
Feedwater Pump Trip. Reactor Trip Required. Auto Reactor Trip Failure.
Manual Trip Required. TDAFW Trips; MDAFW Fails to Start; MDAFW Trips.
Time Position Applicant's Actions or Behavior Booth Instructor: When directed, insert the following command:
MAL ATS4A ACT MAY refer to ONOP-FW-1 Directs reactor trip based upon BOTH MBFPs tripped and NO CRS automatic reactor trip.
o Directed in ONOP-FW-1 Step 1 RNO CRS Opens E-0, Reactor Trip or Safety Injection Critical Manually trip reactor Task 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 Determine if Si is actuated RO o Any SI annunciator lit OR a
SI pumps-ANY RUNNING
Appendix D Operator Action Form ES-D-2 lOpTest No.:
1 Scenario#
I Event #
5, 6, 7, 8, 9 Page 24 of 39 Event
Description:
Feedwater Pump Trip. Reactor Trip Required. Auto Reactor Trip Failure.
Manual Trip Required. TDAFW Trips; MDAFW Fails to Start; MDAFW Trips.
Time Position Applicant's Actions or Behavior Determine if SI required using posted operator aid RO o Determines SI NOT required Start Both Motor Driven ABFPs BOP o
Starts 31 ABFP manually o
33 ABFP will NOT start CRS Direct transition to ES-0.1, Reactor Trip Response RO Check RCS temperature - Stable at or trending to 5470F Check Feedwater status:
RO o RCS temperature less than 5540F o
Main and bypass FW reg valves - CLOSED Booth Instructor: When 31 ABFP is started manually, then insert the following command:
MAL CFW1A ACT,0,0 BOP Determines 31 ABFP has tripped. NO ABFPs available Determine RED path on Heat Sink CSF Status Tree.
CRS Transition to FR-H.1, Loss of Secondary Heat Sink
Appendix D Operator Action Form ES-D-2 Op Test No.:
I Scenario #
1 Event #
5, 6, 7, 8, 9 Page 25 of 39 Event
Description:
Feedwater Pump Trip. Reactor Trip Required. Auto Reactor Trip Failure.
Manual Trip Required. TDAFW Trips; MDAFW Fails to Start; MDAFW Trips.
Time Position Applicant's Actions or Behavior Check if secondary heat sink is required:
CREW o
RCS pressure - Greater than any non-faulted SG pressure o RCS Hot Leg temperatures - Any greater than 3500F Prepare to establish AFW flow:
o Check SG Blowdown o SG Blowdown Isolation Valves - CLOSED o SG Sample Isolation Valves - CLOSED BOP o CST level - Greater than 3.0 feet o
Check AFWP suction valves open o
CT-6 o
CT-64 Establish AFW flow using Motor Driven pumps o
Check ABFP 480V power supplies - ANY ENERGIZED BOP o
Check motor driven ABFPs - BOTH RUNNING BOP May attempt to start Motor driven ABFPs
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
I Event #
5, 6, 7, 8, 9 Page 26 of 39 Event
Description:
Feedwater Pump Trip. Reactor Trip Required. Auto Reactor Trip Failure.
Manual Trip Required. TDAFW Trips; MDAFW Fails to Start; MDAFW Trips.
Time Psition Applicant's Actions or Behavior Close motor driven ABFP Aux FW reg valves o 31 ABFP o
FCV-406A BOP o
FCV-406B o 33 ABFP o
FCV-406C o FCV-406D CRS Go to attachment 2, 32 ABFP operation BOP Check Turbine driven AFW pump - RUNNING Check the following alarms:
o AUX FEED PUMP ROOM Hi TEMP alarm on Panel BOP SDF - Has remained clear o 32ABFP OVERSPEED TRIP VALVE CLOSED alarm on Panel SKF - CLEAR (NO)
BOP/CRS Dispatch NPO to investigate cause of alarm and to reset trip Return to Procedure Section, step 4 until cause of trip CRS determined RO Stop all RCPs BOP Check all MSIVs closed
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
1 Event #
5, 6, 7, 8, 9 Page 27 of 39 Event
Description:
Feedwater Pump Trip. Reactor Trip Required. Auto Reactor Trip Failure.
Manual Trip Required. TDAFW Trips; MDAFW Fails to Start; MDAFW Trips.
Time Position Applicant's Actions or Behavior Try to establish FW flow to any SG:
BOP o
Check Condensate pump power supplies - ANY ENERGIZED Go to attachment 3, establishing feedwater flow from CRS secondary plant, page 37 Check if a low pressure water source is available:
o Check Condensate Pumps - ANY RUNNING BOP o
Check Condensate Pumps - ONLY ONE RUNNING o
Stop all but one condensate pump Block automatic Si actuation as follows:
BOP o
Check SI - Has NOT actuated o Place SI Block Key switches to DEFEAT CAUTION Closely monitor SG WR levels for Bleed and Feed criteria during SG depressurization I
I
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
1 Event #
5, 6, 7, 8, 9 Page 28 of 39 Event
Description:
Feedwater Pump Trip. Reactor Trip Required. Auto Reactor Trip Failure.
Manual Trip Required. TDAFW Trips; MDAFW Fails to Start; MDAFW Trips.
Time Position A
licant's Actions or Behavior NOTE o
Feed flow should be maintained to all intact SGs until NR levels are greater than 9%
o SG feed flow limitations of 50,000 Ibm/hr, which is equivalent to 100 gpm, apply when RCS hot leg temperature is greater than 5501F AND SG WR level is less than 12%
DEPRESSURIZE at least one SG to less than 450 psig to establish feed flow BOP o
Manually dump steam using atmospheric from at least one SG at maximum rate Dispatch NPO to MBFP discharge valve breakers CRS o MCC-36A; BFD-MOV-2-31 o
MCC-36B; BFD-MOV-2-32 Prepare to align flow path:
o Place feedwater isolation defeat key switches to BOP DEFEAT:
o 1/FW1DA, Safeguards initiation rack 1-1 o
1/FWlDB, Safeguards initiation rack 2-1 Reset SI as follows:
130P o
Check SI initiated (NO)
_ I I
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
I Event #
5, 6, 7, 8, 9 Page 29 of 39 Event
Description:
Feedwater Pump Trip. Reactor Trip Required. Auto Reactor Trip Failure.
Manual Trip Required. TDAFW Trips; MDAFW Fails to Start; MDAFW Trips.
Time Position Applicant's Actions or Behavior Establish initial AFW conditions o
Ensure bypass feedwater MOVs open BOP o Ensure main feedwater MOVs open o
Crack open bypass feedwater FRVs o
Place main feedwater FRVs in MANUAL and CLOSE Align feedwater header:
o Manually close MBFP recirc valves o
Align MBFP discharge valves BOP o
BFD-MOV-2-31 o
BFD-MOV-2-32 o
When MBFP discharge valves are open, then direct NPO to open MBFP discharge valve breakers Booth Instructor: When directed to de-energize MBFP discharge MOVs, insert the following commands:
LOA CFW66 T LOA CFW67 T RO Place steam and feedwater flow recorders to NARROW CRITICAL Control bypass feedwater FRVs to rapidly restore at least one TASK RO SG NR level to greater than 9%
Terminate scenario when Condensate flow is established if bleed and feed is not required
Appendix D Operator Action Form ES-D-2 Op Test No.:
I Scenario #
I Event #
5, 6, 7, 8, 9 Page 30 of 39 Event
Description:
Feedwater Pump Trip. Reactor Trip Required. Auto Reactor Trip Failure.
Manual Trip Required. TDAFW Trips; MDAFW Fails to Start; MDAFW Trips.
Dl Time I
Position I
Applicant's Actions or Behavior Evaluator note: If Bleed and Feed becomes required, the following steps describe initiation.
Check for loss of secondary heat sink:
CRS o
Check average of the 3 lowest WR SG levels - less than 25%
Manually actuate SI as follows:
BOP o Manually actuate SI o Manually close all MSIVs Evaluator note:
When SI is initiated, CRS MAY direct BOP to perform actions of RO-1. This guide contains the actions of RO-1 beginning on page 32.
I I
-d c
RO fneCK all RI-'s stopped i
Ir-l BOP Verify RCS Feed Path:
o Check HHSI pumps - ANY RUNNING o
Verify SI valve alignment - PROPER EMERGENCY ALIGNMENT o
Verify Safeguard Valve Off-Normal Position on panel SBF CLEAR o
Ensure BIT discharge valves 1835A, 1835B -
OPEN o
Ensure BIT inlet valves 1852A, 1852B - OPEN o
Ensure High Head Stop valves 856J, 856H, 856C, 856E - OPEN i
I
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
1 Event #
5, 6, 7, 8, 9 Page 31 of 39 Event
Description:
Feedwater Pump Trip. Reactor Trip Required. Auto Reactor Trip Failure.
Manual Trip Required. TDAFW Trips; MDAFW Fails to Start; MDAFW Trips.
Time Position Applicant's Actions or Behavior Establish RCS Bleed Path:
o Check both PRZR PORV block valves - POWER RO AVAILABLE o
Check PRZR PORV block valves - BOTH OPEN o
Open both PRZR PORVs CRITICAL Verify adequate RCS Bleed path:
TASK (If Required)
RO o Check PRZR PORVs - BOTH OPEN o
Check PRZR PORV block valves - BOTH OPEN Terminate scenario when bleed and feed is established and verified
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
All Event #
Attachment I Page 32 of 39 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
- 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.
- 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
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
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
All Event#
Page 33 of 39 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Verify SI Valve alignment - Proper Emergency Alignment
- a. Verify Safeguard Valve Off Normal Position alarm on panel SBF CLEAR
- b. Ensure BIT Discharge valves 1835A, 1835B -
OPEN BOP
- 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:
- a. Check Motor Driven Pumps - BOTH RUNNING
- b. Check Turbine Driven Pump - RUNNING Verify ABFP valve alignment:
Set to 0% (full open)
BOP FCV-406A FCV-406B FCV-406C FCV-406D
- b. Check SG Blowdown Isolation Valves -
CLOSED Verify CCW Pump status:
- a. Check CCW pumps - ALL RUNNING
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario All Event #
Page 34 of 39 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior 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
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
All Event #
Page 35 of 39 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Verify Emergency Diesel Generator status:
- a. Check EDGs - ALL RUNNING
SWN-FCV-1 176 SWN-FCV-1i 76A Verify Control Room Ventilation:
- a. SET Control Room ventilation control switch to - 10% INCIDENT MODE (switch position 3)
- 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 36 of 39 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:
- Train 2 SI Reset
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 37 of 39 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Check if additional SI actions should be performed:
- 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-1 111 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 38 of 39 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-1 228, 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-Essential service Water Pump - AVAILABLE BOP
- b. Check SWN-FCV-1 111 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.:
I Scenario #
All Event #
Page 39 of 39 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or BehaviorI 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
=130P Inform CRS that RO-1 is complete and advise on the status BOP of actions
Appendix D Scenario Outline Form ES-D-1 Facility:
IP3 Scenario No.:
2 Op Test No.:
1 Examiners:
Candidates:
53% power BOL 31 Charging Pump OOS 32 CCW Pump OOS Small SG Tube Leak < 25 GPD Turnover:
I&C repair is complete on 32 MBFP Speed Controller. Raise power to 100%
at 100 MWe per hour Critical Tasks:
Manual SI initiation Isolate AFW flow to faulted SG Event Malf.
Event No.
No.
Type*
Event Description 1
R (RO)
Raise power N (BOP)
N (CRS) 2 PRS2A C
Spray valve fails open slowly (RO/CRS) 3 CVC17 C
Letdown Pressure controller failure (BOP/CRS) 4 SWS6D C (ALL)
Loss of Service Water SWS6E SWS6F 5
MSS2A M (ALL)
Faulted SG 6
SIS1A C (BOP)
SI fails to actuate SIS1B
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 2 The crew will assume the shift and a power increase will be commenced. The RO will initiate a dilution IAW SOP-CVCS-3 and the BOP will raise load IAW POP-2.1.
Spray valve PCV-455A will fail open, requiring the RO to take manual control to close it IAW ONOP-RCS-2.
When the spray valve is closed in manual, PCV-135, Letdown Pressure Control Valve, will fail closed. The BOP will be required to manually reopen the valve, reestablish Letdown, and control Letdown pressure lAW ARP-9 or ONOP-CVCS-1.
A loss of Service Water occurs due to a header rupture. The crew will respond using ONOP-RW-1. The plant will degrade over a period of about 5 - 10 minutes. The reactor subsequently trips due to loss of Circulating Water pumps or manual trip by the crew.
A Steam Line Break occurs on 31 SG upon reactor trip. SI fails to actuate and must be manually actuated.
EOPflowpath: E-0-E-2-E-1 -ES-1.1 Indian Point Unit 3 2003 NRC Initial License Examination Simulator Scenario Setup Scenario 2 RESET TO IC-37 31 Charging Pump OOS:
32 CCW Pump OOS:
Si fails to actuate:
Faulted 31 SG on Rx Trip:
OVR CVC46A 2 OVR CVC46C 2 OVR CVC46D 1 OVR CVC46F 2 OVR CVC46G 2 OVR CCW3A 2 OVR CCW3C 2 OVR CCW3D 1 OVR CCW3F 2 OVR CCW3G 2 MAL SIS1A ACT MAL SIS1 B ACT MAL MSS2A ACT,1.5E6,30,0,C,JPPLP4 Materials needed for scenario:
POP-2.1 Tags for tagged equipment Graph Book 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 2 The plant is at 53% power, steady state conditions exist.
Beginning of Life, Cbis 1521 ppm.
Burnup = 150 MWD/MTU Control Bank D = 171 steps Tavg = 556.91F RCS Pressure = 2235 psig Pressurizer Level on program (34%)
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:
I&C repairs are complete on 32 MBFP Speed Controller.
In accordance with POP-2.1, raise power to 100% at 100 MWe per hour.
32 MBFP was left in current state after retest. SOP-FW-1, section 4.13.4 will be used to place the MBFP in service at 60% power.
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
1 Page 5
of 38 Event
Description:
Raise Power TPosition
_Alicant's Actions or Behavior CRS Refer to POP-2. 1, Section 4.2 Maintain applicable requirements of Attachment 1, Watch CRS Routines/Operating Requirements at all times CRS When desired to raise plant load, then go to Attachment 2
_ [I_
CAUTION Running with only one Heater Drain Pump in service and the 10" dumps open requires OM approval due to the large potential for unrecoverable transients NOTE o Attachment 2 shall be used for any significant (>5% RTP) power increase o
When reactor power is increased to greater than 20% prior to the fuel being conditioned, then power increases shall be restricted to less than or equal to 3%
per hour unless otherwise authorized by the Operations Manager/Designee and the Reactor Engineer o
Following fuel conditioning, when reactor power is increased to greater than 20%, then the rate of power increase shall be determined by the Operations Manager and is limited to a maximum of approximately 200 MW per hour o
The maximum plant load with only one Heater Drain pump is based on keeping the 10" dumps closed and using the 4" dumps to control Heater Drain Tank level.
Having only two Condensate pumps and NO CPF Booster pumps in service will allow plant load to be maximized without opening the 10" dumps.
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
2 Event#
1 Page 6
of 38 Event
Description:
Raise Power Time Position Applicant's Actions or Behavior NOTE When greater than 45% reactor power, then any of steps 7.0 through 14.0 that are inappropriate may be N/A If reactor power is greater than 45%, N/A, Initial, and date in CRS appropriate steps Obtain Shift Manager permission to increase reactor power and CRS continue performance of this attachment CRS Notify Entergy system operator of load increase Commence/continue performance of 3PT-V053A, Power CRS Ascension Surveillance Requirements Prior to exceeding 50% power, position control rods for power CRS ascension per graph RV-1 2 OR as recommended by the Reactor Engineer
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
1 Page 7
of 38 Event
Description:
Raise Power Time Position Applicant's Actions or Behavior Initiate Reactor power increase to 100%
o Adjust FW regulators manual setpoint to null manual-auto deviation o Maintain FW regulators nulled while continuing with this attachment CREW o Adjust control rod position per:
o Graph RV-13, D Bank position to maintain HFP Target Flux Difference OR o Reactor Engineer guidance RO MAY initiate dilution IAW SOP-CVCS-3
[
I I
CAUTION Do not dilute VCT while filling PWST. The addition of colder water bypasses the PWST heating coils and could have an adverse effect on RCP seals If desired to increase dilution rate then:
o Energize additional PRZR heaters per CRS o
Establish approximately 120 gpm letdown flow RO per SOP-CVCS-2 a Maintain VCT level between 30% and 50% after initiating dilution o
Divert letdown using CH-LCV-1 12A as necessary
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
1 Page 8
of 38 Event
Description:
Raise Power Time Position Applicant's Actions or Behavior 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 reduction in boron concentration Determine the volume of Primary water required for dilution by using any of the following:
o CCR Reactivity Summary Sheet RO o CCR Computer Program o CVCS-3, Dilution Nomograph for hot RCS o CVCS-4, Dilution Nomograph for cold RCS o
The boration/dilution book from Westinghouse Set YIC-1 11, Primary Water flow Integrator, for desired quantity RO of water RO Ensure 1 Pri Water Makeup Pump is running Ensure non-running Pri Water Makeup Pump switch is in TRIP-RO PULLOUT
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
2 Event#
1 Page 9
of 38 Event
Description:
Raise Power Time Position Applicant's Actions or Behavior Adjust FCV-1 1 1A, Makeup H20 to Boric Acid Blender controller for desired flow rate.
RO o
If desired to increase dilution rate then set FCV-1 1 1A to approximately 75 gpm or as directed by CRS RO Place RCS Makeup Mode Selector switch in DILUTE Turn RCS Makeup Control switch to START and return to RO NORM 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 dilution:
o Rod motion is in wrong direction or becomes blocked o Subcritical count rate increases by a factor of 2 or more RO AND a deliberate approach to criticality is NOT in progress o Tavg decreases o Axial flux target band is exceeded o RCP seal injection flow becomes erratic RO Operate PRZR heaters and letdown flows as directed by CRS
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
1 Page 10 of 38 Event
Description:
Raise Power Time Position Applicant's Actions or Behavior NOTE o
When PW Integrator reaches preset value, then dilution will automatically terminate o When RCS boron concentration is less than 500 ppm, then flushing makeup lines with blended makeup is unnecessary If performing additional dilution without flushing of lines, then RO depress PW integrator reset PB. Return to step 4.3.9 (NOT PERFORMED)
If RCS boron concentration is less than 500 ppm, then go to RO step 4.2.17.2 (NOT APPLICABLE)
When dilution operation is complete, then flush makeup lines RO with a minimum of 20 gallons of blended makeup per step 4.2 Proceed to Event 3 at Lead Evaluator's discretion
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
2 Page 11 of 38 Event
Description:
Spray Valve Fails Open Slowly Time I
Position 1
Applicantfs Actions or Behavior Booth Instructor: When directed, insert the following command:
MAL PRS2A ACT,100,180,0 Refers to ONOP-RCS-2, Malfunction of Pressurizer Pressure CRS Control system Check Pressurizer Pressure Channels - NORMAL o
PI-455 RO o P1-456 o PI-457 o P1-474 Check Pressurizer Pressure Master Controller functioning RO NORMAL o
May take manual control
~~~ ~ ~~I I
CAUTION Auxiliary Spray shall NOT be initiated with the delta T between the pressurizer and charging flow greater than or equal to 3200F
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
2 Page 12 of 38 Event
Description:
Spray Valve Fails Open Slowly Time Position Applicant's Actions or Behavior NOTE o Per ITS 3.4.11 if the block valve is closed because of an inoperable PORV, the control power for the block valve must be removed. (within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Mode 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) o Removal of the PORV solenoid circuit fuses will de-energize the solenoid and cause the valve to fail closed o The PORV solenoid circuit fuses are located behind the flight panel, in the lower fuse racks of sections FBR and FCR o
Per ITS 3.4.1 if PRZR pressure can NOT be restored to greater than 2205 psig in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or less than 2265 psig in one hour, then the reactor shall be placed in Mode 2 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> RO Check PRZR PORVs CLOSED NOTE o
Removal of the spray valve controller's fuse will de-energize the controller and cause the valve to fail closed o SOP-CVCS-2 will provide additional guidance when establishing Aux Spray RO Check PRZR spray and aux spray valves closed (NO)
RO Close the PRZR spray valve in manual RO Verify PRZR heaters all energized RO Verify PRZR pressure stable at or trending to 2235 psig
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
2 Event#
2 Page 13 of 38 Event
Description:
Spray Valve Fails Open Slowly Time Position Applicant's Actions or Behavior Operate the pressurizer heaters and spray valves as required RO to maintain normal pressurizer pressure (Per SOP-RCS-2)
When repairs have been completed, then restore operable CREW components in the automatic mode Proceed to Event 4 at Lead Evaluator's discretion
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
2 Event #
3 Page 14 of 38 Event
Description:
Letdown Pressure Controller Failure Time EPosition 1
Applicant's Actions or Behavior Booth Instructor: When directed, insert the following command:
MAL CVC17 ACT,100,10,0 Refer to ONOP-CVCS-1 AND/OR ARP 9 for LD Pressure High CRS/BOP (The following steps are from ONOP-CVCS-1)
RO Check PRZR level greater than 19%
RO Check VCT level greater than 5%
RO Check VCT level greater then 9%
Check Charging flow established RO o Charging flow indicated on Fl-128B CAUTION o
If the RCS is water solid, then letdown and charging flows will control RCS pressure o
If there is a leak in the Non-Regenerative Heat Exchanger, ONOP-CC-2, Leakage Into the Component Cooling Water System should be entered to address the leak and possible reactivity effects NOTE Shift Manager approval is required prior to restarting a tripped Charging Pump ips - AT LEAST ONE RUNNING
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
3 Page 15 of 38 Event
Description:
Letdown Pressure Controller Failure I
Time I
Position Applicant's Actions or Behavior Check Charging flow established RO o
Charging flow indicated on Fl-128B I
I Determine letdown status:
o Check Letdown flow - APPROXIMATELY 0 gpm o
Check Orifice Isolation Valves - ALL CLOSED o
Close all Letdown orifice Isolations CH-AOV-200A CH-AOV-200B CH-AOV-200C o
Prepare PCV-1 35, Low Pressure Letdown Line, for service o
Check PCV-135-IN MAN BOP Place in AUTO BAL
- Adjust manual setpoint to null deviation meter Place in MAN o
Adjust PCV-135 controller to approximately 50%
o Prepare TCV-1 30, Non-regenerative heat exchanger CCW outlet temperature control valve, for service:
o Check TCV-130 in MAN Place in AUTO BAL
- Adjust manual setpoint to null deviation meter Place in MAN o
Slowly adjust TCV-130 controller to approximately 50%
+
+
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
3 Page 16 of 38 Event
Description:
Letdown Pressure Controller Failure Time ll Position Applicant's Actions or Behavior Check the following valves OPEN:
o CH-AOV-201 BOP o CH-AOV-202 o CH-LCV-459 o
CH-LCV-460 Check the following valves - IN AUTO BOP o CH-TCV-149, Demineralizer Diversion Valve o CH-LCV-1 12A, VCT Inlet Diversion Valve BOP Open CH-AOV-200B and immediately go to next step Check Letdown flow established BOP o Letdown flow indicated on Fl-134 Control Charging and Letdown:
o Adjust PCV-135, low pressure letdown line, to maintain the following conditions:
o PI-135 LP Letdown Pressure between 225 and 275 psig CREW o Total charging and letdown flow rates balanced o Adjust TCV-130 to maintain letdown temperature between 100 and 130OF o TI 130, LP Letdown Temp o Maintain RCP seal injection between 6 - 12 gpm a
Check charging and letdown flows balanced
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event#
3 Page 17 of 38 Event
Description:
Letdown Pressure Controller Failure l
Time I
Position ll Applicant's Actions or Behavior Evaluator note: the following steps for Letdown restoration are from ARP-9 based upon high Letdown Pressure I
I BOP Verify alarm by observing LP Letdown pressure indicator Adjust CH-PCV-135, Letdown Backpressure controller, to BOP reduce letdown pressure If CH-PCV-1 35 does NOT respond in AUTO, then perform the following:
BOP o Place CH-PCV-135 in MANUAL and control pressure Proceed to Event 5 at Lead Evaluator's discretion
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
2 Event #
4,5,6 Page 18 of 38 Event
Description:
Loss of Service Water; Faulted SG; SI Fails to Actuate Time Position ll Applicant's Actions or Behavior Booth Instructor: When directed, insert the following commands:
MAL SWS9B ACT,100,300,0 MAL SWS6D ACT,12,400,0 CREW Refer to ARP-12 for Low SW header pressure Verify alarm by observing indicated service water header BOP pressure If low pressure condition exists, then:
o Start 1 additional pump per SOP-RW-5, Service Water BOP System operation o
Starts pump 37 or 39 to maintain SW pressure 60 -97.5 psig CRS Investigate cause of alarm CRS If necessary, Go to ONOP-RW-1, Service Water Malfunction Evaluator Note: SW header pressure will continue to degrade. Reactor trip will occur either when the Circ pumps are lost or the crew determines that a manual reactor trip is required.
Verify Service Water Header pressure is adequate for plant loads - greater than 60 psig (NO) o Start backup Service Water pumps to restore pressure BOP
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
2 Event #
4,5,6 Page 19 of 38 Event
Description:
Loss of Service Water; Faulted SG; SI Fails to Actuate
[Time Position Applicant's Actions or Behavior BOP Check Intake Structure SW Pumps - ANY AVAILABLE Determine if unit can remain on-line BOP o Verify Service Water Header Pressure can be maintained above 50 psig (NO)
CREW Trip the reactor (If not already tripped) and enter E-0.
CRS Go to E-0, Reactor Trip or Safety Injection 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#
2 Event#
4,5,6 Page 20 of 38 Event
Description:
Loss of Service Water; Faulted SG; SI Fails to Actuate
[
Time Position Applicant's Actions or Behavior Determine if SI is actuated Crew o
Any SI annunciator lit Crew OR o
Sl pumps-ANY RUNNING CRITICAL Determine if Sl is required using posted operator aid TASK RO o SI is required o
MANUALLY initiate SI o
Manually 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 Direct BOP operator to perform RO-1, BOP operator actions CRS during use of EOPs (steps begin on page 31 of this guide)
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
4,5,6 Page 21 of 38 Event
Description:
Loss of Service Water; Faulted SG; SI Fails to Actuate Time Position E
Applicant's Actions or Behavior Verify Feedwater Isolation:
o Verify MBFPs tripped o Verify MBFP discharge valves closed o BFD-MOV-2-31 RO 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 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)
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
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
4,5,6 Page 22 of 38 Event
Description:
Loss of Service Water; Faulted SG; SI Fails to Actuate Time F
Position Applicant's Actions or Behavior Check RCP seal cooling:
o Verify CCW flow to RCP thermal barriers RO o
RCP BEARING COOLANT LOW FLOW alarm on panel SGF clear o
THERMAL BARRIER CCW HEADER LOW FLOW alarm on panel SGF clear RO Check RCS average temperature stable at or trending to 5470F Stop dumping steam:
o Control total feed flow RO o Maintain greater than 365 gpm flow until at least one SG NR level greater than 9% (14%)
o Close all MSIVs (Should already be closed)
Check if RCPs should be stopped RO o HHSipumps-ATLEAST1RUNNING o
RCS Subcooling - LESS THAN REQUIRED (NO)
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 a
Check CH-AOV-212 closed
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
4,5,6 Page 23 of 38 Event
Description:
Loss of Service Water; Faulted SG; Si Fails to Actuate Time 1
Position l
Applicant's Actions or Behavior Determine if SGs are faulted:
o ANY DECREASING IN AN UNCONTROLLED MANNER (YES)
CRS Go to E-2, Faulted SG Isolation CAUTION o At least one SG must be maintained available for RCS cooldown o
Any faulted SG or secondary break should remain isolated during subsequent recovery actions unless needed for RCS cooldown RO Check Main Steamline isolation and bypass valves closed Determine if any SG is intact:
RO o Check SG pressures - ANY STABLE OR INCREASING (YES)
Identify Faulted SG o
Check SG pressures - ANY DECREASING IN RO UNCONTROLLED MANNER o ANY DEPRESSURIZED (YES, 31 SG is faulted)
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
4,5,6 Page 24 of 38 Event
Description:
Loss of Service Water; Faulted SG; SI Fails to Actuate Time Position Applicant's Actions or Behavior CAUTION If the turbine driven AFW pump is the only available source of feed flow, then the steam supply to the turbine driven AFW pump must be maintained from one SG CRITICAL Isolate Faulted SG:
TASK o
Check 32 and 33 SGs - BOTH INTACT o
Isolate 31 SG lines:
AFW flow o
Verify SG Atmospherics closed o
Close SG BD isolation valves o
Close SG sample valves o
Isolate MSIV upstream traps using posted operator aid Check secondary radiation:
o Check seismic event not occurred o
Direct Watch Chemist to sample all SGs for activity o
Direct Watch HP to perform contact radiation surveys on all SG steamlines and blowdown lines o
Reset SG sample valves:
o Place BD valve control switches to close o
Ensure 200A,B,C closed o
Reset Phase A Crew o
Press SG BD and sample valves reset PBs 17 through 24 on Panel SMF o
Check secondary radiation recorder trends indicate normal o
R-15, Steam Air Ejector o
R-19, Blowdown Tank area o R62A-D, Main steam lines a
Check SG levels stable
_ L
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
2 Event#
4,5,6 Page 25 of 38 Event
Description:
Loss of Service Water; Faulted SG; SI Fails to Actuate
[Time Position I
Applicant's Actions or Behavior CRS Go to E-1, Loss of Reactor or Secondary Coolant Check if RCPs should be stopped RO o
HHSI pumps - AT LEAST 1 RUNNING o
RCS Subcooling - LESS THAN REQUIRED (NO)
Determine if SGs are faulted:
o Check SG pressures:
RO o ANY DECREASING IN AN UNCONTROLLED MANNER (YES) o ANY COMPLETELY DEPRESSURIZED Check all faulted SGs isolated, unless needed for RCS cooldown:
o Check 31 steam lines - isolated:
o MSIVs o
MSIV bypasses Crew o MFW FRVs or MOVs o
AFW flow o
Verify SG Atmospherics closed o
Close SG BD isolation valves o
Close SG sample valves o
SG traps Crew Check affected SG to TDAFW isolated (N/A)
Appendix D Operator Action Form ES-D-2 Op Test No.:
I Scenario#
2 Event#
4,5,6 Page 26 of 38 Event
Description:
Loss of Service Water; Faulted SG; Si Fails to Actuate Time Position ]
Applicant's Actions or Behavior Check Intact SG levels RO o
Check level response in all intact SGs - NORMAL o
Control feed flow to maintain intact SG NR level between 9% (14%) and 50%
Reset SI as follows:
- a. Check verification of Si automatic actions of steps 2 - 12 of RO-1 is complete
- b. Press BOTH Si RESET pushbuttons on Panel RO/BOP SBF-2:
Train 1 SI Reset Train 2 SI Reset
- c. Check Si - RESET SI ACTUATED light-EXTINGUISHED 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
200B a
200C o
Reset Phase A a
Reset Phase B, if required (NO)
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
4,5,6 Page 27 of 38 Event
Description:
Loss of Service Water; Faulted SG; Si Fails to Actuate Time Position ll Applicant's Actions or Behavior Check secondary radiation:
o Check seismic event not occurred o
Direct Watch Chemist to sample all SGs for activity o
Direct Watch HP to perform contact radiation surveys on all SG steamlines and blowdown lines o
Reset SG sample valves:
o Place BD valve control switches to close o
Ensure 200A,B,C closed o
Reset Phase A RO/BOP o
Press SG BD and sample valves reset PBs 17 through 24 on Panel SMF o
Check secondary radiation recorder trends indicate normal o
R-15, Steam Air Ejector o
R-19, Blowdown Tank area o R62A-D, Main steam lines o
Check SG levels stable Check PRZR PORVs and Block Valves:
RO o Check power to block valves available o
Check PORVs closed o
Check block valves - ANY OPEN Establish Instrument Air to containment:
o Check INST AIR LOW PRESS alarm on panel SJF BOP clear o
Press Instr. Air Reset PB 28 on panel SMF a Open IA-PCV-1228, Inst Air to Cont.
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
2 Event #
4,5,6 Page 28 of 38 Event
Description:
Loss of Service Water; Faulted SG; SI Fails to Actuate Time Position ll Applicant's Actions or Behavior Check RCP Seal Cooling:
RO o Seal injection established OR o Thermal Barrier cooling established Check Component Cooling Water for Charging Pump Cooling BOP available Determine if Charging flow has been established:
o Check Charging Pump suction valves - Both energized and one valve open o CH-LCV-112B o CH-LCV-112C RO o Check CH-AOV-204B, Normal Charging isolation-OPEN o Check HCV-142 fully open o Check Charging pumps -ANT RUNNING Determine if SI should be terminated:
o Check RCS subcooling based on qualified CETs greater than 400F (OR table) 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%
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
4,5,6 Page 29 of 38 Event
Description:
Loss of Service Water; Faulted SG; SI Fails to Actuate Time Position Applicant's Actions or Behavior 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 I SI Reset
- b. Train 2 SI Reset o
Check SI - RESET
- a. SI ACTUATED light-EXTINGUISHED 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
200B 200C 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
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event #
4,5,6 Page 30 of 38 Event
Description:
Loss of Service Water; Faulted SG; SI Fails to Actuate Time Position E
Applicant's Actions or Behavior 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.
Stop SI pumps and place in AUTO 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 31 of 38 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
- 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.
- 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
Damper C - CLOSED (bypass)
Damper D - OPEN (outlet)
- d. Place control switches for 1 104 and 1 105 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 32 of 38 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position 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:
- a. Check Motor Driven Pumps - BOTH RUNNING
- b. Check Turbine Driven Pump - RUNNING Verify ABFP valve alignment:
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 33 of 38 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Verify CCW Pump status:
- 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 34 of 38 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior
- a. Check EDGs - ALL RUNNING
SWN-FCV-1 176 SWN-FCV-1 176A Verify Control Room Ventilation:
- a. SET Control Room ventilation control switch to - 10% INCIDENT MODE (switch position 3)
- 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 35 of 38 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:
- d.
Press BOTH Si RESET pushbuttons on Panel SBF-2:
BOP Train 1 Si Reset Train 2 SI Reset
- e.
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
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 36 of 38 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Check if additional Si actions should be performed:
- 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-1 111 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 37 of 38 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-1 111 and SWN-FCV-1 112
- 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 38 of 38 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position I
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
Appendix D Scenario Outline Form ES-D-1 Facility:
IP3 Scenario No.:
3 Op Test No.:
1 Examiners:
Candidates:
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 (RO/CRS) 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 DSG1 B C (ALL)
Two Running DGs trip. 480 volt bus 3A tie breaker trips open.
DSGIC 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 lAW 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 I OVR DSG6E 2 OVR DSG6F 2 EDG trip on reactor trip:
Bus 3A Tie Breaker fail to close:
MAL DSG1C ACT,0,C,JPPLP4 MAL DSG1 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, CbJS 1581 ppm.
Burnup = 150 MWDIMTU 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 #
I Page 5
of 34 Event
Description:
Reduce Power.
Time Position 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, 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 34 Event
Description:
Reduce Power.
Time Position I
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 34 Event
Description:
Reduce Power.
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.:
I Scenario #
3 Event #
1 Page 8
of 34 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 RO 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 Pc 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 34 Event
Description:
PR NI Failure Time I
Position I
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-11.1) 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 I
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
3 Event #
2 Page 10 of 34 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 34 Event
Description:
Steam Flow Transmitter fails low Time Position 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 34 Event
Description:
Steam Flow Transmitter fails low l
Time l
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 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)
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 13 of 34 Event
Description:
Loss of 6.9 KV Bus 6; DG Output Breaker Fail to Auto Close Time Position 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 o
Refer to ONOP-RW-2 if necessary
_ J
_ ~~I
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
3 Event #
4 Page 14 of 34 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-11 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/BOPo 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 15 of 34 Event
Description:
Loss of 6.9 KV Bus 6; DG Output Breaker Fail to Auto Close Time Position A
licant'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 16 of 34 Event
Description:
Loss of 6.9 KV Bus 6; DG Output Breaker Fail to Auto Close Time Position ll Applicant's Actions or BehaviorI Evaluate Tech Spec impact CRS o LCO 3.8.1 o LCO3.8.9 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 17 of 34 Event
Description:
Loss of Off-Site Power. Running DGs Trip. Inadvertent SI Time Position 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 18 of 34 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 NOWby inserting the following commands:
MAL DSGIC 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 19 of 34 Event
Description:
Loss of Off-Site Power. Running DGs Trip. Inadvertent Si Time Position Applicant'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,FH 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.:
1 Scenario #
3 Event #
5, 6, 7 Page 20 of 34 Event
Description:
Loss of Off-Site Power. Running DGs Trip. Inadvertent SI Time 1
Position 1
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 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 21 of 34 Event
Description:
Loss of Off-Site Power. Running DGs Trip. Inadvertent SI I
Time 1
Position 1
Applicant's Actions or Behavior Booth Instructor.: When BOP verifies 2 ESWpumps 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 IL I __
I _______
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
3 Event #
5, 6, 7 Page 22 of 34 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
SI pumps-ANY RUNNING (YES) o Manually actuate SI o
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 T
T Direct BOP operator to perform RO-1, BOP operator actions during use of EOPs (steps begin on page 27 of this guide)
CRS 1~
-I-
}
r Verify Feedwater Isolation:
o Verify MBFPs tripped o
Verify 0
0 MBFP discharge valves closed BFD-MOV-2-31 BFD-MOV-2-32 RO o Verify Main and Bypass feedwater isolated o Main and Bypass FW MOVs closed OR o Main (SNF panel) and Bypass FW FRVs closed I
I
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
3 Event #
5, 6, 7 Page 23 of 34 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 low
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
3 Event #
5, 6, 7 Page 24 of 34 Event
Description:
Loss of Off-Site Power. Running DGs Trip. Inadvertent SI Time Position I
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:
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 25 of 34 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%
Crew (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 2 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 26 of 34 Event
Description:
Loss of Off-Site Power. Running DGs Trip. Inadvertent SI Iii ime 11 r-USIbul 11 A nnl._nntnc A.tfinn.
n c.r P.1-As-i TimP~ ~
~
~~~~.
A I~itn lAz/
-d:_ -_--,
RO/BOP Reset Containment Isolation Phase A and Phase B as follows:
o Place switches for letdown orifice isolation valves to close:
o 200A o
200B o
200C o Reset Phase A o Reset Phase B, if required (NO) i i
I I Direct BOP operator to initiate performance of attachment 3, Re-establishing operator control of valves following phase A reset CRS 1
I 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-1228, 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 27 of 34 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position A
licant's Actions or Behavior Monitor Control Room Annunciators:
- a. Acknowledge all Supervisory Panel Alarms as time permits
- 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.
- 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
Damper C - CLOSED (bypass)
Damper D - OPEN (outlet)
- d. Place control switches for 1 104 and 1 105 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 28 of 34 Event
Description:
RO-1, BOP Operator Actions During EOPs l
Time L Position 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:
- a. Check Motor Driven Pumps - BOTH RUNNING
- b. Check Turbine Driven Pump - RUNNING Verify ABFP valve alignment:
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 29 of 34 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Verify CCW Pump status:
- 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 30 of 34 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior
- a. Check EDGs - ALL RUNNING
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)
- 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 31 of 34 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
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 32 of 34 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position Applicant's Actions or Behavior Check if additional SI actions should be performed:
- 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 33 of 34 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position I
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-1i1 1 and SWN-FCV-1 112
- 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 34 of 34 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 130P Inform CRS that RO-1 is complete and advise on the status of actions
Appendix D Scenario Outline Form ES-D-1 Facility:
IP3 Scenario No.:
4 Op Test No.:
1 Examiners:
Candidates:
_RO PO 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 Malf.
Event No.
No.
Type*
Event Description 1
R (RO)
Reduce load N (BOP)
First Stage Shell Pressure PT-412B fails low 3
MSS3 I (RO)
Steam Pressure transmitter 404 fails high I (CRS) 4 CCW1A CCW Pump Trip.
5 RCS1 OC 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-41 2B 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:
Boration failure:
OVR CVC47A 2 OVR CVC47C 2 OVR CVC47D 1 OVR CVC47F 2 OVR AFW9A 2 OVR AFW9C 2 OVRAFW9D 1 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 OVR CVC16A 1 OVR CVC16C 1 OVR CVC16D 2 OVR CVC16B 2 Materials needed for scenario:
POP-2.1 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 12 Indian Point Unit 3 2003 NRC Initial License Examination Simulator Scenario Tumover Information Scenario 4 The plant is at 94% power, steady state conditions exist.
End of Life, Cb is 14 ppm.
Bumup = 23135 MWD/MTU Control Bank D = 213 steps Tavg = 565.30F 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 Time 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 10ppm 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 I
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-11 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 l_Time Position Applicant's Actions or Behavior Booth Instructor: When directed, insert the following command:
MAL TURIOB 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 o 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 Position Applicant's Actions or Behavior Check SG Instrumentation - NORMAL 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)
When attachment 12 is complete or at Lead Evaluator's discretion, 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 1
Position 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 Time Position 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 2
Event
Description:
CCW Pump Trip.
Time 1
Position ll 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
_ I __
_ I 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 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 BOP If surge tank levels decrease to less than 5% level in BOTH tanks then trip all CCW pumps (NIA) 1 1
Appendix D Operator Action Form ES-D-2 Op Test No.:
I Scenario #
4 Event #
4 Page 14 of 29 Event
Description:
CCW Pump Trip.
Time Position Applicant's Actions or Behavior IF CCW has been lost to 32 header and cannot be restored, then perform the following before RCP motor bearing temperatures reach 200OF as read on the CFMS (N/A)
CREW o
Manually trip the reactor o Manually trip all RCPs o Go to E-0, Reactor Trip or Safety Injection If any charging pump is running, then establish temporary CRS cooling using SOP-ESP-001, Local Operation of Safe Shutdown Equipment (N/A)
Evaluator note: Subsequent action steps 5.1 through 5.4 do not apply to this event, and are not covered in this scenario guide.
If the CCW pumps cannot be started, then an electrical fault could exist. Investigate and attempt to correct the fault.
BOP o
If necessary, place the 32 CCW pump on the alternate feed per SOP-EL-12 o Reduce Component Cooling loads as necessary (N/A)
~~~ ~ ~~I I
A Thermal Barrier Heat Exchanger Tube leak and RCP Vibration will lead to Event 5
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 Time Position 1
Applicant's Actions or Behavior
[This event was initiated via time delay on the previous event I
I 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 I
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 Neutron flux decreasing
_ ~
~
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 Time E Position Applicant's Actions or Behavior Manually trip reactor RO o
Insert control rods in manual o
Dispatch NPO to trip reactor using posted operator aid 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 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) o (Failing air to FCV-11 OA)
Evaluator note: Attachment 1 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 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 o
FCV-l1 A closed o CH-330, Boric acid blender primary water bypass isolation closed
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 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 Time Position 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 o
Rod position indication less than 20 steps o
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 Time 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
Si 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 #
All Event #
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
- c. Monitor status of the following alarms:
HIGH CONT ATMOS TEMPIRTD 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.
- 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 1 104 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 l
Time Position 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:
- a. Check Motor Driven Pumps - BOTH BOP RUNNING
- b. Check Turbine Driven Pump - RUNNING Verify ABFP valve alignment:
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:
- 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
SWN-FCV-1 176
- SWN-FCV-1l 76A Verify Control Room Ventilation:
- a. SET Control Room ventilation control switch to - 10% INCIDENT MODE (switch position 3)
- 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 Tie Position IApplicant'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
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 E
Applicant's Actions or Behavior Check if additional Si actions should be performed:
- 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-1 111 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 l
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-1 228, 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-Essential service Water Pump - AVAILABLE BOP
- 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:
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 29 of 29 Event
Description:
RO-1, BOP Operator Actions During EOPs Time l
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 BOP of actions
Appendix D Scenario Outline Form ES-D-1 Facility:
IP3 Scenario No.:
5 Op Test No.:
1 Examiners:
Candidates:
CRS RO PO0 Initial Conditions:
9% power BOL Plant startup in progress Turnover:
Raise power and synchronize the Main Generator Critical Tasks:
Place ECCS equipment in PTL Isolate ruptured SG Event Malf.
Event No.
No.
Type*
Event Description 1
R (RO)
Raise reactor power. Synchronize Main Generator N (BOP)
N (CRS) 2 RCS20B I (ALL)
Tcold instrument fails high 3
SGN5C C (ALL)
Steam Generator Tube Leak 4
SGN5C M (ALL)
SGTR 5
XMT C (RO)
Atmospheric Dump valve on ruptured SG fails open SGN10 6
RPS6B C (BOP)
Train 'B' RTB fails closed. Manual action to reset Si prior to stopping ECCS pumps
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 5 The crew will assume the shift to raise power and synchronize the Main Generator to the grid IAW POP-1.3 and SOP-TG-4.
When the generator is on-line, a Tcold instrument will fail high. IAW ONOP-RPC-1, the RO will place the running Charging Pump in manual, the BOP will trip bistables, and the CRS will refer to Technical Specifications.
When the plant is stable, a steam generator tube leak will develop, requiring action IAW ONOP-SG-1. Leak rate will be quantified, secondary systems will be isolated, and the crew will begin a plant shutdown IAW POP-3.1.
While the crew is shutting the plant down, the tube leak will increase in severity. The crew will determine that pressurizer level cannot be maintained, and a reactor trip will be required.
When the reactor trips, one Atmospheric Dump Valve will fail open, requiring manual action to close it to minimize radioactive release to atmosphere. Additionally, the 'B' RTB will stick closed. Manual action will be required to reset safeguards actuation pin relays prior to stopping ECCS equipment to terminate the event.
EOP flow path: E E ES-3.1 Scenario Event Description NRC Scenario 5 The crew will assume the shift to raise power and synchronize the Main Generator to the grid IAW POP-1.3 and SOP-TG-4.
When the generator is on-line, a Tcold instrument will fail high. IAW ONOP-RPC-1, the RO will place the running Charging Pump in manual, the BOP will trip bistables, and the CRS will refer to Technical Specifications.
When the plant is stable, a steam generator tube leak will develop, requiring action IAW ONOP-SG-1. Leak rate will be quantified, secondary systems will be isolated, and the crew will begin a plant shutdown IAW POP-2.1.
While the crew is shutting the plant down, the tube leak will increase in severity. The crew will determine that pressurizer level cannot be maintained, and a reactor trip will be required.
When the reactor trips, one Atmospheric Dump Valve will fail open, requiring manual action to close it to minimize radioactive release to atmosphere. Additionally, the 'B' RTB will stick closed. Manual action will be required to reset safeguards actuation pin relays prior to stopping ECCS equipment to terminate the event.
EOP flow path: E E ES-3.1 Indian Point Unit 3 2003 NRC Initial License Examination Simulator Scenario Setup Scenario 5 RESET TO IC40 No equipment OOS Train B reactor trip breaker failure:
MAL RPS6B ACT Override Feed Heater Hi Level annunciators:
OVR ANN FWH1 2 OVR ANN FWH4 2 OVR IND FWH33 50 OVR IND FWH34 50 OVR IND FWH35 50 Materials needed for scenario:
POP-1.3 signed off up to step 4.35 SOP-TG-4 signed off up to step 4.2.16 Graph Book OA-99-29 (Operator Aid)
Daily Reactivity Sheet Allow crew to begin scenario brief approximately 30 minutes prior to entering simulator Note: None Scenario built from IC 8 Indian Point Unit 3 2003 NRC Initial License Examination Simulator Scenario Turnover Information Scenario 5 The plant is at 8% power in preparation for generator synchronization Beginning of Life, CbiS 1580 ppm.
Burnup = 150 MWD/MTU Control Bank D = 105 steps Rod Control in Manual Tavg = 5501F RCS Pressure = 2235 psig 31 MBFP in manual, 32 MBFP in standby Low Flow Bypass FRVs in service The following equipment is out of service:
None Crew instructions:
In accordance with POP-1.3, step 4.35, and SOP-TG-4, step 4.2.16, synchronize the Main Generator and commence power increase not to exceed 10% per hour.
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
5 Event #
1 Page 5
of 29 Event
Description:
Raise reactor power. Synchronize Main Generator.
Time Position A plicant's Actions or Behavior Refers to POP-1.3, step 4.35, Perform excitation and CRS synchronization of Turbine Generator per SOP-TG-4, Turbine Generator Operation CRS Refers to SOP-TG-4, step 4.2.16 When synchroscope indicates approximately 2 minutes before BOP 12 o'clock, then close the selected generator output breaker Adjust governor speed changer to obtain 10 to 20 MWe BOP generator load BOP Place synchroscope switch in OFF Check H2 cooler gas outlet temperatures within 2.0C of each BOP other BOP Ensure all stator RTD ATs are within limits Adjust governor speed changer to obtain 20 to 40 MWe generator load and perform the following:
BOP o Maintain load 20 to 40 MWe until 6.9 KV busses are transferred o
Verify Unit Aux Transformer tap changer hangup alarm clears (SHF)
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
5 Event#
I Page 6
of 29 Event
Description:
Raise reactor power. Synchronize Main Generator.
Time Position Applicant's Actions or Behavior Ensure generator megavar meter indicates zero or slightly to BOP the right by adjusting regulator voltage adjuster until proper indication is obtained Adjust regulator base adjuster to maintain voltage regulator DC BOP Milliammeter nulled CRS Notify Coned S.0 that generator output breaker is closed Contact Coned D.O and request permission to close other 345 CRS KV breaker When permission obtained to close the other generator breaker, then perform the following:
o Place potential selector switch in position for breaker to be closed BOP o Place synchroscope in MAN o
Verify synchroscope is at 12 o'clock o
Close second breaker o
Place synchroscope in OFF o
Place Potential Selector switch in OFF BOP Ensure turbine aux oil pump is stopped and in AUTO BOP Ensure bearing oil pump is stopped and in AUTO Return to POP-1.3
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
5 Event #
1 Page 7
of 29 Event
Description:
Raise reactor power. Synchronize Main Generator.
[ Time Position Allicant's Actions or Behavior When power above P-10 illuminates, then block NIS Rod Stop CRS and trips Transfer loads on 6.9 KV busses 1 - 4 to UAT per SOP-EL-5, BOP Operation of Onsite power sources When busses 1-4 are transferred, proceed to Event 2
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
5 Event #
2 Page 8
of 29 Event
Description:
Tcold Instrument Fails High Time 1
Position IAlicant's Actions or Behavior Booth Instructor: When directed, insert the following command:
MAL RCS20B ACT,645,00 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 o
May take manual control of charging flow 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 (NO) Loop 2 High 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.:
I Scenario#
5 Event#
2 Page 9
of 29 Event
Description:
Tcold Instrument Fails High Time Position Applicant's Actions or Behavior Determine appropriate attachment for RCS Hot and Cold Leg RTD failures:
CRS o
Temperature high, Delta T low, go to Attachment 1 Performs attachment 1 RO/BOP (Evaluator note: Attachment I procedure is attached to the end of this scenario guide)
When attachment 1 is complete or at Lead Evaluator's discretion, proceed to Event 3
Appendix D Operator Action Form ES-D-2 Op Test No.:
I Scenario#
5 Event#
3 Page 10 of 29 Event
Description:
Steam Generator Tube Leak Time I
Position lAlicant's Actions or Behavior Booth Instructor: When directed, insert the following command:
MAL SGN5C ACT,0.05,0,0 CRS Refers to ONOP-SG-1, SG Tube Leak Check pressurizer level can be maintained greater than 5%
RO and stable or increasing Monitor VCT level RO o Maintain VCT level greater than 22% with makeup in auto or manual per SOP-CVCS-3 NOTE o
For direction on the classification of events, refer to initiating conditions and emergency action levels in VOL II of the Emergency Plan o
Blowdown sample lines may be unisolated for sampling purposes o
If R-15 is NOT in service, then R-15 should be restored to operable as soon as possible o
The leaking SG may be identified by:
o Positive chemistry sample o
R-62 radiation monitor o
HP surveys o
Unexplained increase in SG level Identify leaking SG CREW o
33 SG is leaking NOTE Shutdown due to exceeding Tech Spec limits requires a four hour NRC notification
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
5 Event 3
Page
- i of 29 Event
Description:
Steam Generator Tube Leak Time Position Applicant's Actions or Behavior CREW Monitor leakage - IN EXCESS OF TECH SPECS CRS Determine Emergency classification Refer to Emergency Response Activation, Volume II CRS o
Be in Mode 3 in next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Initiate Attachment 2, Monitoring Frequency CREW (Evaluator note: Attachment provided at end of scenario guide)
NOTE o Chemistry sample is considered the most reliable leakrate and does not require validation o
Validation only requires supporting indication of an actual tube leak, NOT the magnitude of the leak o
If validation of the calculated leak rate cannot be performed within 15 minutes of initial leakrate quantification then the most recent calculated reading shall be considered valid o Plant shutdown and cooldown procedures should be reviewed as time permits CRS Check sample results - OBTAINED Booth Instructor note: Approximately 15 minutes after Chemistry sample request, report leakage at 80 GPD in 33 SG Check primary to secondary leakage - LESS THAN 75 gpd CRS o
Be in Mode 3 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
5 Event#
3 Page 12 of 29 Event
Description:
Steam Generator Tube Leak Time Position A
licant's Actions or Behavior CRS Initiate attachment 1, Isolation of Secondary side Performs attachment 1 BOP (Evaluator note: Attachment provided at end of scenario guide)
CRS Check leakrate in any steam generator greater than 75 GPD CRS Check reactor in Mode 1 or 2 CRS Initiate a Plant Shutdown
~~~ ~~I I
When decision is made to shut down after attachment 1 is commenced, proceed to Event 4
Op Test No.:
1 Scenario#
5 Event#
4, 5, 6 Page 13 of 29 Event
Description:
SGTR, Atmospheric Dump Valve on ruptured SG fails open; Train 'B" RTB fails closed. Manual action to stop ECCS pumps.
l-Time_
Position 3Alicant's Actions or Behavior Booth Instructor: When directed, insert the following command:
MAL SGN5C ACT,10,60,0 OVR XMT SGN10 1400,60,0 Based upon increase in RCS leakrate, decide to trip reactor CRS and enter E-0 CRS Go to E-0, Reactor Trip or Safety Injection Verify reactor trip:
o Reactor trip and bypass breakers open ('B' RTB Closed)
RO o
Rod bottom lights lit o
Rod position indicators less than 20 steps o
Neutron flux decreasing o
Direct NPO to open RTB 'B' Verify Turbine Trip:
Verify all turbine stop valves closed BOP Verify 480V AC Busses - All energized by offsite power Determine if SI is actuated Crew o
Any SI annunciator lit OR a
SIlpumps-ANY RUNNING (YES)
Op Test No.:
1 Scenano #
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:
l 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 l Direct BOP operator to perform RO-1, BOP operator actions during use of EOPs (steps begin on page 22 of this guide)
CRS l Verify Feedwater Isolation:
o Verify MBFPs tripped o Verify 0
0 MBFP discharge valves closed BFD-MOV-2-31 BFD-MOV-2-32 RO 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
Op Test No.:
1 Scenario #
5 Event #
4,5,6 Page 15 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 Aplicant's Actions or Behavior Verify Si flow:
RO o
Check RCS pressure less than 1650 psig (2000 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 RO o
RCP BEARING COOLANT LOW FLOW alarm on panel SGF clear o
THERMAL BARRIER CCW HEADER LOW FLOW alarm on panel SGF clear Critical Check RCS average temperature stable at or trending to 5470 F task o
STOP Dumping steam action)
RO o
33 SG Atmospheric in MANUAL and CLOSE o
Additional cooldown actions Check if RCPs should be stopped RO o
HHSipumps-ATLEAST1RUNNING o
RCS Subcooling - LESS THAN REQUIRED (NO)
Check PRZR PORVs, Safety Valves, and Spray Valves a
Check both PRZR PORVs - CLOSED a
Check PRZR Safety Valves - CLOSED RO o
Tailpipe temperatures normal o
Acoustic monitors normal a
Check normal PRZR Spray Valves closed a
Check CH-AOV-212 closed
Op Test No.:
1I Scenario #
5 Event#
- 4. 5, 6 Page 16 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 E
7Applicant's Actions or Behavior 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
________(NO
)
CRS Direct transition to E-3, Steam Generator Tube Rupture RO Determine if RCPs should be stopped (NO)
Identify Ruptured SG RO o 33 SG identified CAUTION o
If the turbine driven AFW pump is the only available source of feed flow, steam supply to the turbine driven AFW pump should be maintained from at least I SG a
At least 1 SG must be maintained available for RCS cooldown
Op Test No.:
I Scenario#
5 Event#
4,5,6 Page 17 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 AXlicant's Actions or Behavior CT Isolate flow from ruptured SG (isolation action) o Adjust atmospheric controller to 1040 psig o
Check ruptured atmospheric closed o
Manually close Check 32 and 33 SGs intact CREW o
Dispatch NPO to close 33 SG steam supply to TD ABFP BOP Verify BD isolation valves from 33 SG closed Dispatch NPO to locally isolate ruptured SG using posted CRS operator aid Ensure ruptured SG steam line valves closed BOP O
MSIV o
MSIV bypass CREW Ensure ruptured SG isolated from at least one intact SG CAUTION If any ruptured SG is faulted, feed flow to that SG should remain isolated during subsequent recovery actions unless needed for RCS cooldown RO Check ruptured SG level greater than 9%
Op Test No.:
1 Scenario #
5 Event #
4, 5,6 P age 18 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 I
Position l=_
Aeplicant's Actions or Behavior RO/BOP Stop feed flow to 33 SG CAUTION If any PRZR PORV opens because of high pressure, step 5.b should be repeated after pressure decreases to less than the PORV setpoint L
Check PORVs and block valves RO o
Power available to block valves o
PORVs closed o
Any block valves open Check if SGs are faulted RO o Any SG depressurizing in an uncontrolled manner o Any SG depressurized Check intact SG levels RO o
Level response in intact SGs normal o
Control feed flow to maintain 9% to 50%
Reset Si BOP o
Check RO-1, steps 2-12 completed o
Press both SI reset buttons on panel SBF-2 Check SI reset (NO) (Train B RTB stuck closed)
BOP o
Use DEFEAT keys and reset pin relays BOP Reset Containment Isolation Phase A
Op Test No.:
1 Scenario #
5 Event #
4, 5, 6 Page 19 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 BOP Establish Instrument Air to Containment CAUTION RCS pressure should be monitored. If RCS pressure decreases in an uncontrolled manner to less than 325 psig (650 psig) then the RHR pumps must be manually restarted to supply water to the RCS Determine if RHR pumps should be stopped BOP o
Stop RHR pumps and place in AUTO CAUTION Isolation of the ruptured SG should be completed by closing the MSIV and bypass for the ruptured SG or for the intact SGs before continuing to step 12, unless a ruptured SG is needed for RCS cooldown NOTE o
RCS cooldown should proceed as quickly as possible and should NOT be limited by the 100OF Tech Spec limit. Integrity limits should NOT be exceeded since the final temperature will remain above 3200F.
o After an operator-induced cooldown in step 13 is begun, the continuous action for RCP trip criteria no longer applies I
I Initiate RCS cooldown RO o Determine required Core Exit temperature from table
Op Test No.:
1 Scenario #
5 Event #
4, 5, 6 Page 20 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 A22licant's Actions or Behavior Dump steam from all intact SGs at maximum rate RO o Manually open Atmospherics When RCS temperature is below the required core exit RO temperature, STOP the cooldown and maintain temperature below the required limit RO Check RCP seal cooling established RO Establish charging flow CAUTION RCS cooldown shall be completed before continuing RO Check ruptured SG pressure stable or increasing RO Check RCS subcooling greater than 600F (OR table)
I_ [I__
[ _
I NOTE If pressure does not decrease or decreases only slowly then go to step 20 to expedite recovery I
T I Depressurize RCS using pressurizer spray to minimize break flow and refill pressurizer RO l
l
Op Test No.:
1 Scenario #
5 Event#
4, 5, 6 Page 21 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 A
licant's Actions or Behavior Terminate depressurization when RCS pressure is less than SG pressure and pressurizer level is greater than 14%
RO OR When pressurizer level exceeds 71%
Determine if Si should be terminated:
o Check RCS subcooling based on qualified CETs greater than 400F (OR table) o Check secondary heat sink o
Total AFW to intact SGs greater than 365 psig available, OR RO o
Intact SG NR levels - ANY greater than 9%
(14%)
o RCS pressure o Stable or increasing o
Pressurizer level greater than 14%
Task BOP Stop HHSI pumps and place in AUTO Terminate scenario any time after ECCS pumps are stopped
Appendix D Operator Action Form ES-D-2 l Op Test No.:
1 Scenario#
All Event #
Page 22 of 29 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position Aplicant's Actions or Behavior Monitor Control Room Annunciators:
- a. Acknowledge all Supervisory Panel Alarms as time permits
- c. Monitor status of the following alarms:
HIGH CONT ATMOS TEMPIRTD 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.
- 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
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 #
Attachment I Page 23 of 29 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position 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:
- a. Check Motor Driven Pumps - BOTH RUNNING
- b. Check Turbine Driven Pump - RUNNING Verify ABFP valve alignment:
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 A
licant's Actions or Behavior Verify CCW Pump status:
- 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 A
licant's Actions or Behavior
- a. Check EDGs-ALL RUNNING
SWN-FCV-1 176 SWN-FCV-1 176A Verify Control Room Ventilation:
- a. SET Control Room ventilation control switch to - 10% INCIDENT MODE (switch position 3)
- 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
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 #
Attachment I 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:
- 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-11 1 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 l Op Test No.:
1 Scenario #
All Event #
Page 28 of 29 Event
Description:
RO-1, BOP Operator Actions During EOPs Time Position Aplicant'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-1 228, 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-I 111 and SWN-FCV-1 112
- 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 #
Attachment I Page 29 of 29 Event
Description:
RO-1, BOP Operator Actions During EOPs Time ll Position I
Applicant's Actions or Behavior I
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 130P Inform CRS that RO-1 is complete and advise on the status BOP of actions