ML071350583

From kanterella
Jump to navigation Jump to search
Draft - Section C Operating Exam (Folder 2)
ML071350583
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 03/12/2007
From:
Entergy Nuclear Vermont Yankee
To: Todd Fish
Operations Branch I
Sykes, Marvin D.
Shared Package
ML062050096 List:
References
Download: ML071350583 (57)
v • d • e


Text

VY 2007 NRC Scenario 1 Rev b Page 3 of 21 SIMULATOR EVALUATION GUIDE Eva1uato rs: Crew:

SM CRS CRO BOP STA Senior Management Observer Scenario Template:

Template

Title:

TITLE Critical Task Performance: SAT UNSAT (Circle One)

Lead Evaluator:

Signature Date Administered:

Activity Code:

Prepared by: Date:

Reviewed by: Date:

Approved by: Date:

Appendix D NUREG 1021 Revision 9

VY 2007 NRC Scenario 1 Rev b Page 8 of 21 OPERATOR ACTIONS EVENT NUMBER 1 Crew Task

Description:

Weekly Remote Testing of Turbine Oil Pumps per OP-4160.

STEP POS. CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS CRS Direct Turbine Pump Performance IAW OP 4160 Section B.

pq ~~~~

Performs OP 4160 Section 111. Steps 1.a thru 1.f I l l EXAMINERS NOTE: SEE ATTACHED COPY OF PROCEDURE FOR SPECIFIC STEP DETAIL.

i NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 1 Rev b Page 9 of 21 OPERATOR ACTIONS EVENT NUMBER 2 Crew Task

Description:

Power Ascension IAW OP 0105 STEP

- POS.

- - - CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS CRS Directs Power Increase IAW OP-0105 With recirc flow CRO Increase recirc flow with master recirc flow controller Q 1% per 3 minutes CRO Monitors power, pressure, level.

NOTE:

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 1 Rev b Page 10 of 21 0PERATOR ACTIONS EVENT NUMBER 3 & 4 Crew Task

Description:

Respond to a Loss of Bus 89B; Loss of Circ Water STEP POS. CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS CREW Recognize a loss of Bus 898 power.

CRS Enter and direct actions IAW OP 2143 and ARS.

CRS Direct maintenance to investigate the loss of MCC 89B.

SM/CRS Review Tech Specs and determine per 3.10.B.4 and 3.5.A.4 enter a 7-day LCO for "B" LPCI.

CRS Direct A 0 to document indicating lights at RUPS 1B and MCC 898 per OP 2143.

CRS Conduct a shift brief CREW Recognize a loss of Circ Water Pump 'B'.

BOP Enter ARS 6-B-2 for loss of the pump.

CRS Directs contacting maintenance due to pump trip and auxiliary operator to investigate locally.

CRS Conduct a shift brief.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 1 Rev b Page 11 of 21 OPERATOR ACTIONS EVENT NUMBER 5 Crew Task

Description:

CRD Pump A Trips (ON)

POS. CANDIDATE ACTIONS/BEHAVIOR S N/O I COMMENTS CREW Recognizes Trip of ACRD pump.

CRS Directs actions ON 3145

-Step 2 immediately stop B RWCU

-Step 4 - start Alternate CRD pump seal purge must be secured when

>2 minutes Directs A 0 and maintenance to investigate.

NOTE: SEE Attached copy .~of ON 3145 for specific steps.

CRO References ON 3145

-Takes action to stop RWCU pump B.

- Starts B CRD pump per ON 3145

- Takes action to isolate seal purge CREW Recognizes the following alarms are in due to excessive drywell cooling due to loss of RWCU heat loads:

5-G DW Pressure HVLO 5-G DW Pressure Low NOTE: Operator will open 156-3 IAW ARS to clear alarms.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 1 Rev b Page 12 of 21 OPERATOR ACTIONS L

EVENT NUMBER 6 Crew Task

Description:

Control Rod 18-31 Drifts Outward (OT)

I CANDIDATE ACTIONS/BEHAVIOR I S

~~~~ ~

POS.

I CREW I Acknowledgehespond to Rod Drift annunciator (5-D-5);inform CRS.

Identify rod 18-31 as drifting rod; inform CRS. I CRS 0 Enter and direct actions IAW OT 3167 (Control Rod Drift):

0 Observe drive water flow indication Fl-3-305 0 Select rod 18-31 and attempt to insert ONCE to original position.

When directed:

0 Observe drive water flow indication Fl-3-305 Select rod 18-31 and attempt to insert ONCE to original position 0 Identify that rod continues to drift outward when insert signal removed; inform CRS NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 1 Rev b Page 13 of 21 STEP POS. CANDIDATE ACTIONS/BEHAVIOR Direct the following IAW OT 3167 S N/O I COMMENTS and OT 3110 (Positive Reactivity Insertion):

0 Manually scram rod 18-31.

0 Reduce Recirc flow to 27.5 - 29 Mlb/hr at a rate not to exceed 10% / minute.

0 Notify Reactor Engineering.

0 Attempt to determine if cause of control rod drift is a stuck collet.

0 Consult OT 3166 (Mispositioned Control Rod).

~~~~ ~ ~

BOP When directed, manually scram rod 18-31.

CRO When directed, reduce Recirc flow to 27.5 - 29 Mlb/hr at a rate not to exceed 10% / minute.

CREW When directed, notify Reactor Engineering of Rod 18-31 drift.

CRS Conduct a crew brief.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasMStep

VY 2007 NRC Scenario 1 Rev b Page 14 of 21 OPERATOR ACTIONS EVENT NUMBER 7 Crew Task

Description:

Inadvertent HPCl Initiation (TS)

I CANDIDATE ACTIONS/BEHAVlOR U I N/O I COMMENTS Recognize and inform the CRS of a HPCl initiation.

Enters OT 31 10 - Positive Reactivity Insertion, Step 2.F.

1 NOTE: See Attached OT 3110.

1I I CRS Confirm no initiation signals present.

(Two indications at least).

Directs that HPCl be tripped per Step 4.

Directs opening SGT 1A & 1B due to auto start of SBGT.

BOP Places Autohhibit switch to Inhibit.

Verify SBGT operation. Opens SGT lA&lB.

CRS Consult Tech Specs and determine that a 14-day LCO condition has been met per 3.5.E.2.

OT 3110 - Step 9.Contacts RE CRS Brief the crew.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 1 Rev b Page 15 of 21 OPERATOR ACTIONS EVENT NUMBER 8 Crew Task

Description:

Loss of Offsite Power 1 STEP I POS. I CANDIDATE ACTIONS/BEHAVIOR I I CRO I Report reactor scram.

CREW Recognize and inform CRS of Loss of Off Site Power.

0 Report power on buses 3,4,8,9 from the Diesels.

l I CRo I Report feed and condensate are unavailable.

I I CRS I Enter and direct actions IAW OT 3122, LNP CREW Respond to LNP IAW OT 3122.

0 Verify both DGs start and power busses.

0 Verify SW pumps start.

0 Restart station AC A & B.

~ ~~ ~~~

CRS Enter and direct crew actions IAW OT 3100, Rx Scram and EOP-1, RPV Control.

1 CRO 1 0 Verify all rods fully inserted.

0 When steam flow < 0.5 Mlbm/hr per steamline, place the mode switch in S/D.

E NOTE: THIS STEP IS AN Immediate Action, and may be performed without direction.

CRO Insert IRMs and SRMs.

CRS Direct reactor water level maintained 127" - 177" using RClC initially/ then HPCl as needed (must take out of INHIBIT).

Direct pressure maintained 800 -

1000 psig using SRVs/HPCI.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 1 Rev b Page 16 of 21 STEP POS. CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS BOP Maintain RPV level as directed with RClC initially.

HPCl (must be taken out of inhibit).

CREW Verify Table A: ECCS/PCIS actuations.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 1 Rev b Page 17 of 21 OPERATOR ACTIONS EVENT NUMBER 9,10, & 11 Crew Task

Description:

HPCl Flow Controller Failure; Recirc Loop Rupture (0.6% Over 600 Sec.); HPCl Trip; RPV-ED on Low Level; CS-12A and CS-128 Failure to Auto Open, RHR 27A Failure to Auto Open POS. CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS BOP Report HPCl trip.

Direct AO/ maintenance to investigate HPCl trip Direct RPV level maintained I l l between 6 inches (TAF) and 177 inches by maximizing CRD flow I

Maximize available CRD flow Report increasing drywell pressure.

I CRS I Enter EOP-3 on High Drywell Pressure. I l l CRS I Direct BOP to restart drywell RRU's. II ll ll I I BOP I Restart drywell RRU's.

I I CRS BOP I Before torus pressure reaches 10 psig, direct torus sprays Spray the torus, as directed.

CRS When torus pressure exceeds 10 0 Verify drywell pressure and temperature in the safe region of the DWSIL graph.

0 Verify drywell RRUs secured.

0 Direct drywell sprays.

E BOP Secure drywell RRUs.

BOP Spray the drywell as directed.

CRS When ADS timer initiated, direct ADS inhibited.

BOP Inhibit ADS as directed.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 1 Rev b Page 18 of 21 CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS Direct SLC for reactor water level control.

Direct RPV level maintained between 6 inches (TAF) and 177 inches Inject SLC, as directed.

~~ ~~~ ~ ~

Report level approaching 6 .

When RPV level cannot be maintained above 6 , directherify at least 2 injection subsystems lined up for injection.

Lineup ECCS systems as directed.

With the reactor shutdown and reactor pressure greater than the

~ shutoff head of the low pressure systems, initiate RPV-ED BEFORE RPV level reaches -19 inches.

Standard:

Initiate RPV-ED (begin opening valves) BEFORE RPV level reaches - 48 inches CREW Inform CRS when level reaches 6 .

CRS Before level reaches - 19 inches, enter and direct crew actions IAW EOP-5 RPV-ED.

CRS Direct all SRVs opened.

CRO/BOP When directed, place all SRV control switches to open. Inform CRS that all SRVs are open.

h NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 1 Rev b Page 19 of 21 STEP I POS. CANDIDATE ACTIONS/BEHAVIOR COMMENTS

  • CREW Action is taken to restore RPV EOP-1 water level above -19 inches by CT-2 operating available low pressure ECCS system(s) when RPV pressure decreases below the shutoff head of the low pressure systems.

~~~~

Standard:

0 At least 2 ECCS pumps are lined up for injection and running prior to RPV pressure reaching the injection valve open permissive pressure.

0 No pumps are secured until adequate core cooling is assured.

0 Initiate manual opening of injection valves once valve open permissive pressure is reached.

I CREW Continue to monitor and report RPV Level and Pressure decrease.

1 I

,BOP Report failure of RHR-27A, CS-12A and CS-12B to AUTO open.

Direct RHR and CS injection valves opened.

Manually open RHR-27A, CS-12A and CS-128 as directed.

CRS Direct CRO/BOP to ensure adequate core cooling and restore water level to 127-177.

I CREW Verify adequate core cooling and level rising.

CRS As necessary, prevent injection from Core Spray and RHR Pumps not required to assure adequate core cooling.

BOP/CRO When directed, prevent injection from Core Spray and RHR Pumps not required to assure adequate core cooling.

2) * = Critical TasWStep

VY 2007 NRC Scenario 1 Rev b Page 20 of 21 i

STEP POS. CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS BOP/CRO When directed, prevent injection from Core Spray and RHR Pumps not required to assure adequate core cooling.

SM/STA Consult AP 3125 and determine an Alert EAL has been reached IAW AP 3125, A-3-a and/or A-3-b.

15 minute clock NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 3 of 26 SIMULATOR EVALUATION GUIDE Evaluators: Crew:

SM CRS CRO BOP STA Senior Management Observer Scenario Template:

Template

Title:

TITLE Critical Task Performance: SAT UNSAT (Circle One)

Lead Evaluator:

Signature Date Administered:

Activity Code:

Prepared by: Date:

Reviewed by: Date:

Approved by: Date:

Appendix D NUREG 1021 Revision 9

VY 2007 NRC Scenario 2 Rev b Page 8 of 26 0PERATOR ACTIONS EVENT NUMBER 1 Crew Task

Description:

Place CW in Closed Cycle for Chlorination STEP POS. CANDIDATE ACTIONS/BEHAVIOR CRS Directs Placing CW in closed Cycle for chlorination.

BOP Procedure OP 2180 Section F.

Reviews procedure and checks prereqs.

BOP Ensures all Circ Water & Circ Water Booster Pumps running.

BOP Contacts Chemistry - Are we treating service water at the same time.

EVALUATORS CUE: Report back - not treating SW simultaneously.

1

~~

BOP Opens Circ Water Recirc Gate

>85% by taking Circ Water Recirc Gate switch to open, Observes indicator POL1 04-3 >85%

Observes weir level indicator LI-104-10-1 is e 225 I I Calls field operator to throttle valve cw-7.

BOP Closes all intake gates by taking hand switches Circ Water Intake Gate 1A (1 B, 1C) to close.

BOP Monitors intake level and condenser backpressure.

I NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 9 of 26 OPERATOR ACTIONS EVENT NUMBER 2 Crew Task

Description:

Power Reduction IAW OP 0105 STEP

- POS. CANDIDATE ACTIONS/BEHAVIOR

~ S U

~ COMMENTS CRS Directs power reduction IAW OP-0105 CUE USE provided power reduction memo.

CRO Selects Rod 22-19 first Using Rod Movement Control switch, insert rod to 00 Monitors four-rod and full core display, monitors power indications ,

CRD parameters Continues with subsequent control rods.

EVALUATORS NOTE: May receive alarm 5-E-6 FW Control System trouble. Due to mismatch of level and setpoint during power reduction. The alarm is expected and will clear.

GO TO NEXT EVENT AT EXAMINER DISCRETION.

DO NOT INSERT NEXT EVENT UNTIL LEVEL STABILIZES.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 10 of 26 OPERATOR ACTIONS EVENT NUMBER 3 Crew Task

Description:

Feedwater Regulating Valve Lockup (OT) 1 STEP I POS. CANDIDATE ACTIONS/BEHAVIOR U I N/O I COMMENTS Recognizes A FRV Lockup.

Enters ARS 5-E-2

~~ ~

Directs field operator to check problem with A FRV.

Contacts I&C.

Directs FRV lockup reset per ARS.

Attempts to reset FRV lockup by Performs steps 1.b. thru 1.f.,

Step 1.a.g and h. do not apply.

Goes to step 2.

CRS CREW Brief on FRV operation and level control per guidance in OTs and ARS NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 11 of 26 OPERATOR ACTIONS EVENT NUMBER 4 Crew Task

Description:

APRM A Fails Downscale (TS)

STEP POS. CANDIDATE ACTIONS/BEHAVIOR S U N/0 COMMENTS CREW Recognizes Alarm 5-M-4 annunciates APRM Downscale.

Also, 5-D-3 for Rod Withdraw Block CRS Enters TS and Directs contacting I&C.

TS Table 3.1.1 , Notes 2 and 3, - 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to put in trip on A side.

CRO Review ARS 5-D-3 and 5-M-4 direction:

0 increased board monitoring 0 contacts I&C.

CRS Crew Brief.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 12 of 26 OPERATOR ACTIONS EVENT NUMBER 5 Crew Task

Description:

EPR Oscillations (OT)

CANDIDATE ACTIONS/BEHAVIOR S N/O COMMENTS Recognize oscillating reactor pressure Enters OT 3115.

Coordinate determination of EPR at fault; inform CRS.

Enter and direct actions IAW OT 31 15 (Reactor Pressure Transients):

0 Place the EPR in CUTOUT 0 Verify that the MPR has control 0 Lower MPR setpoint as necessary When directed:

Place the EPR in CUTOUT at peak pressure 0 Verify that the MPR has control 0 Lower MPR setpoint as necessary.

Direct BOP to restore pressure to the pre-transient pressure.

When directed, adjust MPR to adjust pressure to pre-transient level.

Direct Crew member to contact I&C to check and repair EPR.

When directed, contract I&C, inform them of EPR problem and request repair efforts begin.

Brief the Crew. I Direct STNCrew to begin work on a CR to ensure an Operability Determination is made.

S = Satisfactory; U - Unsatisfactory; N/O= Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

  • = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 13 of 26 OPERATOR ACTIONS EVENT NUMBER 6 Crew Task

Description:

Loss of 480 Volt Bus 8, Failure of SBGT A to Auto Start 1 STEP I POS. CANDIDATE ACTIONS/BEHAVIOR COMMENTS l I CREW Recognize and inform CRS of a loss of 480 volt Bus 8.

/ I CRo Inform CRS of half scram.

Report power, pressure, level Recognize/respondto a Group Ill isolation and bus loss.

Board walkdown to recognize equipment affected 0 BCSvalves B RHRvalves 0 Drywell RRUs alarm for seismic panel (in due to power loss, not an actual event)

CRS Direct the following actions:

0 Backup Group Ill isolation Direct call to chemistry for sampling per T.S. 4.6.B.3.b 0 Direct crew to initiate an investigation into bus loss.

BOP When directed, backup Group Ill isolation 0 Recognize failure of the SBGT trains to auto start 0 Stadalign SBGT A Inform CRS of failure to auto start.

I I BOP I When directed shut RWCU 18. I I I I NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 14 of 26 CANDI DATE ACT IONS/BEHAVlOR COMMENTS Consult Tech Specs and identify the following:

0 24-hour S/D LCOs 3.10.A.3.

(Bus Loss) AND 0 Core Spray and RHR due to loss of valve power 3.5.A.6.

0 7 days - -3.7.B.3 (SBGT)

Monitor and control DW pressure rise due to loss of Drywell RRUs and isolation.

Direct start of all available Drywell RRUs per OT3111, High Drywell Pressure.

Enter EOP-3 as required due to High Drywell temperature.

When directed shut RWCU 18 Starts available Drywell RRUs.

Direct the CRO to begin preparations I

for a normal plant S/D per OP 0105.

Provide a crew brief on conditions and shutdown.

When directed, commence preparations to shutdown IAW OP-0105.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 15 of 26 OPERATOR ACTIONS EVENT NUMBER 7 Crew Task

Description:

SRV-716 Leak (OT) Leads to Rx Scram (100% over 6OOsec)

STEP I POS. CANDIDATE ACTIONS/BEHAVlOR COMMENTS Recognize the "B" SRV leaking.

Enter OT 3121, Inadvertent Opening of SRV.

Using available indications, determine that SRV 71-B is leaking:

inform CRS CRS Enter and direct actions IAW OT 3121 (Inadvertent Opening of a Relief Valve) 1 EVALUATOR'S NOTE: SRV is part-way open and may be assessed as either OPEN or leaking.

1 EVALUATOR'S NOTE: No actions t o stop leak will be successful.

1 EVALUATOR'S NOTE: Recognize can't place torus cooling in service.

0 Inform Operations Manager 0 Inform System Engineering 0 Commence plant shutdown IAW OP-0105 0 Determine that SRV has no known pilot valve leakage.

0 Attempt to close valve by cycling control switch from AUTO to OPEN to AUTO (if valve is open enough to indicate it is open and not leaking).

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 16 of 26 STEP I POS. I CANDlDATEACTIONS/BEHAVIOR I S U I N/O I COMMENTS Attempt to cycle B SRV; report valve failure to close.

CRS IF the SRV remains OPEN, Place the ADS Appendix R Bypass Switch on CRP 9-3 to BYPASS.

EVALUATORS NOTE: (Onlv if assessed as OPEN.)

When directed, place the ADS Appendix R Bypass Switch on CRP 9-3 to BYPASS.

EVALUATORS NOTE: (Onlv if assessed as OPEN.)

I CRS If core flow is greater than 29 Mlbm/Hr then reduce reactor power I10% RTP/min using recirc flow until core flow is 27.5 to 29 Mlbm/Hr.

EVALUATORS NOTE: (Only if assessed as OPEN.)

When directed, reduce reactor power I10% RTP/min using recirc flow until core flow is 27.5 to 29 Mlbm/Hr.

EVALUATORS NOTE: (Only if assessed as OPEN.)

CRS I Direct the following actions:

Transfer station loads to the Startup Transformers (as time permits).

Reactor shutdown/cooldown as required by OT-3121.

CRO/BOP When directed, commence plant shutdown IAW OP 0105.

CREW Recognize torus volume > 70,000 cu ft; inform CRS of EOP-3 entry condition CRS When torus volume exceeds 70,000 cu ft, enter and direct actions IAW EOP- 3 Direct torus cooling.

EVALUATORS NOTE: Recognize cant place torus cooling in service.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 17 of 26

=

CANDIDATE ACTIONS/BEHAVIOR N/O COMMENTS Report Drywell pressure approaching 2.5 psig.

Enteddirect actions IAW OT-3111 (as time permits):

Reduce Recirc flow to 27.5 - 29 Mlbs/hr at a rate not to exceed 10 percent per minute Above the MELLLA boundary, stop lowering core flow and reduce power using the rapid shutdown sequence in reverse order EVALUATORS NOTE: May go above MELLLA for a short period of time during a transient.

Transfer house loads to the Startup Transformers.

0 Start all available drywell RRUs.

CRS Direct manual scramhurbine trip prior to drywell pressure exceeding 2.3 psig.

When directed, insert a manual reactor scram.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 18 of 26 OPERATOR ACTIONS EVENT NUMBER 8 Crew Task

Description:

Failure of Manual Scram; ARI Required I

~ _ _ ~~

1 STEP I POS. I CANDlDATEACTIONS/BEHAVIOR I S N/O COMMENTS

  • CREW With the reactor at power and a full auto scram signal, manually EOP-2 scram the reactor.

CCT-1 Standard:

Actuate the manual scram pushbuttons, place the mode switch in SHUTDOWN, or actuate the ARI-RPT pushbuttons within 1 minute of reaching the Limiting Safety System Setting CRO Initiate ARI/RPT and Trip the Drive Motor Breakers.

Report Partial Rod Insertion.

CRO When steam flow c 0.5 Mlbm/hr per stearnline, place mode switch in SHUTDOWN.

0 Verify all rods inserted; inform CRS.

0 Insert IRMs and SRMs.

l I CRS I Direct CRO to maintain level from 127" - 177".

CRO/BOP Maintain reactor level as directed.

0 Determine HPCl not required for level control 0 HPCl tripped and inhibited I

Direct CRO/BOP to maintain reactor pressure 800 - 1000 psig using CRS BPVs.

R I CSROOp/ I Maintain reactor pressure as directed.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 19 of 26 STEP POS. CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS CRS Direct crew to monitor the plant cooldown.

BOP When directed monitor cooldown.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 20 of 26 OPERATOR ACTIONS EVENT NUMBER 9 & 10 Crew Task

Description:

45% Hydraulic ATWS (A) 55% Hydraulic ATWS (8); SLC Pump A Trips; B SLC Squib Valve Fails to Fire STEP POS. CANDIDATE ACTIONS/BEHAVIOR S COMMENTS CRO Recognize failure of control rods to insert; inform CRS.

"CREW With reactor scram required and the reactor not shutdown, take EOP-2 action to reduce power by CCT-2 tripping the recirc pumps.

Standard:

Actuate the ARI/RPT logic AND ensure that the recirc drive motor breakers are tripped within 2 minutes of the scram failure (or within 1 minute of RPV pressure exceeding 1200 psig)

Attempt to initiate ARI/RPT and secure the Recirc pumps.

1 0 Report failure of ARVRPT to CRS I Trip Recirc pump drive motor breakers CRS When informed of the scram failure enter and direct crew actions IAW EOP-1 and EOP-2 I sTA I When directed, verify EOP-1 Table A automatic actions I l l CREW Recognize/respond to high Drywell pressure and entry into EOP-3; inform CRS CRS Enter/direct actions per EOP-3 0 Restart Drywell RRUs.

BOP When directed:

0 Restart Drywell RRUs.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 21 of 26 STEP 1 POS. CANDIDATE ACTIONWBEHAVIOR N/O COMMENTS

  • CREW With a reactor scram required and the reactor not shutdown, EOP-2 INHIBIT ADS to prevent an CCT-3 uncontrolled RPV depressurization to prevent causing a significant power excursion.

Standard:

Inhibit ADS prior to automatic initiation.

CRS Direct per EOP-2:

Inhibit ADS Implement App P to keep the MSlVs Open 0 When steam flow c0.5lbmhr per steamline, place Mode Switch in SHUTDOWN EVALUATORS NOTE: This step is an Immediate Action, and may be performed without direction.

~~ ~~

0 Verify ARVRPT initiated 0 Insert control rods with one or more appropriate appendices EVALUATORS NOTE: Implement appendix F, BB or H of OE 3107.

0 Stabilize pressure RPV pressure 800-1,000 psig with BPVs.

When directed:

0 Inhibit ADS.

0 Implement App P to keep the MSlVs Open.

Stabilize pressure 800-1000 psig with BPVs.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 22 of 26 STEP I POS. CANDI DATE ACTIONS/BEHAV IOR U N/OI COMMENTS

  • CREW During an ATWS with conditions met to perform powerJlevel EOP-2 control TERMINATE AND CCT-4 PREVENT INJECTION into the RPV using appendix GG,until conditions are met to re-establish injection.

Standard:

Completion of Terminate and prevent injection IAW OE 3107 Appendix GG within 5 minutes of loss of forced circulation.

I CRS Inject SLC I CRS Terminate/prevent injection per Appendix GG.

Standard:

Actions taken within 10 minutes of the scram failure to implement appropriate appendices and/or inject SLC. Only one method needs to be used. The method must result in successful control rod insertion or SLC injection.

When steam flow c0.5lbmhr per steamline, place Mode Switch in SHUTDOWN.

EVALUATORS NOTE: This step is an Immediate Action, and may be performed without direction.

0 Insert control rods using directed appendices.

0 Start A SLC Pump. Recognize trip of SLC pp.

EVALUATORS NOTE: After trip of SLC< control rod insertion becomes only means available to satisfy the critical task.

0 When directed, terminate/prevent injection per Appendix GG.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 23 of 26 STEP POS. CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS BOP When directed, terminate/prevent injection per Appendix GG.

  • CREW When conditions are met to re-establish injection, use available EOP-2 injection systems to RESTORE &

CCT-5 MAINTAIN RPV water level above

-19".

Standard:

Restore and maintain RPV level to between -19" and the level to which it was lowered AND no significant power excursion occurs.

CRO Recognize when power drops below 2 %; inform CRS CRS Direct RPV level maintained between -1 9 and 90 inches CRO Maintain RPV level between -1 9 and 90 inches CRO/STA Recognize all rods inserted; inform CRS CRS When all control rods inserted, exit EOP-2 and enteddirect actions IAW EOP-1:

0 Terminate boron injection 0 Verify Table A automatic actions 0 Restore / maintain RPV level 127 - 177 inches.

Commence cooldown at less than 100 degrees F per hour.

BOP When directed, commence cooldown at less than 100 degrees F per hour.

CRO Terminate boron injection:

0 Restore / maintain RPV level 127 - 177 inches.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O= Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 2 Rev b Page 24 of 26 STEP I POS. CANDIDATE ACTIONS/BEHAV IOR S COMMENTS CRS When all rods inserted, exit EOP-2, enter EOP-1, and direct RPV level restored and maintained 127 -1 77 inches.

1 I

SMISTN CRS

~ ~~~

Classify the event as a Site Area Emergency IAW AP 3125 Appendix A (S-7-c).

EVALUATORS NOTE: 15 minute clock.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 3 Rev b Page 3 of 20 SIMULATOR EVALUATION GUIDE Evaluators: Crew:

SM CRS CRO BOP STA Senior Management Observer Scenario Template:

Template

Title:

TITLE Critical Task Performance: SAT UNSAT (Circle One)

Lead Evaluator:

Signature Date Administered:

Activity Code; Prepared by: Date:

Reviewed by: Date:

Approved by: Date:

Appendix D NUREG 1021 Revision 9

VY 2007 NRC Scenario 3' Rev b Page 8 of 20 OPERATOR ACTIONS EVENT NUMBER 1 Crew Task

Description:

Perform Turbine Chest Warmup

~ ~~ ~

STEP POS. CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS CRS Directs Performing Turbine Chest Warmup IAW OP 0105 Phase 2.D.

Step 1.

Direct CRO to monitor Reactor Power, Pressure and Level during Turbine Chest Warm-up.

BOP Enters OP 0105 Phase 2.0. Step 1.

for Turbine Chest Warm-up and reviews Takes actions IAW OP 0105 for Turbine Chest Warmup CRO Maintains Reactor Power, Pressure and Level as Turbine Chest Warm- 1 up is placed in service.

steps attached.

I I I I I

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 3 Rev b Page 9 of 20 OPERATOR ACTIONS EVENT NUMBER 2 Crew Task

Description:

Pull Rods to Continue Power Ascension STEP POS. I CANDIDATEACTIONS/BEHAVIOR I S I U I N/O I COMMENTS CRS Directs power ascension per OP 0105 until 1 YZ bypass valves open CRO Withdraws control rods to increase power.

CREW I Monitors reactor parameters ~

EVALUATORS NOTE: Specific guidance for rod pulls in OP 0105.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 3 Rev b Page 10 of 20 0PERATOR ACTIONS EVENT NUMBER 3 Crew Task

Description:

IRM A Fails Upscale (TS)

CANDlDATE ACTIONS/BEHAVIOR N/O COMMENTS Recognizes IRM A failed upscale Recognizes YZ scram ALARMS CRS Recognizes IRMA upscale, references OP2131 section C.

Directs confirmation of upscale .

Directs I & C to investigate.

Directs bypassing IRM A.

Directs reset of YZ scram.

Consults Tech Specs - Table 3.1.1

- no restriction with one IRM inop.

CRO Bypasses IRM Resets % scram per OP 21 34 RPS.

I CRS I Crew Brief NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 3 Rev b Page 11 of 20 0PERATOR ACTIONS EVENT NUMBER 4 Crew Task

Description:

CRD Flow Control Valve Fails Closed (ON)

-~ ~

POS. I CANDIDATE ACTIONS/BEHAVIOR N/O COMMENTS CREW Recognizes abnormal CRD conditions.

Control Rod wont move.

CRS Enters ON 3145 - Loss of CRD Reg Function.

Directs actions per ON 3145, Step 9 for placing flow controller in manual, 1 and swapping controllers.

CRO Takes steps described in Step 9.

places in service flow controller in manual 0 determines problem still exists 0 swaps to alternate controller CRS Crew Brief.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; NIO = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 3 Rev b Page 12 of 20 OPERATOR ACTIONS EVENT NUMBER 5 Crew Task

Description:

Stuck Control Rod 26-27 (ON)

STEP POS. CANDIDATE ACT IONS/BEHAVlO R S COMMENTS CRO Determines control rod 26-27 is stuck and notifies CRS CRS Enters ON 3143 - Stuck Control Rod and directs actions contained on ON 3143 flow chart.

CRO Takes actions as directed to unstick control rod per ON 3143 flowchart e attempt one notch insert e attempt a single notch withdraw e determines drive water pressure e raises drive water pressure 10-50 psig e attempt to insert control rod one notch (successful) e attempt to withdraw one notch (successful) e insert 26-27 one notch e withdraw 26-27 one notch e return drive water press. to 250-275 e insert then withdraw 26-27 one notch (done twice)

CRO insert then withdraw 36-27 one notch (done twice).

CRS Crew Brief.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 3 Rev b Page 13 of 20 OPERATOR ACTIONS EVENT NUMBER 6 Crew Task

Description:

Seismic Event; Trip of A T B X W Pump with B TBCCW Pump Failing to Auto Start STEP POS. CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS CREW Recognize and inform the CRS of indication of a seismic event CRS Enter and direct crew actions IAW OP 3127 CRS Direct CRO/BOP to dispatch A 0 to check for damage to structures or equipment IAW OP 3127 CRO/BOP When directed, dispatch AOs to check for damage to structures or equipment IAW OP 3127 CRS Direct CROlBOP to verify the seismic event by checking indications on the seismic monitor CRO/BOP When directed, check seismic monitor report valid indication of a seismic event CRS Direct CRO to check control rod display for rod drift CRO When directed, check control rod display. Report no drifts Crew Recognize and gross fail alarms and Y2 scram alarms due to low level CRS Direct A 0 to check local level indications CREW Report other level indications are normal

~ ~ ~~~

CREW Direct STA to check the seismic monitor to determine if OBE was exceeded CREW Report loss of A TBCCW Declares ALERT for seismic event A-5-C.

2) * = Critical TasWStep

VY 2007 NRC Scenario 3 Rev b Page 14 of 20 I STEP POS.

BOP CANDIDATE ACTIONS/BEHAVIOR Starts B TBCCW pump manually.

EVALUATORS NOTE:

S U N/O COMMENTS CRO must be distracted to ensure ACRO gets credit for this malfunction.

Ensure Sim Booth places a follow-up phone call from RB RO to CRO in regard to CRD flow control valve.

F CREW Call Electrical Maintenance to investigate the loss of valve indication, and failed level transmitter CRS Conduct a crew brief on plant conditions and priorities.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 3 Rev b Page 15 of 20 0PERATOR ACTIONS EVENT NUMBER 7 Crew Task D scription:

RClC Steam Leak (TS); RClC Fails to Auto Isolate STEP POS. I CANDIDATE ACTIONS/BEHAVIOR I S N/O COMMENTS CREW I Responds to Annunciator 9-4-U-2 RCIC Steam Line DP High

=

CRS May Enter ON 3158 RX BLDG High Area Tempwater Level DirectsNerifies Isolating RClC when it fails to auto isolate.

Tech Specs 3.5.G.2.- 14 day LCO BOP Refers to Alarm Response Procedure for 9-44-2.

Manually Isolates RClC valves 15 i3 16 due to failure to auto isolate.

(Successful)

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 3 Rev b Page 16 of 20 0PERATOR ACTIONS EVENT NUMBER 8,9, & 10 Crew Task

Description:

Seismic Aftershock; Group 1 Isolation; Auto Scram Failure; Manual Scram Required; PClS Group 111 Failure STEP POS. CANDIDATE ACTIONS/BEHAVIOR U COMMENTS CRO Spurious Group 1 Isolation due to seismic event and the reactor should have scrammed CREW Recognize auto scram failure

  • CREW With the reactor at power and a full auto scram signal, manually EOP-2 scram the reactor CCT-1 Standard:

Actuate the manual scram pushbuttons, place the mode switch in SHUTDOWN, or actuate the ARI-RPT pushbuttons within 1 minute of reaching the Limiting Safety System Setting CRO Insert manual scram.

CRS Enter and direct actions per OT 3100 and EOP-1 Verify applicable Table A automatic actions CRO When steam flow < 0.5 Mlbm/hr per steamline, place mode switch in SHUTDOWN Verify all rods inserted; inform CRS Insert IRMs and SRMs CREW Recognizes SDV Drain valves CRD

-33A & 338 fail to isolate on scram.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 3 Rev b Page 17 of 20 POS. CANDlDATEACTIONS/BEHAVIOR IS 1U N/O COMMENTS CRO Attempts to Isolate SDV valves (unsuccessful)

Reports to CRS failure to isolate.

CRS Enters OP 3127 Natural Phenomena due to alarm 7-M Seismic Monitor Alarm from aftershock.

CRS Enters EOP-4 on Alarms 4-L-4 -Equip.drain N/S sump hi 4-M Floor drain N/S sump hi Due to increasing sump levels caused by SDV failure to isolate.

CREW Maintains pressure/level as directed BOP CRO Controls Pressure 800-1000 psig Control RPV water level 127-177 with feedwater t NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 3 Rev b Page 18 of 20 OPERATOR ACTIONS EVENT NUMBER 11 Crew Task

Description:

Torus Leak at ARHR SucLm (5 b Over 900 Secs); PRV-ED on -ow Torus Level lsTEP POS. I CANDIDATE ACTIONS/BEHAVIOR COMMENTS CREW 1 Report high sump levels in reactor building.

CRS I Direct an A 0 to investigate.

CRS When A 0 reports RHR suction line break, enter and direct actions per ON 3108, Loss of Containment Integrity Emergency Procedure and ON 3158, Hi Rx Building Temperature or Water Level.

CRS Direct maintenance to attempt to restore primary containment integrity.

CREW Respond to reactor building sump level alarm.

CRS Re-enter EOP-4, Secondary Containment Control, due to high floor drain sump levels.

CRS I Verify all available sump pumps are running.

CRS I Enter EOP-3 on low torus volume CRS Direct CREW to initiate makeup to the torus IAW Table N (multiple systems should be used).

BOP Initiates torus makeup, as directed.

  • CREW When torus level cannot be maintained above 7 ft, perform CCT-2 RPV emergency depressurization.

Standard:

Initiate RPV-ED such that RPV pressure is e 50 psig when Torus level reaches 5.5 ft.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 3 Rev b Page 19 of 20

-~

STEP I POS. CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS EVALUATOR'S NO

__ ~ _ _ _

When torus level cannot be maintained above 7 ft, enter EOP-5 Inhibit HPCl and and direct all 4 SBVs opened.

HPCl injection is terminated before Torus level falls below 6 ft. if HPCl is running.

Open SRVs as directed.

Direct CRO to restore and maintain level 6" - 177" using condensate and feed. EOP-1, Step RC/L-2 Maintain RPV level as directed.

Consult AP 3125 and determine an SAE EAL has been reached IAW t Appendix S-5-c, NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 4 Rev b Page 3 of 20 SIMULATOR EVALUATION GUIDE Evaluators: Crew:

SM CRS CRO BOP STA Senior Management Observer Scenario Template:

Template

Title:

TITLE Critical Task Performance: SAT UNSAT (Circle One)

Lead Evaluator:

Signature Date Administered:

A ctivify Code:

Prepared by: Date:

Reviewed by: Date:

Approved by: Date:

Appendix D NUREG 1021 Revision 9

VY 2007 NRC Scenario 4 Rev b Page 8 of 20 0PERAT0 R ACTIONS EVENT NUMBER 1 Crew Task

Description:

Speed Load Changer Bypass Test OP 4160 CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS Direct Speed Load Changer Bypass IAW OP-4160 Reviews OP-4160, Section F -

Speed Load Changer Bypass Test.

1. Slowly Operate the Speed Load Changer Bypass switch by going to LOWER until it is noted that there is a slight decrease in electrical output and the #1 bypass valve begins to open.
2. Slowly operate the Speed Load

\

changer Bypass switch by going to RAISE until no further load decrease is noted (bypass valve closed).

3. Record required data.

EVALUATORS NOTE: GO TO Next Event at Examiner discretion.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 4 Rev b Page 9 of 20 OPERATOR ACTIONS EVENT NUMBER 2 Crew Task

Description:

Power Ascension IAW OP-0105 STEP POS. CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS CRS Directs Power increase IAW OP-0105 CRO increases power using recirc flow control or control rods CRO/ACRO Monitors control board indications NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 4 Rev b Page 10 of 20 OPERATOR ACTIONS EVENT NUMBER 3 Crew Task

Description:

LOSSOf MCC-8A (TS)

STEP POS. CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS CREW Recognize and respond to a loss of MCC.

Directs Field operator to investigate I alarm.

CRO Recognizes 1/2 scram on A side of RPS BOP Recognizes Bus 8 MCC trouble annunciator 8-J-8 Contacts field operator.

CREW Recognize Group Ill isolation.

CRS Reviews OP 2143 - MCC-8A Load List when informed feeder bkr tripped Directs electrical maintenance to investigate loss of MCC-8A.

CRS Receives report that MCC-8A can be returned to service CRO Resets Half scram by:

Resets YZ scram BOP Backs up and resets Group Ill isolation per OP2115 Section L.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 4 Rev b Page 11 of 20 1 STEP I POS. I CANDlDATEACTIONS/BEHAVIOR I S I U I N/O I COMMENTS I CRS Evaluate Tech Specs, determines that 3.7.6.3 - 7day LCO applies Conduct a Shift Brief NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 4 Rev b Page 12 of 20 0PERATOR ACTIONS EVENT NUMBER 4 Crew Task

Description:

Condensate Pump A Trips, Failure of RFP B to Trip (OT) (RP); Feedwater Pump B CD Trip Bypass Switch in Bypass STEP I POS. I CANDIDATEACTIONSIBEHAVIOR I S I U I N/O I COMMENTS CREW Recognize and inform CRS of the trip of the Acondensate pump.

CRO Recognize and report B FW Pump has tripped as a result of the condensate pump trip CRS Enter and direct crew actions IAW OT 31 13, Low Reactor Level 0 DirecVverify manual runback of recirc pumps using the PB1 pushbuttons on both pump controllers 0 Verify Reactor Vessel Level Master Controller setpoint sets down to 155 inches CRO 0 Manually runback recirc pumps Immediate Operator Action using the PB1 pushbuttons on OT3113 both pump controllers 2-184-16A(B)

. 0 Verify Reactor Vessel Level Master Controller setpoint sets down to 155 inches NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 4 Rev b Page 13 of 20 STEP POS. CANDIDATE ACTIONS/BEHAVIOR U I N/O I COMMENTS CRS Direct thk CRO to begin reducing power to 70 to 75%

Below the MELLLA boundary, reduce power using recirc flow 0 When above the MELLLA boundary, stop lowering core flow and reduce power using the rapid shutdown sequence in reverse order CRO Reduces power as directed.

CRS Direct CRO/BOP to contact maintenance and/or A 0 to investigate cause of the pump issues.

~~

CRO/BOP When directed, contact maintenance and/or A 0 to investigate cause of the pump trip.

CRS Brief the crew on plant conditions NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O= Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 4 Rev b Page 14 of 20 OPERATOR ACTIONS EVENT NUMBER 5 Crew Task

Description:

Steam Flow Summer Fails Upscale (OT) (100% over 60 sec)

STEP POS. CANDIDATE ACT IONS/BEHAVlO R S U N/O COMMENTS CREW Recognizes steam flow summer fails upscale EVALUATORS NOTE: See attached copy . . of OT 3114 for specific actions.

CRS References OT3114 - Rx High level and directs immediate actions CRS Directs CRO to:

Place level control in single element once conditions stabilize (OT3114).

Place Master Controller in Automatic Control CRO Takes action to stop level increase.

Takes Mater Feedwater level Controller to Manual and controls level prior to reaching Scram and Main Turbine trip setpoint.

Places level control in single element once conditions stabilize (OT3114).

Places Master Controller in Automatic Control CRO Contact I&C Crew Brief NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 4 Rev b Page 15 of 20 0PERATOR ACTIONS EVENT NUMBER 6 Crew Task

Description:

Recirc Leak (OT) (TS)

STEP POS. CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS CREW Recognize and respond to Rising Drywell Pressure.

CRS Directs Actions IAW OT 31 11-Drywell pressure HVLO.

0 Reduce core flow 0 Close AC-20 N2 M/U 0 Start all available Drywell RRUs CRO Reduces core flow as directed in OT3111 BOP Closes AC N2 M/U Starts all available Drywell RRUs CRS Reviews TS and determines an LCO is required for 3.6.C.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O= Not Observed All Unsatisfactoryratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 4 Rev b Page 16 of 20 OPERATOR ACTIONS EVENT NUMBER 7 & 8 Crew Task

Description:

MS Line A Rupture in Drywell (10% over 1200 secs); AC-6 and AC-6B Fail to Auto Close.

STEP POS. CANDIDATE ACTIONS/BEHAVIOR S U N/O COMMENTS EVALUATORS NOTE: The first few steps here do not ai )ly. Did not find event for recirc leak.

Recognize rising Drywell pressure; inform CRS Enter and direct actions IAW OT 31 11 (High Drywell Pressure).

0 Enter EOP-3 and EOP-1.

0 Directs manual Scram.

0 Enters OT 3100.

Directs manual Scram Enters 013100 Restart Drywell RRUs per EOP-3 I CRS Enter and direct actions IAW OT 3100/ EOP-1:

Verify Automatic Actions per Table A.

CREW When directed, verify Automatic Actions per Table A NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 4 Rev b Page 17 of 20 STEP POS. CANDlDATEACTIONS/BEHAVIOR IS I U N/O I COMMENTS CRS Enter EOP-1, and direct the following:

0 When steam flow < 0.5 Mlb /

main steam line, place Mode Switch in SHUTDOWN 0 Restorehaintain RPV level between 127-177 inches 0 Maintain RPV pressure between 800-1000 psig using BPVs 0 Insert IRMs and SRMs CRO 0 Insert IRMs and SRMs Restorehnaintain RPV level 127 to 177 inches

  • CREW When PClS Group 3 fails to isolate valves AC-6 an AC-6B with EOP-3 a leak present, initiate PClS CCT-1 Group manually Standard:

Leak or release terminated within 10 minutes of receipt of the auto isolation signal BOP Recognize containment isolation valves AC-6 and AC-6B still open; inform CRS.

EVALUATORS NOTE: BOP may close valves and then inform CRS.

I CRS I Direct isolation of AC-6 and AC-6B I I I Complete isolation of AC-6 and AC-6B s/initiations BOP When directed, maintain pressure 800 - 1000 psig using Bypass valves CREW Recognize Drywell pressure is still increasing; inform CRS CRS Enter and direct actions IAW OT 31 11 (High Drywell Pressure)

Start all available drywell RRUs.

BOP When directed, start all available drywell RRUs.

NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O = Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep

VY 2007 NRC Scenario 4 Rev b Page 18 of 20 STEP I POS. I CANDIDATE ACTIONS/BEHAVIOR N/O COMMENTS CRS Direct spraying the torus IAW EOP-3 BEFORE torus pressure reaches

' 10 psig

~

  • CREW When torus pressure exceeds 10 psig, initiate drywell spray while EOP-3 in the safe region of the drywell CT-2 spray initiation limit.

Standard:

Spray the drywell within 10 minutes of exceeding 10 psig torus pressure CRS When drywell temperature cannot be maintained below 280 F or torus pressure exceeds 10 psig, direct the following IAW EOP-3:

Shutdown Drywell RRUs and recirc Pumps.

Initiate Drywell spray.

(When directed) initiate Drywell spray 0 Shutdown Drywell RRUs and Recirc pumps.

0 Initiate Drywell spray Direct Drywell Spray using RHR I

I I When directed, spray the Drywell using RHR Recognize Drywell pressure lowering; inform CRS

: " SM/ STA / Classify event as a Alert IAW AP 0125 Appendix A (A-3-a or A-3-b).

I EVALUATOR'S NOTE: 15 minute clock, Crew Brief NOTES: 1) S = Satisfactory; U - Unsatisfactory; N/O= Not Observed All Unsatisfactory ratings require comments; a comment sheet is attached.

2) * = Critical TasWStep
Retrieved from "https://kanterella.com/w/index.php?title=ML071350583&oldid=2577061"