ML091520347
| ML091520347 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/07/2008 |
| From: | NRC/RGN-III |
| To: | Entergy Nuclear Palisades |
| Shared Package | |
| ML082200311 | List: |
| References | |
| Download: ML091520347 (16) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility: PALISADES Scenario No.: TWO Op-Test No.: 1 Examiners: _________________________ Operators: ____________________________
Initial Conditions: 25% power.
Turnover: The plant is at approximately 25% power MOL following a startup from a forced outage. The Turbine Drain Valves are closed per SOP-8. A Chemistry hold has just been lifted with S/G chemistry within specifications. GCL-5.1, Power Escalation in Mode 1, has been completed through Step 2.12f. Shift orders are to place DEH Speed Loop to OUT and commence a power escalation to full power at 8%/hour.
Event No.
Malf. No.
Event Type*
Event Description 1
N/A BOP (N)
Place DEH Speed Loop to OUT 2
N/A SRO (N)
RO (R)
BOP (N)
Power escalation 3
RP11D SRO (I)
BOP (I)
Power Range NI-08 fails 4
SW04B SRO (C)
RO (C)
P-7B, Service Water Pump, trips, STANDBY SW pump does not start 5
RC03 SRO (C)
RO (C)
BOP (C)
PCS leak ramps to 50 gpm (requires a plant trip) 6 FW06B BOP(I)
CV-0703, B S/G FRV fails to close 7
SG01B ALL (M)
Steam Generator Tube Rupture on B S/G (initiates at time of trip)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Scenario 2 - Simulator Operator Instructions IC-68 (on tape drive)
ENSURE TAVE is less than TREF INSERT MF SW10C (PIDSW03) P-7C failure to auto start INSERT MF FW16C (PIDFW01) Failure of Aux. FW P-8C (Tagged out)
INSERT DI P-8C-G (PAL04B2) P-8C AFW Pump Green Light OFF (Tagged out)
INSERT DI P-8C-W (PAL04B2) P-8C AFW Pump White Light OFF (Tagged out)
Place Caution Tag on handswitch for P-8C stating Pump tagged out Remote Type Instructions 1
MF RP11D (PIDRPNI3) Loss of NI 8 Power Range Detector (fails low) 2 MF SW04B (PIDSW03) Loss of P-7B Service Water Pump 4
MF RC03 (PIDRC01) Small Coolant Leak, Severity = 15, 4 minute ramp. PCS leak 15 gpm.
Create event trigger 7: Event: Reg Group 1 Rod 21 less than 110 Action: imf rc03 50 (PCS leak goes to 50 gpm at trip)
MF FW06B (PIDFW03) Steam Gen FRV CV-0703 fail, Severity = 23.67. FRV CV-0703 fails as is.
Create event trigger 5: Event: Reg Group 1 Rod 21 less than 110 Action: leave blank MF SG01B (PIDSG01) Steam Gen No.2 Tube Rupture, Severity = 40, 10 minute ramp, 10 minute delay. 400 gpm tube leak.
Create event trigger 6: Event: Reg Group 1 Rod 21 less than 110 Action: leave blank 8
RM MS18 (PIDMS01) Main Steam Dump Manual Valve CA-0779 and MS19 (PIDMS01) Main Steam Dump Manual Valve CA-0780, Remote value =
CLOSED SG10 (PIDMS01) Manual Throttle Vlv MS-102 for CV-0779 and SG12 (PIDMS01) Manual Throttle Vlv MS-104 for CV-0780, Remote value = 0.
Special instructions:
Provide a marked up copy of GCL 5.1 completed through step 2.12f.
Provide Reactivity Sheets for Core Life.
Scenario 2 - Turnover Information The plant is at approximately 25% power MOL following a startup from a forced outage. The Turbine Drain Valves are closed per SOP-8. A Chemistry hold has just been lifted with S/G chemistry within specifications. GCL-5.1, Power Escalation in Mode 1, has been completed through Step 2.12f. Shift orders are to place DEH Speed Loop to OUT and commence a power escalation to full power at 8%/hour.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: TWO Event No.:
1 Page 1 of 1 Event
Description:
Place DEH Speed Loop to Out Time Position Applicant's Actions or Behavior BOP Change status of Speed Feedback Loop:
ENSURE DEH is in HOLD PRESS Feedback Loops on Display keypad MOVE cursor to SPEED feedback loop field PRESS SELECT on numeric keypad PRESS STOP/START on Control Keypad Speed Feedback Loop on DEH should indicate OUT
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: TWO Event No.:
2 Page 1 of 1 Event
Description:
Raise Power Following a Chemistry Hold at 25% Power Time Position Applicant's Actions or Behavior BOP Operates turbine generator on the DEH panel for power escalation @ 8% per hour:
May Set Limiter:
DEPRESS Set Limiter to access Set Limiter Screen PRESSES SELECT PRESS LIMIT RAISE on the keypad ENTERS setter value SELECTS rate of 8% per hour PUSHES GO pushbutton and observes white light illuminate Informs CRS/RO that turbine is in GO RO Performs periodic dilutions and/or control rod manipulations to maintain TAVE within 3°F of TREF For Dilution:
SET quantity and batch flow limit on FIC-0210A, PMW flow controller OPEN CV-2155, Make Up Stop Valve PUSH start pushbutton on FIC-0210A VERIFIES FIC-0210A output signal at zero when dilution complete CLOSES CV-2155 MONITORS reactor power and TAVE For Control Rod manipulations:
WITHDRAWS Group 4 Regulating Rods in increments specified by CRS MONITORS reactor power and TAVE RO May divert CVCS letdown to Clean Waste as VCT level rises:
PLACES CV-2056, Letdown to VCT or Radwaste, in the TO CLEAN WASTE RCVR TANKS position When desired VCT level is achieved, PLACES CV-2056 to the AUTO or TO VOL CNTRL TANK position (then AUTO)
After power has been raised 1%-2% OR at the discretion of the Lead Examiner, INSERT TRIGGER #1.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: TWO Event No.:
3 Page 1 of 2 Event
Description:
Power Range NI-08 Fails Time Position Applicant's Actions or Behavior BOP Diagnose failure of Power Range NI-08:
Indications: NI-08 Lower and Upper power meters read 0%; HI voltage meter reads 0 volts; Rod Drop tell-tale light illuminated Major Alarms: EK-0948, Dropped Rod; EK-06 Rack C Window 3, Channel Deviation Level 1 5%; EK-06 Rack C Window 4, Channel Deviation Level 2 10%; EK-06 Rack C Window 7, Dropped Rod; EK-06 Rack C Window 8, NI Channel Trouble; EK-06 Rack D Window 4, Nuclear T Power Deviation BOP May go to HOLD on the turbine BOP Performs Operator Actions of EK-06 Rack C Windows 3 and 4; If Reactor Power less than 25%:
CHECK Rod positions normal Follow Up Actions:
REMOVE faulty Power Range Nuclear Instrument from service per SOP-35 BOP Performs Operator Actions of EK-06 Rack C Windows 8:
CHECK detector voltage for NI-08 greater than 650 VDC Follow Up Actions:
NI detector voltage less than 650 VDC, REMOVE from service per SOP-35 SRO May reference or enter ONP-5.1, Dropped Rod. ONP-5.1 does not apply Directs removal of NI-08 from service declares Channel D Flux-Delta T Comparator and ASI alarm function of TMM D Channel inoperable Directs monitoring and logging the Power Density status of the remaining operable TMMs hourly Calls Reactor Engineer to assist in Quadrant Power Tilt and Linear Heat Rate with an NI out of service using Incore Detectors
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: TWO Event No.:
3 Page 2 of 2 Event
Description:
Power Range NI-08 Fails Time Position Applicant's Actions or Behavior BOP Removes NI-08 from service per SOP-35, Section 7.2.2:
For D Channel RPS, Place in BYPASS the following the following Trip Units per SOP-36:
Variable High Power Key # 289 High Power Rate Key # 290 TM/LP Key # 297 Loss of Load Key # 298 INSERT bypass key above affected RPS Trip Unit TURN key 90° clockwise VERIFY the yellow light above the bypass keyswitch is ON BOP May RESET Rod Drop Telltale and alarm on Panel C-06:
PUSHES Rod Drop Telltale pushbutton BOP May check the Power Density status (OK) of the remaining operable TMMs (not in tripped)
SRO The following T.S. LCOs apply:
(THESE ARE MOST IMPORTANT) 3.3.1, Action: A.1, VHP and TM/LP, 7 days 3.3.1, Action: B.1, High SUR, Prior to entering MODE 2 from MODE 3 3.3.1, Action: C.1, Loss of Load, Prior to increasing power 17% from MODE 3 (THESE ARE OF LESSER IMPORTANTANCE)
The following ORM, Operating Requirements Manual, items apply:
3.17.6, Item: 12.1, Flux-Delta T Comparator, Prior to next MODE 1 entry from MODE 2 3.17.6, Item: 15, Excore deviation alarm, Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3.17.6, Item: 16, ASI alarm, Prior to next MODE 4 entry from MODE 5 3.11.2, Excores unable to monitor Linear Heat Rate After BOP bypasses RPS trip units on D Channel RPS OR CRS has briefed loss of NI-08 OR at the discretion of the Lead Examiner, INSERT TRIGGER #2.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: TWO Event No.:
4 Page 1 of 1 Event
Description:
P-7B, Service Water Pump, trips (Standby pps do not start)
Time Position Applicant's Actions or Behavior RO Diagnose failure of P-7B:
Indications: P-7B tripped (green light for pump breaker); P-7B amps read 0 amps; SW Critical header pressures read approximately 32#
Major Alarms: EK-1137, Service Water Pump P-7B Overload/Trip; EK-1163, Critical Serv Water Header B LO Pressure; EK-1164, Critical Serv Water Header A LO Pressure; EK-1165, Non-Critical Serv Water LO Press; EK-0551, Diesel Gen No 1-1 Trouble; EK-0557, Diesel Gen No 1-2 Trouble SRO Enters ONP-6.1, Loss of Service Water Directs start of available SW Pump, P-7C RO STARTS P-7C RO No Operator actions for alarms EK-1137, EK-1163, EK-1164, EK-1165 (refer to ONP-6.1)
BOP Performs Operator Actions of EK-0551 and EK-0557 Directs AO to CLEAR D/G alarms locally (due to low Raw Water Pressure)
Simulator Operator - When contacted by Control Room to clear local D/G alarms (low raw water pressure), INSERT ED27 (PIDED08), D/G 1-1 Trouble alarm, value = 0, and INSERT ED28 (PID ED08), D/G 1-2 Trouble alarm, value = 0.
SRO/BOP May direct AO to check pump and breaker Simulator Operator - When contacted by Control Room as AO to check pump and/or breaker status, wait 5 minutes and REPORT: the pump is hot to the touch and the breaker is tripped, time over current relay.
SRO Exits ONP-6.1 SRO The following T.S. LCO applies:
3.7.8, Action: A.1, SW train (P-7B), 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> After CRS has briefed loss of P-7B OR at the discretion of the Lead Examiner, INSERT TRIGGER #4.
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: TWO Event No.:
5 Page 1 of 1 Event
Description:
PCS Leak requiring a Plant trip Time Position Applicant's Actions or Behavior RO/BOP/SRO Diagnose PCS leak:
Indications from PPC: Containment Sump level rising; Containment Sump fill rate rising; Charging line flow rising; P-55B Charging Pump Start (may occur)
Major alarms: EK-0734, Charging PP Seal Cooling LO Press (may occur)
SRO Enters ONP-23.1, Primary Coolant Leak:
Directs actions of ONP-23.1 Reviews reactor trip criteria SRO Directs PCS Leak Rate calculation by ONP-23.1 or DWO-1 RO/BOP PERFORMS PCS Leak Rate calculation SRO May direct closing:
CV-1064 and CV-1065, CWRT Vent Valves CV-1910 and CV-1911, PCS Sample Valves SRO Directs reactor trip (unidentified PCS leakage > 10 gpm) (CRITICAL TASK PL-343 223 05 01)
SRO The following T.S. LCO applies:
3.4.13, Action: A.1, PCS leakage > 1 gpm unidentified, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SRO: Emergency Classification Level: Unusual Event, SU5.1, Unidentified PCS Leakage > 10 gpm RO PUSHES reactor trip pushbutton on Panel C-02
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: TWO Event No.:
6/7 Page 1 of 7 Event
Description:
CV-0703 B S/G FRV fails to close/B S/G tube rupture Time Position Applicant's Actions or Behavior BOP Informs SRO that Main Feeds Pumps are being tripped due to stuck open FRV, CV-0703 for B S/G, CONTINGENCY ACTION:
Main FRV and B/Ps CLOSED, except for CV-0703 PUSHES trip pushbutton for running MFW Pump (CRITICAL TASK PL-000 007 05 01)
SRO EOP-1.0 verbal verifications RO Reactivity Control: YES Reactor power lowering negative SUR maximum of one control rod not inserted BOP Main Turbine Generator criteria: YES Main Turbine tripped Generator disconnected from grid BOP Feedwater criteria: NO:
PLACES Main FWP Controllers to MANUAL RAMPS to minimum speed CV-0703 could not be closed, ALL Main Feed Pumps TRIPPED BOP Vital Auxiliaries-Electric: YES Buses 1C and 1D energized Bus 1E energized Bus 1A and Bus 1B energized Y-01 energized Six DC Buses energized 3 of 4 Preferred AC Buses energized RO PCS Inventory Control: YES PZR level 20% - 80%
PZR level trending 42% - 57%
PCS 25°F subcooled
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: TWO Event No.:
6/7 Page 2 of 7 Event
Description:
CV-0703 B S/G FRV fails to close/B S/G tube rupture Time Position Applicant's Actions or Behavior RO PCS Pressure Control: YES PZR pressure 1650 - 2185 psia PZR pressure trending toward 2010 - 2100 psia RO Core Heat Removal: YES at least one PCP operating Verify Loop T less than 10°F Verify PCS at least 25°F subcooled BOP PCS Heat Removal: YES Verify at least one S/G has; level 5% - 70%; Feedwater available Verify TAVE 525°F - 540°F Verify BOTH S/G pressures 800 psia - 970 psia RO Containment Isolation: YES Verify Containment pressure < 0.85 psig BOP Containment Isolation: YES Verify Containment Area Monitor alarms clear Verify Condenser Off Gas Monitor alarm clear Verify Main Steam Line Monitor alarms clear This may be a NO answer for Condenser Off Gas and Main Steam Line Monitor depending upon the amount of time required to get this far in procedure RO Containment Atmosphere: YES Verify Containment temperature < 125°F Verify Containment Pressure < 0.85 psig RO Vital Auxiliaries - Water: YES Verify at least two SW Pumps operating Verify BOTH Critical SW Headers in operation with pressure > 42 psig Verify at least one CCW Pump operating
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: TWO Event No.:
6/7 Page 3 of 7 Event
Description:
CV-0703 B S/G FRV fails to close/B S/G tube rupture Time Position Applicant's Actions or Behavior RO Vital Auxiliaries - Air: YES Instrument Air Pressure > 85 psig BOP Verify BOTH of the following: YES At least one Condensate Pump operating At least one Cooling Tower Pump operating BOP PLACES left train CRHVAC in emergency mode:
STARTS V-26A Air Filter Unit Fan ENSURES OFF: V-94, Purge Fan; V-47, Switchgear Exhaust Fan SRO Performs Event Diagnostic Flow Chart per EOP-1.0, Attachment 1:
(IF CONDENSER OFF GAS MONITOR IS IN ALARM, MAY GO TO EOP-9)
Diagnoses EOP-4.0, Loss of Coolant Accident Recovery Performs EOP-4.0 strategy brief Establishes PCS pressure and temperature bands with RO Directs SE to perform Safety Function Status checks for EOP-4.0 SRO May direct Chemistry to sample S/Gs for lithium SRO May direct closing CV-2001 and CV-2009 Letdown Isolation Valves RO CLOSES CV-2001 and CV-2009 SRO May direct closing CV-1910 and CV-1911, PCS Sample Vales BOP CLOSES CV-1910 and CV-1911
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: TWO Event No.:
6/7 Page 4 of 7 Event
Description:
CV-0703 B S/G FRV fails to close/B S/G tube rupture Time Position Applicant's Actions or Behavior SRO/RO/BOP Diagnoses change in PCS parameters, B SGTR PZR pressure lowering Second and Third Charging Pumps operating due to lowering PZR level Condenser Off Gas Monitor counts rising with eventual high alarm B S/G level rising, A S/G level lowering Plant Stack Gas Monitor counts rising SRO Re-performs Event Diagnostic Flow Chart per EOP-1.0, Attachment 1 Diagnoses EOP-9.0, Functional Recovery Procedure SRO May direct Emergency Boration RO/BOP PERFORMS Emergency Boration per SOP-2A, Attachment 14, Emergency Manual Boration:
START P-56A or P-56B, BA Pump OPEN MO-2140, BA Pump Feed Isolation AND/OR OPEN BA Gravity Feed Valves: MO-2169 and MO-2170 CLOSE MO-2087, VCT Outlet Valve ENSURE CLOSED MO-2160, SIRW Tank to Charging Pumps Isolation SRO May direct starting Auxiliary Feedwater SRO May direct AFW isolation to B S/G based on EOP-1 criteria RO Isolates AFW to B S/G:
SELECTS MANUAL on FIC-0727, P-8A/B flow to S/G B SELECTS MANUAL on FIC-0736A, P-8C flow to S/G B Ensuring/raising flow output to 100% on each controller (RED signal indicator to the full right position)
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: TWO Event No.:
6/7 Page 5 of 7 Event
Description:
CV-0703 B S/G FRV fails to close/B S/G tube rupture Time Position Applicant's Actions or Behavior SRO Directs closing CV-1064 and CV-1065, CWRT vent valves BOP CLOSES CV-1064 and CV-1065 SRO Directs performance of EOP Supplement 5, Checklist for Safeguards Equipment Following SIAS BOP Completes EOP Supplement 5 SRO Directs placing a Hydrogen Monitor in service BOP Places left train H2 monitor in service on back of Panel C-11A:
PLACES HS-2417 to OPEN and RELEASES PLACES HS-2413A, HS-2413B, HS-2415A, and HS-2415B, to OPEN Energizes H2 Recorder, AR-2401, by: PLACING to ON Power Switch and PLACES to ON Chart Drive Switch PLACES HS-2427L to ANALIZE position SRO Determines success paths for each safety function:
WITH NO SIAS Reactivity: RC-1 OR RC-2 (If Emergency Boration in progress)
Maintenance of Vital Auxiliaries-Electric: DC-1, AC-1 PCS Inventory: IC-1 PCS Pressure: PC-1 PCS/Core Heat Removal: HR-1 Containment Isolation: CI-1 Containment Atmosphere: CA-1 Maintenance of Vital Auxiliaries-Air: MVAW-1, MVAA-1 Determines Containment Isolation (CI-1) is jeopardized due to SGTR not isolated
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: TWO Event No.:
6/7 Page 6 of 7 Event
Description:
CV-0703 B S/G FRV fails to close/B S/G tube rupture Time Position Applicant's Actions or Behavior SRO Determines success paths for each safety function:
WITH SIAS Reactivity: RC-3 Maintenance of Vital Auxiliaries-Electric: DC-1, AC-1 PCS Inventory: IC-2 PCS Pressure: PC-3 PCS/Core Heat Removal: HR-2 Containment Isolation: CI-1 Containment Atmosphere: CA-1 Maintenance of Vital Auxiliaries-Air: MVAW-1, MVAA-1 Determines Containment Isolation (CI-1) is jeopardized due to SGTR not isolated SRO Directs cooldown of PCS to < 524°F THOT RO Begins PCS cooldown of PCS using the Turbine Bypass Valve:
PIC-0511, CV-0511 Turbine Bypass Valve Controller, PLACED in MANAUAL Manual Signal Lever used to OPEN CV-0511 for PCS cooldown SRO Directs PCS depressurization per HR-2 RO Begins PCS de-pressurization using PIC-0101B, PCS Pressure Controller:
MANUAL pushbutton PUSHED Manual Signal Lever used to OPEN CV-1057 and CV-1059 PZR Spray Valves
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: TWO Event No.:
6/7 Page 7 of 7 Event
Description:
CV-0703 B S/G FRV fails to close/B S/G tube rupture Time Position Applicant's Actions or Behavior RO SECURES A and 'D' PCPs at 1300 psia SRO Directs isolation on B S/G per EOP Supplement 13, B S/G SGTR Isolation Checklist BOP Isolates B S/G per Supplement 13:
Isolation from inside the Control Room:
ENSURE OPEN MO-0510, A S/G MSIV Bypass Valve CLOSE CV-0703, B S/G Main Feed Reg Valve (valve stuck partially open)
CLOSE CV-0744, B S/G Main Feed Block Valve CLOSE S/G E-50B Blowdown Valves: CV-0768, CV-0770, and CV-0738 (CRITICAL TASK PL-000 216 05 01)
Simulator Operator: When instructed by BOP to isolate B S/G outside the Control Room per Supplement 13, INSERT TRIGGER # 8, isolating air and manual isolation valves to CV-0779 and CV-0780, B S/G Atmospheric Steam Dump Valves.
SRO: Emergency Classification Level: After the PCS leak reaches 10 gpm before the reactor trip, the conditions are met for SU5.1, PCS leakage greater than 10 gpm. After the trip, the classification will change to an Alert, FA1, Loss or Potential Loss of PCS Barrier (SG Tube Rupture that results in SIAS)
TERMINATE Scenario when B S/G has been isolated per EOP Supplement 13 OR at the discretion of the Lead Examiner.