ML032521468
| ML032521468 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/01/2003 |
| From: | Hensley D Nuclear Management Co |
| To: | NRC/RGN-III |
| References | |
| 50-255/03-301 | |
| Download: ML032521468 (48) | |
Text
palisades nuclear plant Page 1 of 52 July 2003 Appendix D Scenario Outline Form ES-D-1 (R8, S1)
Facility: PALISADES Scenario No.: 1 Op-Test No.: ___1____
Examiners:
Operators:
Initial Conditions:
Approx. 25% power, MOL, D/G 1-1 tagged out for inspection.
Turnover:
Power escalation in progress. One Main Feed Pp. in service. Shift orders are to swap from Startup Power to Station Power and continue the power escalation at 6% per hour to full power.
Event No.
Malf. No.
Event Type*
Event Description 1
NA SRO (N)
BOP (N)
Alternate from Startup to Station Power 2
NA SRO (N)
BOP (N)
RO (R)
Continue power escalation 3
RP22B SRO (I)
RO (I)
BOP (I)
Hot Leg #1 RTD fails low 4
SW11A SRO (C)
RO (C)
P-7A Service Water Pp. Basket Strainer high dP 5
RX15A SRO (I)
BOP (I)
Main Steam Flow Transmitter FT-0702 fail to lower than normal 6
FW10 SRO (M)
BOP (M)
RO (M)
Feedwater line rupture outside containment (ramp in) 7 RC17 SRO (C)
RO (C)
Stuck open PZR spray valve 8
FW02 SRO (C)
BOP (C)
RO (C)
Condensate Storage Tank ruptures
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
palisades nuclear plant Page 2 of 52 July 2003 Scenario 1 - Simulator Operator Instructions
Reset to IC 14 (25% - MOL).
Tagout D/G 1-1
One MFW Pp. I/S
Ensure 4160V buses are still on S/U power.
Ensure P-7A SWS Pump is operating.
May have to OVRD EK-1316 to prevent T-82A Hi-Lo Press alarm from coming in when resetting to IC-14.
Event No.
Simulator Operator Instruction 3
REMOTE 1 INSERT RP-22B (Hot Leg RTD) to fail LOW (Value = 0.0%)
4 REMOTE 2 INSERT OVRD for EK-1132, P-7A Basket Strainer Hi dP. IF REQUESTED to locally check basket strainer dP, report gauge reads ~9 psid.
5 REMOTE 3 INSERT MF RX15A (Main Steam FT-0702) to active at 0.65. NOTE: DO NOT ENTER WHILE DILUTION IS IN PROGRESS.
6 REMOTE 4 INSERT FW10 (FW Line 2 Break Outside Cont.) to RAMP in 10 minutes from 0-50%.
EK-0171, "CONDENSATE PUMP ROOM FLOODING" should alarm ~30 seconds after Turb. Bldg sump alarm. May need Event Trigger.
7 REMOTE 5 INSERT RC17 (PZR Spray Vlv.) @100% at time of Reactor trip When operator manually closes CV-1057, RC17 will be deleted via the following Event Trigger:
Event:
.NOT.ZDI2P(160) (CV-1057 to CLOSE)
Action:
DMF RC17 8
REMOTE 6 INSERT FW02 (T-2 Leak) Ramp = 10 minutes from 0-100%.
(Insert when EOP-2.0 SFSCs are assigned.)
Will need to lineup Service Water to P-8C or P-8A when directed.
SPECIAL NOTES:
- 1. When AO is dispatched to investigate Turbine Building Sump level alarm, wait 1 minute and report:
"There's some kind of steam/water leak on the East side of the Turbine Building in the vicinity of the E-5s and E-6s. I can't get close enough to see exactly what it is." Info only for Simulator Operator:
the FW line leak is downstream of the E-6s.
- 2. If dispatched to investigate T-2 low level, report that a fork lift has punctured the tank.
palisades nuclear plant Page 3 of 52 July 2003 Scenario 1 - Shift Turnover Approx. 25% power, MOL, D/G 1-1 tagged out for inspection.
Power escalation in progress. One Main Feed Pp. in service. Shift orders are to swap from Startup Power to Station Power and continue the power escalation at 6% per hour to full power.
palisades nuclear plant Page 4 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
1 Event No.:
1 Page _1_ of _2_
Event
Description:
Alternate from Startup to Station Power.
Time Position Applicant's Actions or Behavior SRO BOP Enters SOP-30, 7.1.1 BOP Checks control power lights LIT for Bus 1A, 1B.
BOP Ensures Startup Transformer UV relays reset.
227X-5 227X-6 BOP Checks for proper voltages on Station Power Transformers.
BOP Inserts synch switch and turns ON for associated breakers, as needed (may check synch scope energized).
BOP Scopes and closes the following breakers:
Bus 1A 252-101
Bus 1B 252-201
Bus 1F 252-301
Bus 1G 252-401
palisades nuclear plant Page 5 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
1 Event No.:
1 Page _2_ of _2_
Event
Description:
Alternate from Startup to Station Power.
Time Position Applicant's Actions or Behavior BOP Verifies the following breakers open: (as corresponding Station Power breaker is closed)
Bus 1A 252-102
Bus 1B 252-202
Bus 1F 252-302
Bus 1G 252-402 BOP Acknowledges associated breaker trip alarm after each transfer.
BOP As each breaker swap is made, ensures charging motor lamp for Station Power breakers lights within 10 seconds.
BOP Matches breaker control switch targets by placing switch for Startup Power breakers (just opened) to TRIP.
palisades nuclear plant Page 6 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
1 Event No.:
2 Page _1_ of _1_
Event
Description:
Continue Power Escalation Time Position Applicant's Actions or Behavior SRO Enters/continues and directs the actions of GOP-5.
SRO Reviews GOP-5 Precautions and Limitations with crew.
SRO May discuss ASI control strategy. Determines target ASI = -0.02.
CUE:
Reactor Engineering says it is acceptable to be outside of the ASI band.
BOP RO Continue power escalation as directed by CRS.
Note to Examiner: Various techniques may be used for the power ascension (e.g., start with a 50 gal. dilution, follow with a 100 gal. dilution, etc.)
BOP Selects DEH rate at 6% per hour.
BOP Initiates GO on DEH control for Main Turbine load increase.
palisades nuclear plant Page 7 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
1 Event No.:
3 Page _1_ of _1_
Event
Description:
Hot Leg #1 RTD fails low Time Position Applicant's Actions or Behavior SRO BOP RO Diagnoses low failure of Hot Leg #1 RTD EK-0604, Rack D, NUCLEAR - DELTA T POWER DEVIATION, T-INLET OFF NORMAL/CALCULATOR TROUBLE Thermal Margin Monitor Channel B indicates "0".
TI-0112HB failed LOW.
EK-0967, LOOP 1 LOOP 2 Tave DEVIATION SRO Enters and directs the actions of various ARPS.
BOP Bypass the Variable High Power Trip and the TM/LP trip for B Channel of RPS, per SOP-36.
1.
Insert bypass key above affected RPS Trip Unit.
2.
Turn key 90º clockwise.
3.
Verify lit YELLOW light above bypass keyswitch.
4.
Log evolution.
SRO Notify I&C to troubleshoot.
SRO Refers to various Technical Specifications:
T.S. 3.3.1
T.S. 3.1.6 (does not apply because Thot B channel does not feed PDIL calculator.
T.S. 3.3.7 requirements are met
T.S. 3.3.8 does not apply
T.S. 3.4.12 does not apply.
ORM 3.17.6, item 12 does apply.
palisades nuclear plant Page 8 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
1 Event No.:
4 Page _1_ of _1_
Event
Description:
P-7A SW pump Basket Strainer Hi dP Time Position Applicant's Actions or Behavior RO Diagnoses P-7A Basket Strainer Hi dP:
EK-1132, SERVICE WATER PUMP P7A BASKET STR HI dP
May check running amps for P-7A SRO RO Implement actions of EK-1132:
Start Standby Service Water Pump.
Then stop P-7A.
May locally check basket strainer dP.
(If local check of basket strainer is requested, Simulator Operator will report a high reading.) After local report of high reading, above actions will be implemented.
SRO May refer to ONP-6.1, Loss of Service Water, but this is not required.
SRO Refers to Tech. Spec. 3.7.8. Service Water Pump is NOT inoperable.
SRO Initiates troubleshooting/repair.
palisades nuclear plant Page 9 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
1 Event No.:
5 Page _1_ of _1_
Event
Description:
Main Steam Flow Transmitter FT-0702 fails low Time Position Applicant's Actions or Behavior SRO RO BOP Diagnoses failure of steam flow transmitter FT-0702 on A S/G
Steam flow lower than feed flow
CV-0701 closing to lower feed flow
Feed pump speed lowering
SG A level lowering
SG B level lowering, then restoring to normal as CV-0703 opens SRO Enter and direct the actions of ONP-3, "Loss of Main Feedwater" BOP
Take manual control of CV-0701 and feed pumps, if needed, to maintain S/G levels at program.
CRITICAL STEP to establish steam generator level control prior to Reactor Trip BOP Monitor feed/steam flow.
SRO Initiates troubleshooting and repair.
palisades nuclear plant Page 10 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
1 Event No.:
6 Page _1_ of _3_
Event
Description:
Feedwater Line Rupture (outside Containment)
Time Position Applicant's Actions or Behavior SRO BOP RO Diagnose feedwater line rupture:
S/G levels lowering (possible low level alarms)
EK-1354, TURBINE FLR SUMP HI LEVEL
EK-0171, CONDENSATE PUMP ROOM FLOODING
EK-0967, LOOP 1 LOOP 2 TAVE DEVIATION SRO BOP May dispatch AO to Turbine Bldg. sump to check level.
SRO Enter ONP-3, Loss of Main Feedwater as a precaution, but no actions directly apply.
SRO BOP RO Diagnose that, based on Condensate Pump Room Flooding alarm, a manual reactor trip is required.
SRO Orders a manual Reactor trip, tripping of both Condensate Pumps, and enters and directs the actions of EOP-1.0.
NOTE: Next malfunction (stuck open PZR spray) entered at trip.
RO Determines Reactivity Control is MET.
BOP Control the Feedwater System:
Places all operating MFPs to manual and ramp one to minimum speed.
As Tave lowers toward 525ºF, ramps second MFP to minimum speed.
Closes ALL MFRVs and Bypass FRVs.
CRITICAL TASK to prevent PCS overcooling.
palisades nuclear plant Page 11 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
1 Event No.:
6 Page _2_ of _3_
Event
Description:
Feedwater Line Rupture (outside Containment) (including Event 7, Stuck Open PZR Spray Valve)
Time Position Applicant's Actions or Behavior BOP Determines Vital Auxiliaries - Electric acceptance criteria all MET.
RO Determines that PCS Inventory Control acceptance criteria are MET.
RO Diagnoses stuck open PZR spray valve and closes valve, and reports condition to CRS.
PCS Pressure Control acceptance criteria are met.
RO Determines Core Heat Removal acceptance criteria are met.
RO BOP Determine that PCS Heat Removal acceptance criteria are met.
RO BOP Determine that Containment Isolation acceptance criteria.
RO BOP Determine that Containment Atmosphere acceptance criteria are met.
RO Determines that Vital Auxiliaries - Water acceptance criteria are met.
RO Determines that Vital Auxiliaries - Air acceptance criteria are met.
BOP RO BOP turns panels over to RO and reports to CRS.
palisades nuclear plant Page 12 of 52 July 2003
palisades nuclear plant Page 13 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
1 Event No.:
6 Page _3_ of _3_
Event
Description:
Feedwater Line Rupture (outside Containment)
Time Position Applicant's Actions or Behavior SRO BOP Align Control Room HVAC to Emergency Mode within 20 minutes of reactor trip.
SRO Directs closing of both MSIVs (due to no Condensate Pumps operating), and ensure both Main Feedwater Pumps are tripped.
SRO BOP Assigns/performs Emergency Shutdown Checklist per GOP-10.
SRO Refers to EOP-1.0, Attachment 1, "Event Diagnostic Flow Chart" and diagnoses the event.
SRO Transitions to EOP-2.0, "Reactor Trip Recovery" due to all acceptance criteria being met.
SRO Assigns performance of EOP-2.0 Safety Function Status Checks to STA individual.
Note:
Condensate Storage Tank malfunction entered here.
palisades nuclear plant Page 14 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
1 Event No.:
8 Page _1_ of _2__
Event
Description:
Condensate Storage Tank Ruptures Time Position Applicant's Actions or Behavior SRO BOP RO Diagnoses Condensate Storage Tank rupture:
EK-1108, CONDENSATE STORAGE TANK T-2 HI-LO LEVEL Note:
Crew may dispatch an AO to investigate.
SRO Re-enters EOP-1.0 Diagnostic Flow Chart and diagnoses a Loss of All Feedwater, EOP-7.0.
SRO Assigns EOP-7.0 Safety Function Status Checks to STA.
SRO RO Stops all Primary Coolant Pumps.
CRITICAL TASK RO Commence emergency boration.
SRO BOP Conserve S/G inventory by closing ALL S/G blowdown valves:
'A' S/G '
B' S/G CV-0767 CV-0768 CV-0771 CV-0770 CV-0739 CV-0738 RO Since Primary Coolant Pumps are off, may need to use Auxiliary Spray to control Pressurizer pressure (requires a key).
palisades nuclear plant Page 15 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
1 Event No.:
8 Page _2__ of _2__
Event
Description:
Condensate Storage Tank Ruptures Time Position Applicant's Actions or Behavior SRO Evaluates feedwater options and determines Aux. FW from Service Water via P-8C (or P-8A) should be used.
NOTE: Cannot use Main FW option because of no steam available to operate steam driven FW pp. (MSIVs are closed.)
SRO Direct performance of EOP Supplement 31 for supplying AFW P-8C from Service Water.
RO Place P-8C Start Select Switch to Manual.
SRO BOP Direct AO to perform SW lineup to P-8C.
RO When lineup is complete, reset Low Suction Pressure Trip, if required (take P-8C handswitch to TRIP).
SRO RO Monitor S/G levels. When @ ~ -75%, start P-8C to feed both S/Gs to restore levels to 60-70%.
END SCENARIO WHEN FEED FLOW IS ESTABLISHED.
Appendix D Scenario Outline Form ES-D-1 (R8, S1)
palisades nuclear plant Page 16 of 52 July 2003 Facility: PALISADES Scenario No.: 2 Op-Test No.: _______
Examiners:
Operators:
Initial Conditions:
Approx. 87% power, MOL; P-66B HPSI Pump tagged out. Aux. Spray CV-2117 is tagged out.
Turnover:
Approx. 87% power, EOL. P-66B HPSI pump is out of service for pump alignment and should be restored to service in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Aux. Spray CV-2117 is also inoperable due to a wiring problem with the handswitch.
Boron concentration is 333 ppm. A Power Control request to adjust reactive loading on the Main Generator has been approved and Shift Orders are to first raise VARs OUT by 30 MVARs. Then continue raising power at 4% per hour.
Event No.
Malf.
No.
Event Type*
Event Description 1
NA SRO (N)
BOP (N)
Adjust reactive loading on Main Generator 2
NA SRO (N)
RO (R)
BOP (N)
Raise power 3
CV05 SRO (C)
RO (C)
Loss of Letdown Pressure Control high 4
RP11D SRO (I)
BOP (I)
Power Range Safety Channel (8) Power Failure 5
RX05B SRO (I)
RO (I)
PZR Pressure Control Fail High (Channel B) 6 TU01 SRO (C)
BOP (C)
Main Turbine High Vibration (requires trip) 7 OVRD ED12B SRO (C)
BOP (C)
De-energization of Bus 1D / D/G 1-2 does not AUTO start 8
MS06A SRO (M)
BOP (M)
RO (M)
Steam Generator A Code Safety fail open (1) 9 SG01B SRO (C)
BOP (C)
RO (C)
Steam Generator B Tube Leak / Rupture 10 SW10A SW10C SRO (C)
RO (C)
Bus 1D powered SW pumps do not sequence on.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
palisades nuclear plant Page 17 of 52 July 2003 Scenario 2 - Simulator Operator Instructions
Reset to IC 86.9% MOL (Turbine Valve Testing).
Tagout Aux Spray CV-2117
Aux Spray is OOS, with a caution tag hung on the hand switch
- OVRD DI CV-2117 H/S OFF
- OVRD LO CV-2117-G, CV-2117 GREEN light OFF
- OVRD LO CV-2117-R, CV-2117 RED light OFF
HPSI Pump P-66B is OOS, with a caution tag hung on the hand switch
- REMOTE SI24 RACKOUT
INSERT ED12B to ACTIVE (D/G 1-2 fail to auto start)
INSERT SW10A, SW10C to ACTIVE (to prevent SW pps. auto start)
Info Only: During validation the following turbine vibration readings were noted just prior to the crew manually tripping the plant:
- 3 bearing = 7.1 mils
- 4 = 12.8 mils
- 5 = off-scale hi
- 6 = 11.3 Event No.
Simulator Operator Instruction 3
REMOTE 1 INSERT CV05 (LD Press. Fail High) to ACTIVE 4
REMOTE 2 INSERT RP-11D (PWR Range NI Power Supp. Failure) to ACTIVE 5
REMOTE 3 INSERT RX05B (PPCS fail Hi) to ACTIVE 6
REMOTE 4 INSERT TU01 (Main Turb Hi Vibe) Severity = 100% Ramp = 5 min If asked as AO to report readings from Bentley-Nevada panel, access information at instructor station to report actual readings.
REMOTE 5 INSERT OVRD 152-203-1 (S/P Incoming) to ON (trips Bus 1D) 8 REMOTE 6 INSERT MS06A (S/G Code Safety leak) Severity = 100% No ramp.
(sometime after Bus 1D restored) 9 REMOTE 7 INSERT SG01B (SGTR) @70% Ramp = 5 minutes (insert after transition to EOP-6.0) 10 SW10A and SW10C (ACTIVE AT SETUP)
Bus 1D powered Service Water Pps. do not sequence back on after restoration of Bus 1D.
In this scenario there was an overload trip alarm in for P-7A. Per the C+E Manual this should not occur. May need to OVRD the alarm off.
palisades nuclear plant Page 18 of 52 July 2003 Scenario 2 - Shift Turnover Approx. 87% power, EOL. P-66B HPSI pump is out of service for pump alignment and should be restored to service in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Aux. Spray CV-2117 is also inoperable due to a wiring problem with the handswitch.
Boron concentration is 333 ppm. A Power Control request to adjust reactive loading on the Main Generator has been approved and Shift Orders are to first raise VARs OUT by 30 MVARs. Then continue raising power at 4% per hour.
palisades nuclear plant Page 19 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
2 Event No.:
1 Page _1_ of _1_
Event
Description:
Adjust Reactive Loading on Main Generator Time Position Applicant's Actions or Behavior BOP Operates AC Adjuster to raise excitation and increase VARS OUT by 30 MVARS.
BOP May refer to SOP-8 (not required); monitors Main Generator terminal voltage during the adjustment.
SRO BOP Notifies Power Control that requested adjustment has been made.
palisades nuclear plant Page 20 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
2 Event No.:
2 Page _1_ of _1_
Event
Description:
Raise Power Time Position Applicant's Actions or Behavior SRO Enters and directs the actions of GOP-5.
SRO Reviews GOP-5 Precautions and Limitations with crew.
SRO May discuss ASI control strategy.
Note: Various techniques may be used for the power ascension, (e.g., start with a 50 gal. dilution and follow with a 100 gal. dilution).
BOP Selects DEH rate at 4% per hour.
BOP RO Continue power escalation as directed by SRO.
BOP RO Monitor Tave and Tref BOP Initiates GO on DEH control for Main Turbine.
palisades nuclear plant Page 21 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
2 Event No.:
3 Page _1_ of _1_
Event
Description:
Loss of Letdown Pressure Control HIGH Time Position Applicant's Actions or Behavior RO Diagnoses failure of the intermediate letdown pressure controller
Selected intermediate letdown pressure control valve opens.
Flashing in the Letdown Heat Exchanger, resulting in pressure and flow oscillations on the letdown line.
EK-0704, LETDOWN HT EX TUBE INLET HI-LO PRESS, alarms.
SRO Enters and directs the actions of EK-0704.
RO Determines charging and letdown flows NOT matched.
RO Determines Letdown Pressure Controller PIC-0202 NOT controlling at approximately 460 psig.
RO Selects manual on the pressure controller.
RO Manually repositions selected valve to control pressure at approximately 460 psig.
SRO Initiates troubleshooting and repairs.
palisades nuclear plant Page 22 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
2 Event No.:
4 Page _1_ of _2_
Event
Description:
Power Range Safety Channel (8) Power Failure Time Position Applicant's Actions or Behavior ALL Diagnose failure of NI-08:
NI-008 detector voltage indicates 0 VDC
Alarms:
- EK-0948, DROPPED ROD
- EK-06 C03, CHANNEL DEVIATION LEVEL 1 5%
C04, CHANNEL DEVIATION LEVEL 2 10%
C07, DROPPED ROD C08, NI CHANNEL TROUBLE
- TMM Channel D NI indicates 0
- NI-008 Upper and Lower indicate 0% power SRO Enter and direct the actions of various ARPs SRO Refer to SOP-35 for removing a Power Range NI from service.
palisades nuclear plant Page 23 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
2 Event No.:
4 Page _2_ of _2_
Event
Description:
Power Range Safety Channel (8) Power Failure Time Position Applicant's Actions or Behavior SRO Refer to EM-04-02 to monitor Quadrant Power Tilt (or call Rx Engineer).
SRO Verify Incore Monitoring System operable for monitoring LHR (or call Rx Engineer).
BOP Bypass the Variable High Power Trip, the TM/LP Trip, the High Power Rate Trip and Loss of Load Trips per SOP-36 1.
Insert bypass key above affected RPS Trip Unit.
2.
Turn key 90º clockwise.
3.
Verify lit yellow light above bypass keyswitch.
4.
Log evolution in the Reactor Logbook SRO Declare inoperable the following:
Channel D Flux - delta T Power Comparator
ASI alarm function of Thermal Margin Monitor D Channel RO BOP Monitor and log the "Power Density" status of the remaining operable TMM channels hourly.
SRO Initiate troubleshooting and repairs SRO Refers to various Tech. Specs:
T.S. 3.2.1 for LHR - No action as long as Incore System is operable.
T.S. 3.3.1 - Actions A.1, B.1, C.1 apply
ORM 3.17.6, Action 12.1.a applies.
ORM 3.17.6, Action 16 applies.
May also refer to ORM 3.11.1, 3.11.2.
palisades nuclear plant Page 24 of 52 July 2003
palisades nuclear plant Page 25 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
2 Event No.:
5 Page _1_ of _1_
Event
Description:
PZR Pressure Control Fail High (Channel B)
Time Position Applicant's Actions or Behavior RO Diagnoses high failure of pressurizer pressure controlling channel
EK-0753, PRESSURIZER PRESSURE OFF NORMAL HI-LO, alarms
Spray valves open
Proportional heaters off
Pressurizer pressure lowers
PIA-0101B indicating high SRO Enters and directs the actions of ARP-4 and ONP-18 RO Takes manual control of PPCS controller 'A' or alternates Pressurizer pressure controllers per SOP-1 SRO Initiates troubleshooting and repairs
palisades nuclear plant Page 26 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
2 Event No.:
6 Page _1_ of _2_
Event
Description:
Main Turbine High Vibration Time Position Applicant's Actions or Behavior SRO BOP Diagnose high vibration on turbine
EK-0105, TURBINE HIGH VIBRATION
Indications on Control Room vibration recorders NOTE: If AO is sent to verify vibration, report that Control Board vibration readings are correct.
SRO Enter and direct the action of EK-0105 BOP Checks normal indications on:
- Bearing oil temperature
- Eccentricity
- Differential expansion
- Generator frequency
- Feedwater heater levels SRO Determine plant trip required due to vibration level and orders reactor trip NOTE: May first determine that level is between 10-14 mils and commence a plant shutdown per GOP-8. This is acceptable if a trip is directed when vibration exceeds 14 mils with reactor power above 15%.
RO BOP Trips the reactor as directed INSERT Bus 1D de-energizes at time of Reactor trip.
palisades nuclear plant Page 27 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
2 Event No.:
6 Page _2_ of _2_
Event
Description:
Main Turbine High Vibration Time Position Applicant's Actions or Behavior SRO Enters and directs the actions of EOP-1.0 RO Determine that Reactivity Control acceptance criteria are MET.
BOP Control the Feedwater System:
Places all operating MFPs to manual and ramp one to minimum speed.
As Tave lowers toward 525ºF, ramps second MFP to minimum speed.
Closes ALL MFRVs and Bypass FRVs.
CRITICAL TASK to prevent PCS overcooling.
BOP (EVENT 7) Determine Vital Auxiliaries - Electric acceptance criteria are NOT met:
Bus 1D is NOT energized.
D/G 1-2 did NOT auto start.
BOP Take prescribed contingency action for Vital Auxiliaries - Electric:
Manually start D/G 1-2.
Ensure D/G breaker 152-213 is closed.
(Note: D/G breaker will close and loads will sequence on EXCEPT for Service Water Pumps P-7A and P-7C.)
EVENT 8 - ENTER "A" S/G Code Safety Fails Open HERE.
palisades nuclear plant Page 28 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
2 Event No.:
8 Page _1_ of _4_
Event
Description:
Steam Generator "A" Code Safety (1) Fail Open Time Position Applicant's Actions or Behavior RO Determine PCS Inventory Control acceptance criteria are MET.
RO Verifies status of PCS Pressure Control acceptance criteria.
If SIAS has occurred due to effects of "A" S/G code safety open, verifies SIAS.
Otherwise, acceptance criteria are MET.
RO Determines Core Heat Removal acceptance criteria are MET.
RO Verifies status of PCS Heat Removal acceptance criteria:
May see effects of "A" S/G code safety open (audible noise, Tave lowering, S/G level, PZR pressure, etc.
If these efffects are not noticeable yet, RO will note acceptance criteria as being MET.
BOP If either S/G pressure is less than 800 psia:
Ensure Turbine Bypass Valve closed.
Ensure ADVs are closed.
Close both MSIVs.
Recommend isolating AFW to "A" S/G.
RO BOP Determine that Containment Isolation acceptance criteria are MET.
RO Determine that Containment Atmosphere acceptance criteria are MET.
palisades nuclear plant Page 29 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
2 Event No.:
8 Page _2_ of _4_
Event
Description:
Steam Generator "A" Code Safety (1) Fail Open Time Position Applicant's Actions or Behavior RO Determine Vital Auxiliaries - Water acceptance criteria are NOT met.
RO Take prescribed contingency action for Vital Auxiliaries - Water:
Manually start SW pumps P-7A and P-7B.
RO Determine that Vital Auxiliaries - Air acceptance criteria are MET.
BOP RO BOP turns panels over to RO and reports to SRO.
SRO BOP Align Control Room HVAC to Emergency Mode within 20 minutes of Reactor trip.
SRO Verifies at least ONE Condensate Pump and ONE Cooling Tower Pump operating.
SRO BOP If SIAS has initiated, assign/perform EOP Supplement 5 for SIAS Checklist.
SRO BOP Assign/perform Emergency Shutdown Checklist per GOP-10.
palisades nuclear plant Page 30 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
2 Event No.:
8 Page _3_ of _4_
Event
Description:
Steam Generator "A" Code Safety (1) Fail Open Time Position Applicant's Actions or Behavior RO If both MSIVs are closed, trip BOTH Main Feed Pps.
SRO Refers to EOP-1.0, Attachment 1, "Event Diagnostic Flow Chart" and diagnoses the event.
SRO Transitions to EOP-6.0, Excess Steam Demand Event".
SRO Assigns performance of EOP-6.0 Safety Function Status Checks to STA.
SRO RO If Letdown Orifice Stop Valves are closed, place:
HS-2003
HS-2004
HS-2005 to CLOSE.
RO If PZR pressure lowers to less than 1300 psia, trip ONE PCP in each loop.
RO If PCS subcooling less than 25ºF, trip ALL PCPs.
RO Commence / verify emergency boration.
(Note: Should already have auto initiated due to SIAS.)
ENTER EVENT 9 ("B" S/G Tube Rupture) after first round of SFSCs are completed SAT.
palisades nuclear plant Page 31 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
2 Event No.:
8 Page _4_ of _4_
Event
Description:
Steam Generator "A" Code Safety (1) Fail Open Time Position Applicant's Actions or Behavior SRO Determines affected S/G as "A" and initiates EOP Supplement 17 for S/G isolation.
Actions Outside Control Room Close MV-MS103, MV-MS101 (preferred)
Close MV-CA781, MV-CA782 (alternate)
Actions Inside Control Room Ensure both MSIVs closed.
Ensure MV-0510 closed (MSIV bypass)
Close CV-0701, Main Feed Reg Close CV-0742 Main Feed Reg Block (keyswitch)
Close CV-0735, Bypass Feed Reg "A" S/G Blowdown Valves: CV-0767, CV-0771, CV-0739 "A" S/G AFW FCVs: CV-0737, CV-0737A, CV-0749 Close CV-0522B (P-8B AFW Pp. steam supply)
palisades nuclear plant Page 32 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
2 Event No.:
9 Page _1_ of _2_
Event
Description:
Steam Generator "B" Tube Rupture Time Position Applicant's Actions or Behavior ALL Diagnose Steam Generator "B" Tube Leak/Rupture:
"B" S/G level rising.
PZR pressure and level respond accordingly SRO Transitions to EOP-9.0, "Functional Recovery Procedure" due to more than one faulted S/G.
SRO Direct performance of Section 4.0, Operator Actions.
BOP RO Close CWRT Vent Valves: CV-1064, CV-1065.
BOP Place one Hydrogen Monitor in operation, with key switch in "ACCI", per SOP-38.
palisades nuclear plant Page 33 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
2 Event No.:
9 Page _2_ of _2_
Event
Description:
Steam Generator "B" Tube Rupture Time Position Applicant's Actions or Behavior SRO Identifies Success Paths for satisfying each safety function.
(Note: Candidate must be able to justify selection if it does not agree with below list suggested by validators.)
RC-3
MVAE DC-1, AC-2
IC-2
PC-3
HR-2
CI-1
CA-1
MVAW-1
MVAA-1 SRO Direct actions of HR-2 (highest jeopardized safety function) and direct a cooldown via steaming of least affected S/G.
CRITICAL TASK END OF SCENARIO
palisades nuclear plant Page 34 of 52 July 2003 Appendix D Scenario Outline Form ES-D-1 (R8, S1)
Facility: PALISADES Scenario No.: 3 Op-Test No.: _______
Examiners:
Operators:
Initial Conditions:
100% power, EOL, P-66B HPSI tagged out for bearing inspection.
Turnover:
Shift orders are to commence a power reduction at 20% per hour for refueling outage.
GOP-8 has been completed up to Att.1, Step 2.0. Crew begins there for the power reduction.
Event No.
Malf.
No.
Event Type*
Event Description 1
NA SRO (N)
BOP (N)
Setup Main Turbine DEH controls 2
NA SRO (N)
RO (R)
BOP (N)
Power reduction 3
IA04C SRO (C)
RO (C)
Plant Air Compressor C-2C trips (requires realignment) 4 CV06 SRO (I)
RO (I)
Letdown pressure demand fails low 5
OVRD SRO (C)
BOP (C)
Turbine bypass valve fails partial open (isolatable) 6 RX10C SRO (I)
BOP (I)
S/G Level Transmitter LT-0703 fails high 7
RC21 SRO (M)
BOP (M)
RO (M)
PZR PRV fails open (~1%), then full open (100%)
8 TC02 SRO (C)
BOP (C)
Main Turbine fails to auto trip 9
SI09A SRO (C)
RO (C)
P-66A HPSI fails to auto start
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
palisades nuclear plant Page 35 of 52 July 2003 Scenario 3 - Simulator Operator Instructions
100% EOL
ENSURE C-2A and C-2C in service.
INSERT OVRD C-2B handswitch OFF to prevent auto or manual start.
ENSURE HPSI Pump P-66B is OOS, with a caution tag hung on the hand switch
- REMOTE SI24 RACKOUT
INSERT TC02 to ACTIVE (turb fails to auto trip)
INSERT SI09A to ACTIVE (P-66A HPSI fails to auto start)
Event No.
Simulator Operator Instruction 3
REMOTE 1 INSERT IA04C (C-2C trips) 4 REMOTE 2 INSERT CV06 (LD Press. Fail Low) 5 REMOTE 3 Setup for TBV Fails Open:
1.
CV-0511 Man PB:
- PIC-0511-MAN to ON
- PIC-0511-M light to OFF
- PIC-0511-A Auto lamp to ON
- PIC-0511-MNC-2 to ON
- PIC-0511-MAN [ZD13P(717)]
2.
Trigger #6 Go to Event _______
- type in ZDI3P(717)
- Action is dor pic-0511-MNC-2 3.
Trigger #7
- zdi 3p(717)
- dor pic-0511-m 4.
Trigger #8
- zdi 3p(717)
- dor pic-0511-a 6
REMOTE 4 INSERT RX10C (SG LT-0703) Value = 70%. No ramp.
7 REMOTE 5 INSERT RC21 (RV-1040 leak) Value = 1%. Ramp = 10 minutes.
(PRV Temperature alarms @ ~1%)
7 REMOTE 9 After crew diagnoses PORV weeping, CHANGE value of RC21 to 100%.
Crew Trips the Reactor 8
TC02 (Main Turb Fail to Auto Trip) (ACTIVE AT SETUP) 9 SI09A (HPSI Fail to Auto Start) (ACTIVE SETUP) 1.
If dispatched to check PZR Shed Fans, report ALL 3 fans running. (V-61A/B/C.)
palisades nuclear plant Page 36 of 52 July 2003 Scenario 3 - Shift Turnover 100% power, EOL, P-66B HPSI tagged out for bearing inspection.
Shift orders are to commence a power reduction at 20% per hour for refueling outage.
You are to start the power reduction at Step 2.0 of GOP-8, Attachment 1. All steps up to Step 2.0 have been completed.
palisades nuclear plant Page 37 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
3 Event No.:
1 Page _1_ of _1_
Event
Description:
Setup Main Turbine DEH Controls Time Position Applicant's Actions or Behavior BOP Ensure DEH is in Operator Auto:
Observe GREEN "Operator Auto" message on CRT screen.
BOP Sets LOAD and RATE values:
Press CONTROL SETPOINT on DISPLAYS keypad.
ENTER Setter value (as desired).
Press SELECT.
Press TAB to move cursor to "RATE" field.
Enter RATE as 20% per hour.
Press SELECT.
palisades nuclear plant Page 38 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
3 Event No.:
2 Page _1_ of _1_
Event
Description:
Power Reduction Time Position Applicant's Actions or Behavior SRO Review Precautions and Limitations of GOP-8 with crew.
(Note: This may already have been performed at pre-job brief.)
RO Commence boration / rod insertion (as determined in pre-job brief).
BOP Press GO on Main Turbine DEH control.
BOP RO Monitor Tave and Tref as power lowers.
palisades nuclear plant Page 39 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
3 Event No.:
3 Page _1_ of _1_
Event
Description:
Air Compressor C-2C Trips Time Position Applicant's Actions or Behavior SRO RO Diagnose C-2C trip:
EK-1104, AIR COMPRESSORS C2A, C2B, C2C TRIP, alarms.
EK-1102, INSTRUMENT AIR LO PRESS, may alarm.
RO Attempt manual start of Standby air compressor (C-2B). Inform SRO it will NOT start.
SRO Enter and direct actions of ONP-7.1, "Loss of Instrument Air".
SRO RO Crosstie to FWP Air System:
Open Air from Feedwater Purity CV-1221.
RO Diagnose that Instrument Air System pressure is restoring.
SRO BOP May dispatch an AO to monitor C-903A/B FWP air compressors.
SRO Complete and exit ONP-7.1 Note: There are no Tech. Specs. for air compressors.
palisades nuclear plant Page 40 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
3 Event No.:
4 Page _1_ of _1_
Event
Description:
Letdown Pressure Controller Demand Fails Low Time Position Applicant's Actions or Behavior RO Diagnose failure of Letdown Pressure controller (PIC-0202):
Selected Letdown Pressure Control valve fails CLOSED.
EK-0703, Letdown Ht Ex Tube Inlet Hi-Lo Press, alarms.
EK-0702, Relief Valve 2006 Disch Hi Temp, alarms.
SRO RO Enter and perform actions per the above alarm response procedures.
RO Determine charging and letdown flows are NOT matched.
RO Determine PIC-0202 NOT controlling at 460 psig.
RO Select MANUAL on PIC-0202 and manually adjust selected backpressure CV to control letdown pressure at ~460 psig.
SRO Initiate troubleshooting and repair.
SRO RO Diagnose RV-2006 reseats.
SRO Refer to Tech. Spec. 3.4.13 for PCS Leakage.
Determine a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> completion time for reducing leakage to within limits.
palisades nuclear plant Page 41 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
3 Event No.:
5 Page _1_ of _1_
Event
Description:
Turbine Bypass Valve Fails Partially Open Time Position Applicant's Actions or Behavior ALL Diagnose Turbine Bypass Valve has failed open:
Various alarms, including:
EK-0603, Nuclear Power / delta T BOP Manually close the TBV.
Note: Candidate is allowed to perform prior to ONP entry, but is not required to.
SRO Enter and direct the actions of ONP-9.0, Excessive Load Increase".
SRO BOP Reduce turbine load to restore reactor power to pre-event power level or less.
Note:
Not required if TBV has been manually closed.
palisades nuclear plant Page 42 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
3 Event No.:
6 Page _1__ of _1_
Event
Description:
S/G Level Transmitter LT-0703 Fails High Time Position Applicant's Actions or Behavior BOP Diagnose failure of feed flow transmitter LT-0703 on "B" S/G:
Feed flow lower than steam flow.
"B" S/G level lowering.
Heat Balance power lowering.
SRO Enter and direct actions of ONP-3, "Loss of Main Feedwater".
BOP Take manual control of CV-0703 and Main FW pumps, as needed, to stabilize/restore S/G level.
SRO Initiate troubleshooting and repair.
palisades nuclear plant Page 43 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
3 Event No.:
7 Page _1_ of _6_
Event
Description:
PZR PRV Fails Open (~1%), then FULL Open Time Position Applicant's Actions or Behavior ALL Diagnose a leaking/weeping PRV:
EK-0745, Pressurizer Safety Valve RV-1040 Disch Hi Temp, alarms.
Check Quench Tank parameters for indication of PRV discharge.
SRO Enter and direct actions of ONP-23.1, "Primary Coolant Leak".
RO Close CWRT Vent Valves, CV-1064 and CV-1065.
NOTE:
Once crew has diagnosed that RV-1040 is leaking, RAISE leak severity to 100%.
ALL Determine leak rate is significantly HIGHER:
Exceeds 20 gpm (Reactor trip criteria).
RO Manually trip reactor.
ALL Enter EOP-1.0, "Standard Post Trip Actions" and carry out Immediate Actions.
palisades nuclear plant Page 44 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
3 Event No.:
8 Page _1_ of _1_
Event
Description:
Main Turbine Fails to Auto Trip Time Position Applicant's Actions or Behavior SRO BOP Diagnose failure of Main Turbine to auto trip:
Governor valve position indicators.
Steam Generator pressure lowering.
PCS cooldown and depressurization.
BOP Trip the Main Turbine using MSIV closure.
Continue with Event 7, page 2 on next page.
palisades nuclear plant Page 45 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
3 Event No.:
7 Page _2_ of _6_
Event
Description:
PZR PRV Fails Open (~1%), then FULL Open Time Position Applicant's Actions or Behavior RO Determine that Reactivity Control is MET.
BOP Control the Feedwater System:
Places all operating MFPs to manual and ramp one to minimum speed.
As Tave lowers toward 525ºF, ramps second MFP to minimum speed.
Closes ALL MFRVs and Bypass FRVs.
CRITICAL TASK to prevent PCS overcooling.
BOP Determine that Vital Auxiliaries - Electrical acceptance criteria are MET.
RO Determine that PCS Inventory Control acceptance criteria are MET.
(may not be met, depending on progress of event).
RO Determine that PCS Pressure Control acceptance criteria are NOT met.
If PZR pressure is less than 1605 psia:
Verify SIAS initiated per EK-1342.
___ Ensure all available HPSI and LPSI pumps operating with loop valves OPEN.
palisades nuclear plant Page 46 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
3 Event No.:
9 Page _1_ of _1_
Event
Description:
P-66A HPSI Fails to Auto Start Time Position Applicant's Actions or Behavior RO Observe that P-66A HPSI pump has NOT started.
RO Inform SRO and manually start P-66A HPSI pump.
Continue with Event 7, page 3 on next page.
palisades nuclear plant Page 47 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
3 Event No.:
7 Page _3_ of _6_
Event
Description:
PZR PRV Fails Open (~1%), then FULL Open Time Position Applicant's Actions or Behavior RO If PZR pressure is less than 1300 psia, STOP PCPs to have one in each loop operating.
RO Determine that Core Heat Removal acceptance criteria are MET.
(may not be, depending on progress of event).
BOP RO Determine that PCS Heat Removal acceptance criteria are MET.
BOP RO Determine that Containment Isolation acceptance criteria are NOT met.
(due to Containment pressure > 0.85 psig)
RO Determine that Containment Atmosphere acceptance criteria are NOT met.
(due to Containment pressure > 0.85 psig)
RO Take prescribed Contingency Actions for Containment Atmosphere:
If SIAS not present, check ALL Containment Air Cooler fans operating.
Open CAC hi cap outlet valves as Service Water capacity permits.
palisades nuclear plant Page 48 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
3 Event No.:
7 Page _4_ of _6_
Event
Description:
PZR PRV Fails Open (~1%), then FULL Open Time Position Applicant's Actions or Behavior RO Determine that Vital Auxiliaries - Water acceptance criteria are MET.
RO Determine that Vital Auxiliaries - Air acceptance criteria are MET.
BOP RO BOP turns panels over to RO and reports to SRO.
SRO BOP Align Control Room HVAC to Emergency Mode within 20 minutes of reactor trip.
SRO RO Verify at least ONE Condensate Pump and ONE Cooling Tower Pump operating.
SRO BOP Perform EOP Supplement 5 for SIAS Checklist.
SRO BOP If CHP/CHR has initiated, perform EOP Supplement 6 for Containment Isolation Checklist.
SRO BOP Perform Emergency Shutdown Checklist per GOP-10.
palisades nuclear plant Page 49 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
3 Event No.:
7 Page _5_ of _6_
Event
Description:
PZR PRV Fails Open (~1%), then FULL Open Time Position Applicant's Actions or Behavior BOP or RO Trip both Main Feed Pumps (since MSIVs have been closed).
SRO Refer to EOP-1.0, Attachment 1, "Event Diagnostic Flow Chart" and diagnose the event.
SRO Transition to EOP-4.0, "Loss of Coolant Accident Recovery".
SRO Assign performance of EOP-4.0 Safety Function Status Checks to STA.
SRO BOP Verify at least minimum SI flow per EOP Supplement 4.
SRO RO If Letdown Orifice Stop Valves are closed, place:
HS-2003
HS-2004
HS-2005 to CLOSE.
RO If PCS is less than 25ºF subcooled, stop ALL PCPs.
palisades nuclear plant Page 50 of 52 July 2003
palisades nuclear plant Page 51 of 52 July 2003 Appendix D Operator Actions Form ES-D-2 (R8, S1)
Op-Test No.:
Scenario No.:
3 Event No.:
7 Page _6_ of _6_
Event
Description:
PZR PRV Fails Open (~1%), then FULL Open Time Position Applicant's Actions or Behavior ALL Attempt to isolate LOCA:
Verify PORVs closed.
Letdown Stop Valves closed (CV-2001, CV-2009)
Ensure closed PCS Sample Valves, CV-1910, CV-1911.
Ensure closed Reactor vessel and PZR vent valves.
SRO BOP Place one Hydrogen Monitor in operation with keyswitch in "ACCI", per SOP-38.
SRO BOP If Containment pressure is > 4.0 psig:
Verify CIS initiated (EK-1126 alarmed).
Perform EOP Supplement 6 (if not previously performed).
Verify adequate Containment Spray flow.
Ensure at least one CAC accident fan operating ("A" fan).
SRO RO Verify emergency boration in progress.
(Should be, since SIAS has initiated.)
SRO BOP Commence a controlled PCS cooldown.
SRO RO Determine PCS existing cooldown rate, per EOP Supplement 33.
SRO RO When PCS cooldown rate is within limits, start a controlled cooldown using Turbine Bypass Valve. (May use ADVs).
CRITICAL TASK
palisades nuclear plant Page 52 of 52 July 2003 END OF SCENARIO