ML071350583

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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)
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Text

Eva1 u ato rs:

VY 2007 NRC Scenario 1 Rev b Page 3 of 21 SIMULATOR EVALUATION GUIDE Senior Management Observer Scenario Template:

Template

Title:

Critical Task Performance:

Lead Evaluator:

Date Administered:

Activity Code:

TITLE Crew:

SM CRS CRO BOP STA SAT UNSAT (Circle One)

Signature Prepared by:

Reviewed by:

Approved by:

Date:

Date:

Date:

Appendix D NUREG 1021 Revision 9

VY 2007 NRC Scenario 1 Rev b Page 8 of 21 STEP OPERATOR ACTIONS EVENT NUMBER 1 POS.

CANDIDATE ACTIONS/BEHAVIOR S

U N/O COMMENTS CRS Direct Turbine Pump Performance IAW OP 4160 Section B.

Crew Task

Description:

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

EXAMINERS NOTE:

SEE ATTACHED COPY OF PROCEDURE FOR SPECIFIC STEP DETAIL.

i I

l l

~~~~

Performs OP 4160 Section 111. Steps 1.a thru 1.f p q 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 POS.

CANDIDATE ACTIONS/BEHAVIOR S

CRS Directs Power Increase IAW OP-0105 With recirc flow Increase recirc flow with master recirc flow controller Q 1 % per 3 minutes CRO CRO Monitors power, pressure, level.

OPERATOR ACTIONS EVENT NUMBER 2 U

Crew Task Description :

Power Ascension IAW OP 0105 N/O STEP COMMENTS 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 STEP 0 P ERATO R ACTIONS EVENT NUMBER 3 & 4 POS.

CANDIDATE ACTIONS/BEHAVIOR S

U N/O COMMENTS CREW Recognize a loss of Bus 898 power.

CRS Enter and direct actions IAW OP 21 43 and ARS.

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

Review Tech Specs and determine per 3.1 0.B.4 and 3.5.A.4 enter a 7-day LCO for "B" LPCI.

Direct A 0 to document indicating lights at RUPS 1 B and MCC 898 per OP 21 43.

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

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

to pump trip and auxiliary operator to investigate locally.

CRS Conduct a shift brief.

CREW BOP CRS Directs contacting maintenance due Crew Task

Description:

Respond to a Loss of Bus 89B; Loss of Circ Water 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.

CREW CRS NOTES:

CANDIDATE ACTIONS/BEHAVIOR S

Recognizes Trip of A CRD pump.

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.

N/O I COMMENTS SEE Attached copy of ON 3145 for specific steps.

.~

References ON 31 45

-Takes action to stop RWCU pump B.

- Starts B CRD pump per ON 3145

- Takes action to isolate seal purge 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:

CRO CREW NOTE:

Operator will open 156-3 IAW ARS to clear alarms.

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 CRS L

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 OPERATOR ACTIONS EVENT NUMBER 6 Crew Task

Description:

Control Rod 18-31 Drifts Outward (OT)

~~~~

~

POS. I CANDIDATE ACTIONS/BEHAVIOR I S Acknowledgehespond to Rod Drift I CREW I annunciator (5-D-5); inform CRS.

Identify rod 18-31 as drifting rod; inform CRS.

I NOTES:

1)

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

2)
  • = Critical TasWStep

STEP POS.

BOP CRO CREW CRS CANDIDATE ACTIONS/BEHAVIOR Direct the following IAW OT 31 67 and OT 31 10 (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 31 66 (Mispositioned Control Rod).

~~~~

~

~

When directed, manually scram rod 18-31.

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

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

Conduct a crew brief.

S -

VY 2007 NRC Scenario 1 Rev b Page 13 of 21 N/O I COMMENTS NOTES:

1)

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

2)
  • = Critical TasMStep

Crew Task

Description:

Inadvertent HPCl Initiation (TS)

CRS VY 2007 NRC Scenario 1 Rev b Page 14 of 21 Brief the crew.

OPERATOR ACTIONS EVENT NUMBER 7 II CAN DI DATE ACTION S/BEH AVl OR Recognize and inform the CRS of a HPCl initiation.

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

11 NOTE:

See Attached OT 31 10.

U I N/O I COMMENTS I1 I

Confirm no initiation signals present.

(Two indications at least).

CRS Directs that HPCl be tripped per Step 4.

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

BOP CRS Places Autohhibit switch to Inhibit.

Verify SBGT operation. Opens SGT l A & l B.

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

OT 31 10 - Step 9.Contacts RE 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 CREW OPERATOR ACTIONS Recognize and inform CRS of Loss of Off Site Power.

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

EVENT NUMBER 8 CREW Crew Task

Description:

Loss of Offsite Power Respond to LNP IAW OT 31 22.

0 Verify both DGs start and power busses.

0 Verify SW pumps start.

0 Restart station AC A & B.

11 STEP I

POS.

I CANDIDATE ACTIONS/BEHAVIOR

~

~~

CRS II I

CRO I Report reactor scram.

~~~

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

CRO CRS Report feed and condensate are ll I

CRo I unavailable.

Insert IRMs and SRMs.

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

Direct pressure maintained 800 -

1000 psig using SRVs/HPCI.

CRS II I

I 3122, LNP Enter and direct actions IAW OT 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.

NOTE:

E NOTES:

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

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

BOP Maintain RPV level as directed with RClC initially.

HPCl (must be taken out of inhibit).

actuations.

CREW Verify Table A: ECCS/PCIS U

N/O COMMENTS 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 POS.

BOP OPERATOR ACTIONS EVENT NUMBER 9,10, & 11 CANDIDATE ACTIONS/BEHAVIOR S

U N/O Report HPCl trip.

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 I

Maximize available CRD flow Report increasing drywell pressure.

BOP CRS Direct AO/ maintenance to investigate HPCl trip Spray the torus, as directed.

When torus pressure exceeds 10 I

l l

BOP BOP CRS BOP Direct RPV level maintained between 6 inches (TAF) and 177 inches by maximizing CRD flow Secure drywell RRUs.

Spray the drywell as directed.

When ADS timer initiated, direct ADS inhibited.

Inhibit ADS as directed.

Enter EOP-3 on High Drywell I

CRS I Pressure.

I l

l Direct BOP to restart drywell CRS I RRU's.

I l

l II I

BOP I Restart drywell RRU's.

I l

l Before torus pressure reaches 10 I

I CRS I psig, direct torus sprays E

0 Verify drywell pressure and temperature in the safe region of the DWSIL graph.

0 Verify drywell RRUs secured.

0 Direct drywell sprays.

COMMENTS 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 S

U CANDIDATE ACTIONS/BEHAVIOR N/O COMMENTS Direct SLC for reactor water level control.

CREW CRS CRS CRO/BOP Direct RPV level maintained between 6 inches (TAF) and 177 inches Inform CRS when level reaches 6.

Before level reaches - 19 inches, enter and direct crew actions IAW Direct all SRVs opened.

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

EOP-5 RPV-ED.

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 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 CRS BOP/CRO STEP I POS.

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

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

CREW 1, I

BOP CRS I

CREW CANDIDATE ACTIONS/BEHAVIOR Action is taken to restore RPV water level above -19 inches by 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.

injection valves once valve open permissive pressure is reached.

0 Initiate manual opening of Continue to monitor and report RPV Level and Pressure decrease.

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.

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

Verify adequate core cooling and level rising.

COMMENTS

2)
  • = Critical TasWStep

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

1)

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

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

2)
  • = Critical TasWStep

Evaluators:

VY 2007 NRC Scenario 2 Rev b Page 3 of 26 SIMULATOR EVALUATION GUIDE Senior Management Observer Scenario Template:

Template

Title:

Critical Task Performance:

Lead Evaluator:

Date Administered:

Activity Code:

Crew:

SM CRS CRO BOP STA TITLE SAT UNSAT (Circle One)

Signature Prepared by:

Reviewed by:

Approved by:

Date:

Date:

Date:

Appendix D NUREG 1021 Revision 9

I BOP BOP VY 2007 NRC Scenario 2 Rev b Page 8 of 26 Closes all intake gates by taking hand switches Circ Water Intake Gate 1 A (1 B, 1 C) to close.

Monitors intake level and condenser backpressure.

0 P ERATO R ACTIONS EVENT NUMBER 1 Crew Task

Description:

Place CW in Closed Cycle for Chlorination STEP POS.

CRS BOP BOP BOP CANDIDATE ACTIONS/BEHAVIOR Directs Placing CW in closed Cycle for chlorination.

Procedure OP 21 80 Section F.

Reviews procedure and checks prereqs.

Ensures all Circ Water & Circ Water Booster Pumps running.

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

EVALUATORS CUE:

Report back - not treating SW simultaneously.

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 Calls field operator to throttle valve I

I cw-7. 1 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 STEP OPERATOR ACTIONS EVENT NUMBER 2 POS.

CANDIDATE ACTIONS/BEHAVIOR S

U COMMENTS CRS CUE

~

~

Directs power reduction IAW OP-01 05 USE provided power reduction memo.

Crew Task

Description:

Power Reduction IAW OP 0105 CRO Selects Rod 22-1 9 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 CRS OPERATOR ACTIONS EVENT NUMBER 3 CREW Brief on FRV operation and level control per guidance in OTs and ARS Crew Task

Description:

Feedwater Regulating Valve Lockup (OT) 11 STEP I POS.

CANDIDATE ACTIONS/BEHAVIOR 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.

U I N/O I COMMENTS 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 STEP OPERATOR ACTIONS EVENT NUMBER 4 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 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.

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

0 increased board monitoring 0

contacts I&C.

CRS CRO CRS Crew Brief.

Crew Task

Description:

APRM A Fails Downscale (TS)

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

Recognize oscillating reactor pressure Enters OT 31 15.

Coordinate determination of EPR at fault; inform CRS.

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

0 0

0 Lower MPR setpoint as 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.

Place the EPR in CUTOUT Verify that the MPR has control necessary 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.

N/O COMMENTS 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 ll I CREW OPERATOR ACTIONS EVENT NUMBER 6

//

I CRo Crew Task

Description:

Loss of 480 Volt Bus 8, Failure of SBGT A to Auto Start CRS BOP BOP When directed shut RWCU 18.

.I 11 STEP I POS.

I BOP I When directed shut RWCU 18.

I I

I I

CANDIDATE ACTIONS/BEHAVIOR Recognize and inform CRS of a loss of 480 volt Bus 8.

Inform CRS of half scram.

Report power, pressure, level Recognize/respond to 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)

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.

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.

COMMENTS 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 I

NOTES:

CAN D I DATE ACT ION S/BE H AVl OR 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 for a normal plant S/D per OP 01 05.

Provide a crew brief on conditions and shutdown.

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

COMMENTS

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

OPERATOR ACTIONS EVENT NUMBER 7 Crew Task

Description:

SRV-716 Leak (OT) Leads to Rx Scram (1 00% over 6OOsec)

STEP I POS.

CRS CANDIDATE ACTION S/BEH AVlOR Recognize the "B" SRV leaking.

Enter OT 3121, Inadvertent Opening of SRV.

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

inform CRS Enter and direct actions IAW OT 3121 (Inadvertent Opening of a Relief Valve)

COMMENTS 11 EVALUATOR'S NOTE:

SRV is part-way open and may be assessed as either OPEN or leaking.

11 EVALUATOR'S NOTE:

No actions to stop leak will be successful.

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 CRS STEP I POS. I CANDlDATEACTIONS/BEHAVIOR I S IF the SRV remains OPEN, Place the ADS Appendix R Bypass Switch on CRP 9-3 to BYPASS.

Attempt to cycle B SRV; report valve failure to close.

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

EOP-3 EVALUATORS NOTE:

(Onlv if assessed as OPEN.)

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

EVALUATORS NOTE: (Onlv if assessed as OPEN.)

If core flow is greater than 29 Mlbm/Hr then reduce reactor power I

10% 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 I 10% RTP/min using recirc flow until core flow is 27.5 to 29 Mlbm/Hr.

EVALUATORS NOTE: (Only if assessed as OPEN.)

CRO/BOP U I N/O I COMMENTS CRS I Direct the following actions:

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

Reactor shutdown/cooldown as required by OT-3121.

When directed, commence plant shutdown IAW OP 0105.

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 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

=

N/O -

COMMENTS 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 CRO/BOP OPERATOR ACTIONS EVENT NUMBER 8 Maintain reactor level as directed.

0 Determine HPCl not required for level control 0

HPCl tripped and inhibited Crew Task

Description:

Failure of Manual Scram; ARI Required 11 STEP I POS.

I CANDlDATEACTIONS/BEHAVIOR I S

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

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 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.

Direct CRO to maintain level from ll I

CRS I 127" - 177".

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

Maintain reactor pressure as R

I CSROOp/ I directed.

~ _ _

~~

N/O I COMMENTS 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 BOP When directed monitor cooldown.

Direct crew to monitor the plant 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 CRS OPERATOR ACTIONS EVENT NUMBER 9 & 10 When informed of the scram failure enter and direct crew actions IAW EOP-1 and EOP-2 Crew Task

Description:

45% Hydraulic ATWS (A) 55% Hydraulic ATWS (8); SLC Pump A Trips; B SLC Squib Valve Fails to Fire CREW CRS BOP STEP Recognize/respond to high Drywell pressure and entry into EOP-3; inform CRS Enter/direct actions per EOP-3 0

Restart Drywell RRUs.

When directed:

0 Restart Drywell RRUs.

POS.

CRO "CREW EOP-2 CCT-2 CANDIDATE ACTIONS/BEHAVIOR S

Recognize failure of control rods to insert; inform CRS.

With reactor scram required and the reactor not shutdown, take action to reduce power by 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.

0 Report failure of ARVRPT to 1

CRS Trip Recirc pump drive motor I

breakers COMMENTS I

l l

When directed, verify EOP-1 Table I

sTA I A automatic actions

2)
  • = Critical TasWStep

STEP N/O COMMENTS

POS.

CRS CANDIDATE ACTION WBEHAVIOR With a reactor scram required and the reactor not shutdown, INHIBIT ADS to prevent an uncontrolled RPV depressurization to prevent causing a significant power excursion.

Standard:

Inhibit ADS prior to automatic initiation.

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 VY 2007 NRC Scenario 2 Rev b Page 21 of 26 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.

CRS I

CRS

  • CREW EOP-2 CCT-4 CAN D I DATE ACTION S/BE H AV IO R During an ATWS with conditions met to perform powerJlevel control TERMINATE AND 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 31 07 Appendix GG within 5 minutes of loss of forced circulation.

Inject SLC Terminate/prevent injection per Appendix GG.

With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron and/or inserting control rods, to prevent exceeding the primary containment design limits.

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.

U N/OI COMMENTS 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

  • CREW EOP-2 CCT-5 CRO CRS CRO CRO/STA CRS BOP CRO When directed, terminate/prevent injection per Appendix GG.

When conditions are met to re-establish injection, use available injection systems to RESTORE &

MAINTAIN RPV water level above

-1 9".

Standard:

Restore and maintain RPV level to between -1 9" and the level to which it was lowered AND no significant power excursion occurs.

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

EOP-1:

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

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

STEP I

POS.

CRS SMISTN 1

CRS CAN D I DATE ACTIONS/BEH AV IO R When all rods inserted, exit EOP-2, enter EOP-1, and direct RPV level restored and maintained 127 -1 77 inches.

~

~~~

Classify the event as a Site Area Emergency IAW AP 31 25 Appendix A (S-7-c).

S VY 2007 NRC Scenario 2 Rev b Page 24 of 26 COMMENTS I

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

Evaluators:

VY 2007 NRC Scenario 3 Rev b Page 3 of 20 SIMULATOR EVALUATION GUIDE Senior Management Observer Scenario Template:

Template

Title:

Critical Task Performance:

Lead Evaluator:

Date Administered:

Activity Code; Crew:

SM CRS CRO BOP STA TITLE SAT UNSAT (Circle One)

Signature Prepared by:

Reviewed by:

Approved by:

Date:

Date:

Date:

Appendix D NUREG 1021 Revision 9

Crew Task

Description:

Perform Turbine Chest Warmup BOP OPERATOR ACTIONS EVENT NUMBER 1 Enters OP 01 05 Phase 2.0. Step 1.

for Turbine Chest Warm-up and reviews Takes actions IAW OP 01 05 for Turbine Chest Warmup STEP CRO POS.

Maintains Reactor Power, Pressure and Level as Turbine Chest Warm-up is placed in service.

1 CRS CANDIDATE ACTIONS/BEHAVIOR 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.

S -

U -

I I

I I

N/O VY 2007 NRC Scenario 3' Rev b Page 8 of 20

~

~~

~

COMMENTS

steps attached. 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 CRS CRO OPERATOR ACTIONS EVENT NUMBER 2 Directs power ascension per OP 0105 until 1 YZ bypass valves open Withdraws control rods to increase power.

Crew Task

Description:

Pull Rods to Continue Power Ascension STEP POS.

I CANDIDATEACTIONS/BEHAVIOR I S I U I N/O I COMMENTS 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 N/O 0 P ERATO R ACTIONS EVENT NUMBER 3 COMMENTS Crew Task

Description:

IRM A Fails Upscale (TS)

CRO CANDl DATE ACTIONS/BEHAVIOR Bypasses IRM Resets % scram per OP 21 34 RPS.

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.

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

0 P ERATO R ACTIONS EVENT NUMBER 4 Recognizes abnormal CRD conditions.

Control Rod wont move.

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.

Crew Task

Description:

CRD Flow Control Valve Fails Closed (ON)

CRS POS. I CANDIDATE ACTIONS/BEHAVIOR Crew Brief.

CREW CRS CRO Takes steps described in Step 9.

places in service flow controller in manual 0

determines problem still exists 0 swaps to alternate controller VY 2007 NRC Scenario 3 Rev b Page 11 of 20

-~

~

N/O COMMENTS 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 CRO CRS OPERATOR ACTIONS EVENT NUMBER 5 insert then withdraw 36-27 one notch (done twice).

Crew Brief.

Crew Task

Description:

Stuck Control Rod 26-27 (ON)

STEP POS.

CRO CRS CRO CAN D I DATE ACT ION S/BE H AVlO R Determines control rod 26-27 is stuck and notifies CRS Enters ON 31 43 - Stuck Control Rod and directs actions contained on ON 3143 flow chart.

Takes actions as directed to unstick control rod per ON 31 43 flowchart e

e e

e e

e e

e e

e attempt one notch insert attempt a single notch withdraw determines drive water pressure raises drive water pressure 10-50 psig attempt to insert control rod one notch (successful) attempt to withdraw one notch (successful) insert 26-27 one notch withdraw 26-27 one notch return drive water press. to 250-275 insert then withdraw 26-27 one notch (done twice)

S COMMENTS 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 STEP POS.

CANDIDATE ACTIONS/BEHAVIOR S

CREW CRS CRS Recognize and inform the CRS of indication of a seismic event Enter and direct crew actions IAW OP 3127 Direct CRO/BOP to dispatch A0 to check for damage to structures or equipment IAW OP 31 27 When directed, dispatch AOs to check for damage to structures or equipment IAW OP 31 27 Direct CROlBOP to verify the seismic event by checking indications on the seismic monitor monitor report valid indication of a seismic event Direct CRO to check control rod display for rod drift When directed, check control rod display. Report no drifts Recognize and gross fail alarms and Y2 scram alarms due to low level Direct A 0 to check local level indications Report other level indications are normal Direct STA to check the seismic monitor to determine if OBE was exceeded Report loss of A TBCCW Declares ALERT for seismic event CRO/BOP CRS CRO/BOP When directed, check seismic CRS CRO Crew CRS CREW CREW

~

~

~~~

CREW A-5-C.

OPERATOR ACTIONS EVENT NUMBER 6 U

N/O COMMENTS Crew Task

Description:

Seismic Event; Trip of A T B X W Pump with B TBCCW Pump Failing to Auto Start

2)
  • = Critical TasWStep

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

POS.

STEP BOP CANDIDATE ACTIONS/BEHAVIOR Starts B TBCCW pump manually.

EVALUATORS NOTE:

CRO must be distracted to ensure ACRO gets credit for this S

U N/O COMMENTS malfunction.

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

F CREW CRS NOTES:

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

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 CRS 0 P ERATO R ACTIONS EVENT NUMBER 7 May Enter ON 31 58 RX BLDG High Area Tempwater Level DirectsNerifies Isolating RClC when it fails to auto isolate.

Tech Specs 3.5.G.2. - 14 day LCO Crew Task D scription:

RClC Steam Leak (TS); RClC Fails to Auto Isolate BOP STEP Refers to Alarm Response Procedure for 9-44-2.

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

(Successful)

POS.

I CANDIDATE ACTIONS/BEHAVIOR I S CREW I Responds to Annunciator 9-4-U-2 RCIC Steam Line DP High N/O

=

COMMENTS 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 CREW 0 P ERATO R ACTIONS EVENT NUMBER 8,9, & 10 Recognizes SDV Drain valves CRD

-33A & 338 fail to isolate on scram.

Crew Task

Description:

Seismic Aftershock; Group 1 Isolation; Auto Scram Failure; Manual Scram Required; PClS Group 111 Failure STEP POS.

CRO CREW

  • CREW EOP-2 CCT-1 CRO CRS CRO CANDIDATE ACTIONS/BEHAVIOR Spurious Group 1 Isolation due to seismic event and the reactor should have scrammed Recognize auto scram failure With the reactor at power and a full auto scram signal, manually scram the reactor 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 Insert manual scram.

Enter and direct actions per OT 31 00 and EOP-1 Verify applicable Table A automatic actions When steam flow < 0.5 Mlbm/hr per steamline, place mode switch in SHUTDOWN Verify all rods inserted; inform CRS Insert IRMs and SRMs U

COMMENTS NOTES:

1)

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

2)
  • = Critical TasWStep

POS.

N/O CRO COMMENTS CRS CRS CREW BOP CRO NOTES:

CANDlDATEACTIONS/BEHAVIOR I S 1 U Attempts to Isolate SDV valves (unsuccessful)

Reports to CRS failure to isolate.

Enters OP 31 27 Natural Phenomena due to alarm 7-M Seismic Monitor Alarm from aftershock.

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.

Maintains pressure/level as directed Controls Pressure 800-1000 psig Control RPV water level 127-1 77 with feedwater t

VY 2007 NRC Scenario 3 Rev b Page 17 of 20

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 lsTEP NOTES:

OPERATOR ACTIONS EVENT NUMBER 11 Crew Task

Description:

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

CRS I Direct an A 0 to investigate.

CRS CRS CREW When A 0 reports RHR suction line break, enter and direct actions per ON 31 08, Loss of Containment Integrity Emergency Procedure and ON 3158, Hi Rx Building Temperature or Water Level.

Direct maintenance to attempt to restore primary containment integrity.

Respond to reactor building sump level alarm.

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

Verify all available sump pumps are CRS I 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).

Initiates torus makeup, as directed.

When torus level cannot be maintained above 7 ft, perform RPV emergency depressurization.

Standard:

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

BOP

  • CREW CCT-2 COMMENTS
1)

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

2)
  • = Critical TasWStep

STEP I POS.

-~

CANDIDATE ACTIONS/BEHAVIOR EVALUATOR'S NO S

U N/O COMMENTS t

VY 2007 NRC Scenario 3 Rev b Page 19 of 20

__ ~ _ _ _

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 31 25 and determine an SAE EAL has been reached IAW 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

Evaluators:

VY 2007 NRC Scenario 4 Rev b Page 3 of 20 SIMULATOR EVALUATION GUIDE Senior Management Observer Scenario Temp late:

Template

Title:

Critical Task Performance:

Lead Evaluator:

Date Administered:

A ctivify Code:

Crew:

SM CRS CRO BOP STA TITLE SAT UNSAT (Circle One)

Signatu re Prepared by:

Reviewed by:

Approved by:

Date:

Date:

Date:

Appendix D NUREG 1021 Revision 9

\\

S U

0 PER AT0 R ACTIONS EVENT NUMBER 1 N/O Crew Task

Description:

Speed Load Changer Bypass Test OP 4160 CANDIDATE ACTIONS/BEHAVIOR Direct Speed Load Changer Bypass Reviews OP-4160, Section F -

Speed Load Changer Bypass Test.

IAW OP-4160

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.

VY 2007 NRC Scenario 4 Rev b Page 8 of 20 COMMENTS 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 STEP OPERATOR ACTIONS EVENT NUMBER 2 POS.

CANDIDATE ACTIONS/BEHAVIOR S

U N/O COMMENTS CRS Directs Power increase IAW OP-01 05 Crew Task

Description:

Power Ascension IAW OP-0105 CRO CRO/ACRO increases power using recirc flow control or control rods 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 STEP OPERATOR ACTIONS EVENT NUMBER 3 POS.

CANDIDATE ACTIONS/BEHAVIOR S

U N/O COMMENTS CREW Recognize and respond to a loss of MCC.

Directs Field operator to investigate Crew Task

Description:

LOSS Of MCC-8A (TS)

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

Recognize Group Ill isolation.

Reviews OP 21 43 - MCC-8A Load List when informed feeder bkr tripped Directs electrical maintenance to investigate loss of MCC-8A.

Receives report that MCC-8A can be returned to service I alarm.

CRO Resets Half scram by:

Resets YZ scram BOP NOTES:

1)

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

Backs up and resets Group Ill isolation per OP2115 Section L.

2)
  • = Critical TasWStep

VY 2007 NRC Scenario 4 Rev b Page 11 of 20 CRS 11 STEP I POS.

I CANDlDATEACTIONS/BEHAVIOR I S I U I N/O I COMMENTS II 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 CREW 0 P ERATO R ACTIONS EVENT NUMBER 4 Recognize and inform CRS of the trip of the A condensate pump.

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 0

Verify Reactor Vessel Level Master Controller setpoint sets down to 155 inches CRO CRS CRO Recognize and report B FW Pump has tripped as a result of the condensate pump trip 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 Master Controller setpoint sets down to 155 inches 0

Verify Reactor Vessel Level 0

Manually runback recirc pumps using the PB1 pushbuttons on both pump controllers 2-1 84-1 6A( B)

Immediate Operator Action OT3113 NOTES:

1)

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

2)
  • = Critical TasWStep

STEP POS.

CRS CRO CRS CRO/BOP CRS CANDIDATE ACTIONS/BEHAVIOR 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 Reduces power as directed.

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

~~

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

Brief the crew on plant conditions VY 2007 NRC Scenario 4 Rev b Page 13 of 20 U I N/O I COMMENTS 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 S

U OPERATOR ACTIONS EVENT NUMBER 5 N/O COMMENTS Crew Task

Description:

Steam Flow Summer Fails Upscale (OT) (1 00% over 60 sec)

STEP POS.

CREW CAN D I DAT E ACT ION S/BEH AVlO R Recognizes steam flow summer fails upscale EVALUATORS NOTE:

See attached copy of OT 3114 for specific actions.

CRS CRS CRO CRO NOTES:

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

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

Automatic Control Place Master Controller in 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 Contact I&C Crew Brief

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 STEP 0 P ERATO R ACTIONS EVENT NUMBER 6 POS.

CANDIDATE ACTIONS/BEHAVIOR S

U N/O COMMENTS CREW Recognize and respond to Rising Drywell Pressure.

Crew Task

Description:

Recirc Leak (OT) (TS)

CRS CRO BOP 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 Reduces core flow as directed in OT3111 Closes AC N2 M/U Starts all available Drywell RRUs Reviews TS and determines an LCO is required for 3.6.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 16 of 20 CRS CREW OPERATOR ACTIONS EVENT NUMBER 7 & 8 Enter and direct actions IAW Verify Automatic Actions per When directed, verify Automatic Actions per Table A OT 31 00/ EOP-1:

Table A.

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 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 0131 00 Restart Drywell RRUs per EOP-3 I

)ly. Did not find event for recirc leak.

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 CREW CRS BOP STEP Recognize Drywell pressure is still increasing; inform CRS Enter and direct actions IAW OT 31 11 (High Drywell Pressure)

When directed, start all available drywell RRUs.

Start all available drywell RRUs.

POS.

CRS CRO

  • CREW EOP-3 CCT-1 BOP CANDlDATEACTIONS/BEHAVIOR I S I U 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 127-1 77 inches 0

Maintain RPV pressure between 800-1 000 psig using BPVs 0

Insert IRMs and SRMs 0

Insert IRMs and SRMs Restorehnaintain RPV level 127 to 177 inches When PClS Group 3 fails to isolate valves AC-6 an AC-6B with a leak present, initiate PClS Group manually Standard:

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

N/O I COMMENTS EVALUATORS NOTE:

BOP may close valves and then inform CRS.

I CRS I Direct isolation of AC-6 and AC-6B I Complete isolation of AC-6 and I

I AC-6B s/in itiat ions BOP When directed, maintain pressure 800 - 1000 psig using Bypass valves 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 CRS

  • CREW EOP-3 CT-2 Direct spraying the torus IAW EOP-3 BEFORE torus pressure reaches

' 10 psig

~

When torus pressure exceeds 10 psig, initiate drywell spray while in the safe region of the drywell 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 0

Initiate Drywell spray Recirc pumps.

Direct Drywell Spray using RHR I

When directed, spray the Drywell I

I using RHR SM/ STA /

Recognize Drywell pressure lowering; inform CRS Classify event as a Alert IAW AP 0125 Appendix A (A-3-a or A-3-b).

I EVALUATOR'S NOTE:

15 minute clock, N/O -

COMMENTS 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
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