ML022410248
| ML022410248 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/02/2002 |
| From: | Santiago M Entergy Nuclear Generation Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-293/02301 | |
| Download: ML022410248 (72) | |
Text
Scenario Outline Facility:
Examiners:
Pilgrim Scenario No.
1 Operators:
Op-Test No.:
1 Initial Conditions: 100% RCIC OOS, 'A' APRM Bypassed Turnover: Reduce reactor power to 50% in prep for backwash, shift TBCCW pumps for maintenance to perform vibration tests.
Event Malf.
Event l Event No.
No.
Type*
l Description 1
N/A N-BOP Shift TBCCW pumps for maintenance vibration test 2
N/A R-RO Reduce reactor power for thermal backwash 3
I/O C-RO
'A' Recirc scoop tube lockup TBCCW pump trip with failure to auto-start of other 4
CW03 I-BOP pump 5
FW23 C-RO FWLC transmitter fails high 6
MS011 Steam line break inside containment with all reactor FW01 M-ALL feed pumps tripping on the scram 7
HP04 C-BOP HPCI flow controller fails downscale
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Operator Actions Op-Test No.:
Scenario No.:
1 Event No.:
I Page 1 of Event
Description:
Shift TBCCW Pumps for Maintenance Vibration Test Time Position Applicant's Actions or Behavior Direct Starting 'B' TBCCW pump and securing 'A' TBCCW CRS pump IAW PNPS 2.2.31 section 7.6.
Start 'B' TBCCW pump. Verify proper indications, TBCCW BOP system pressure between 50 and 60 psig.
Secure 'A' TBCCW pump. Monitor/verify proper system BOP response.
Operator Actions Op-Test No.:
Scenario No.:
X Event No.:
2 Page 1 of 1 Event
Description:
Reduce Power for Thermal Backwash Using Recirc Time [Position Applicant's Actions or Behavior CRS Brief/Direct power reduction. IAW PNPS 2.1.14 section 7.3.
Inform l&C standby to adjust AGAFs to less than or equal to CRS 0.975.
RO Perform channel check PBDS IAW PNPS 2.1.5.
At Panel 904, use the Recirc. Pump speed controllers to RO lower core flow to 40Mlbm/hr.
BOP Verify SPEED LOAD CHANGER position 100 percent.
RO Plot position on power to flow map.
RO Monitor power, pressure and level.
Operator Actions Op-Test No.:
1 Scenario No.:
1 Event No.:
3 Page 1 of 1 Event
Description:
'A' Recirc Scoop Tube Lockup Time Position Applicant's Actions or Behavior Acknowledges /announces 'A' recirc tube lockup alarms.
RO Verifies by RED A" Recirc pump lockup light lit on 904.
CRS Directs entry into 2.4.19.
CRS Direct assessment of power to flow conditions.
RO Plot power and flow on power to flow map.
Monitor PBDS recorders for oscillations (no oscillations RO noted).
=
RO Ensures loop flows balanced IAW PNPS 2.1.5.
Determine cause to be loss of signal based on speed signal RO indication.
CRS Notify l&C to investigate and repair.
Request licensed operator standby for manual operation of CRS scoop tube positioner.
CRS Verify pump speeds within Tech Spec limits 3.6.F (within 10%
above 80% power).
=
CRS Identifies need to trip Recirc pump in event of SCRAM.
Operator Actions Op-Test No.:
1 Scenario No.:
1 Event No.:
4 Page 1 of 1 Event
Description:
TBCCW Pump Trip with Failure of Standby Pump to Auto-Start Time Position Applicant's Actions or Behavior Acknowledge/Announce Annuciator -trip of 'B' TBCCW BOP pump.
BOP Manually start 'A' TBCCW pump.
CRS Direct entry into PNPS 2.4.41.
CRS Identify 60 second delay to feed pump trip/loss of feed.
BOP Monitor /verify proper system response.
CRS Inform EM/maintenance to investigate and repair.
Reset Acknowledge Reset GEN MONITOR TROUBLE alarm BOP using KAYE computer.
Operator Actions Op-Test No.:
1 Scenario No.:
1 Event No.:
5 Page 1 of I Event
Description:
'B' FWLC Level Instrument Fails High Time Position Applicant's Actions or Behavior Recognize/announce annunciators
- RX FEED PUMP HI WTR LEVEL TRIP, REACTOR WTR LEVEL HI, RO RX FEED PUMP HI WTR LEVEL CHAN UPSCL in alarm RO/BOP Refer to ARP.
Check FWLC range level indication and Narrow Range Level RO indication on C905.
Determine that channel 'B' of the FWLC range has failed RO upscale and is currently selected.
Select channel 'A' on the REACTOR LEVEL SELECTOR RO switch on C905.
Acknowledge and announce that REACTOR WTR LEVEL HI RO alarm has cleared.
I CRS Direct entry into PNPS 2.4.49.
CRS Direct l&C to investigate and correct cause of alarm.
CRS Refer to Tech. Specs. Table 3.2.F.
CRS Enter 30 day active LCO for failure of one FWLC level instrument.
Operator Actions Op-Test No.:
1 Scenario No.:
1 Event No.:
6 Page 1 of 3 Event
Description:
Steam Line Break Inside Containment - All Reactor Feed Pumps Trip on the Scram Time Position Applicant's Actions or Behavior ALL Identify Drywell pressure increasing CRS Direct SCRAM when drywell pressure approaches 2.2 psig CRS Directs entry into EOP 1 and EOP 3 RO Place mode switch in shutdown and enter PNPS 2.1.6.
RO Verify and announce the status of APRM downscales.
RO Verify all control rods are fully inserted.
Insert IRM and SRM detectors, select two SRMs for RO recording, and place selector switch for APRM/IRM to "IRM".
Verify or manually place reactor recirc pumps at minimum RO speed.
Restore and maintain RPV water level between +20 inches and +40 inches.
BOP Identify/announce no RFPs operating CRS Direct alternate level control using HPCI/ CRD (see Event 7)
Starts HPCI for level control to maintain level +20 - +40 BOP inches
Operator Actions Op-Test No.:
1 Scenario No.:
1 Event No.:
6 Page 2 of 3 Event
Description:
Steam Line Break Inside Containment Time Position Applicant's Actions or Behavior Direct RPV pressure be maintained within 900 -1040 psig CRS using Bypass valves.
BOP Adjusts Bypass valves.
Directs maximizing Drywell cooling when Drywell temperature CRS cannot be maintained below 150 degrees.
BOP Maximize drywell cooling IAW PNPS 5.3.35.
Directs Torus sprays placed in service prior to Torus bottom CRS pressure exceeding 16 psig.
BOP Places Torus Spray in service IAW PNPS 5.3.35.
CRS Directs Hydrogen monitoring system placed in service.
Directs ADS be placed in inhibit when/if RPV level drops below - 45 inches.
CRS NOTE: CRITICAL TASK BOP Places ADS inhibit switch in INHIBIT when/if directed.
Directs Drywell Spray initiated if/when Torus bottom pressure exceeds 16 psig.
CRS NOTE: CRITICAL TASK Directs Drywell Spray initiated before Drywell temperature CRS exceeds 280 degrees.
Operator Actions Op-Test No.:
1 Scenario No.:
1 Event No.:
6 Page 3 of 3 Event
Description:
Steam Line Break Inside Containment Time Position Applicant's Actions or Behavior Determines primary containment parameters are being CIRS maintained and directs focus on EOP 1.
Directs RPV cooldown be established not to exceed 100 CRS degrees per hour.
BOP Establishes cooldown using HPCI/ Bypass valves.
Operator Actions Op-Test No.:
1 Scenario No.:
1 Event No.:
7 Page 1 of I Event
Description:
HPCI Flow Controller Fails Downscale Time Position Applicant's Actions or Behavior BOP Recognize/announce failure of HPCI flow controller.
CRS Direct taking HPCI to manual control.
Place HPCI controller in manual. Use HPCI to maintain reactor water level above TAF.
BOP NOTE: CRITICAL TASK CRS Direct l&C to troubleshoot HPCI controller.
The scenario will be terminated at the direction of the Chief Examiner after the plant has been stabilized and drywell spray is in service.
Expected EAL is 3.4.1.2.
Notes: Scenario 1
- 1.
Shift TBCCW pumps for maintenance vibes (2.2.31, Section 7.6).
- 2.
Reduce reactor power for thermal backwash. Per power maneuver plan 2.1.14 reduce flow to 40 Mlbm/hr then consult reactor engineering.
- 3.
'A' Recirc scoop tube lockup, after Reactivity manipulation, 2.4.19 while still adjusting Recirc. (A pump) B pump will trip from LPCI loop select. Check power/flow map dispatch operator locally, notify EM, licensed operator standing by locally. Follow action per 2.1.6 after scram to trip Recirc pump.
- 4.
'A' TBCCW pump trips with fail to auto-start of other pump. 2.4.41 Manually start 'B' TBCCW pump, 60 second delay Feed pump trip if not started. C-100 gen monitor trouble must reset on Kaye investigate cause.
- 5.
FWLC transmitter fails high (selected). Actual level drops, Operator must select other channel immediately or SCRAM will occur on low level. 2.4.49 place FRV in manual if this is done will SCRAM on low level. (No procedural guidance for selecting other channel). Tech Spec entry 3.2.F
- 6.
Steam line break inside containment all reactor feed pumps trip on the scram (10 % with 20 minute ramp) prior to SCRAM after SCRAM then 100 percent for 10 minutes.
Maximize Drywell cooling. Benchmark and SCRAM brief based on drywell press.
SCRAM 2.1.6 Trip A Recirc pump. All RFPs trip on SCRAM.
- 7.
HPCI flow controller fails downscale. Flow controller fails low conditional at 1000 GPM operator must take manual control to raise level.
- 8.
Classify as unusual event/site area based on drywell temperature.
Actions: Pending/ Active
- 1. IC-14
- 2. RCIC INOP active
- 3. A APRM Bypass active
- 4. A scoop tube lockup pending
- 5. B TBCCW pump breaker trip pending
- 6. A TBCCW fail to start (do not put in until after pumps are swapped) C/S trip pending, delete conditional on C/S to start active
- 7. Steam line break inside DW 10% /20 min ramp pending.
- 8. All RFPs breakers trip conditional with Mode switch to shutdown active
- 9. steam line break 100 % 10 min ramp conditional with M/S to shutdown active
- 10. HPCI flow controller fail low conditional 1000 gpm active
Critical Tasks: Scenario 1
- 1.
Inhibit ADS if level drops to less than -45 inches (may not)
- 2.
Manually initiate HPC maintain level above TAF
- 3.
Spray Drywell prior to Torus bottom pressure exceeding 16 psig EOPs ENTERED
- 1.
EOP 1
- 2.
EOP3 EOP CONTINGENCY NONE
Scenario Outline Facility:
Examiners:
Pilgrim Scenario No.:
2 Op-Test No.:
1 Operators:
Initial Conditions: 60% Power, 'A' IRM Bypassed, Core Flow 40 Mlbm/hr Turnover: Shutting down for maintenance outage per PNPS 2.1.14, Section 7.3.
Event Malf.
Event Event No.
No.
Type*
Description I
N/A N-BOP Remove 'C' RFP from service tag out 2
N/A R -RO Continue shutdown 3
RD07 C-RO Rod drift 4
NM1 I I-RO
'G' IRM fails upscale 5
HP01 C-BOP HPCI spurious ECCS actuation 6
FW01 C-BOP
'B' RFP trips 7
FWOL M-ALL Large break LOCA trip of remaining RFP on SCRAM 8
RH04 C-BOP RHR LPCI injection valve fails to open I
I
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Operator Actions Op-Test No.:
1 Scenario No.:
2 Event No.:
1 Event
Description:
Remove 'C' RFP From Service Tag-Out Page 1 of Time Position Applicant's Actions or Behavior Direct removal of 'C' RFP per PNPS 2.2.96 attachment 16 CRS section 7.3.3.
BOP Review PNPS 2.2.96, Attachment 16.
Performs steps 3.1[1] through [10]
Record pump to be secured (C)
- Place RFP TRIP SEQUENCE ENABLE switch in OFF position Verify total feedwater flow is less than 60 percent
- Place 'C' RFP control switch to STOP
- Verify Reactor water level is stable
- ACK and Reset all expected alarms
- Verify 'A' and 'B' RFP motor current is less than 650 amps
- Verify Aux lube oil pump for 'C' RFP auto starts Verify 'C' RFP recirc valve close Direct 'C' RFP Hydrogen injection valve be closed BOP Direct control switch SW619 taken to CLOSED BOP Monitor 'C' RFP pump lube oil temperature.
When lube oil temperature cooled to 90 -110 degrees:
BOP Shutdown 'C' RFP Auxiliary lube oil pump.
CRS Direct tag out of 'C' RFP.
BOP Hang tag on 'C' RFP control switch.
Operator Actions Op-Test No.:
Scenario No.:
2 Event
Description:
Continue Shutdown Event No.:
2 Page 1 of 1 Time Position Applicant's Actions or Behavior Directs power reduction to 50 percent power using reverse CRS order of withdrawal sheet IAW PNPS 2.1.14, Section 7.3.
RO Reduces power using reverse order of withdrawal sheet.
Monitors Reactor power plots power/flow on power to flow RO map.
RO If approaching monitored region, verifies both channels of PBDS operable.
Operator Actions Op-Test No.:
1 Scenario No.:
2 Event No.:
3 Page 1 of 1 Event
Description:
Rod Drift Time Position Applicant's Actions or Behavior Acknowledges/announces rod drifting out when drive in switch released.
RO Acknowledge Annuciator refers to ARP C905L-A3.
RO Verifies rod selected, identifies affected rod.
CRS Directs entry into PNPS 2.4.11.
CRS Determines power cannot be reduced further by Recirc flow.
CRS Directs affected rod be fully inserted.
RO Inserts affected rod to 00 position Identifies rod remains at 00 position and is no longer drifting RO out.
Contacts Reactor engineering to modify Rod Sequence sheet CRS and power maneuvering guidance.
Notifies I&C to develop troubleshooting guide IAW PNPS CRS 3.M. 1-34.
CRS Refers to Tech Spec 3.3.H for verifying BPWS CRS Initiates condition report to document rod drift.
Operator Actions Op-Test No.:
1 Scenario No.:
2 Event No.:
4 Page 1 of I Event
Description:
'G' IRM Fails Upscale Time Position Applicant's Actions or Behavior RO Acknowledges/announces 'G' IRM HI HI alarm (refers to A R P).
=
CRS Determines 'G' IRM failed upscale.
CRS Direct 'G' IRM placed in BYPASS.
CRS Refers to Tech Spec Tables 3.1.1 and 3.2.C.
CRS Initiates tracking LCO for Table 3.1.1 I RM scram.
Operator Actions Op-Test No.:
1 Scenario No.:
2 Event No.:
5 Page 1 of 1 Event
Description:
HPCI Spurious ECCS Actuation Time J Position Applicant's Actions or Behavior ALL Identify unexplained increase in power.
Direct entry into PNPS 2.4.13, Unexplained Rapid Increase in CRS Reactor Power.
ALL Recognize that HPCI has started.
Direct entry into PNPS 2.4.35, "Inadvertent Initiation of Core CRS Standby Cooling Systems".
Inadvertent initiation is verified (Drywell < 2.2 psig/RPV level CRS/BOP
> -46 inches) on two independent instruments.
BOP Depress and hold the HPCI Turbine Trip pushbutton.
After the turbine has come to a complete stop, places the Aux. Oil Pump (P-229) control switch to the PULL TO LOCK BOP position.
BOP Releases the Turbine Trip push button.
Assess operating conditions by plotting power versus core flow on the Pilgrim Power/Flow Map, then perform action CRS/RO required IAW 2.1.14 Section 7.10.
CRS References 2.1.14 Section 7.10.
Monitor PBDS Recorders for any indications of power RO oscillations. (No indication of oscillations.)
Check process Radiation Monitors for indications of Fuel CRS/BOP damage. (No indication of oscillations.)
Verify that peak power and pressure did not exceed any CRS/RO limits.
CRS Investigate cause of inadvertent initiation by calling l&C.
Operator Actions Op-Test No.:
1 Scenario No.:
2 Event No.:
6 Page 1 of 2 Event
Description:
'B' RFP Trips Time Position l
Applicant's Actions or Behavior BOP Acknowledges/announces trip of 'B' Feed pump.
=
CRS Directs entry into PNPS 2.4.49.
RO Acknowledges/announces lowering reactor water level approaching SCRAM setpoint.
Directs mode placed in SHUTDOWN perform actions of CRS PNPS 2.1.6.
RO Place mode switch in shutdown and enter PNPS 2.1.6.
RO Verify and announce the status of APRM downscales.
RO Verify all control rods are fully inserted.
Insert IRM and SRM detectors, select two SRMs for RO recording, and place selector switch for APRM/IRM to "IRM".
RO Verify or manually place reactor recirc pumps at minimum speed.
RO Verify or manually place reactor recirc pumps at minimum speed.
Maintain reactor water level +20 - +40 inches using RO feedwater.
Restore and maintain RPV water level between +20 inches and +40 inches.
BOP Identifies trip of remaining feed pump.
Operator actions Op-Test No.:
1 Scenario No.:
2 Event No.:
6 Page 2 of 2 Event
Description:
'B' RFP Trips Time Position Applicant's Actions or Behavior CRS Directs entry into EOP-1 based on Reactor water level CRS Directs Reactor water level band +20 to +40 inches BOP Announces 'A' RFP tripped on SCRAM CRS Directs starting HPCI/ RCIC alternate method of level control.
Starts HPCI/RCIC as needed to maintain water level above TAF.
BOP NOTE: CRITICAL TASK
Operator Actions Op-Test No.:
1 Scenario No.:
2 Event No.:
7 Page 1 of 4 Event
Description:
LOCA Time l
Position ]
Applicant's Actions or Behavior BOP/RO Recognize/announce rising drywell parameters.
CRS Recognize/announce EOP-03 entry conditions.
Report to the CRS when out of current RPV level/pressure RO/BOP band.
Establish new pressure bands as the reactor depressurizes CRS due to the leak.
When Drywell temperature cannot be maintained < 150'F, directs that Drywell cooling be maximized.
Note:
Drywell area cooler load shed must be defeated to do CRS this.
Maximizes RBCCW on the 'B' loop of RBCCW RO/BOP Maximizes Drywell cooling When Torus temperature cannot be maintained < 800F, CRS directs that Torus cooling be maximized.
BOP Maximizes RBCCW. Maximizes Torus cooling.
Before drywell pressure reaches 16 psig, directs that Torus spray be placed in service using 'A' or 'B' RHR. Directs that CRS Torus Spray secured if Drywell pressure goes below 2.2 psig.
BOP Starts Torus Spray using 'A' or 'B' RHR.
Operator actions Op-Test No.:
1 Scenario No.:
2 Event No.:
7 Page 2 of 4 Event
Description:
LOCA Time Position Applicant's Actions or Behavior When Drywell pressure exceeds 16 psig:
Verifies Drywell temperature and pressure within DSIL (Fig. 5).
- Verifies torus water level below 180 inches.
- Verifies Recirc pumps shutdown.
- Directs that Drywell sprays be placed in service using A/B RHR loops.
Directs that Drywell spray secured if Drywell pressure CR5 goes below 2.2 psig.
Places drywell sprays in service using A/B RHR loops.
BOP NOTE: CRITICAL TASK Recognize/announce that HPCI is not keeping up with the l
RO leak.
Determines water level cannot be maintained above + 12 and establishes a new band between -125 and +45. Directs thatl CRS CRD be placed in 2 pump operation.
Directs that the RBO lineup the CRD system for 2 pump operation.
IF OPERATOR: If asked to line up the CRD pumps for 2 pump operation, wait 5 minutes and report that the CRD RO pumps are lined up for two pump operation.
When the Reactor Building Operator reports that the CRD system is lined up for two pump operation, starts the second RO CRD pump.
Operator Actions Op-Test No.:
1 Scenario No.:
2 Event No.:
7 Page 3 of 4 Event
Description:
LOCA Time l
Position l
Applicant's Actions or Behavior BOP Recognizes/announces any/all of the following:
- RPV water level at or below -46 inches.
2 minute timer initiated.
Directs that the ADS Inhibit keylock switch be taken to the CRS "INHIBIT" position.
Places the ADS Inhibit switch in the "INHIBIT" position.
BOP NOTE: CRITICAL TASK Orders a cooldown at a rate < 1 000F/hr.
Note:
The RPV should be depressurizing slowly on its own due to the medium break LOCA and the use of CRS HPCI to maintain level.
BOP Monitors pressure bands established by the CRS.
Determines water level cannot be maintained above -125.
Directs that 2 or more Injection Systems, Table C lined up for CRS injection and the pumps started.
Lines up for injection and starts all available RHR and Core BOP Spray pumps.
If RPV level reaches TAF, determines that Alternate RPV Depressurization is required and enters EOP-17.
- Determines steam cooling is not required.
- Verifies Torus water level is > 50 inches.
CRS Directs that all 4 SRVs opened.
Operator Actions Op-Test No.:
1 Scenario No.:
2 Event No.:
7 Page 4 of 4 Event
Description:
LOCA Time Position Applicant's Actions or Behavior Opens all 4 SRVs.
BOP NOTE: CRITICAL TASK Verifies that they have opened:
Checks the acoustic monitor lights on Panel C171.
BOP Checks SRV tail pipe temperatures on Panel C921.
CRS Asks if RPV water level can be determined.
BOP/RO Report that RPV water level can be determined.
When RPV pressure goes below the shutoff head of the low pressure ECCS directs that RPV level restored and CRS maintained +20 to +40 using the low pressure ECCS pumps.
Restores and maintains RPV +20 and +40 using low-BOP pressure ECCS pumps.
The scenario shall be terminated when RPV level is restored and maintained between +20 and +40 and when directed by the Chief Examiner.
Expected EAL is "Alert" 3.4.1.2.
Operator Actions Op-Test No.:
1 Scenario No.:
2 Event No.:
8 Page 1 of 1 Event
Description:
LPCI Injection Valve Fails to Open Time Position Applicant's Actions or Behavior BOP Announces no injection flow 'B' loop during RHR 29B being closed.
CRS Directs RHR 29 B to be opened.
BOP Opens 29B and verifies injection flow.
Notes: Scenario 2
- 1.
Remove 'C' RFP from service tag out immediately to make unavailable
- 2.
Continue shutdown
- 3.
Rod drift 4th rod and last rod in step 66, step 67 complete, drift out when released remove drift when 00 position reached
- 4.
'G' IRM fails upscale (Tech Spec entry) 3.1
- 5.
- 6.
'B' RFP trips level drops manual SCRAM on level
- 7.
Large break LOCA ramped in 5000 gpm ramped 5 min B loop trip remaining feed pump on scram insert 1000 gpm leak other loop
- 8.
RHR 29-B fails to open
Actions: Scenario 2 Pending/ Active
- 1.
!C-14 ramp down to 60 percent
- 2.
A IRM Bypassed active
- 3.
G IRM downscale pending
- 4.
Rod drift last rod in and 4th rod in step 66 step 67 Delete conditional on rod select light and full in light.
- 5.
HPCI spurious actuation pending
- 6.
B RFP breaker trip pending
- 7.
LOCA 5000 B loop gpm ramp 5 minutes pending
- 8.
C RFP pump breaker trip conditional with mode switch in shutdown
- 9.
LOCA A loop 1000 gpm pending
- 10. RHR 29B fail to open pending
Critical Tasks: Scenario 2
- 1.
Spray Drywell
- 2.
Manually initiate HPCI
- 3.
Blow down when level less - 150 inches EOPs ENTERED
- 1.
EOP 1
- 2.
EOP 3
- 3.
EOP 17 EOP CONTINGENCY Emergency depressurization
Scenario Outline Facility:
Pilgjrim Scenario No.:
3 Op-Test No.:
1 Examiners:
Operators:
Initial Conditions: 20% turbine synchronized to grid, 'A' RBCCW pump out of service.
Turnover: Starting up following scram MSIV twice weekly surveillance, PNPS 8.7.4.5 needs to be performed on the 'A' Inboard and Outboard MSIVs.
Event Malf.
Event Event No.
No.
Type*
Description 1
N/A N-BOP MSIV twice weekly surveillance, PNPS 8.7.4.5 post l_
work testing.
2 N/A N-RO Continue reactor startup.
3 I/O C-RO CRD FCV controller failure closed.
4 CW05 C-BOP
'B' RBCCW pump trip.
5 FW19 I-RO FRV lockup.
MT03/
Turbine high vibration. Bypass valves fail closed 30 6
TC09 C-BOP seconds after turbine trip.
7 IO/RD2 M-ALL ATWS.
l RD16 8
LP02/
C-RO SLC pump failure.
l _
LPO 1 t (N)ormal, (K)eactivity, (I)nstrument, (u)omponent, (M)aJor
Operator Actions Op-Test No.:
1 Scenario No.:
3 Event No.:
1 Page 1 of 1 Event
Description:
MSIV Twice Weekly Surveillance T
Position Applicant's Actions or Behavior J
Brief/direct PNPS 8.7.4.5, "MSIV Twice Weekly Exercise".
Logs the performance of the test in the Station Log Book CRS when the test is completed.
Reviews precautions and limitations of 8.7.4.5. Reads appropriate Notes and Cautions. Correctly performs steps of BOP the procedure. Verifies Acceptance Criteria met.
Observes steam flows through the steam lines while the MSIVs are being tested. Announces "MSIV Not Full Open" annunciators and provides verification that the MSIV is open.
RO Verifies the Acceptance Criteria is met.
IF OPERATOR: When asked as the OSS to sign off the Acceptance Criteria, come in as the OSS and take the completed procedure for review.
Operator Actions Op-Test No.:
1 Scenario No.:
3 Event No.:
2 Page 1 of 1 Event
Description:
Continue Raising Power Using Control Rods Time Position Applicant's Actions or Behavior CRS Brief/Direct power increase IAW PNPS 2.1.1 and 2.1.14.
Withdraws control rods in a safe and controlled manner.
- Regularly checks APRM channel indications.
RO Plots power to flow.
Serves as peer checker/second verifier during control rod BOP movement.
RO Monitors RPV power, pressure and level.
Operator Actions Op-Test No.:
1 Scenario No.:
3 Event No.:
3 Page 1 of 1 Event
Description:
CRD FCV Controller Failure Closed Time Position Applicant's Actions or Behavior Determines no rod movement while attempting to withdraw rods.
RO Identifies CRD flow indication low.
Identifies FCV failed closed.
CRS Directs entry into PNPS 2.4.11.1, Attachment 4.
Places CRD FLOW CONTROLLER to MANUAL.
RO Control flow at 50 GPM Check DRIVE WTR and COOLING WTR DIFF PRESS RO indicators adjust as needed.
RO Adjust DRIVE WTR PCV as necessary.
Operator Actions Op-Test No.:
1 Scenario No.:
3 Event No.:
4 Page 1 of 1 Event
Description:
'B' RBCCW Pump Trips Time Position Applicant's Actions or Behavior BOP Acknowledges/announces trip of 'B' RBCCW pump.
CRS Directs entry into PNPS 2.4.42 section 4.4.
BOP Monitors/verifies RBCCW system for proper response.
Refer to Tech Spec 3.5.B to initiate active LCO for inoperable CRS containment cooling loop.
Operator Actions Op-Test No.:
1 Scenario No.:
3 Event No.:
5 Page 1 of 1 Event
Description:
'A' FRV Lockup Time
[Position Applicant's Actions or Behavior Acknowledge announce 'A' Feed Reg. Valve Control Signal RO Failure.
RO Checks power, pressure, level.
RO Announces 'A' Feed Reg. Valve Lockup.
CRS Direct 'A' Feed Reg. Valve Placed in Manual.
RO Places 'A' Feed Reg. Valve Placed in Manual.
CRS Directs entry into PNPS 2.4.49.
CRS Notify l&C to investigate and repair.
CRS Directs actions for Reactor level control.
Note: IF operator should call in as I&C and report that the lockup was due to the spurious blowing of a fuse and request permission to replace the fuse. If permission is l
given, delete malfunction.
RO Depress and release pushbutton for 'A' FRV Reset on C905.
Operator Actions Op-Test No.:
1 Scenario No.:
3 Event No.:
6 Page 1 of 1 Event
Description:
Turbine High Vibration Bypass Valve Fail to Open When Turbine Tripped Time Position Applicant's Actions or Behavior Recognize/announce "Turbine Vibration Hi" alarm. Refers to ARP C2L-A3. Checks Vibration & Eccentricity recorder (VR-BOP 3000 on Panel C2).
Enters and executes steps of 2.4.46, "Turbine Bearing CRS/BOP Malfunction".
Recognizes/announces Step 4.0[1], which establishes vibration limits. Directs the crew to make note of the time which turbine bearing vibration reaches 10 mils. Attempts to reduce vibration levels by directing the RO to reduce Reactor CRS power.
In order to reduce Main Turbine vibrations, lowers Speed BOP Load Changer setting.
Places Vibration & Eccentricity recorder VR-3000 to fast BOP speed.
When turbine vibrations have been at 10 mils for 10 minutes, directs a reactor scram and entry into PNPS 2.1.6, "Reactor CRS Scram" turbine trip.
Directs a reactor scram by taking the MODE switch to the "SHUTDOWN" position and the RO to take the actions of CRS 2.1.6. Directs RPV level maintained +20 to +40 inches and RPV pressure 900 - 1050 psig.
NOTE: Power reduction may result in the stop valve closure scram being bypassed. If so, the plant should be scrammed when reactor pressure starts to increase due to bypass valve failure. If the stop valve closure scram is not bypassed, the reactor should be scrammed prior to turbine trip.
Operator Actions Op-Test No.:
1 Scenario No.:
3 Event No.:
7 Page 1 of 3 Event
Description:
ATWS Time Position J Applicant's Actions or Behavior Enters EOP-01 and immediately transitions to EOP-02 based CRS on all controls rods not at or beyond position 02.
Verifies the immediate actions required by EOP-02:
Verifies mode switch in "SHUTDOWN".
- Verifies both channels of ARI initiated.
Verifies the turbine has tripped.
Recognizes reactor power is above 3%.
- Verifies both Recirc. pumps are tripped.
Performs the following actions:
Verifies mode switch in "SHUTDOWN".
Initiates both channels of ARI.
Recognizes the turbine has tripped.
Recognizes reactor power is above 3%.
- Trips/verifies tripped both Recirc. pumps.
Orders new RPV level and pressure bands:
Level -25 to -45 inches.
- Pressure 1000 to 1050 psig using SRVs.
Orders the RO to enter into PNPS 5.3.23, "Alternate Rod CRS Insertion".
CRS Direct initiation of SBLC as required by EOP-02.
RO Recognize/report that after starting the 'A' SBLC train, the 'A' pump starts, but the 'A' squib valve fails to fire (see Event 8).
Operator Actions Op-Test No.:
1 Scenario No.:
3 Event No.:
7 Page 2 of 3 Event
Description:
ATWS Time Position Applicant's Actions or Behavior Enters PNPS 5.3 23, "Alternate Rod Insertion". Determines that there is an hydraulic lock and goes to Section 2.3 of the procedure and performs it concurrently with the "General RO Actions" section of the procedure.
When RPV level is determined to be greater than - 25 inches enters the 'Q' Leg of EOP-02 and performs the following steps:
Orders stop and prevent all injection into the vessel CRS except from SBLC and CRD.
Closes/verifies closed the feedwater reg valves and Startup Feed Reg. Valve.
RO NOTE: CRITICAL TASK NOTE: IF THE 'A' FRV IS STILL LOCKED, THE OPERATOR MUST CLOSE THE FEEDWATER HEATER DOWNSTREAM BLOCK VALVES OR TRIP THE RFP'S SINCE THE FRV'S CANNOT BE CLOSED. THE CRITICAL l
PORTION IS THAT FEED IS SECURED.
Places the control switches for the RHR and Core Spray pumps in the PTL position. Trips/verifies stopped the HPCI turbine and places the Aux. Oil pump control switch in the PTL position. Trips the RCIC turbine.
BOP NOTE: CRITICAL TASK Asks the crew to report any of the following plant conditions:
Rx power <3% (APRM downscales are in).
CRS RPV water level reaches -125 inches TAF.
Operator Actions Op-Test No.:
1 Scenario No.:
3 Event No.:
7 Page 3 of 3 Event
Description:
ATWS Time Position l
Applicant's Actions or Behavior Performs the following actions to reset and scram the reactor:
Resets and verifies reset the scram using the RPS reset switch.
- Places the Air Dump System Test Switch to "ISOLATE".
Waits for/verifies the "SPVAH Pressure Lo" alarm clears.
Places the Air Dump System Test Switch to "NORMAL".
Verifies either SDIV Level Hi or SDIV East Not Drained and SDIV West Not Drained alarms are clear.
- Initiates a manual scram.
- Verifies and announces all rods in.
RO NOTE: CRITICAL TASK NOTE: EXAMINER WILL CUE THE IF OPERATOR TO ALLOW RPS/ARI TO BE RESET SO THAT RODS CAN BE SCRAMMED.
When all rods are in transitions to EOP-01. Orders RPV water level be restored and maintained between +20 and +40 inches. Initiates a cooldown using HPCI or SRVs at less than CRS 1000 per hour.
Restores and maintains RPV level +20 to +40. Initiates a BOP cooldown at less than 100° per hour.
The scenario will be terminated at the direction of the Chief Examiner when level has been restored to between +20 and
+40 and a cooldown has been initiated.
Expected EAL is 2.3.1.3.
Operator Actions Op-Test No.:
1 Scenario No.:
3 Event No.:
8 Page 1 of 1 Event
Description:
SBLC Failure Time Position Applicant's Actions or Behavior Direct initiation of SBLC as required by EOP-02 or CRS Operations Policy Statement.
Start one SBLC system by placing the SLC ACTUATE switch RO to SYS 'A' or SYS 'B' position on Panel C905.
Recognize/report that after starting the 'A' SBLC train, the 'A' RO pump starts but the 'A' Squib valve fails to fire.
CRS Direct using other train of SBLC.
RO Start the 'B' SBLC train with the SLC ACTUATE switch.
Recognize/report that after starting the 'B' SBLC the 'B' pump l
RO trips but the 'B' Squib valve fires.
CRS Direct using other train of SBLC.
RO Start the 'A' SBLC train with the SLC ACTUATE switch.
Recognize/report The 'A' SBLC pump is running injecting through the 'B' Squib valve. Verifies Boron injection based on pump discharge pressure and lowering tank level.
RO NOTE: CRITICAL TASK NOTE: THE OPERATOR MAY CHOOSE TO USE RWCU TO INJECT BORON INSTEAD OF USING 'A' SBLC PUMP VIA 'B' SQUIB VALVE. THE CRITICAL PORTION IS THAT BORON BE EITHER INJECTED WITH SBLC OR ORDERED INJECTED WITH RWCU.
Notes: Scenario 3
- 1.
Continue reactor startup: lAW 2.1.1 using rod pull sheet
- 2.
MSIV twice weekly surveillance, PNPS 8.7.4.5 post work testing: may only have 2-3 valves to test
- 3.
CRD FCV controller failure closed: Initiate after Reactivity manipulation complete, identify call for repairs restore to auto
- 4.
'B' RBCCW pump trip: enter 2.4.42 A RBCCW tagged out auto start C RBCCW auto start failed, must start manually. Tech Spec addressed active LCO containment cooling 3.5.B.3
- 5.
FRV lockup: 905R G8 2.4.49 place FRV in manual 2.2.82 may want to do at 30% to make sure both FRV in service.
- 6.
Turbine high vibration bypass valve fail to open when turbine tripped:
enter 2.4.46 May use speed load changer to reduce load and stay below turbine trip bypass thus not requiring Scram if so when turbine tripped 30 seconds later bypass valve closes pressure increase requiring Scram. EPIC group display #28 manual trip required 1Omils for 10 minutes
- 7.
ATWS: EOP 2 entry Q leg stop and prevent feed -25 inches
- 8.
SLC failure: One pump and one valve inop. must fire both sides to inject depending on sequence may require third switch cycle, must verify flow and level indications to verify injection
Actions: Scenario 3;Pending/ Active
- 1. IC-9
- 3. FRV AUTO signal lockup pending
- 4. B RBCCW pump trip pending
- 5. C RBCCW pump C/S trip active
- 6. C RBCCW trip delete conditional C/S to start active
- 8. Turbine bearing # 5 high vibs 11 mils 10 min ramp pending delete conditional turbine trip pending
- 9. Bypass fail to open conditional turb trip 30 second delay active 10.ATWS SDIV level inst failed both active
- 11. SDIV drn valve stem broken both sides active
- 12. SDIV 100 % both active
- 13. SDIV high level inst delete conditional with scram 14.SDIV stem broken delete conditional air dump system test
Critical Tasks: Scenario 3
- 1. Insert control rods
- 2. Initiate Standby Liquid
- 3. Q leg Stop and prevent greater than -25 inches EOPs ENTERED
- 1. EOP 1
Scenario Outline Facility:
Pilgrim Scenario No.:
4 Op-Test No.:
1 Examiners:
Operators:
Initial Conditions: 100% Power, RHR Pump 'A' Tagged Out for Bearing Replacement Turnover: Swap CRD FCV for maintenance, PNPS 2.1.37 in effect, Step 7.2(6) complete, Ops manager consulting REMVEC evaluating power reduction. In day one of seven day LCO for 'A' RHR pump OOS.
Event Malf.
Event Event No.
No.
Type*
Description 1
N/A R-RO Reduce power due to report of Coastal storm 3
RD05 C-RO CRD pump trips 5
MS14 C-BOP SRV fails open 6
IO/
ED06 M-ALL Degraded grid leading to LOSP RC06/
7 10 M-ALL Steam leak in Secondary Containment in RCIC quad v
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Operator Actions Op-Test No.:
1 Scenario No.:
4 Event No.:
1 Page 1 of 1 Event
Description:
Swap CRD FCV Time Position Applicant's Actions or Behavior CRS Brief/Direct changeover of flow control valves.
RO Establish communications between Control Room and the master control station.
At Panel C905, place FIC-340-1, CRD Flow Control, setpoint RO 0 GPM (controller may be left in automatic).
Direct NLO to:
- 1) Slowly open 301 -40B, Standby Flow Control Valve 'B' Inlet Valve
- 2) Slowly open 301-41 B, Outlet Valve from Standby Flow Control Valve
- 3) Close 301-41A, Outlet Valve from In-Service Flow Control Valve
- 4) Close 301-40A, Inlet Valve for the Previously In-Service Flow Control Valve
- 5) On local valve control panel, swap Selector Switch 3B-S1, for electrical signal to E/P unit, from valve in-service to standby valve position
- 6) Swap valve 301-29, CRD Air Diversion Valve to Selected Flow Control Valve, from valve in-service position to that RO of standby valve.
At Panel C905, slowly raise setpoint of FIC-340-1, CRD flow control, to 50 GPM, observing the flow increase as setpoint RO increases.
At Panel C905, check the following AP indicators and adjust pressures if needed:
Drive water differential pressure.
RO Cooling water differential pressure.
Operator Actions Op-Test No.:
1 Scenario No.:
4 Event No.:
2 Page 1 of I Event
Description:
Reduce Power Due to Report of Coastal Storm Time Position Applicant's Actions or Behavior Note: Cue the following:
Ops manager directs power reduction below 70 percent load line IAW PNPS 2.1.14 section 7.3.
CRS Direct power reduction using recirc flow to 40MIbm/hr.
RO Lowers Recirc flow to 40 Mlbm/hr.
Operator Actions Op-Test No.:
1 Scenario No.:
4 Event No.:
3 Page 1 of 1 Event
Description:
Time Position Applicant's Actions or Behavior Recognize/announce various annunciators associated with the loss of 'A' RPS bus.
Recognize/announce loss of 'A' RPS bus.
Recognize/announce annunciator "RPS MG Set A Trip" is in alarm.
CRS Directs that action be taken per ARP C905R-C1.
Direct transfer RPS bus 'B' to Standby Transformer (Panel CRS C511) and reset half-scram.
NOTE: MAY CALL NLO TO THE CONTROL ROOM FOR A BRIEF PRIOR TO PLACING RPS ON BACKUP
l Directs TBO transfer 'A' RPS Bus to the standby transformer per 2.2.79.
Resets the Y scram when A' RPS Bus is on the standby RO transformer.
Direct I&C to determine the cause of the breaker trip and inspect equipment powered from this source for electrical CRS faults.
CRS Refers to Tech Specs 3.1 and Table 3.1.1.
Resets the Main Steam Line and Air Ejector Offgas Rad BOP monitors.
Operator Actions Op-Test No.:
1 Scenario No.:
4 Event No.:
4 Page 1 of 1 Event
Description:
'A' CRD Pump Trips Time Position Applicant's Actions or Behavior RO Acknowledges/announces trip of 'A' CRD pump.
CRS Directs entry into PNPS 2.4.4.
Checks power, pressure, level. Performs immediate actions of PNPS 2.4.4:
RO Notes pressure greater than 950 psig.
No inoperable accumulator alarms.
CIRS Directs RO to start standby CRD pump IAW with PNPS 2.4.4
- Transfers FCV to manual and closes.
- Starts 'B' CRD pump.
- Verifies pump amp and discharge pressure stabilize.
- Balances deviation meter.
Transfers CRD controller to AUTO.
Operator actions Op-Test No.:
1 Scenario No.:
4 Event No.:
5 Page 1 of 1 Event
Description:
'A' SRV Fails Open Time Position Applicant's Actions or Behavior ALL Identify/announce 'A' SRV open.
CRS Direct entry into PNPS 2.4.29.
CRS Direct monitoring of Torus bulk temperature and note time.
CRS Direct BOP to attempt cycling of 'A' SRV switch.
BOP Cycles 'A' SRV switch identifies 'A' SRV remains open.
Directs opening of ADS power supplies:
- Panel D-4 Bkr#1 opened.
BOP Panel D-5 Bkr #2 opened.
NOTE: CRITICAL TASK Verifies 'A' SRV closes:
BOP Verifies acoustic monitor indicates 'A' SRV closed.
BOP Directs local control of 'A' SRV be taken at ASP and closed.
Directs reclosing of ADS power supplies:
- Panel D-4 Bkr #1 closed.
BOP Panel D-5 Bkr #2 closed.
Briefs manual operation of 'A' SRV will be required if CRS blowdown needed.
Operator Actions Op-Test No.:
1 Scenario No.:
4 Event No.:
6 Page 1 of 3 Event
Description:
Degraded Grid Leading to LOSP Time Position Applicant's Actions or Behavior Note: Cue: REMVEC notifies "can't guarantee SUT voltage will remain above 342 KV if unit trips" ALL Identify/announce degraded voltage condition.
CRS Directs entry into PNPS 2.4.144.
Directs/brief if voltage drops to 3868 on Bus A5 or A6 initiate CRS SCRAM perform actions of PNPS 2.1.6.
CRS Direct Recirc pump scoop tube lock up be initiated.
Depresses both scoop tube lock up pushbuttons for 'A' and RO
'B' recirc pumps.
CRS Note: Either D/G may be selected first.
Direct 'B' EDG started and loaded onto A6 bus.
Places 'B' EDG in service IAW PNPS 2.4.144 BOP Section 4.1(2).2a-o.
ALL Identify voltage on bus A5 drops to less than 3868 volts.
Directs mode switch taken to SHUTDOWN and perform CRS action of PNPS 2.1.6.
RO Place mode switch in shutdown and enter PNPS 2.1.6.
RO Verify and announce the status of APRM downscales.
RO Verify all control rods are fully inserted.
Operator Actions Op-Test No.:
I Scenario No.:
4 Event No.:
6 Page 2 of 3 Event
Description:
Degraded Grid Leading to LOSP Time Position Applicant's Actions or Behavior Insert IRM and SRM detectors, select two SRMs for RO recording, and place selector switch for APRM/IRM to "IRM".
RO Manually trip Reactor Recirc Pumps.
RO Verify or manually trip the turbine.
Maintain reactor water level +20 - +40 inches using RO feedwater.
ALL Identify LOSP when turbine taken offline.
BOP/RO Report EOP-01 entry conditions.
Enters EOP-1. Verifies:
l Isolations.
- ECCS initiations.
lCRS
- Emergency Diesel Generator initiations.
Announces entry into 2.4.16, "Distribution Alignment Electrical Systems Malfunctions". Directs actions be taken CRS per 2.4.16.
Using PNPS 2.4.16, "Distribution Alignment Electrical Systems Malfunctions", performs the following steps concurrently:
Places the Fast Transfer switches Al -A6 to the "OFF" position.
l Performs 5.3.6, Loss of Instrument Air.
l Connects Atlas COPCO air compressor.
l Verifies TBCCW system operation IAW 2.4.41.
Operator Actions Op-Test No.:
1 Scenario No.:
4 Event No.:
6 Page 3 of 3 Event
Description:
Degraded Grid Leading to LOSP Ti Position Applicant's Actions or Behavior All Close/verify closed MSIVs.
Directs that RPV level be maintained using HPCI and RPV CRS pressure maintained using SRVs.
RO Maintain RPV level using HPCI +20 - +40 inches.
BOP Maintains RPV pressure using SRVs 900 - 1040 psig.
Directs that CRD pump load shed be defeated per PNPS CRS 2.4.4, "Loss of CRD Pumps".
Using PNPS 2.4.4, "Loss of CRD Pumps" calls l&C and has RO CRD Pump load shed defeated.
Directs that Drywell cooler load shed be defeated per PNPS lI RS 2.4.44, "Loss of Drywell Area Coolers".
Using PNPS 2.4.44, "Loss of Drywell Area Coolers", calls l&C RO and has Drywell cooler load shed defeated.
Operator Actions Op-Test No.:
I Scenario No.:
4 Event No.:
7 Page 1 of 2 Event
Description:
Steam Leak Outside Containment RCIC Quad Time Position Applicant's Actions or Behavior BOP Check/report area temperature alarms in RCIC quad.
CRS Enter EOP-04 on high area temperature in RCIC quad.
CRS Direct isolation of RCIC when report of steam leak is received.
CRS Direct RP to take EOP-04 surveys.
CRS Direct starting all area coolers.
Before any area temperature exceeds Max Normal Value, CRS enter EOP-04.
Operator actions Op-Test No.:
1 Scenario No.:
4 Event No.:
7 Page 2 of 2 Event
Description:
Steam Leak Outside Containment RCIC Quad Time Position Applicant's Actions or Behavior ALL Recognize failure of RCIC to isolate.
CRS Direct manual isolation of RCIC.
Attempt to manual close MO-1301-16 and MO-1 301-17.
l BOP Report the attempt was unsuccessful.
Dispatch Maintenance or NLO's to attempt to close l
CRS MO-1301-16 and MO-1301-17.
When temperature exceeds Max Safe Value in two areas, l
CRS exit EOP-04 pressure control leg and enter EOP-1 7.
Open all SRV's:
BOP NOTE: CRITICAL TASK
- Enter 5.3.24 to supplement depressurization.
NOTE: CRITICAL TASK Verify (Acoustic Monitor or Tailpipe Temperature) that all BOP SRV's are open.
CRS Exit EOP-1 7 and re-enter EOP-01 pressure control leg.
The scenario will be terminated at the direction of the Chief Examiner after the Emergency Depressurization is complete.
Expected EAL is 4.2.1.3.
Notes: Scenario 4
- 1.
- 2.
Reduce power due to report of Coastal storm per power maneuver plan 2.1.14
- 3.
RPS MG set trip 905R C-1 Tech Spec 3.1., 3.11 lAW 2.2.79 direct operator to transfer to standby transformer reset recombiner temp alarm reset rad monitors
- 4.
CRD pump trips 2.4.4 swap pumps reset annunciator
- 5.
SRV fails open; 2.4.29 cycle switch 5 minutes until as scram required dispatch operator locally to open D-4 and D-5 breakers close SRV (CRITICAL TASK). tech spec ADS inop valve will operate in safety mode only
- 6.
Degraded grid leading to LOSP 2.4.146 have BOP place a EDG on A-5 orA-6 initiate scoop tube lockup. before second EDG aligned drop voltage below 3860 to require scram. Mode switch to shutdown 2.1.6 direct MSIVs closed no circ water pumps running. EOP 1 entry due to level.
- 8.
Steam Break outside containment RCIC break 10 percent ramped for 15 minutes. Enter EOP 4 on high temperature. A SRV disabled when 2 areas greater than max safe direct Blow down (CRITICAL TASK). Must direct local operation of A SRV to have 4 SRVs open(CRITICALTASK). consider using survey results to prompt blow down if necessary.
Establish shutdown cooling
Actions: Pending/ Active 1.
2.
3.
4.
5.
6.
7.
8.
9.
10.
11.
12.
13.
14.
15.
16.
17.
18.
19.
20.
21.
22.
23.
24.
25.
CRD FCV 41 B 100 percent pending CRD FCV 41 A 0 percent pending CRD selector false pending A RHR tagged green light / red light off active Switch pull to lock MCB Knife blade closed false active RPS MG trip true pending Feed from RPS Bus false pending Feed B-10 RPS true pending CRD pump trip true pending SRV 3A fails open true pending Red /green light all SRV false pending 903L A-1 on pending C-156 open pending C-156 delete pending All SRV red/green light delete pending 903L-A-1 delete pending A SRV ASP closed pending Degraded grid Imaginary generator voltage lower pending Imaginary generator volt lower delete conditional as A6 less than 3860 volts Bypass valve cam closed conditional turb trip 30 second delay RCIC steam line break 10 percent over 15 minute ramp pending Group 5 isolation failure active C-156 open pending A SRV ASP pending open
Critical Tasks:Scenario 4
- 1.
Close SRV
- 2.
Blow down when 2 areas greater than max safe
- 3.
Open SRV to blow down with 4 SRVs EOPs ENTERED
- 1.
EOP 1
- 2.
EOP4
- 3.
EOP 17 EOP CONTINGENCY Emergency depressurization
Scenario Outline Facility:
Examiners:
Pilgrim Scenario No.:
Spare Op-Test No.:
Operators:
I Initial Conditions: 84% power, 'A' EDG tagged out for bearing replacement.
Intake screening cleaning is in progress Turnover: Continue raising feedwater correction factor.
power to 100% following control valve testing, block Currently in day 2 of a 14 day LCO for 'A' EDG OOS.
Event Malf.
Event Event No.
No.
Type*
Description 1
N/A N-BOP Block feed flow correction factor 2
N/A R-RO Ramp up to 100%
3 EGO4 C-BOP Voltage regulator failure 4
RR20 I-RO
'A' Recirc Pump runaway 5
I/O C-BOP RBCCW temperature controller fails high 6
RRO7 C-RO
'A' Recirc MG trip 7
CW02/
M-ALL Loss of Intake Structure, Scram LOSP ED06 8
I/O M-ALL
'B' EDG fails - loss of all AC - SBO start
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Operator Actions Op-Test No.:
1 Scenario No.:
5 Event No.:
1 Page 1 of 1 Event
Description:
Block Feed Flow Correction Factor Time Position Applicant's Actions or Behavior Direct Feedwater Correction Factor Blocked IAW PNPS CRS 2.1.14, Attachment 4.
At EPIC computer "Pilgrim Main Menu", access the "Point l
BOP Data Service Menu".
In the "Single Point Change Service Menu" box, select BOP "for display/change".
When the computer point is highlighted in blue, eliminate the BOP computer point and return the cursor to the left side of the highlighted area.
Type the Feedwater Flow Correction Factor Computer Point BOP "CFWFACUT" and press the enter key of the numbers keypad.
BOP Select "Select Point" "Do" box and click the left mouse button.
The "Point Data Change For CFWFACUT" screen should appear.
BOP Position the mouse arrow on the radio point to the right of "Processing:" and click the left mouse button to obtain "On".
l Position the mouse arrow on the "Apply Changes" "Do" box and click the left mouse button. Observe that the computer BOP point "CFWFACUT" State is "NO" and the Status is "NML".
BOP Verifies that the State of point "CFWAPPLD" is "NO".
Verify EPIC computer points "CFWFACUT" and BOP "CFWAPPLD" changed.
Operator Actions Op-Test No.:
1 Scenario No.:
5 Event No.:
2 Page 1 of 1 Event
Description:
Raise Reactor Power to 100%
Time J Position Applicant's Actions or Behavior CRS Directs power increase IAW 2.1.14, Section 7.4.
RO Raises power using Recirc flow and pull sheets.
Operator Actions Op-Test No.:
1 Scenario No.:
5 Event No.:
3 Page 1 of 1 Event
Description:
Voltage Regulator Failure Time Position Applicant's Actions or Behavior Identifies/announces VOLTAGE REGULATURE BOP MALFUNCTION annunciator. Refers to ARP.
BOP Verifies voltage regulator shifted to MANUAL.
BOP Places VOLTAGE REGULATOR XFER SWITCH in manual.
Adjust MANUAL VOLTAGE ADJUSTER. To control reactive BOP load.
CRS Notifies l&C/EM to investigate and repair.
CRS Notifies REMVEC that voltage regulator is in manual.
Determines voltage regulator adjustment will be in manual CRS control for further power changes.
Operator Actions Op-Test No.:
1 Scenario No.:
5 Event No.:
4 Page 1 of 2 Event
Description:
'A' Recirc Pump Runaway Tm Position Applicant's Actions or Behavior RO/BOP Recognize/announce increasing reactor power.
Determine the cause of the unexplained rapid increase:
l Reactor Recirculation System Speed or Flow Control l
RO/CRS System Malfunction, PNPS 2.4.20.
l_
CRS/RO Refer to PNPS 2.4.20.
CRS Direct initiating scoop lockup of 'B' Recirc pump.
RO Initiates 'B' Recirc pump scoop tube lockup.
CRS Direct entry into PNPS 2.4.19 CRS Direct assessment of power to flow conditions.
RO Plot power and flow on power to flow map.
Monitor PBDS recorders for oscillations (no oscillations RO noted).
Ensures loop flows balanced lAW PNPS 2.1.5. (Within 10%
RO above 80% power.)
Operator Actions Op-Test No.:
1 Scenario No.:
5 Event No.:
4 Page 2 of 2 Event
Description:
'A' Recirc Pump Runaway Time Position Applicant's Actions or Behavior Determine cause to be loss of signal based on speed signal RO indication.
CRS Notify l&C to investigate and repair.
Request licensed operator standby for manual operation of CRS scoop tube positioner.
NOTE: licensed operator will not be available.
CRS Verify pump speeds within Tech Spec limits 3.6.F Determines that if pump speeds cannot be brought within CRS limits within 30 minutes shutdown will be required.
CRS Identifies need to trip Recirc pump in event of SCRAM.
Operator Actions Op-Test No.:
1 Scenario No.:
5 Event No.:
5 Page 1 of I Event
Description:
RBCCW Temperature Controller Fails High Time Position Applicant's Actions or Behavior ALL Identifies Drywell pressure increasing slowly.
CRS Directs checking for indications of Drywell leakage.
ALL No indications of leakage inside Drywell.
Refers to PNPS 2.4.42 Section 4.7 CRS NOTE may refer to. PNPS 5.3.35.
NOTE: BOP operator should recognize controller malfunction and place in manual control. If not, performance of PNPS 2.4.42 section 4.7 or PNPS 5.3.35 MAXIMIZING DRYWELL COOLING will mitigate instrument malfunction.
Places 'B' RBCCW temperature controller in manual and adjust output to control RBCCW temperature approximately 70 degrees OR Closes MO-4083 'B' RBCCW heat exchanger bypass AND BOP Throttles MO-3806 SSW outlet 'B' RBCCW` heat exchanger.
Operator Actions Op-Test No.:
1 Scenario No.:
5 Event No.:
6 Page 1 of 1 Event
Description:
'A' Recirc MG Trip Time Position Applicant's Actions or Behavior RO Recognize announce trip of 'A' Recirc pump.
CRS Direct entry into PNPS 2.4.17 section 4.1.
RO Close MO-202-5B.
Estimate total core flow.
RO Determines total core flow to be approximately 32Mlbm/hr Determines core flow is within limits:
RO Restricted region entry.
CRS Directs rod movement to exit restricted region.
RO Opens MO-202-5B after 5 minutes.
Operator Actions Op-Test No.:
1 Scenario No.:
5 Event No.:
7 Page 1 of 2 Event
Description:
Intake Structure Fouling ('A' Bay / 'B' Seawater Pump)
Time Position Applicant's Actions or Behavior Recognize/announce annunicator "Travelling Screen AP Hi" and refers to ARP C1 R-C3. Verifies the alarm using the EPIC SW/SSW graphic display. Recognizes that 'A' BOP Seawater bay's level is lowering.
Enters PNPS 2.4.154, "Intake Structure Fouling".
Directs that screenwash for all travelling screens be placed in service per 2.2.94.
CRS Refers to Attachment 1 of 2.2.154.
Recognize/announce that 'A' and 'B' Seawater bay level is BOP approaching -10 ft.
CRS Directs that 'A' and 'B' Seawater pumps be stopped.
CRS Directs SCRAM and entry of PNPS 2.1.6.
NOTE: CRITICAL TASK Directs a reactor scram by taking the MODE switch to the "SHUTDOWN" position and the RO to take the actions of CRS 2.1.6. Directs RPV level maintained +20 to +40 inches and RO Place mode switch in shutdown and enter PNPS 2.1.6.
RO Verify and announce the status of APRM downscales.
RO Verify all control rods are fully inserted.
Insert IRM and SRM detectors, select two SRMs for RO recording, and place selector switch for APRM/IRM to "IRM".
Verify or manually place reactor recirc pumps at minimum RO speed.
Operator Actions Op-Test No.:
1 Scenario No.:
5 Event No.:
7 Page 2 of 2 Event
Description:
Intake Structure Fouling ('A' Bay / 'B' Seawater Pump)
Time l Position Applicant's Actions or Behavior Insert IRM and SRM detectors, select two SRMs for RO recording, and place selector switch for APRM/IRM to "IRM".
Verify or manually place reactor recirc pumps at minimum RO speed.
Maintain reactor water level +20 - +40 inches using RO feedwater.
BOP Maintains RPV pressure 900 - 1050 psig using SRVs.
CIRS Directs MSIVs closed.
Operator Actions Op-Test No.:
1 Scenario No.:
5 Event No.:
8 Page 1 of 2 Event
Description:
'B' EDG Fails - Loss of all AC - SBO Start l Time Position Applicant's Actions or Behavior ALL Recognize LOSP.
CRS Direct entry into PNPS 2.4.16.
l CRS Determines type of malfunction.
Recognize:
Loss of off site power.
ALL
- 'A' EDG tagged out.
l
'B' EDG trips when ties to A6.
Determines Station Blackout directs entry into PNPS 5.3.31 CRS and 2.4.146 section 7.1.
BOP Starts and loads SBODG from the control room.
BOP Verifies breaker A600 open.
BOP Verifies 24 KV incoming breaker open.
BOP Verifies shutdown XFMR breaker A802 tripped.
BOP Check shutdown transformer relay reset.
Place BLACKOUT DIESEL GENERATORS START control BOP switch to start.
After 30 seconds place BLACKOUT DIESEL GENERATOR BOP breaker A801 to close.
Operator Actions Op-Test No.:
1 Scenario No.:
5 Event No.:
8 Page 2 of 2 Event
Description:
'B' EDG Fails - Loss of all AC - SBO Start Time Position Applicant's Actions or Behavior CRS Direct SBODG placed on A6 bus.
Direct RHR pump 'B' and 'D' and 'B' core spray pumps be CRS pulled to locked.
Place control switches for RHR pumps 'B' and 'D' and 'B' RO Core Spray pumps pulled to locked.
BOP Place breaker A501 to pull to lock position.
Depress the 'B' load shed manual initiation pushbuttons for 5 BOP seconds.
BOP Close breaker A600.
l BOP Verify SBODG comes up to rated voltage.
BOP Close breaker A601.
NOTE: CRITICAL TASK CRS Direct loading A6 as necessary.
BOP Monitor SBODG loads as loads started.
The scenario will be terminated at the direction of the Chief Examiner after the SBO has been placed in service supplying A-5 or A-6.
Expected EAL is 6.3.2.1.
Notes: Scenario 5
- 1.
80-85% power following Turbine Stop Valve testing. Block feed flow correction factor per 2.1.14 section 7.4 step 6 att. 4 section 1
- 2.
Ramp up to 100% using Recirc
- 3.
Voltage regulator failure auto shifts to manual will require manual adjustment during power changes C3R E-3 D-4 A-1 200 vars ok call EM
- 4.
Runaway of 'A' Recirc Pump.
- 5.
Failure of 'B' RBCCW temperature controller high. Will notice drywell pressure increase. Maximize RBCCW cooling either with temp controller or SSW valves, may not notice if SSW valves used but will still mitigate failure.
- 6.
Trip of 'A' Recirc MG. 2.4.17 restricted region entry if high enough in power with flow if not may scram. Be high in power with Recirc
- 7.
Loss of Intake Structure, 2.4.154 at 9 feet reduce power 8 feet trip CW pumps, close MSIVs HPCI pressure control RCIC injecting EOP I entry Scram LOSP 2.1.6 actions then LOSP allow BEDG to tie on then fail Delete intake level failure after CW pumps tripped to allow operation of SSW pumps. ensures TBCCW operable
- 8.
'B' EDG fails - loss of all AC - SBO 2.4.146 tie on in less than 10 minutes 2000 KW continuous 2200 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating check load prior to starting loads Torus cooling
Actions: Scenario 5 Pending/ Active 1.
2.
3.
4.
5.
6.
7.
8.
9.
10.
IC-14:
A EDG tagged out, A EDG fail to start active Voltage regulator failure high Pending
'B' RBCCW Temperature Controller, fails high temperature set point 100 % pending
'A' Recirc MG drive breaker trip pending
'A' Recirc Pump runaway LOSP pending
'B' EDG emergency stop switch pending Intake screens D/P 100 percent clogged ramped 10 minutes pending delete 5 min ramp conditional on circ pumps tripped
Critical Tasks: Scenario 5
- 1.
Start SBO D/G and energize Bus within 10 minutes 2.
3.
EOPs ENTERED
- 1.
EOP 1
- 2.
EOP 3 possibly based on drywell pressure due to loss of cooling EOP CONTINGENCY NONE