ML032880216
| ML032880216 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 09/29/2003 |
| From: | Santiago M Entergy Nuclear Operations |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-293/03-301 | |
| Download: ML032880216 (33) | |
Text
Appendix D Scenario Outline Form ES-D-1 u
Event Type*
R(RO)
N(SR0, BOP)
I(R0, SRO)
Facility: PNPS Scenario No.:
1 Event Description Power change - pull rods to continue power ascension CRD Flow Control Valve failure Op-Test No.:
1 1
2 3
4 5
6 7
8 Examiners:
Operators:
NIA NM20 RD02 CW03 I10 PCOl PC23 I/O Initial Conditions: 15% Power, reactor startup is in progress C(BOP, SRO)
M(ALL)
M(ALL)
Turnover: Reactor is in the process of being started, currently at step 120 in 2.1.I.
The goal for this shift is to continue the reactor startup. A TBCCW pump is 00s.
RClC cooling valve fails to open Recirc leak within makeup capacity Torus leak leading to Emergency Depressurization SRV fails to open due to solenoid failure I
I I
I(R0, SRO) I APRM Fails upscale I
C(ALL)
I B TBCCW pump trips causing loss of TBCCW I
I I
I I
I (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-I 021, Draft Revision 9 40 of 41
Appendix D Required Operator Actions Form ES-D-2
/I Op-Test No.:
1 Scenario NO.:^ Event No.:
1 Page 1 of 1
Position CRS 905 Awlicant's Actions or Behavior Event
Description:
Power change - pull rods to continue power ascension p G -
Direct the RO to raise Reactor power with control rods Withdraw control rods in accordance with PNPS 2.1.1 and verify:
9 Selected rod PB comes ON.
9 CONTROL ROD POSITION FOUR ROD DISPLAY indicates the control rod 9
The associated Full Core Display rod select light comes ON.
position.
Simultaneously place the Rod Control switch to NOTCH OUT and the Emergency In Notch Override switch to NOTCH OVERRIDE and observe the following:
P The IN green light comes ON momentarily.
9 The OUT red light comes ON and the NOTCH OVERRIDE amber light comes 9 CONTROL ROD POSITION FOUR ROD DISPLAY indicates control rod ON.
movement.
Prior to reaching the desired control rod position, simultaneously release both the Rod Control Switch and the Emergency In Notch Override switch and observe the following:
9 The OUT red light goes OUT.
P The SETTLE amber light comes on for = 6 seconds, then goes out.
9 CONTROL ROD POSITION FOUR ROD DISPLAY indicates the control rod 9 At position 48, the applicable Full Core Display FULL OUT red light comes had settled to the desired position.
ON.
Indicate the completion of the movement on the Pull Sheet.
NUREG-I 021, Draft Revision 9 41 of 41
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:
1 Scenario No.:
1 Event No.: 2 II Page 1 of 1
Event
Description:
CRD Flow Control Failure Time I Position I Applicant's Actions or Behavior IF Operator: Insert CRD FCV Failure upon direction of Chief Examiner. This will be directed after sufficient rod movement has occurred to satisfy the reactivity change.
905 9
9 9 Identify FCV failed closed.
Determine no rod movement while attempting to withdraw rods.
Identify CRD flow indication low.
Direct entry into PNPS 2.4.1 1.I,.
CRS I
905 9
9 Position controller to CLOSED.
9 9
9 9
9 Raise CRD controller setpoint to 50 GPM:
Check DRIVE WTR and COOLING WTR DlFF PRESS indicators adjust as needed.
Place CRD FLOW CONTROLLER to MANUAL.
Direct standby inlet valve verified locally.
Direct standby flow control outlet valve opened slowly.
Direct in-service flow control valve outlet closed.
Direct selector switch to standby position.
Direct valve 301-29 positioned to standby.
9 Verify flow increases.
Return flow controller to AUTO.
Adjust DRIVE WTR PCV as necessary.
NUREG-1021, Draft Revision 9 41 of 41
Appendix D Required Operator Actions Form ES-D-2 Time I Position Applicants Actions or Behavior IF Operator: At the direction of the Chief Examiner, insert B APRM upscale malfunction.
Op-Test No.:
1 Scenario No.:
1 Event No.:
3 Page 1 of 1
11 Event
Description:
B APRM fails upscale Recognize / announce % scram. Recognize / announce the following:
9 9
9 9
Neutron Monitoring Trip (C905R-C3).
RPS Channel B APRM Hi-Hi-/INOP (C905L-A9).
APRM Hi Restricted Region Entry (C905L-C8).
Auto Scram Channel B (C905R-A4).
Refer to the ARPs for the Annunciators in alarm.
Determine that B APRM is the source of the alarms.
Send the BOP operator to check the failed APRM on Panel C937.
Go to C937 to verify that B APRM has failed high based on meter indication and the lights in alarm.
Order the RO to place the B APRM in the BYPASS position and reset the scram.
Refer to Tech Specs. Table 3.1.I and Table 3.2.C.1 for the failed APRM.
Recognize I announce that the plant will enter a tracking LCO for the failed APRM.
Direct I&C to troubleshoot APRM B failure.
NUREG-I 021, Draft Revision 9 41 of41
Appendix D Required Operator Actions Form ES-D-2 Page I of 2 Op-Test No.: I Scenario No.: I Event No.:
4 Event
Description:
B TBCCW pump trips causing loss of TBCCW Time I Position 905 Applicants Actions or Behavior Attempt to start I restart TBCCW pump@).
Scram the reactor:
9 Depress both Reactor Scram push buttons.
9 Place Reactor Mode switch in SHUTDOWN.
9 Verify and announce the status of APRM downscales.
9 Verify all control rods are fully inserted.
> Insert IRM and SRM detectors, select 2 SRMs for recording and place 9 Verify or manually trip the turbine.
9 Verify or manually place Reactor Recirc Pumps at minimum speed.
9 Verify ALL scram discharge Volume Vent and Drain Valves are closed at 9 Restore and maintain RPV water level between +20 inches and +40 inches 9 Stabilize RPV pressure between 900 and 1050 with HPCI.
9 Verify or manually transfer house loads to the Startup Transformer.
9 Direct tripping ETS.
9 Direct shutting down EHWC.
9 Direct starting all available drywell cooling fans on Panel C61.
9 Open I verify open all available Drywell Cooler Motor Operated Supply Valves on Panel C7.
9 Direct securing GEZIP.
9 Notify Radiation Protection that a scram has occurred.
9 Notify Radwaste that a scram has occurred.
9 Notify Chemistry to secure oxygen injection to the Condensate Pumps.
9 Secure the Gland Seal Condenser Drain Tank system by placing the control selector switch for APRMIIRM to IRM.
panel C905.
using RCIC.
switch for AO-3367 on Panel C10 to CLOSE.
Trip all feedwater pumps AND all but one Condensate Pump.
Place HPCI in Pressure Control Mode:
9 9
9 9
9 9
Verify Flow Controller FIC-2340-12 is in AUTO.
Start P-233, Gland Seal Condenser Blower.
Open MO-2301-15, HPCI Test Return Valve.
Jog Open MO-2301-10, HPCl Full Flow Test Valve.
Open MO-2301-3, Turbine Supply Valve and Start P-229, Aux. Oil Pump.
Observe flow increases and stabilizes at 4250 GPM.
NUREG-I 021, Draft Revision 9 41 of 41 W
Appendix D Required Operator Actions Form ES-D-2 Page 2 of 2
Op-Test No.: I Scenario No.: I Event No.: 4 Event
Description:
B TBCCW pump trips causing loss of TBCCW Time Position BOP CRS BOP 905 Applicants Actions or Behavior Use RClC in Injection Mode for level control:
9 9
9 Verify:
9 MO-1306-61, Turbine Supply OPEN.
9 9
9 9
9 9 P-222 Vacuum Pump STARTS.
9 P-221 Cond pump STARTS.
9 9 Verify the MANUAL START lamp is OUT (about 30 seconds after initiation).
9 Closely monitor Reactor Level.
Momentarily depress the RClC Injection PB.
Verify MANUAL START light in ENERGIZED.
MO-1301-49, RClC Pump Discharge Injection Valve #2 OPEN.
MO-1301-60, Min Flow Valve CLOSES when flow > 100 GPM.
MO-1301-34 & 35 Stm Line Drain valve OPEN.
MO-1301-12 & 13, Condr Drain Valves CLOSED.
MO-1301-62, Cooling water Supply OPEN.
RClC flow stabilizes at 400 GPM.
When the main turbine trips, then close the MSlVs AND trip the remaining condensate pump.
Investigate the cause of the TBCCW Pumps trip and initiate corrective action.
9 9
Place both Auxiliary Oil pumps in PULL-TO-LOCK.
If turbine lube oil temp reaches 140 degrees F:
> Break condenser vacuum.
9 Secure steam seal system.
9 Prevent start of turbine lift pumps.
9 Prevent turning gear engagement.
9 Direct start of temporary air compressor.
Reset Scram:
9 Bypass SDlV Hi LEVEL SCRAM BYPASS signal.
9 Reset Scram:
9 Momentarily Actuate Scram Reset Selector switch.
9 Verify all group scram lights on C905 are ON.
9 Wait approx. 1 minute, verify SPVAH PRESSURE LO alarm does 9 Place AIR DUMP SYSTEM TEST switch to ISOLATE.
9 When SPVAH PRESSURE LO alarm clears, return AIR DUMP SYSTEM
> If necessary, reset the control rod drift lights on full core display by 9 Place SDlV HI LEVEL SCRAM BYPASS switch to NORMAL.
not clear.
TEST switch to NORMAL.
momentarily placing ROD DRIFT RESETREST in RESET position.
L NUREG-I 021, Draft Revision 9 41 of41
Appendix D Required Operator Actions Form ES-D-2 Time Op-Test No.:
1 Scenario No.:
1 Event No.:
5 ll Position Applicant's Actions or Behavior BOP CRS BOP Determine that the MO-1301-62 valve failed to automatically open.
Direct MO-1301-62 valve be manually opened.
Manually rotate control switch for MO-1301-62 valve in the counter-clockwise direction. Notes that the MO-1301-62 opens.
Page 1 of -
1 11 Event
Description:
RClC Cooling Valve Fails to Open NUREG-I 021, Draft Revision 9 41 of 41
Appendix D Required Operator Actions Form ES-D-2 Page I of 2
Op-Test No.: I Scenario No.: I Event No.: 6 Event
Description:
Leak in Drywell Time Position BOP/905 CRS 905/BOP CRS BOP Amlicant's Actions or Behavior Recognize / announce rising drywell parameters. and EOP-03 entry conditions Report to the CRS when out of current RPV IeveVpressure band.
Enter EOP-03 Establish new pressure bands as the reactor depressurizes.
When drywell temperature cannot be maintained e 150 degrees F, directs that drywell cooling be maximized.
Maximize Drywell Cooling:
9 Maximize RBCCW:
9 Start / verify 2 RBCCW pumps running in each loop.
P Start / verify 2 SSW pumps running in each loop.
9 Fully open MO-3800 for loop A and/or MO-3806 for loop B RBCCW HX.
9 Lower RBCCW loop temp controller setpoint to less than 50 degrees, and/or close MO-4084 OR MO-4083, RBCCW HX bypass valve..
9 Start additional RBCCW pumps as needed.
> Fully open all drywell cooler RBCCW valves by rotating all pots on C7 to the fully clockwise position.
Before drywell pressure reaches 16 psig, direct that torus spray be placed in service using A or B RHR. Directs that torus spray be secured before torus pressure goes below 0.0 psig.
Start torus spray using A or B RHR:
9 Start / verifL one RHR pump running.
9 Open/ verify MO-1001 18A, Min Flow Valve for selected loop.
9 Place LPCl OVERRIDE switch to MANUAL OVERRIDE.
9 Open MO-1001-34A (B),Torus Cooling/Spray Block Vlv in the RHR loop with the operating pump.
9 Throttle open MO-1001-37A (B), Torus Spray Valve, in the RHR loop with the operating pump.
> Slowly open MO-1001-36A (B), Torus Cooling Valve and increase flow to 9 Close MO-1001-18A (B), Pump Min Flow.
4500 - 4800 GPM..
NUREG-1021, Draft Revision 9 41 of 41
Appendix D Required Operator Actions Form ES-D-2 Page 2 of 2 Op-Test No.: I Scenario No.:
1 Event No.: 6 Event
Description:
Leak in Drywell Time Position CRS BOP CRS Amdicant's Actions or Behavior When drywell pressure exceeds 16 psig:
> Verifies drywell temperature and pressure within safe region of the DSIL.
P Verifies torus water level below 180 inches.
P Verifies recirc pumps shutdown.
P Directs that drvwell sDravs be tiaced in service usina A/B RHR IOODS.
Direct that drywell spray be secured before drywell pressure goes below 0.0 psig.
Place drywell sprays in service using N B RHR loops: (CRITICAL TASK) 9 If running, trip recirc pumps.
P Start / verify one RHR pump running in each loop.
> Open / Verify MO-1001-18A, Min Flow Valve.
9 Place LPCl OVERRIDE to MANUAL OVERRIDE position.
9 Fully open:
9 MO-1001-23A, RHR Loop A Upper Drywell Spray Valve #2 AND MO-
> MO-1001-23B, RHR Loop B Upper Drywell Spray Valve #2 AND MO-
> Open / verify MO-1001-34A (B), Torus Cooling/Spray Block valve.
1001-26A, RHR Loop A Upper Drywell Spray Valve #I.
1001-26A, RHR Loop B Upper Drywell Spray Valve #I.
Determine that water level can be maintained above +I2 inches.
NUREG-I021, Draft Revision 9 W
41 of 41
Amendix D Reauired ODerator Actions Form ES-D-2 Position BOP1905 Op-Test No.: -
1 Scenario No.:
1 Event No.:
7 Applicant's Actions or Behavior Determine that torus level is lowering and report to CRS.
Page I of 1
CRS Event
Description:
Torus Leak Leading to Emergency Depressurization Re-enter EOP-03.
Direct initiation of makeup to the torus.
Determine that torus level cannot be maintained above 95 inches. Order HPCl Aux. Oil Pump be placed in PULL-TO-LOCK.
Time CRS
~~~~
Determine that torus level cannot be maintained above 90 inches.
Briefs Emergency Depressurization and enters EOP-17.
Places HPCl Aux. Oil Pump in PULL-TO-LOCK.
I u
NUREG-1021, Draft Revision 9 41 of 41
.A Appendix D Required 0 perat or Act ions Form ES-D-2 W
d Page 1 of 1
Op-Test No.: I Scenario No.: I Event No.:
8 Event
Description:
D SRV Fails to Open Due to Solenoid Failure Time Position CRS BOP CRS BOP 905/BOP Amlicants Actions or Behavior Verify torus level above 50 inches.
Direct opening all 4 SRVs Take the control switch for all 4 SRVs to the open position and takes action to verify that all 4 SRVs have opened: (CRITICAL TASK) 9 Checks the acoustic monitor on C171.
9 Checks the C921 panel for rising tailpipe temperatures..
Recognize and announce that D SRV has not opened.
Direct entering PNPS 5.3.24, Alternate Methods for Venting and Depressurizing the RPV under Emergency Conditions.
~~
Enter 5.3.24.
Call Reactor Building operator to open D SRV from the Alt. Shutdown panel.
IF OPERATOR: When asked to open D SRV from the ASP, wait approx. 3 minutes and then execute the step for opening the D SRV from the ASP.
Alternate methods of depressurizing the RPV that my be pursued include:
9 RClC Steam Line:
9 If RClC is operating then raise RClC flow to 400 GPM. Open Full 9 IF RClC is not operating and is not isolated or tripped, then start Flow Test valve if necessary.
RClC in test mode IAW 2.2.22.5. Bypass Auto-closure of valves if necessary IAW 5.3.21.
9 RPV Head Vent:
9 If RPV pressure is above 100 psig, ask OSS for permission to use the 9 Stop and prevent pumping from drywell sumps 9 Open head vents to drywell sumps 9 Have Chemistry monitor drywell atmosphere for increased particulate head vent.
levels.
Note: Steps that dump steam to the main condenser should not be pursued.
Terminate the scenario when all 4 SRVs are open and water level has stabilized between +20 and +40 inches.
EAL is Site Area Emergency, 3.3.2.3.
NUREG-I 021 Draft Revision 9 41 of 41
Appendix D Scenario Outline Form ES-D-1 Event No.
1 W
Malf.
Event Type*
Event No.
Description RP09 C(SR0)
3 4
Facility: PNPS Scenario No.:
Main Steam Line Rad Monitor fails downscale HPOI C(BOP, SRO)
Inadvertent initiation of HPCl Op-Test No.:
1 I
5 RR21 6
MT03 7
RD26 I RP16 Examiners:
Operators:
I(R0, SRO)
A Recirc Pump runs back, requires locking scoop tube Failure to scram upon tripping of turbine C(ALL)
Turbine bearing high vibration M(ALL) 11 Initial Conditions: 100% Power, A EDG tagged out for bearing replacement.
8 9
Turnover: Continue operating the plant at 1 OO%, Currently in day 5 of a 14 day extended (due to verifying SBODG operable) LCO for A EDG 00s.
LP02 C(R0, SRO)
SBLC Squib valve fails to fire WF I(BOP, SRO)
RWCU fails to isolate I
I I
2 I
NIA I N(R0, BOP) I Place RPS bus on backup I1 I
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor I
I NUREG-1021, Draft Revision 9 40 of 41
Appendix D Required Operator Actions Form ES-D-2 Time I Position Page I of I Op-Test No.: I Scenario No.:
2 Event No.: I Event
Description:
Trip of RPS MG Set Applicants Actions or Behavior downscale malfunctions.
RO CRS P Recognize I announce various annunciators associated with the loss of A P Use the collection of annunciators to diagnose a trip of the RPS A MG Set.
P Recognize I announce loss of A RPS bus.
P Recognize /announce annunciator RPS MG Set A Trip is in alarm.
P Verify ?4 scram RPS Channel A.
RPS bus.
P Directs that action be taken per ARP C905R-C1.
P Refers to Tech Specs 3.1 and Table 3.1.I.
P Direct troubleshootinghepair of RPS MG Set A.
9 Direct placing RPS A on the backup power supply.
NUREG-I 021, Draft Revision 9 41 of 41
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:
1 Scenario No.:
2 Event No.: 2 Page 1 of 1 Event
Description:
Place RPS bus on backup Time Posit ion 905/BOP 905 Applicants Actions or Behavior P Directs TB operator to transfer A RPS Bus to the standby transformer per 9 When A RPS Bus is on the standby transformer:
2.2.79.
P Reset the % scram when SDlV LEVEL HI alarm clears.
P Verify Group Scram lights on C905 are illuminated.
P Reset the Main Steam Line and Air Ejector Offgas Rad monitors.
P Reset the Refuel Fir Vent EXH CH A and B Rad Monitors and Carbon Bed Vault Rad Monitor.
P Direct resetting of ATS alarms P Reset flow comparator alarms.
P Reset all APRM FCTR and PBDS trips that have occurred due to power transfer.
P Reset all APRMs A, C, and E Hi AND Hi-Hi lights on C937.
If necessary, reset RBM A and B downscale alarms by deselecting and reselectina a control rod on the Rod Select Matrix.
u NUREG-I 021, Draft Revision 9 41 of 41
Appendix D Required Operator Actions Form ES-D-2 Page 1 of 1
Op-Test No.: I Scenario No.:
2 Event No.:
3 II 11 Event
Description:
Main Steam Line Rad Monitor fails downscale Position BOP CRS Atmlicants Actions or Behavior 9 Recognize I announce annunciator Main Stm Line Rad Dnscl did not clear 9 Refer to ARP C904LC-C6.
9 Checks recorder 40-RR-1705-11 on Panel C902 and Log Rad Monitors 1705-2A, B, C, and D on C910.
9 Recognize I report that RM-1705-2A has failed downscale.
when power was restored to A RPS bus.
9 Directs the Turbine Building operator to check Breakers 5A and 58 on Panel 9 Call I&C to investigate the cause of the downscale condition.
9 Direct I&C to check fuses 17A-F13 and 17A-F11 on Panel C910.
9 Refer to Tech Specs 3.8.2 and determine I announce 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO based on C511.
3.8.2A:
- 1. Restore channel to Operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OR
- 2. Place channel or associated trip system in trip within24 hours.
9 The CRS may refer to 2.2.155, Process Radiation Monitoring System.
IF OPERATOR: If asked as I&C to troubleshoot the MSL Rad Monitor report that the problem is a failed power supply and that it will take about 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to repair.
NUREG-I 021, Draft Revision 9 41 of 41
Appendix D Required Operator Actions Form ES-D-2 Time I Position Op-Test No.:
1 Scenario No.: 2 Event No.:
4 II Applicants Actions or Behavior Page 1 of I Event
Description:
HPCl Inadvertent Start Recognize that HPCI has started.
Enters PNPS 2.4.35, Inadvertent Initiation of Core Standby Cooling Systems.
Inadvertent initiation is verified (Drywell c 2.2 psig & RPV level > -46 inches) on two independent instruments.
9 9
Depress and hold the HPCl Turbine Trip pushbutton.
After the turbine has come to a complete stop, place the Aux Oil Pump (P-229) control switch to the PULL-TO-LOCK position.
Releases the Turbine Trip PB.
Assess operating conditions by plotting power verses core flow on the Pilgrim Power/Flow Map, then perform action required IAW 2.1.14, Section 7.10.
Monitor PBDS recorders for any indication of power oscillations.
Check Process Rad Monitors for indications of fuel damage.
~~
Verify that peak power and pressure did not exceed any limits.
Investigate cause of inadvertent initiation by calling I&C.
NUREG-1021, Draft Revision 9 41 of 41
Appendix D Required Operator Actions Form ES-D-2 Page 1 of 1
Op-Test No.: I Scenario N O. : ~
Event No.:
5 Event
Description:
A Recirc #I Speed Limiter Failure (TS Implications)
Time Position 905 905/CRS 905 905/CRS 905 CRS 905 CRS Applicants Actions or Behavior Recognize / announce annunciators MG A SPEED LIMITER O N and MG A SPEED DEVIATION HI at Panel C904RC and refers to the ARPs.
Enter PNPS 2.4.20, Reactor Recirculation System Speed of Flow Control System Malfunction.
Initiates a scoop tube lockup by depressing the Manual Scoop Tube Positioner Lockup PB and refers to PNPS 2.4.19, Recirculation Pump MG Set Scoop Tube Lockup.
Assess the operating conditions by plotting power versus core flow on the Pilgrim Power/Flow Map and performs the required actions IAW 2.1.14, Sections 7.10 &
7.1 1.
IF OPERATOR: If asked as the CR Annexl3rd SRO if PBDS is operable, report that PBDS is operable.
Monitor PBDS recorders for any indications of power oscillations.
9 Refer to Tech Specs Section 3.6.F.1.
9 Recognize / announce that the percent mismatch is outside the Tech Spec limit. If the mismatch is not corrected within 30 minutes, an orderly shutdown must be initiated and the reactor in Cold Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the speed mismatch is brought within limits.
k Attempt to bring the mismatch to within limits by either raising the A Recirc.
pump speed locally at the scoop tube positioner or lowering the speed of the B Recirc. Pump using the speed controller at C904. The correct action is dependent on the plants position on the Power/Flow Map.
Either coordinate with the licensed operator in the field to bring the mismatch to within limits using the A Recirc. Pump scoop tube positioner or lower the speed of the B Recirc. Pump using the speed controller at C904.
Call I&C to investigate the A Recirc. Pump speed controller failure.
NUREG-I 021, Draft Revision 9 41 of 41
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:
1 Scenario No.:
2 Event No.: 6 II Page 1 of 1
Event
Description:
Turbine Bearing High Vibrations 11 IF OPERATOR: When directed by the Chief Examiner, insert the Turbine Bearing malfunction for #4 bearing.
1 BOP BOP/CRS CRS 905 BOP CRS 905 CRS
~~
9 Recognize / announce Turbine Vibration Hi alarm.
Checks Vibration & Eccentricity recorder (VR-3000 on Panel C2).
~
Enters and executes steps of 2.4.46, Turbine Bearing Malfunction.
9 9
9 Recognize / announce step 4.0 [I], which establishes vibration limits.
Direct the crew to make note of time at which turbine bearing vibration reaches 10 mils.
Attempt to reduce vibration levels by directing the RO to reduce Reactor power.
Varies power by varying N B Recirc. Pump speed in order to reduce main turbine vibrations.
Places Vibration & Eccentricity recorder to FAST speed.
As turbine vibrations continue to rise toward 12 mils, establish a limit above which the reactor will be scrammed.
When limit is exceeded, direct a reactor scram.
9 Scram the reactor:
9 Depress both Reactor Scram push buttons.
h Place Reactor Mode switch in SHUTDOWN.
9 Verify and announce the status of APRM downscales.
9 Verify all control rods are fully inserted.
9 Insert IRM and SRM detectors, select 2 SRMs for recording and place 9 Verify or manually trip the turbine.
9 Verify or manually place Recirc. Pumps at minimum speed.
selector switch for APRM/IRM to IRM.
IF OPERATOR: Ramp down turbine vibrations conditional on the Turbine trip.
Establish RPV level and pressure bands (RPV level +20 to +40 inches, RPV pressure 900 - 1050 psig.
NUREG-1021, Draft Revision 9 41 of 41
Appendix D Required Operator Actions Form ES-D-2 Time Applicants Actions or Behavior Position CRS 905 CRS 905 BOP CRS BOP 905 Enter EOP-01 and immediately transition to EOP-02 based on all control rods not at or beyond position 02.
9 9
9 Place mode switch in SHUTDOWN.
Initiate both channels of ARI.
Recognize the turbine has tripped.
9 9
Recognize reactor power is above 3%.
Trips / verifies tripped both Recirc. Pumps.
9 9
9 9
9 9
9 Verify mode switch in SHUTDOWN.
Verify both channels of ARI initiated.
Verify the turbine has tripped.
Verify reactor power is above 3%.
Verify both Recirc. Pumps tripped.
Order new RPV level and pressure bands (Level -20 to +IO inches; Pressure 1000 to 1050 psig).
Order 905 operator to enter PNPS 5.3.23, Alternate Rod Insertion.
9 9
9 Enter PNPS 5.3.23, Alternate Rod Insertions.
Determine that there is a hydraulic lock and goes to Section 3.3 and performs it concurrently with the General Actions section of the procedure.
Maintain RPV level in given band.
Maintain pressure in given band.
Orders BOP operator to inhibit ADS.
Takes ADS Inhibit switch to INHIBIT position. (CRITICAL TASK)
Perform actions of 5.3.23:
9 9 Verify CRD pump running.
9 9
> Bypass Rod Worth Minimizer.
9 9
Notify Reactor Engineering of the ATWS.
Call RB operator to close 301-25 (CRD 25 valve).
Call I&C to perform Attachments 1 & 2 of 5.3.23.
Increase drive pressure 50 psi above its present value by throttling closed Using EMERG IN switch, inserts all steps of the RPR array first then inserts remaining rods in any order.
MO-302-8.
NUREG-I 021, Draft Revision 9 41 of 41
Amendix D Reauired Ouerator Actions Form ES-D-2 CRS Position I
Amlicant's Actions or Behavior
~~
~
Ask crew to report when level drops below -25 inches.
CRS I Determine Reactor power is above 3% and order SBLC Injection.
CRS 905 Establish level band between -25 and -1 50 inches.
Attempts to inject with SBLC.
905/BOP CRS Maintains level between -25 and -1 50 inches and TAF using Outside Shroud Injection Systems, Table E. (CRITICAL TASK)
Determine that power is above 3% with level above -25 inches:
9 P
Orders stop and prevent all injection into the vessel except from SBLC, RClC and CRD.
Orders MSlV low RPV level isolation bypassed.
905 Close / verify closed the feedwater regulator valves and Startup Feed Reg. valve.
(CRITICAL TASK)
Page 2 of 3
Op-Test No.: I Scenario No.:
2 Event No.:
7 Event
Description:
ATWS - Failure to Scram upon Tripping of Main Turbine pF BOP 9
P Place control switches for the RHR and Core Spray pumps in the PULL-TO-LOCK (PTL) position.
Trip / verify stopped the HPCl turbine and places the Aux Oil Pump control switch in the PTL position. (CRITICAL TASK) 905/BOP 1 Report when RPV level reaches -25 inches.
IF OPERATOR: When water level has stabilized, and SBLC and RWCU malfunctions have been inserted and dealt with, call as I&C and report that Attachments 1 & 2 of 5.3.23 are complete (RPS and ATWS/ARI are bypassed).
905 Reset the scram:
P P
P 9
P P
Initiate a manual scram.
P Reset and verify reset the scram using RPS reset switch.
Place the Air Dump System Test switch to ISOLATE position.
Wait forherify the SPVAH Pressure Lo alarm clears.
Place the Air Dump System Test switch to NORMAL position.
Verify either SDlV Level Hi Drained alarms are clear.
Verifies all rods are in.
SDlV East Not Drained and SDlV West Not
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:
1 Scenario No.:
2 Event No.: 7 I1 Page 3 of 3 Event
Description:
ATWS - Failure to Scram upon Tripping of Main Turbine 11 Time I Position BOP II I
Awlicant's Actions or Behavior When all rods are in, transition to EOP-01.
Order RPV water level restored and maintained between +20 and +40 inches.
Initiates a cooldown at less than 100 degrees F per hour.
Restore and maintain RPV level +20 to +40 inches.
Initiate a cooldown at less than 100 degrees F per hour.
Terminate the scenario when level has initiated. EAL is Site Area Emeraencv.
been restored 2.3.1.3 to between +20 and +40 inches and a cooldown has been NUREG-I 021, Draft Revision 9 41 of 41
L Appendix D Required Operator Actions Form ES-D-2 Page 1 of I Op-Test No.: I Scenario No.:
2 Event No.: 8 ll 11 Event
Description:
SBLC Squib Valve Fails to Fire Position CRS 905 Amlicants Actions or Behavior Direct that SBLC be injected.
9 9
9 Take SBLC keylock switch to the SYS A or SYS B position.
Recognize / announce that the Squib valve did not fire.
Take the SBLC keylock switch to the other position Verify SBLC is injecting by: observation of:
9 Lowering tank level.
9 RWCU isolates.
9 Power starts to lower.
9 9
9 Selected pump motor running indication is ON Pump discharge pressure slightly above reactor pressure.
Squib Valve Continuity Alarm (C905R-A9) is ON.
Squib Valve Continuity Light for the selected system is OFF.
NUREG-I 021, Draft Revision 9 41 of 41
Amendix D Reauired ODerator Actions Form ES-D-2 Time Op-Test No.:
1 Scenario No.:
2 Event No.:
9 Position BOP CRS BOP Page 1 of 1
11 Event
Description:
RWCU Fails to Isolate Amlicants Actions or Behavior Recognize / announce that RWCU did not isolate when SBLC injection is initiated.
9 9
Enter and execute PNPS 2.4.27, RWCU System Malfunctions.
Order that RWCU be isolated manually.
Manually isolate RWCU:
9 9
Close MO-1201-2.
> Close MO-1201-5.
9 Close MO-1201-80.
Trip the running RWCU pump.
NUREG-1021, Draft Revision 9 41 of41
PANEL LOCATION ALARM WINDOW PANEL NUMBER MCR DEVICE:
- 1) overvoltage relay (59-A1, 59-A2)
- 2) underfrequency relay (81 -AI, 81 -A2)
SETPOINT:
- 1) 132V AC (increasing)
- 2) 57 Hz (decreasing)
C905R c 1 RPS MG SET A TRIP OPERATOR ACTIONS:
- 1.
- 2.
- 3.
Confirm Alarm a)
Verifv Automatic Actions a)
Half-Scram (RPS Channel A)
Perform Corrective Actions a)
Check pwr available status light (Panel C916) transformer available, THEN transfer RPS Bus A to Standby Transformer (Panel C511) AND reset half-Scram Ensure Tech Spec 3.1 and Table 3.1.I satisfied Determine the cause of the breaker trip and inspect equipment powered from this source for electrical faults Do not reset the breaker until the cause of the trip is known and is either isolated or corrected b) c)
d)
POSSIBLE CAUSES:
- 1.
Overvoltage
- 2.
Underfrequency
REFERENCES:
I.
- 2.
- 3.
MCR Board C3 Annunciators (El 19)
Reactor Protection System (E21, E14)
PNPS 2.2.79 (Reactor Protection System)
ARP - C905R - C1 Rev. 13
Appendix D Scenario Outline Form ES-D-1 CW05/
I/O FW24 FWOI MCOI ED08 RC06 WF Facility: PNPS Scenario No.: 3 (Spare)
Op-Test No.:
I(R0, SRO)
C(ALL)
C(ALL)
C(ALL)
M(ALL)
Examiners:
Operators:
Initial Conditions: 100% Power, A RBCCW pump 00s Turnover: Continue operating at 100% power, A RBCCW is tagged out for breaker maintenance which is scheduled to be completed by the end of the shift.
Event No.
1 2
3 4
5 6
7 Event Description B RBCCW pump trip, stby pump does not pick up B FWLC Instrument fails downscale B RFP trip Condenser air in-leakage causes scram A I Lockout upon scram, loss of all high pressure feed Unisolable steam leak from RClC Failure of Group 5 Isolation I
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-I 021, Draft Revision 9 40 of 41
Appendix D Required Operator Actions Form ES-D-2 Time Page 1 of 1
Op-Test No.: I Scenario No.:
3 Event No.:
1 Event
Description:
B RBCCW Pump Trips Position BOP CRS BOP CRS 1-Applicants Actions or Behavior 9
9 Starts C RBCCW pump.
9 9
Monitor / verify RBCCW system for proper response.
Acknowledge / announce trip of B RBCCW pump.
Direct entry into PNPS 2.4.42, Section 4.4.
Direct Maintenance investigate cause of pump trip.
~~
_ _ _ _ ~
~
9 P
Determine EAL not exceeded.
Refer to Tech Spec 3.5.8 to initiate active LCO for inoperable containment cooling loop.
NUREG-I 021, Draft Revision 9 41 of41
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.:
1 Scenario No.:
3 Event No.:
2 II Page 1 of 1
Event
Description:
B FWLC Level Instrument Fails Downscale I1 Position 905 9051BOP 905 CRS Amlicants Actions or Behavior Recognize I announce annunciators:
9 REACTOR WTR LEVEL LO 9 RX FEED PUMP HI WTR LEVEL CHAN DNSCL Refer to ARPC905R D7 and D8 9
9 9
Check FWLC range level indication and Narrow Range Level indication on C9051 Determine that channel 6 of the FWLC range has failed downscale and is currently selected.
Select channel A on the REACTOR LEVEL SELECTOR switch on C905.
(CRITICAL TASK) 9 Acknowledge and announce that REACTOR WTR LEVEL LO alarm has cleared.
Direct entry into PNPS 2.4.49.
Direct I&C to investigate and correct cause of alarm.
Refer to Tech Specs. Table 3.2.F.
Enter 30 day active LCO failure of one FWLC level instrument.
Determine the RFPs will not trip on Hi Reactor Level.
9 9
9 9
9
W Time Atmendix D Reauired ODerator Actions Form ES-D-2 Position Applicants Actions or Behavior BOP Acknowledge I announce trip of B Feed pump Op-Test No.:
1 Scenario No.:
3 Event No.:
3 CRS Page 1 of I Direct entry into PNPS 2.4.49.
11 Event
Description:
B Feed Pump Trips 905 9
9 9
9 Acknowledge I announce lowering reactor water level.
Verify or manually runback Recirc. Pumps to 44% speed.
Restore Reactor water level to normal band.
If necessary, open the Startup Feed Regulating Valve.
L NUREG-I 021, Draft Revision 9 41 of 41
Appendix D Required Operator Actions Form ES-D-2 L
Op-Test No.:
1 ScenarioNo.: 3 Event No.:
4 I1 Page 1 of 2
Event
Description:
Condenser Air In-Leakage Position ALL CRS BOP 905 BOP CRS ADDlicants Actions or Behavior Recognize / announce indication of lowering vacuum.
Direct entry to PNPS, 2.4.36, Decreasing Condenser Vacuum.
> Check main condenser vacuum.
> Check hand operated valve 40-HO-I 28 from LP service air (air purge line) is fully closed.
Reduce power IAW PNPS 2.1.14, Sections 7.10 & 7.1 1 to stop vacuum decrease.
Verify open the condenser vapor valves for all in-service condenser water, boxes (AO-3710, AO-3704, AO-3703, & AO-3711).
Check that Turbine steam seal header pressure is approximately 3-4 psig.
When main condenser vacuum approaches 22 Hg with no indication of recovering, direct manual scram of reactor and PNPS 2.1.6 entry.
Appendix D Required Operator Actions Form ES-D-2 v
Op-Test No.:
1 Scenario No.:
3 Event No.: 4 Page 2 of 2
Event
Description:
Condenser Air In-Leakage Time Posit ion 905 Amlicants Actions or Behavior 9
9 Manually Scram the reactor prior to the turbine trip.
Enter 2.1.6, Reactor Scram and perform concurrently.
9 9
9 9
9 9
9 9
9 B
9 9
9 B
9 9
9 9
9 9
Depress both Reactor Scram push buttons.
Place Reactor Mode switch in SHUTDOWN.
Verify and announce the status of APRM downscales.
Verify all control rods are fully inserted.
Insert IRM and SRM detectors, select 2 SRMs for recording and place selector switch for APRM/IRM to IRM.
Verify or manually trip the turbine.
Verify or manually place Reactor Recirc Pumps at minimum speed.
Verify ALL scram discharge Volume Vent and Drain Valves are closed at panel C905.
Restore and maintain RPV water level between +20 inches and +40 inches using RCIC.
Stabilize RPV pressure between 900 and 1050 with HPCI.
Verify or manually transfer house loads to the Startup Transformer.
Direct tripping ETS.
Direct shutting down EHWC.
Direct starting all available drywell cooling fans on Panel C61.
Open / verify open all available Drywell Cooler Motor Operated Supply Valves on Panel C7.
Direct securing GEZIP.
Notify Radiation Protection that a scram has occurred.
Notify Radwaste that a scram has occurred.
Notify Chemistry to secure oxygen injection to the Condensate Pumps.
Secure the Gland Seal Condenser Drain Tank system by placing the control switch for AO-3367 on Panel C10 to CLOSE.
u NUREG-I 021, Draft Revision 9 41 of 41
4 Awendix D Reauired ODerator Actions Form ES-D-2 i,
Op-Test No.:
1 Scenario No.: 3 Event No.:
5 Page 1 of I Event
Description:
Lockout of A-I Upon Reactor Scram Time I Position BOP I
BOP I
CRS Amlicant's Actions or Behavior Recoanize Lockout of A-I.
Recognize Loss of All High Pressure Feed.
Recognize entry condition for EOP-01 at +I2 inches reactor water level.
Direct alternate level control using HPCl or RCIC.
Starts HPCl or RCIC for level control to maintain level +20 to +40 inches.
~~
Direct initiating a cooldown of less then 100 degrees F per hour.
Initiate a cooldown using HPCl or SRVs.
Verify Group 2 isolation, RBlS and Start of SBGT.
Amendix D Position BOP Reauired ODerator Actions Form ES-D-2 Applicant's Actions or Behavior Check / report area temperature alarms in RClC quad.
Page 1 of I Op-Test No.: I Scenario No.:
3 Event No.:
6 II BOP 11 Event
Description:
Unisolable Steam Leak from RCIC 9
9 Open all SRVs. (CRITICAL TASK)
Verify (using Acoustic Monitor or Tailpipe Temperature indication) that all SRVs are open.
Time CRS 9
9 9
9 9
9 9
9 9
9 Direct isolation of RClC when report of steam leak is received.
Before any area temperature exceeds Max Normal Value, enter EOP-04.
Direct RP to take EOP-04 radiation surveys.
Direct starting of all area coolers.
Direct operators to check Reactor Building quads for leakage.
Verify Refuel Floor Radiation below 16 mR/hr.
Determine that a Primary System is discharging into secondary containment.
Before any secondary containment temperature reaches Max Safe, reenter Direct Reactor water level maintained in +20 to +40 inch band.
Direct cooldown at less than 100 dearees F Der hour.
CRS Exit EOP-17 and reenter EOP-01 Pressure Control Leg.
NUREG-I 021, Draft Revision 9 41 of41
i _-
Time Appendix D Required Operator Actions Form ES-D-2 Position Applicant's Actions or Behavior ALL Recognize failure to RCIC to isolate.
Op-Test No.:
1 Scenario No.:
3 Event No.: -
7 Page 1 of 1
Description:
Failure of Group 5 Isolation Direct manual isolation of RCIC.
Attempt to manually close MO-13401-16 and MO-1301-17.
k Dispatch Maintenance or NLOs to attempt to close MO-1301-16 and MO-1301-17.
I CRS I
Terminate scenario at the discretion of the Chief Examiner after the Emergency Depressurization is complete.
EAL is Site Area Emergency, 4.2.1.3