ML082210558

Calvert Cliffs Final - Section C Operating Exam (Folder 3)

ML082210558
Person / Time
Site:	Calvert Cliffs
Issue date:	06/05/2008
From:	Constellation Energy Group
To:	Silk D M Operations Branch I
Shared Package
ML073040307	List: IR 05000317/2008301 ML080500246 ML081570277 ML081690586 ML081690602 ML081690630 ML081690652 ML081690697 ML081690719 ML082210499 ML082210511 ML082210541 ML082210551 ML082210558 ML082480504 ML082590046 ML082590056 ML082590058 ML082590064 ML082590076 ML082590080 ML082590082 ML082590084 ML082590093 ML082590101 ML082590478 ML082620009 ML082810364 ML090490608
References
TAC U01633
Download: ML082210558 (89)

Text

Page 1 of 21 Appendix D Scenario Outline Form ES-D-1 Event Malf. No. Event Type* Event Scenario No.: 1 Facility:

Calvert Cliffs 1 81 2 Scenario No.: 1 Op-Test No.: 2008 Examiners: Operators:

Turnover:

Unit 1 was MOC at 100% for previous 6 months 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago power was reduced to 75% power to perform valve testing which was completed SAT. 11 & 12 charging pumps are running with boron equalization in progress. CVCS makeup is aligned for direct. No equipment out of service. Instructions for the shift are to return to 100% power at approximately 30% per hour.

R I I N (CRO/SRO)

I Raise reactor power from 75% to 100%

Target Quantitative Attributes [Per Scenario:

See Section D.5.d) Actual Attributes

__ __ _- 1. Total malfunctions (5-8) 2. Malfunctions after EOP entrv (1-2) /I 7 If 3 3. Abnormal events (2-4)

4. Major transients (1-2)

5. EOPs enteredlrequiring substantive actions (1-2) 11 5 11 2 I1 1 6. 7. Critical tasks (2-3) EOP contingencies requiring substantive actions (0-2) I/ 1 II 3 Op-Test No.: 2008 Scenario No.: 1 Page 3 of 21 SCENARIO OVERVIEW LOSS 22 DC BUS / ATWS Initial Conditions:

75% Rated Thermal Power, MOC, following valve testing last shift. Crew will begin raising power to 100% power at approximately 30%

per hour following shift turnover.

CVCS system is currently in direct lineup. Pressurizer boron equalization in progress.

The scenario starts with a trip of 11 Component Cooling pump, after the crew verifies no common mode failure 12 Component Cooling pump is started IAW AOP-7C. This will resume CC flow to all components.

LCO 3.7.5 should be entered due to both 12 & 13 CC pps's aligned to 14 480V bus. After switching the power supply for 13 CC pp the LCO can be exited. CVCS Backpressure Transmitter 1-PT-201 fails low which causes backpressure regulator valves to go shut resulting in a loss of letdown. Crew will secure charging and letdown IAW OI-2A prior to exceeding 225" in PZR. A loss of 22 125V DC bus occurs which will cause multiple alarms. The crew will implement AOP-7J for loss of the DC bus. The crew will de-energize ESFAS Channel ZG, AFAS Channel ZG, and RPS Channel D.

11B RCP will trip due to a locked rotor, this will cause numerous alarms. The crew should check RPS calling for a trip due to multiple alarms.

Once crew identifies that reactor should have tripped CRS will order a reactor trip.

The manual pushbuttons will not work causing the crew to perform alternate actions of de-energizing the CEDM MG sets. When the reactor trips one set of turbine valves will fail to go shut causing an overcooling of the RCS. Failure of SGIS to shut MSIV's will require the CRO to manually shut them.

The crew should recognize the SGIS failure and hold Tcold constant at current temperature using ADV's. SIAS B fails to actuate forcing RO to manually initiate SIAS. After completing EOP-0 the CRS will implement EOP-8 due to the loss of 22 DC bus. VA-1 will not be met in EOP-8 and CRO should immediately begin working that safety function causing the RO to assess the rest of the safety functions. After all safety functions are assessed the RO should be assigned PIC4 due to Pressure and Inventory Control not being met in EOP-0. The scenario ends when VA-1 is completed by CRO and he is assigned HR-2.

Page 4 of 21 1. 2. 3. 4. 5. 6. - 7. INSTRUCTOR SCENARIO INFORMATION Reset to IC- 18 Perform switch check. Place simulator in CONTINUE, advance charts and clear alarm display. Place simulator in FREEZE. Enter Trigger

a. None Enter Malfunctions a. Trip 11 CC Pump. CCWOO2-01 on F1 b. CVCS Backpressure transmitter failure CVCSOO5 on F2 C. Loss of 22 125V DC Bus 125VOO1-04 on F3 d. 11B RCP Locked Rotor RCSOOS-02 on F4 d. Auto Trip Failure

& Manual Trip Failure RPSOO5 & RPSOOG at Time Zero e. Stop Valve #1 & Control Valve

1. 1 Fail As-Is TGOO5-01 on F5 f. SIAS B failure ESFASOO1-02 at Time Zero g. SGIS A & B failure ESFAS012 at Time Zero Enter Panel Overrides

a. None Page 5 of 21 8. Enter Remote Functions

/ Administrative - a. Align CVCS makeup for direct.

(1-CVC-254 open, 1-CVC-256 shut, VCT Outlet 1-CVC-501-CV open with pink off normal magnet) - b. Place all PZR Heaters to on and adjust PIC-100 X & Y to equalize boron 2200 psia to 9. Set simulator time to real time, then place simulator in CONTINUE.

10. Give crew briefing.

a. Present plant conditions:

75% load at MOC 10,500 MWDMTU b. Power history: 100% for 9 months, 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago reduced to 75% for valve testing. Currently on step 6.1.5 of OP-3. C. Equipment out of service: None d. Abnormal conditions: CVCS system is aligned for direct makeup and PZR boron equalization in progress with 2 charging pumps Raise power to 100% at approximately 30% per hour. e. Surveillances due:

None f. Instructions for shift:

1 1. Allow crew 3-5 minutes to acclimate themselves with their positions.

12. Instructions for the Booth Operator.

a. Trip of 11 CC Pump when cued by the lead evaluator.

b. Activate F2 CVCS Backpressure Transmitter (1-PT-201) fails low Activate Fl c. d. Activate F3 Loss of 22 DC Bus when cued by lead evaluator.

Use Panel Override for alarm E-56 11B RCP Vibration 20 sec before F4 & F5 e. Activate F4 & F5 when cued by lead evaluator after CRO ordered to de-energize RPS channel D but prior to performance (differences in procedure for de-energizing RPS between the simulator and plant). 11B RCP Locked Rotor (& Turbine valve fail as is)

Op-Test No.: 2008 Scenario No.: 1 Page 6 of 21 RESPONSES TO CREW REQUEST If a request and response is not listed, delay response until reviewed with the examiner.

If one request is dependent upon completion of another, then subsequent actions should not be responded to until the appropriate time delay has been observed. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.

1. 2. 3 4 5 6 1. 2. 3. REQUEST OWC/E&C investigate failure of 11 CC Pump TBO investigate loss of 11 CC Pump AB0 investigate loss of 11 CC Pump TBO shift 13 CC pp to 11 480V Bus OWC/E&C Investigate loss of 22 DC Bus OWC de-energize ESFAS ZG & AFAS ZG RESPONSE Acknowledge request. After 5 minutes report breaker tripped on overload.

Acknowledge request. After 3 minutes report breaker tripped on overload Acknowledge request. After 3 minutes report nothing abnormal at pump Acknowledge request, after 1 minute use the system lineup file to perform, report complete when system lineup complete Acknowledge request Acknowledge request Critical Tasks Evaluate common mode failure and start standby CC pump prior to reaching RCP temperature limits (thrust bearing 195", CBO 200"). Performs alternate actions for tripping reactor within 5 minutes of RCP trip. Recognize Turbine SV/CV still open, shuts MSIV's prior to AFAS actuation.

Appendix D Required Operator Actions Page 7 of 21 Form ES-D-2 Op-Test No.: 2008 Scenario No.: 1 Event No.: 1 Event

Description:

Raise Power from 75% to 100% (Evaluator's Cue) Time Position CRS CRS RO CRO RO Applicant's Actions or Behavior Direct RO

& CRO to commence raising power IAW previously performed brief Contact Plant Chemistry to sample RCS for boron Using 01-2B Section 6.2 add 1000 gallons of DI directly to RCS Determine volume to be added using Reactivity Plaque Get peer check of volume calculated Adjust makeup flow to approximately 20 gpm on 1-FIC-210X at 1C07 Set FQIS-210X on 1C07 to volume determined earlier Open 1-CVC-504 on 1C07 to align DI to charging pump suction Place FIC-210X on 1C07 to Auto Place M/u Mode Selector 1-HS-210 to Dilute on 1C07 Adjust Turbine Load using Load Set to control Tcold on program . Adjust ramp rate to

=: 0.5% per minute on Mk VI screen on 1C02 Adjust Load Ref Cmd to value greater than current load on MK VI screen on 1C02 to raise turbine load and reduce Tcold.

Adjust Load Limit Setpoint to approximately 10% greater than current load on Mark VI screen on 1C02 Withdraw CEA's to raise power . . Select Manual Sequential on CEDS panel on 1C05 Place In-Hold-Out switch to Out to withdraw CEA's Constantly monitor nuclear power indications on 1C05 during CEA withdrawal Appendix D Required Operator Actions Page 8 of 21 Form ES-D-2 Op-Test No.: 2008 Scenario No.: 1 Event No.: 2 Event

Description:

11 CCW Pump Trip (Evaluator's Cue)

Time Position CRO/RO CRS CRO CRS RO Applicant's Actions or Behavior Announce multiple alarms per management expectations CRS directs CRO to check RPS callinn for a trip Check RPS calling for a trip . Checks RPS for active trips (any 2 sets of red lights on same Trip Unit means trip condition)

Checks RPS power supplies (2 RPS channels w/o power indicates trip condition)

Checks RPS Matrix Relays (any combination of right side lights out with left side lights out (6 groups of 4 lights) 9 Report RPS not calling for a trip CRS directs RO to monitor primary Monitor the primary . Check Reactor Power . Check RCS temperatures Check RCS pressure . Check PZR level Report primary is stable CRO/RO CRO CRS CRSKRO Page 9 of 21 Acknowledge alarms. 1C06 E-45 SPDS Alarm 9 1C06 E-49 11A RCP AUX STATUS PANEL . 1C06 E-53 11B RCP AUX STATUS PANEL . 1C06 E-57 12A RCP AUX STATUS PANEL . 1C06 E-61 12B RCP AUX STATUS PANEL . 1C07 X-02, X-10, X-17, X-25 CCW FLOW LO . 1C13 K-09 CC PP(S) DISCH PRESS LO . 1C19 R-04 U-l48OV ESF UNTRLP . Plant Computer Alarm "1 1 CC Pump Stop" Observes 11 CC pump is tripped. . . Green indicating light for 11 CC pp 1-HS-3813

@ 1C13 Zero amps indicated for 11 CC pp @ 1C13 Informs CRS of 11 CC pp trip, requests to place 1-HS-3813 in PTL. Implement AOP-7C "Loss of Component Cooling Water" Make plant page announcement per management expectations Evaluate for common mode failure . . Checks CC Head Tank level @ 1C13 steady (verify no system rupture) Checks alarm R-04 "U-1 480V ESF UNTRIP" @ 1C19 indicating an electrical fault Start a standby CC pump prior to reaching RCP temperature limits (thrust bearing 195', CBO 200') = 12 CC pp should be started with 1-HS-3815 CRSRO CRS CRSKRO CRO CRS CRS Page 10 of ?1 Monitors RCP temperatures including trip criteria . Thrust bearing temp <195" at 1C06 o 1-TIA-158, 1-TIA-159 for 1A RCP o 1-TIA-168, 1-TIA-169 for 1B RCP o 1-TIA-178, 1-TIA-179 for 2A RCP o l-TIA-188,1-TIA-189 for 12B RCP . Controlled Bleedoff temp c200" using plant computer Refers to Tech Specs.

3.7.5 Component

Cooling System

3.6.6 Containment

Spray and Cooling system Declares 11 CC subsystem inoperable due to 12 & 13 CC pp's not having independent power supplies. Direct realignment of 13 CC pump to 11 480V Bus. . Place 13 CC pump 1-HS-3817 in PTL Call TBO to shift disconnects IAW AOP-7C Attachment 1 Place 13 CC pp handswitch 1-HS-3817 in Auto after TBO reports aligned to 11 480V Bus Declares 11 CC subsystem operable, exits Tech Specs. . 3.7.5 Component Cooling System . 3.6.6 Containment Spray and Cooling system Informs maintenance of need to investigate and repair.

• Shading indicates Critical Task Appendix D Required Operator Actions Page 11 of 21 Form ES-D-2 Op-Test No.: 2008 Scenario No.: 1 Event No.: 3 Event

Description:

CVCS Backpressure Transmitter Fails Low (Evaluator's Cue)

Time Position RO RO CRS RO CRS CRS Amlicant's Actions or Behavior Acknowledge and announce alarm F9 "LETDOWN PRESSURE" Recognize L/D backpressure valves shut on 1C07 and process variable on backpressure controller 1-PIC-201 is zero psig on IC07 and report to CRS Direct RO to secure Charging and Letdown IAW 01-2A Using 01-2A Section 6.4 Reducing charging and letdown and Section 6.6 Secure charging and letdown 1. 2. 3. 4. 5. 6. 7. 8. 9. Notify Radiation Safety and Chemistry that charging and letdown are being secured Place 13 charging pump WS in PTL on IC07 Place Backup Charging Pump Selector to 12&13 position on 1C07 Stop 12 charging pump on IC07 Place 13 charging pump WS in normal on 1C07 Contact AB0 and direct Zinc Addition Skid S/D Shift L/D Throttle Valve Controller 1-HIC-110 to Manual on 1C07 Place 11 Charging Pump in PTL on 1C07 Shut Letdown Containment Isolations 1-CVC-5 15

& 1-CVC-516 on 1 C07 . If PZR level exceeds 225 inches enter TS 3.4.9.A and verify PZR level lowering to < 225 inches.

Direct OWC to contact I&C to investigate and repair 1-PT-201 .

Appendix D Required Operator Actions Page 12 of 21 Form ES-D-2 Position CRO/RO CRS CRO CRS Op-Test No.: 2008 Scenario No.: 1 Event No.: 4 Event

Description:

Loss of 22 DC Bus (Evaluator's Cue)

RO RO/CRO CRO Applicant's Actions or Behavior Announce multiple alarms per management expectations CRS directs CRO to check RPS calling for a trip Check RPS calling for a trip Checks RPS for active trips (any 2 sets of red lights on same Trip Unit means trip condition)

Checks RPS power supplies (2 RPS channels w/o power indicates trip condition)

Checks RPS Matrix Relays (any combination of right side lights out with left side lights out (6 groups of 4 lights) . Report RPS not calling for a trip CRS directs RO to monitor primary

~~ Monitor the primary . Check Reactor Power . Check RCS temperatures . Check RCS pressure . Check PZR level Report primary is stable Acknowledge alarms (too many to list all) Investigate bus loss . RPS Channel D de-energized . . Containment Press Transmitter Isolation handswitch 1-HS-53 13D

@ 22 125VDC Bus indicates 0 VDC @ 1C24 1 C 10 de-energized Report loss of 22 125VDC bus CRS CRS CRO CRS Page 13 of Implements AOP-7J "Loss of 125 Volt DC Power" Make plant page announcement per management expectations Directs PWS to de-energize ESFAS

& MAS channels ZG IAW 01-34 & 01-32B Directs CRO to de-energize RPS Channel D De-energize RPS Channel D . When CRO directed to de-energize RPS D initiate next malfunction Determines applicable TS LCO's & TRM actions. 3.8.4 DC Sources - Operating (Most Limiting) . 3.8.7 Inverters - Operating . 3.8.9 Distribution System - Operating . 3.3.1 RPS Instrumentation - Operating . 3.3.3 RPS Logic & Trip Initiation . 3.3.4 ESFAS Instrumentation . 3.3.9 CVCS Isolation Signal . 3.3.10 Post Accident Monitoring Instrumentation 3.3.11 Remote shutdown Instrumentation . 3.3.12 WR Neutron Flux Monitoring . 15.3.1 Radiation Monitoring Instrumentation NOTE - May not perform this step due to timing of scenario malfunctions, student may be asked about Tech Specs after scenario.

Appendix D Required Operator Actions Page 14 of 21 Form ES-D-2 Op-Test No.: 2008 Scenario No.: 1 Event No.: 5 Event

Description:

Locked rotor on 11 B RCP and Reactor Trip EOP-0 (Evaluator's Cue)

Time Position RO/CRO CRO/RO CRS RO CRS CRO Applicant's Actions or Behavior Announce E-56 11B RCP Vibration alarm Announce multiple alarms per management expectations CRS directs RO to monitor primary Monitor the primary . Check Reactor Power . Check RCS temperatures Check RCS pressure Check PZR level Report primary is poJ stable CRS directs CRO to check RPS calling for a trip Check RPS calling for a trip . Checks RPS for active trips (any 2 sets of red lights on same Trip Unit means trip condition)

Checks RPS power supplies (2 RF'S channels w/o power indicates trip condition)

Checks RPS Matrix Relays (any combination of right side lights out with left side lights out (6 groups of 4 lights) . Report RPS calling for a trip Page 15 of 21 RO CRS RO RO Recognize 11B RCP has a locked rotor .

• 1C06 E-56 11B RCP Vibration alarm . 1C06 E43 Selected Computer Point IC05 D-8 Hi Power Trip Reset Demand . 1C05 D-35 CEA Withdrawal Prohibit . 1C05 D-40 Tavg-Tref . 11B RCP ammeter pegged high After 2 minutes w/o action 11B RCP Green Light Indication After 2 minutes w/o action 11B RCP indicates zero amps Directs Reactor trip, implements EOP-0 Attempts Reactor trip @ 1C05 unsuccessfully . Depress both Reactor Trip Pushbuttons on 1C05 Verify all CEA's inserted Verify DI water makeup is secured Reports Reactivity Control is met Ensure Turbine Trip *- Recognize Turbine SV- 1KV- 1 still open At IC02 check valve positions at any turbine control screen Shuts MSIV's prior to AFAS actuation . At 1C03 using 1-HS4043 & I-HS-4048 Reports Turbine is tripped All CRS/CRO CRO RO Page 16 01 Recognize SGIS failure (may not get SGIS if MSIV's shut promptly)

S/G pressure < 685 psia (at 1C03 or plant computer)

Tcold < 510°F (at 1C06 red LED digital or plant computer) SIAS actuation due to overcooling (SGIS &SIAS occur at approx same time on overcooling)

Open ADV's using HIC on 1C03 to hold RCS temp constant

(=: 40-50% output) (this step may not be done until CRO performs Heat Removal Safety Function) Performs Vital Aux Safety Function . Check 11 & 14 4KV buses energized (1C18

& 1C19) Checks 125V Buses

@ 1C24 (22 DC bus de-energized) Checks 120V Vital Buses energized Checks 1Y09

& lYl0 energized Checks Component Cooling flow to RCP's Contact AB0 to check Switchgear Ventilation in service Reports Vital Auxiliaries not met Performs Pressure

& Inventory Control Safety Function Check RCS pressure and perform alternate actions o o Verify SIAS Operate PZR Heaters & Spray Checks HPSI pumps

& HPSI Header valves Recognize SIAS B failure and manually actuate SIAS using pushbutton on lCl0 Secures 11B

& 12A RCP's on 1C06 Check PZR Level Check RCS subcooling Report Pressure and Inventory Safety Function not met (may be reported met if temperature not held due to SGIS failure) Verifies SIAS as part of PIC safety function

'1 CRO ~ CRO or RO CRO or RO Page 17 of Performs RCS Heat Removal Safety Function Check S/G pressure & Tcold and perform alternate actions o o Recognize S/G Pressure fell below 685 psia and SGIS failed Open ADV's to =: 40-50% to stabilize Tcold Recognizes loss of MFW and initiates AFW o Start an AFW pump by performing either: Open 1-MS-4070-CV

& 1-MS4071-CV at 1C04 to start 11 AFW pump Place 13 AFW pump handswitch to start on IC04 . o o o Trip the SGFP's by depressing trip pushbuttons on 1C03 Shut the S/G FW Isolations using handswitches on 1C03 Operate AFW System to restore S/G levels to between (-)170 and (+I30 inches (AFW flow control setpoint between 150 gpm and 300 gpm on 1C04) . Ch ck at least 1 RCP operating in a loop with available S/G If RCP's are operating check Thot - Tcold c 10°F Reports Heat Removal safety Function not met due to low S/G pressure & low Tcold (may be called met if temperature not held due to SGIS failure) Perform Containment Environment Safety Function . . . Check containment pressure < 0.7 psig at lCl0 Check containment temperature

< 120°F Check containment radiation monitor alarms clear Reports Containment Environment is met Perform Rad Levels External to Containment Safety Function . Check RMS alarms are clear Reports Rad Levels External to Containment Safety Function is met CRS CRS Page 18 of?l Perform EOP-0 brief Ensure all are attentive Review Safety Functions not met o Vital Auxiliaries o o Pressure & Inventory (if temp held) RCS Heat Removal (if temp held) Review Safety system Actuations o o SGIS failure SIAS (include SIAS B failure) Solicit Input Conclude the brief Refer to EOP-0 flowchart Vital Auxiliaries not met with 22 DC bus de-energized consider EOP-8 Pressure and Inventory not met due with S/G pressure e800 psia consider Heat Removal not met with S/G press e 800 psia consider EOP-4 EOP-4 Implements EOP-8 due to loss of 22 DC bus

• Shading indicates Critical Task Page 19 of 21 Appendix D Required Operator Actions Form ES-DQ Position ALL RO CRO CRS Applicant's Actions or Behavior Evaluate Resource Assessment Table Report RC-1 Met All CEA's inserted with negative SUR Report PIC-4 Met . SIAS has actuated o o 3 charging pumps running with RCS pressure >1270 psia 11 & 13 HPSI pumps & 11 & 12 LPSI pumps running with 0 gpm injection due to RCS pressure >I270 psia Core covered using RVLMS indication (3 1C05 o Report VA-1 Not Met 500 KV buses available o o o 11 & 14 4KV buses energized 11,12,21 DC buses energized and 22 DC bus de-energized 1YO9 & 1Y 10 energized Commence working VA-1 immediately after reporting status to CRS Directs RO complete Resource Assessment Table Page 20 of 21 RO CRS Report HR-2 Met At least 1 S/G > -350 inches using PAMS display on 1C04 S/G level being restored with AFW flow CET temperature

< 50°F superheat using CET indication on IC05 and steam table with RCS pressure indication on 1C06 o o o Feedwater available SIAS has actuated o o 3 charging pumps running with RCS pressure >1270 psia 11 & 13 HPSI pumps

& 11 & 12 LPSI pumps running with 0 gpm injection due to RCS pressure >1270 psia Core covered using RVLMS indication

@ 1C05 o Report CE-1 Met Containment pressure

< 2.8 psig from lCl0 o Containment temperature

< 220°F CIS not actuated Containment radiation alarms clear with no unexplained rise Report RLEC- 1 Met Normal Radiation levels outside containment o Noble Gas Monitor alarm clear with no unexplained rise fromlC22 Condenser off-gas RMS alarm clear with no unexplained rise from 1C22 S/G B/D RMS alarm clear with no unexplained rise from 1C22 Main Vent RMS alarm clear with no unexplained rise from 1 c22 o o o Containment pressure

< 2.8 psig Direct RO to commence PIC-4 (RC-1 if PIC reported met in EOP-0)

CRO CRS CRS Page 21 of Perform VA-1 ' Determines block step A is N/A (offsite power available)

Determines steps B . l -5 are N/A Verifies 22 DC bus and 14 120VAC Vital bus de-energized and implements AOP-7J o Verify actions of AOP-7J complete from earlier implementation Determines steps B.8-10 are N/A Determines block step C is N/A Report all steps for VA- 1 evaluated, no actions can be taken until E&C returns 22 DC bus to service Direct CRO to commence working HR-2 (may direct PIC if HR called met during EOP-0) Secure scenario after CRO directed to work HR-2 Determines EAL H.A.

1. I. 1 1 Page 1 of 21 Appendix D Scenario Outline Form ES-D-1 r Facility:

Calvert Cliffs 1 & 2 Scenario No.: 2 Op-Test No.: 2008 Examiners: Operators: Turnover: Unit 1 is at 100% power at EOC. 12 AFW pump tagged out for repair of overspeed trip device linkage (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> into 18 hour2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> maintenance window).

Malf. No. AFWoo1-02 RCS026-01 CEDS012-37 CEDS003 Downpower RCS002 CEDSOlO RCSOO2 Panel Override SIAS "B" Block Event Type* (RO) C (ALL) R (RO) C (RO/SRO) R (RO) N (CRO/SRO)

M (ALL) c (RO) M (ALL) C (CRO) 1 2 3 4 5 6 7 8 Event Description 12 AFW Pump Failure PZR Level X Transmitter Failure (high) CEA 37 Drop CEDS Raise Relay sticks when CEA withdrawn Downpower due to expiration of CEA alignment time RCS Leak of 100 GPM Mechanical Binding of 2 CEA's (51 & 62) RCS Leak increases to 200 GPM SIAS B Block Failure iC)omponent, (M)ajor Page 2 of 21 Target Quantitative Attributes (Per Scenario; See Section D.5.d) 1. Total malfunctions (5-8) Actual Attributes

-_ -_ __ I1 7 2. 3. Abnormal events (241 Malfunctions after EOP entry (1-2) I1 3 I1 4 11 6. EOP contingencies requiring substantive actions (0-2) I I 1 4. Major transients (1-2) 5. EOPs enteredreauirina substantive actions fl-2) 7. Critical tasks (2-3) 2 ~ I1 2 I1 1 Page 3 of 21 Op-Test No.: 2008 Scenario No.: 2 SCENARIO OVERVIEW DROPPED CEALRCS LEAK Initial Conditions:

100% Rated Thermal Power, EOC, 12 AFW pump 00s for repair of overspeed trip device linkage (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> into 18 hour2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> maintenance window). Scenario starts with Pressurizer level transmitter X instrument failing high. After identification of instrument failure channel Y level controller will be placed in service and PZR heater cutout selected to Y only (vice WY). Common tap analysis should be consulted and other instruments checked to ensure no instrument line leak. Letdown will isolate due to transient and will be placed back in service IAW 01-2A. CEA 37 in Group 5 will drop completely causing multiple alarms. CRS will implement AOP- lB, with CRO lowering turbine load to restore Tcold to program. CRS will also notify OWC of CEA drop to ensure E&C response.

When crew attempts to realign the CEA the outward motion relay will stick causing the CEA to continue withdrawing even after irdholdout switch is released. CEDS will be placed in off stopping CEA motion. When crew realizes they cannot realign the CEA a power reduction to 70% power should be ordered. During the power reduction IAW OP-3 an RCS leak will begin in excess of 1 charging pump. AOP-2A will be implemented which will eventually lead to a reactor trip. When reactor trips 2 CEA's will fail to insert forcing RO to borate RCS for Reactivity Control. After the trip the leak will increase in size to 200 gpm. EOP-5 will be entered after completing EOP-0. The crew will begin a cooldown and depressurization to minimize leakage, during this step the crew will be unable to block SIAS B from 1ClO but can block locally at ESFAS Panel. The scenario ends when the crew has throttled safety injection flow to prevent overfilling the pressurizer.

CRS will declare EAL H.A.5.1.2. INSTRUCTOR SCENARIO INFORMATION

1. Reset to IC-14

2. Perform switch check. 3. Place simulator in CONTINUE, advance charts and clear alarm display.

4. Place simulator in FREEZE. 5. Enter Trigger

a. T1: CEDS In/Hold/Out switch moved

6. Enter Malfunctions Page 4 of 21 - a. PZRLevel X Transmitter Fails High. RCS026-01 (Low) on Fl b. CEA37Drop CEDSO12-37 on F2 - c. CEDS Raise Relay sticks when CEA withdrawn CEDSOO3 on T1 - d. RCS leak of 100 gpm RCS002 10-100 gpm with 10 minute ramp on F3 - e. 12 AFW Pump Failure AFWOO1-02 at Time Zero - f. CEA Mechanical Binding on 2 CEA's (51 & 62) CEDS010-51&

CEDS010-62 at Time Zero 7. Enter Panel Overrides - a. SIAS B Block Failure SIAS B Block keyswitch to normal at Time Zero - 8. Enter Remote Functions

/ Administrative

a. Place yellow tag on 12 AFW Pump trip pushbutton. - 9. Set simulator time to real time, then place simulator in CONTINUE. - 10. Give crew briefing.

a. Present plant conditions: 100% load at EOC 19,100 MWDMTU b. C. Equipment out of service: d. Abnormal conditions:

None e. Surveillances due:

None f. Instructions for shift:

Maintain 100% power Power history: 100% for 12 months 12 AFW Pump 00s (repairing overspeed trip linkage 6 hrs into 18 hr window) - 11. Allow crew 3-5 minutes to acclimate themselves with their positions. - 12. Instructions for the Booth Operator.

a. Activate F1 PZR Level X transmitter fails high when cued by the lead evaluator.

b. Activate F2 CEA 37 drop when cued by lead evaluator.

c. Remove CEDSO12-37 After E&C reports fuse replaced.

Page 5 of 21 d. Use panel override to depress CMI Bypass button after RO pushes (keeps CMIbypassed)

Activate F3 100 gpm RCS leak when cued by lead evaluator during expeditious power reduction at = 75%. Modify RCS002 Raise RCS leak rate to 200 gpm when reactor trips.

e. f. *5 Block SIAS B minute after requested of PWS. Use remote function for ESFAS and block SIAS B, 1 Page 6 of 21 Op-Test No.: 2008 Scenario No.: 2 RESPONSES TO CREW REQUEST If a request and response is not listed, delay response until reviewed with the examiner.

If one request is dependent upon completion of another, then subsequent actions should not be responded to until the appropriate time delay has been observed. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.

1. 2. 3 4 5 6 REQUEST TBO check 1C43 PZR level indication OWC contact I&C to investigate PZR Level transmitter failure OWC contact EM shop to determine cause of misaligned CEA NFM for Fxyt & Frt Chemistry sample both YG's for activity IAW CP-436 PWS block SIAS B locally at ESFAS cabinet RESPONSE Acknowledge request. After 2 minutes report 216 inches. Acknowledge request. After 5 minutes report blown 2 amp fuse where 5 amp fuse belonged. Request to replace fuse.

After 1 minute report fuse replaced and CEA ready for re-alignment (recorder hooked up and ready). Report Fxyt is 1.023 and Frt 1.58,2 days ago Acknowledge request Critical Tasks Acknowledge request, After 1 minute block SIAS B using panel override for block WS 1. 2. Commence cooldown of RCS prior to subcooling lowering below 30" Borate RCS due to 2 stuck CEA's in EOP-0 Page 7 of 21 Appendix D Required Operator Actions Form ES-D-2 Position RO RO/CRO RO Op-Test No.: 2008 Scenario No.: 2 Event No.: 1 Event

Description:

PZR Level X Transmitter Failure / Loss of Letdown (Evaluator Cue)

RO CRS CRO CRS CRO CRS CRS CRS Applicant's Actions or Behavior Announces and acknowledges 1C06 alarms. Compares Pressurizer Level indicators o o o 1-LI-11OX-1

& 1LI-11OY-1 Digital LED Indicators on 1C06 1 -LR- 1 10 PZR Level Recorder on 1 C06 1-LI103 PZR Compensated Level Indicator on 1C06 Determines 1-LT-1 10X failed high. Informs CRS of failed instrument Refers to 1C06 Alarm Manual for Alarm E-06 Shift Pressurizer Level Control Channels . Shifts PZR LVL CH SEL 1-HS-110 to Channel "Y" Shift PZR HTR LO LVL CUT-OFF SEL 1-HS-100-3 to "Y" (If channels not switched within 45 sec then L/D will isolate) Identifies L/D isolated.

Refers to NO-1-200 Common Tap Analysis Monitor containment parameters to check for common tap RCS leak Directs CRO to confirm other transmitters not affected Verifies LT-1 1OX is only affected transmitter Directs OWC to contact maintenance for repair Determines Tech Spec Actions 3.3.10.A Post Accident Monitoring Instrumentation Directs RO to secure charging and letdown IAW 01-2A prior to PZR Level exceeding 225 inches Page 8 of 21 RO CRS RO ~~ ~~~ Secure Charging and Letdown Notify CRS that Initial Condition for letdown operating not met Place CVCS IX BYPASS 1-CVC-520 to Bypass on 1C07 Shift L/D THROTTLE VLV CONTROLLER 1-HIC-110 to Manual on 1 C07 Place 11 Charging Pump H/S in PTL on 1C07 8 Shut Letdown Containment Isolations o o L/D Stop 1-CVC-515 on 1C07 L/D CONTMT ISOL 1-CVC-516 on 1C07 Direct RO to restore Charging and Letdown IAW 01-2A Restore Charging and Letdown 8 Place L/D PRESSURE CONTROLLER 1-PIC-201 in Manual with 20% output on IC07 Place LETDOWN HX TEMP CONTR 1-TIC-223 in Manual with automatic setpoint at 1 10°F on 1C07 Place L/D THROTTLE VLV CONTROLLER 1-HIC-110 in Manual with 20% output on 1C07 Start 11 Charging Pump using 1-HS-224X on 1C07 Open L/D CNTMT ISOL's o o L/D STOP 1-CVC-515 on 1C07 L/D CONTMT ISOL 1-CVC-516 on 1C07 Adjust L/D PRESS CONTROLLER 1-PIC-201 to maintain WD pressure 460 psig (440-480 psig) on 1C07 Shift L/D PRESS CONTROLLER 1-PIC-201 to Auto with 460 psig setpoint on 1C07 Adjust L/D THROTTLE 1-HIC-110 to stabilize PZR level (=: 38 gpm) on 1C07 Match L/D THROTTLE VLV CONTROLLER 1-HIC-110 Auto & Manual flow signals using the Bias control on 1C07 Shift L/D THROTTLE CONTROLLER 1-HIC-110 to Auto on 1C07 Shift LETDOWN HX TEMP CONTR 1-TIC-223 to Auto on 1C07 When L/D HX temperature stabilizes place CVCS IX in service using 1-CVC-520 on IC07 Page 9 of 21 Appendix D Required Operator Actions Form ES-D-2 Position CRO/RO ~~ CRS CRO CRS RO RO CRS CRS Applicant's Actions or Behavior Announce multiple alarms per management expectations CRS directs CRO to check RPS calling for a trip Ir Op-Test No.: 2008 Scenario No.: 2 Event No.: 2 Event

Description:

Group 5 CEA 37 Dropped (Evaluator Cue)

~~ ~~ Check RPS calling for a trip . Checks RPS for active trips (any 2 sets of red lights on same Trip Unit means trip condition)

Checks RPS power supplies (2 RPS channels w/o power indicates trip condition)

Checks RPS Matrix Relays (any combination of right side lights out with left side lights out (6 groups of 4 lights) . . Report RPS not calling for a trip CRS directs RO to monitor primary Monitor the primary . Check Reactor Power Check RCS temperatures Check RCS pressure Check PZR level Report primary stable

~~ Identifies CEA-37 dropped Implements AOP-1B Directs CRO to lower turbine load to restore Tcold to program CRO CRS CRS CRS RO RO CRS CRS CRS CRS Page 10 of 21 ~ ~ ~ ~ Lowers turbine load to restore Tcold . Compare Reactor Power (AT Power Digital Indication

@ 1C05) with plaque on panel 1C02 to determine program Tcold Operate Turbine Load Set Handswitch 1-CS-80 in Lower Direction to raise Tcold to match program Tcold Direct OWC to request E&C shop to determine cause of misalignment Direct RO to realign CEA-37 . Borate as necessary to maintain Reactor Power o Open 1-CVC-514 on 1C06 o Start 11 or 12 BA Pump for = 3-5 seconds 4 4 . Select Group 5 on CEDS panel on 1C05 Select CEA-37 on CEDS panel on 1C05 Select Manual Individual Mode on CEDS Panel on 1C05 Depress Group 5 Inhibit Bypass Pushbutton Depress and hold the CMI Bypass pushbutton for 5 seconds before and after CEA motion on 1C05 Place In-Hold-Out Switch to Out for 5.25 inches, then release.

Recognize CEA continuing to withdraw, notifies CRS . . . Direct RO to place CEDS to off Places CEDS to off prior to high power pretrip alarm. Informs CRS that CEA motion stops Refers to TS 3.1.4 Control Element Assembly Alignment Enters LCO 3.1.4.B One CEA misaligned by >15" Determine CEA Alignment time . . Contacts NFM for current Frt value Using COLR Figure 3.1.4 and given Frt value determines realignment time of 30 minutes Determine CEA cannot be realigned within 30 minutes. Directs expeditious power reduction to 70%

Page 11 of 21 Appendix D Required Operator Actions Form ES-D-2 Position CRS CRS CRS/CRO CRS/CRO RO RO CRO Amlicant's Actions or Behavior Directs expeditious power reduction to 70% Announces "Expeditious Power Reduction to 70 %" on plant page Notifies Chemistry of power reduction

> 15% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Notifies ESO of power reduction Equalize Boron . 9 Energize all PZR Backup Htrs on IC06 Lower PIC-1OOX & Y to ~2200 psia on 1C06 to maintain pressure

= 2250 psia due to additional heaters being energized Borate from RWT IAW OP-3 . . . Open RWT CHG PP SUCT 1-CVC-504-MOV on 1C06 Shut VCT OUTLET VLV 1-CVC-501-MOV on 1C06 When 2 minutes have elapsed (1 minute if 2"d charging pump started) Open VCT OUTLET VLV 1-CVC-501-MOV . Shut RWT CHG PP SUCT 1-CVC-504-MOV When 5 minutes have elapsed begin boration again and repeat as necessary to lower power to 70% Lowers turbine load to maintain Tcold on program . Compare Reactor Power (AT Power Digital Indication

@ 1C05) with plaque on panel 1C02 to determine program Tcold Operate Turbine Load Set Handswitch 1-CS-80 in Lower Direction to raise Tcold to match program Tcold Adjust Load Limit Setpoint to approximately 10% greater than current load on Mark VI screen on 1C02 .

Page 12 of 21 RO CRS RO CRO Periodically compare all indications of power . PWR RANGE Meters on 1C05 (higher of NI or AT for each channel) Calorimetric Power from plant computer (point PA91 1) . . NI Power at IC15 . AT Power at 1C15 When Power lowered to 70%, direct RO & CRO to level power Shift charging pump suction from RWT to VCT by: . Open 1-CVC-501-MOV VCT Outlet on 1C07 Shut 1-CVC-504-MOV RWT Charging Pump Suction on 1C07 Make final adjustments to turbine load using Turbine Load Set Handswitch 1- CS-80 in Lower Direction to match Tcold to program Tcold Page 13 of 21 Op-Test No.: 2008 Scenario Event

Description:

RCS Leak / L [Time Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008 Scenario No.: 2 Event No.: 3 Event

Description:

RCS Leak / AOP-SA (After Power Lowered L [Time Position CRO CRO CRS RO CRO CRS ' No.: 2 Event No.: 3 AOP-SA (After Power Lowered to 75%) Applicant's Actions or Behavior Announce and acknowledge containment normal sump alarm J-21 on lClO Reference lClO Alarm Manual . Drain Containment Sump IAW 01- 17D Miscellaneous Waste System o Open Containment Sump Normal drain 1 -EAD-5462-MOV using 1-HS5462 on lClO Open Containment Sump Normal drain 1-EAD-5463-MOV using 1-HS5463 on lClO When both valves indicate open for at least 5 seconds then shut both valves and note time containment sump alarm cleared. (this time can be used for determining leak rate) o o Direct RO to monitor primary Monitor the primary . Check Reactor Power Check RCS temperatures . Check RCS pressure . Check PZR level Recognize lowering PZR level lowering with constant Tcold, also mismatch between charging and letdown flows Announce and acknowledge containment normal sump alarm J-21 on lClO . Estimate RCS leak rate (49 gallon sump

/ minutes between alarms

= approximate leak rate)

Implement AOP-2A . Notify Radiation Safety that rad levels in Aux Bldg may be changing due to excessive RCS leakage Direct Chemistry to sample both S/G's for activity per CP-436 Proceeds to Section VI of AOP-2A "RCS Leakage Exceeds One Charging Pump Capacity" . .

CRS RO CRO Page 14 of 21 Directs RO to monitor for trip criteria . PZR Pressure reaches Th4LP pretrip setpoint o o alarm E-14 "TmP CH PRETR1P"on 1C05 White Pretrip Lights on TM/LP Trip Units (TN-7) on RPS 1C15 Control PZR Level . Secure L/D o o Shut I-CVC-515 using 1-HS-2515 on 1C07 Shut 1-CVC-516 using 1-HS-2516 on 1C07 Check for S/G tube leak . Observe for rise in any of the following:

o S/G sample activities o o Condenser Off-Gas radiation levels on 1 -RI- 1752 on 1C22 S/G Blowdown radiation levels on 1-RIC-4095 or 1-RI-4014 on 1c22 Main Steam radiation levels onl-RIC-5421 or 1-RIC5422 on 1c22 Main Steam N-16 radiation levels on 1-RIC-5421A or 1-RIC- 5422A on 2C26 o o o Unexplained S/G water levels o Feed flow mismatch Page 15 of 21 RO CRS Attempt to isolate the leak . . Verify no PORV leakage Verify Letdown isolated (1-CVC-515

& 516 shut) on IC07 o o Quench Tank Parameters on 1C06 PORV discharge piping temps using plant computer points TY 107 & T108 Acoustic Monitor indications on IC06 o . Verify RCS Sample Isolation 1-PS-5464-CV is shut on 1ClO Verify Reactor

& PZR Vent Valves shut o 1-RC-103-SV on 1C06 o 1-RC-104-SV on 1C06 o 1-RC-105-SV on 1C06 o 1-RC-106-SV on 1C06 Determine if leak is on Charging Header Stop all but one charging pump Check charging header pressure

> RCS pressure Determine leak is not on the charging header Restart charging pump previously secured o o o o . Verify RCS leak is occurring in the containment o Verify containment pressure, temperature and humidity are rising on 1ClO Start ALL available Containment Air Coolers in high speed and open Emergency Cooling Outlet Valves on lC10 o . Determine no leakage in Component Cooling System o o Check for rising trends on CC Head Tank on 1C13 Check for rising trend on CC Radiation Monitor Determine appropriate actions for RCS Leakage . Determines leak not isolated . Directs Rx trip . Implements EOP-0 Page 16 of 21 Appendix D Required Operator Actions Form ES-D-2 Position CRS RO Applicant's Actions or Behavior Directs EOP-0 Performs Reactivity Control Depress Manual Reactor Trip Pushbutton on 1C05 Check Reactor tripped using NI power indications on 1C05 Verifies more than 1 CEA failed to insert (CEA's 5 1 & 62) Op-Test No.: 2008 Scenario No.: 2 Event No.: 4 Event

Description:

EOP-0 (After Reactor Trip) Verify DI Water Makeup is secured o o o Check 11 & 12 RC makeup Pumps secured on 1C07 Check VCT M/U 1-CVC-512-CV is shut on IC07 If aligned for direct makeup to RCS then shut RWT Charging Pump Suction 1-CVC-504-MOV on IC07 Reports Reactivity Control Complete Page 17 of 21 CRO CRO Performs Turbine Trip Check Reactor tripped then:

o o o o Depress both Turbine Trip Pushbuttons on IC102 Check Main Turbine stop Valves shut on MK VI screen Check Turbine Speed drops on MK VI screen Checks Turbine Generator Output Breakers open

= 11 GEN BUS BKR 0-CS-552-22 on IC01 11 GEN TIE BKR 0-CS-552-23 on lCOl o o o Check Generator Field Breaker open on lCOl Check Generator Exciter Field breaker open on lCOl Check MSR 2nd Stage Steam source Valves are shut 1-MS-4025-MOV on 1C02 1-MS-4026-MOV on 1C02 Reports Turbine Trip Complete Performs Vital Aux Check 11 or 14 4KV bus energized.

Check ALL 125V DC BUS VOLTS greater than 105 volts on 1C24: 11 12 21 22 Check at least THREE 120V AC Vital Buses are energized on 1C24: 11 12 13 14 Check EITHER 1Y09 OR 1Y 10 energized on 1C24. Verifies Component Cooling Flow to the RCP's by checking CC Pump operating at 1C13 and Containment Supply and Return CV's open on 1c10. Reports Vital Auxiliaries Complete RO CRO CRO Page 18 of 21 Performs Press

& Inventory including verifying alt actions Checks pressurizer pressure at 1C06 and determines that it is lowering and not trending to 2250 PSIA. Verifies main spray CV's indicate shut on 1C06 Determines PORV's not leaking by checking Pressurizer RV Flow Monitor approximately zero volts on 1C06 Checks pressurizer level at 1C06 and determines that it is lowering and not trending to 160 inches. Verifies CVCS letdown isolations CVCJ 15 and 5 16 shut and all charging pumps operating on IC06 Checks subcooling is greater than 30°F by PAMs display on 1C05 Reports Press

& Inventory not met due to FTR level & pressure trends Performs Core & RCS Heat Removal Verifies TBV's controlling S/G pressure 850-920 PSIA on IC03 and Tcold 525535°F on 1C05 Checks S/G level (-)170" to (+) 50" on 1C03 Verifies MFW operating by checking SGFP RPM and HP and LP steam stops open on 1C03. Checks positive DP on FRV PDI on 1C03. 0 0 Checks RCP operating red lights illuminated on 1C06 Verifies Thot minus Tcold is less than 10°F by checking indicators on 1C06 Reports Core and RCS Heat Removal complete Perform Containment Environment including verifying alt actions Checks Containment Pressure

< 0.7 psig using narrow range pressure on lCl0 Verifies Containment Temperature e 120°F using cavity and dome temperature indicators on 1C10. Verifies Containment Gaseous RMS at 1C22 not in alarm with no abnormal rising trend 0 Reports Containment Environment not met due to negative trends in temperature and pressure (may call met based on trends)

CRO CRS CRS Page 19 of 21 Perform Rad Levels External to Containment Check the following RMS alarms are clear with no unexplained rise:

U-1 Wide Range Noble Gas Monitor U-1 Condensor Off Gas @ 1C22 U-1 S/G Blowdown @ 1C22 U-1 Main Vent Gaseous

@ 1C22 Reports Rad Levels External to Containment complete Perform EOP-0 brief Ensure all are attentive Review Safety Functions not met o o Pressure & Inventory due to PZR level trends Containment Environment due to temperature and pressure trends (may be called met) Review Safety system Actuations o None Solicit Input Conclude the brief Refer to EOP-0 flowchart Pressure and Inventory not met with

> 800 psia S/G pressure and no tube leakage indications, consider EOP-5 Containment Environment not met with normal S/G response, consider EOP-5 (may be called met) Implements EOP-5 due to RCS Leakage

• Shading indicates Critical Task Page 20 of 21 Appendix D Required Operator Actions Form ES-DQ Position CRS CRO CRO CRO CRO CRS/CRO RO RO CRO CRO Amlicant's Actions or Behavior Obtains EOP-5 placekeeper and performs EOP entry brief. Open Main

& Aux HPSI Hdr Valves on 1C07 and 1C08 Start 11 & 13 HPSI pumps on 1C07 and IC08 Attempt to Block SIAS on lCl0 when SIAS block permitted alarm annunciates Recognize failure of SIAS B to Block Contact PWS to locally block SIAS B at ESFAS cabinet Perform RCP Trip Strategy 0 Trips 11A and 12B OR 11B and 12A RCP's if RCS pressure lowers to 1725 PSIA as a result of the event Commence RCS Boration 0 0 0 Check Shut VCT M/U 1-CVC-512-CV at 1C07 Open BA direct M/U 1-CVC-514-MOV at 1C07 Open BAST Gravity Feed MOV's 1-CVC-508 and 509 MOV's at IC07 Verify M/U Mode HS-210 in manual at 1C07 Start both BA Pumps at 1C07 Shut VCT OUT Valve 1-CVC-501-MOV at 1C07 Verify all charging pumps operating Commence Cooldown prior to subcooling 40" 0 Places TBV controller at IC03 in manual and adjusts output to control RCS cooldown 400°F in any one hour period. Blocks SGIS A and B at 1C03 when SGIS Block Permitted alarms recieved RO CRO CRS Page 21 of 21 Depressurize RCS to maintain subcooling 0 0 De-energize Pressurizer Heaters at 1C06 Use Main Spray if all RCP's are running Use Aux Spray if any RCP is secured Operate Pressurizer Spray to maintain subcooling as low as possible between 30 and 140°F based on CET temperatures AND above the RCP NPSH limits of Att. 1 Throttle HPSI Flow 0 0 Verifies > 30°F subcooling based on CET's from PAM's display at 1C05 Verifies Pressurizer level >lo1 inches at 1C06 Verifies S/G level > (-) 170" capable of being steamed and supplied feedwater Verifies RVLMS indicates level above hot leg on PAM's display at 1C05 Stops HPSI Pump and/or throttles HPSI MOV's to control Pressurizer level 101 to 180 inches and RCS subcooling 30-140°F based on CET's 0 Secure Scenario after HPSI Flow is throttled Determines EAL H.A.5.1.2

• Shading indicates a Critical Task Page 1 of 25 Appendix D Scenario Outline Form ES-D-1 RCSO11-03 RPSOO7-02 RCS02 1 RCS013-03 N/A N/A ESFA009 CDOOl MS002 01 Op-Test No.: 2008 Scenario No.: 3 Facility:

Calvert Cliffs 1 & 2 Scenario No.: 3 Op-Test No.: 2008 ______________

I (SRO) c (RO) C (RO) K (KO)(SRO)

N(CR0)SRO c (RO) M (CRO) C (CRO) M (All) Examiners: Operators:

1. Total malfunctions (5-8) 2. Malfunctions after EOP entw (1-21 Turnover:

Unit 1 is at 100% power, MOL equilibrium conditions.

13 HPSI pump tagged out for repair of excessive vibration during last STP 0-7B (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> into 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> maintenance window) IAS LCO 3.5.2.A.

11 8 I1 2 Event Malf.

No. Event Event

3. Abnormal events (2-4) 4. Maior transients 11-21 5 I1 6 I1 2 6 5. 6. 7. Critical tasks (2-31 EOPs enteredlrequiring substantive actions (1-2) EOP contingencies requiring substantive actions (0-2) 7 8 ~ ~ ~~~~ 11 1 I1 0 11 2 Q N)ormal, (R)eactivity, (1)nstrur 12A RCP 1 Stage Seal Failure Channel B RPS Matrix Power Supply Failure (TS CRS) PORV 402 leak 12A RCP 3fd Stage Seal Failure Perform Expeditious Reactor Shutdown due to 2 failed seals on 12 RCP VCT Outlet MOV fails (1-CVC-501-MOV) Spurious CIS B Actuation Loss of Vacuum 11 S/G Tube Leak (2 Tubes) II Target Quantitative Attributes (Per Scenario: See Section D.5.d) I Actual Attributes I -- I -- I -- 11 Op-Test No.: 2008 Scenario No.: 3 Page 2 of 25 SCENARIO OVERVIEW RCP SEALS/TUBE LEAK Initial Conditions:

repair of excessive vibration during last STP 0-7B (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> into 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> maintenance window) [AS LCO 3.5.2.A. 100% Rated Thermal Power, MOL, Equilibrium conditions.

13 HPSI pump tagged out for Scenario starts with 12A RCP 1" stage seal failure.

The crew ensures only a single seal failed and notifies engineering.

Channel B RPS matrix power supply will fail causing multiple alarms at 1C05. After ensuring RPS is not calling for a trip the crew should enter LCO's 3.3.3.A & 3.3.3.B. The CRS should call OWC to get I&C working on repairs to the power supply problem.

After determining all LCO's calls for RF'S, PORV 402 will start leaking requiring its block valve to be shut and Tech Specs addressed. While CRS looking at Tech Specs for PORV leakage 12A RCP 31d stage seal will start to fail over 5 minute period. This second seal failure will require an expeditious shutdown IAW Alarm Manual. During the shutdown VCT Outlet valve will fail to shut forcing RO to reduce power using BAST'S instead of RWT which is preferred method of OP-3. During the shutdown a CIS B spurious actuation occurs, which causes a loss of component cooling water to the RCP's. The crew will be unable to reset the CIS B and a reactor trip will be ordered. After verifying Reactivity Control in EOP-0 the RCP's should be secured. During EOP-0 a vacuum leak in the condenser develops causing a loss of Main Feedwater and TBV's. After completing EOP-0 a transition to EOP-2 should occur. After a few steps are completed in EOP-2 a tube leak develops in 12 S/G causing the crew to transition to EOP-6. The scenario will end when the 12 S/G is isolated IAW EOP-6. CRS will declare EAL H.A.5.1.2

1. 2. 3. 4. 5. 6. - Page 3 of 25 INSTRUCTOR SCENARIO INFORMATION Reset to IC-24 Perform switch check. Place simulator in CONTINUE, advance charts and clear alarm display. Place simulator in FREEZE. Enter Trigger

a. Enter Malfunctions CEA #1 on bottom of core a. b. C. d. e. f. g. h. 12A RCP Lower Seal Failure RCSOl1~03,0-100% over a 2 minute ramp on Fl Channel B RPS Matrix Power Supply Failure RPS007-02 on F2 PORV 402 leakage RCS021 at 0-30% over 1 minute ramp on F3 12A RCP 3rd Stage Seal Failure RCS013-03,0-100%

over 5 minute ramp on F4 Spurious CIS B Actuation ESFA009-02 on F5 11 S/G Tube Leak (2 Tubes) MS002-01 at F6 Loss of Condenser Vacuum CDOOl 0-100% over 5 minute ramp on TI 13 **PSI Pump failure SIOO2-03 at Time zero Enter Panel Overrides

a. VCT Outlet Valve Handswitch 1-HS-2501 to open (ensure actual H/S in Auto) b. VCT Outlet Valve Handswitch 1-HS-2501 auto white light on Page 4 of 25 8. Enter Remote Functions

/ Administrative

a. Place yellow tag on 13 HPSI Pump WS in PTL. b. Place red dot on H-20 "13 HPSI PP BKR L/U IMPR' Set simulator time to real time, then place simulator in CONTINUE. - 9. 10. Give crew briefing.

a. Present plant conditions:

100% load at MOL 10,885 MWDMTU b. Power history: 100% for 9 months C. Equipment out of service: 13 HPSI Pump 00s (repairing excessive vibration during STP-0-7,3 hrs into 36 hr window) d. Abnormal conditions:

None e. Surveillances due:

None f. Instructions for shift:

Maintain 100% power Allow crew 3-5 minutes to acclimate themselves with their positions.

Instructions for the Booth Operator.

11. 12. a. Activate Fl b. Activate F2 C. Activate F3 d. Activate F4 e. Activate F5 f. Activate F6 12A RCP Lower Seal Failure when cued by the lead evaluator. Channel B RPS Matrix Power Supply Failure when cued by lead evaluator.

PORV 402 Leakage when cued by lead evaluator.

12A RCP 3rd Stage Seal Failure when cued by lead evaluator.

Spurious CIS B Actuation when cued by lead shortly after crew commences expeditious shutdown.

11 S/G Tube Leak (2 Tubes) when cued by lead Page 5 of 25 Op-Test No.: 2008 Scenario No.: 3 RESPONSES TO CREW REQUEST If a request and response is not listed, delay response until reviewed with the examiner.

If one request is dependent upon completion of another, then subsequent actions should not be responded to until the appropriate time delay has been observed. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.

1. 2. 3 4 5. 6. 7. 8. 1. 2 REQUEST OWC contact Engineering about 12 A RCP lower seal failure OWC contact I&C to investigate loss of RPS matrix power supply OWC contact Engineering about PORV 402 Leakage OWC contact Engineering about 12 A RCP upper seal failure ABORPO check 1-CVC-501 PWS attempt reset of CIS B locally at ESFAS cabinet TBO check condenser for vacuum leak Chemistry sample both S/G's for activity RESPONSE Acknowledge request . Acknowledge request. Acknowledge request Acknowledge request Acknowledge request, after 5 minutes report "Valve appears open with nothing unusual" Acknowledge request, After 2 minute give ESFAS door alarm then clear alarm after another 2 minutes. Call CR and report "unable to reset CIS B locally" Acknowledge request Acknowledge request, after 15 minutes report activity in 11 S/G Critical Tasks Secures all RCP's within 3 minutes of reaching RCP temperature limits. Isolate 11 S/G prior to S/G filling solid and MSSV's opening.

Page 6 of 25 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008 Scenario No.: 3 Event No.: 1 Event

Description:

12A RCP 15' Stage Failure (Evaluator's Cue)

Time Position RO RO CRO CRS CRS Applicant's Actions or Behavior Announce and acknowledges alarm E-59 "12A RCP Seal" on 1C06 Evaluates 12A RCP, determines lower seal failure Evaluate Alarm Manual Checks Controlled Bleed-Off flow and determines normal (vapor seal not failed) Verifies only 1 failed seal and notifies CRS of need to contact Engineering Directs RO to monitor other RCP seals Notifies Engineering of seal failure Page 7 of 25 Appendix D Required Operator Actions Form ES-D-2 Position CRORO CRS CRO Op-Test No.: 2008 Scenario No Event

Description:

Channel B RPS L CRS RO All CRO CRS .: - 3 Event No.: 2 Matrix Power Supply Failure Op-Test No.: 2008 Scenario No.: 3 Event No.: 2 Event

Description:

Channel B RPS Matrix Power Supply Failure L (Evaluator's Cue) Applicant's Actions or Behavior Announce multiple alarms per management expectations (may only announce alarms D- 1 & D-3 and not announce multiple alarms)

CRS directs CRO to check RPS calling for a trip (may not direct this if not announce as multiple alarms)

Check RPS calling for a trip Checks RPS for active trips (any 2 sets of red lights on same Trip Unit means trip condition)

Checks RPS power supplies (2 RPS channels wlo power indicates trip condition)

Checks RPS Matrix Relays (any combination of right side lights out with left side lights out (6 groups of 4 lights) Report RPS not calling for a trip CRS directs RO to monitor primary Monitor the primary Check Reactor Power Check RCS temperatures Check RCS pressure Check PZR level Report primary is stable CRS directs RO

& CRO to evaluate alarms D-1 CEA TCB ll/TCB 15 TRIP D-3 CEA TCB 12/TCB 16 TRIP ~ Report loss of Matrix Power Supply Direct OWC to Contact I&C about RPS Matrix power supply failure CRS Page 8 of 25 Evaluate Tech Specs. Reactor Protective System Logic and Trip Initiation . Enter LCO Action Statement 3.3.3.A

& 3.3.3.B Page 9 of 25 Appendix D Required Operator Actions Form ES-D-2 ~~ Op-Test No.: 2008 Scenario No.: 3 Event No.: 3 Event

Description:

PORV 402 Leakage (Evaluator's Cue)

Time Position RO CRO CRS Applicant's Actions or Behavior Announce and acknowledge alarm E-1 "QUENCH TANK TEMPPRESSLEVEL,"

and E-22 "PORV/SAFETY VLV ACOUSTIC MON' Review Alarm Manual for alarm E-22 Verify no high RCS pressure condition exists Place PORV 402 Override handswitch 1-HS-1402 in "OVERIDE TO CLOSE' at 1C06 (may not be performed) SHUT PORV Block valve 1-RC-403 at 1C07 Monitor PORV tailpiece temperatures using plant computer points T106, T107, and T108 Inform CRS to refer to Tech Specs 3.4.11 & 3.4.12 Refer to Tech Specs Enter Tech spec Action Statement 3.4.1 l.A o Ensure block valve shut with power maintained Page 10 of 25 Appendix D Required Operator Actions Form ES-D-2 11 Op-Test No.: 2008 Scenario No.: 3 Event No.: 4, 5, 6 Event

Description:

12A RCP 3rd Stage Failure, Expeditious power reduction , VCT Outlet Valve failure (Evaluator's Cue)

Position RO RO CRO I Amlicant's Actions or Behavior Announce and acknowledge computer alarm 12A Controlled Bleedoff Flow High Temp and later reflash of alarm E-59 "12A RCP Seal" on IC06 Evaluates 12A RCP, determines a upper seal failure Evaluate Alarm Manual Checks Controlled Bleed-Off flow and determines normal (vapor seal not failed) Verifies 2 failed seals and notifies CRS of need for expeditious shutdown and need to secure 12 A RCP when reactor is shutdown . Recognize need for expeditious shutdown to protect against RCS leak from RCP seals ~~ Directs an expeditious shutdown Notifies Chemistry of power reduction

> 15% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Notifies ESO of power reduction Equalize Boron Energize all PZR Backup Htrs on IC06 Lower PIC-1OOX & Y to =: 2200 psia on 1C06 to maintain pressure =: 2250 psia due to additional heaters being energized RO CRO RO CRS Page 11 of 25 Borate from RWT TAW OP-3 . . Open RWT CHG PP SUCT 1-CVC-504-MOV on 1C06 Attempts to Shut VCT OUTLET VLV 1-CVC-501-MOV on 1C06 Report failure of 1-CVC-501 to shut to CRS Recommend performing power reduction using fast borations IAW OI- 2B Section 6.12 (=: 10 second fast borations every 3-5 minutes)

Open BA Direct Makeup 1-CVC-514-MOV on 1C07 Start 11 or 12 Boric Acid Pump on 1C07 for time agreed upon previously Shut BA Direct Makeup 1-CVC-514-MOV on 1C07 . a eneat -v Lowers turbine load to maintain Tcold on program Compare Reactor Power (AT Power Digital Indication

@ 1C05) with plaque on panel 1C02 to determine program Tcold Operate Turbine Load Set Handswitch 1-CS-80 in Lower Direction to raise Tcold to match program Tcold Adjust Load Limit Setpoint to approximately 10% greater than current load on Mark VI screen on 1C02 . Periodically compare all indications of power Notifies Engineering of 2nd seal failure Page 12 of 25 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008 Scenario No.: Event

Description:

Spurious CIS B L 3 Event No.: 7 - (Evaluator's Cue) Applicant's Actions or Behavior Position Announce and acknowledge alarm G-6 "ACTUATION SYS CIS TRIP" alarm on 1C08 RO/CRO ~ ~_____~ Direct RO to monitor primary Monitor the primary Check Reactor Power Check RCS temperatures Check RCS pressure Check PZR level Report primary is stable CRS RO Monitor RCP temperatures for trip criteria Controlled Bleed-Off Temperature

>200"F RO Bearing Temperatures

> 195°F ~~ Determines CIS alarm is not valid Checks containment parameters normal o o Containment narrow range pressure at

= 0 psig Containment temperature and humidity not changed since shift turnover.

CRO CRO CRS RO CRS Page 13 of 25 Attempt to reset CIS IAW EOP Attachment 4 Match WS's with an asterisk o o o o Shut CC CNTMT SUPPLY 1-CC-3832-CV on lClO Shut CC CNTMT RETURN 1-CC-3833-CV on lClO Verify Shut IA CNTMT ISOL 1-IA-2080-MOV on lClO Verify 1-IA-2080-MOV OVERIDE 1-HS-2080A to normal on lClO Depress CIS RESET Channel A on 1C09 and CIS RESET Channel B on lClO Recognize CIS not reset and inform CRS . Contact PWS and request reset of CIS locally at ESFAS Panel in Cable Spreading Room Recognize trip criteria being met (may order trip prior to exceeding trip criteria)

Controlled Bleed-Off temperature exceeding 200°F Directs Reactor Trip Page 14 of 25 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008 Scenario No.: 3 Event No.: 8, Event

Description:

EOP-0 and Loss of Vacuum (After Reactor Trip)

Time Position CRS RO Applicant's Actions or Behavior Directs EOP-0 Performs Reactivity Control . . . . Depress Manual Reactor Trip Pushbutton on 1C05 Check Reactor tripped using NI power indications on IC05 Verifies no more than 1 CEA failed to insert Verify DI Water Makeup is secured o o o Check 11 & 12 RC makeup Pumps secured on 1C07 Check VCT M/U 1-CVC-512-CV is shut on IC07 If aligned for direct makeup to RCS then shut RWT Charging Pump Suction 1-CVC-504-MOV on 1C07 Reports Reactivity Control Complete Secures 11B RCP within 3 minutes of reaching RCP limits (thrust bearing 195"' CBO 200") and trips all other RCP's prior to exceeding RCP limits for 3 minutes.

CRO CRO Page 15 of 25 Performs Turbine Trip Check Reactor tripped then:

o o o o Depress both Turbine Trip Pushbuttons on 1C02 Check Main Turbine stop Valves shut on MK VI screen Check Turbine Speed drops on MK VI screen Checks Turbine Generator Output Breakers open 11 GEN BUS BKR 0-CS-552-22 on lCOl 11 GEN TIE BKR 0-CS-552-23 on lCOl o o o Check Generator Field Breaker open on lCOl Check Generator Exciter Field breaker open on lCOl Check MSR 2nd Stage Steam source Valves are shut 1-MS-4025-MOV on 1C02 1-MS-4026-MOV on 1C02 Reports Turbine Trip Complete Performs Vital Aux Check 11 or 14 4KV bus energized.

Check ALL 125V DC BUS VOLTS greater than 105 volts on 1C24: 11 12 21 22 Check at least THREE 120V AC Vital Buses are energized on 1C24:

11 12 13 14 Check EITHER 1Y09 OR lYl0 energized on 1C24. Verifies no Component Cooling Flow to the RCP's by checking CC Pump operating at 1C 13 and Containment Supply Valve open and Containment Return Valve shut on 1C10. Verifies all 4 RCP's secured by checking green indicating lights and zero amps at lC06. Reports Vital Auxiliaries Complete RO CRO CRO Page 16 of 25 Performs Press

& Inventory including verifying alt actions 0 Checks pressurizer pressure at 1C06 and between 1850 and 2300 psia and trending to 2250 psia. Checks pressurizer level at 1C06 and between 80 and 180 inches and trending to 160 inches. Checks subcooling is greater than 30°F by Pam's display on 1C05 0 Reports Press

& Inventory is complete Performs Core

& RCS Heat Removal Operate ADV's in manual

(-40-50% output) to control S/G pressure 850 to 920 psia and Tcold between 525 and 535°F (TBV's inoperative due to vacuum leak) Checks S/G level (-)170" to (+) 50" on 1C03 Recognizes MFW secured due to loss of vacuum and initiates AFW 0 o Start an AFW pump by performing either: Open 1-MS-4070-CV

& 1-MS4071-CV at 1CO4 to start 11 AFW pump Place 13 AFW pump handswitch to start on 1C04 o o o Trip the SGFP's by depressing trip pushbuttons on 1C03 Shut the S/G FW Isolations using handswitches on 1C03 Operate AFW System to restore S/G levels to between (-)170 and (+)30 inches (AFW flow control setpoint between 150 gpm and 300 gpm on 1C04) 0 Checks RCP not operating green lights illuminated on 1C06 Reports Core and RCS Heat Removal cannot be met due to no operating RCP's Perform Containment Environment including verifying alt actions Checks Containment Pressure

< 0.7 psig using narrow range pressure on lC10 Verifies Containment Temperature

< 120°F using cavity and dome temperature indicators on 1C10. Verifies Containment Gaseous RMS at IC22 not in alarm with no abnormal rising trend 0 Reports Containment Environment is complete Page 17 of 25 CRO CRS CRS Perform Rad Levels External to Containment 0 Check the following RMS alarms are clear with no unexplained rise: U-1 Wide Range Noble Gas Monitor U-1 Condenser Off Gas @ 1C22 U-1 S/G Blowdown @ 1C22 U-1 Main Vent Gaseous @ 1C22 Reports Rad Levels External to Containment complete Perform EOP-0 brief Ensure all are attentive . Review Safety Functions not met o Core and RCS Heat Removal Review Safety system Actuations o Spurious/Invalid CIS Solicit Input Conclude the brief Refer to EOP-0 flowchart Heat Removal not met due to no RCP's, consider EOP-2 Implements EOP-2 due to loss of RCS forced circulation Page 18 of 25 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008 Scenario No.: 3 Event No.: 8 Event

Description:

EOP-2 (Following EOP-0) Time Position CRS ___ CRS CRO CRS Applicant's Actions or Behavior Hold EOP-2 Entry Brief using EOP-2 placekeeper

~____ Assign Step E Restore Component Cooling flow to CRO Perform Step E Restore Component Cooling Flow Shut CC Containment Supply Valve 1-CC-3832-CV using handswitch on IC10 Verify 11 CC pump running Verify either 11 or 12 CCHX in service with 11 or 12 SW header in service (both HX's and SW headers should be in service) . Prepare to record highest RCP CBO & Lower Seal Temperatures attained (these should be recorded just prior to restoring Component Cooling Flow to the Containment) Inform CRS that Step E is as complete as possible without resetting CIS, and request another sten Assign step G Establish RCS Heat Sink to the CRO CRO Page 19 of 25 Perform Step G Establish RCS heat Sink . Operate ADV's in manual to continue maintaining S/G Press between 850 and 920 psia and Tcold between 525 and 535°F Establish AFW flow using 11 AFW Pump Verify Steam Train Block Valves open with handswitches in auto Open AFW Steam Supply Valves 1-MS-4070 on 1CO4 1-MS-4071 on 1C04 Ensure 11 AFW pump discharge pressure at least 100 psi greater than S/G Pressure Place 13 AFW Pump WS in PTL on IC04 Slowly raise and maintain S/G level to between (-)24 to (+)30 inches using S/G Flow control valves 1 -AFW-45 1 1 -CV on 1 C04 . 1-AFW-4512-CV on 1C04 Contact TBO to ensure AFW Pump Room ventilation maintaining temperature

< 130°F Secure the Main Feed System o o Trip both SGFP using pushbuttons on 1C03 Place all Condensate Booster Pump handswitches in PTL on 1C03 Place all Condensate Pump handswitches in PTL on 1C03 Place both Heater Drain Pump handswitches in PTL on 1C03 Shut S/G Feedwater Isolation valves 1-FW-45 16-MOV on 1 C03 1 -FW-45 17-MOV on 1C03 o o o . o Place Hotwell Level controller l-LIC*4405 in manual with 50% output Protect S/G BD against waterhammer by shutting the following:

o 1-BD-4010-CV on 1C03 ' 1-BD-4011-CV on 1C03 1-BD-4012-CV on 1C03 . 1-BD-4013-CV on 1C03 CD-410 in Turbine Bldg CD-4 1 1 in Turbine Bldg CRS RO ALL CRS Page 20 of 25 Assign Step H Maintain PZR Level to the RO Maintain PZR Level between 101 and 180 inches Operate Charging and Letdown to restore and maintain level Recognize S/G tube rupture by: Lowering PZR level Lowering trend on RCS Pressure No change in Containment Parameters SIAS actuation on low RCS Pressure Rising trend in 11 S/G Evaluate EOP-0 diagnostic flowchart and determine EOP-6 is appropriate Evaluate EOP-6 ISFSC to verify it is correct EOP (Crew may enter EOP-8 Functional Recovery Procedure, following steps would be the same but crew may be delayed by =: 10 minutes due to extra steps associated with EOP-8)

Page 21 of 25 Appendix D Required Operator Actions Form ES-D-2 Position CRS CRS RO CRS Event No.: 9 (Evaluator's Cue after steps assigned in EOP-2) Applicant's Actions or Behavior Transition to EOP-6 and hold entry brief using placekeeper Direct RO to perform Step D Monitor RCS Depressurization Monitor RCS Depressurization Verify SIAS o o o Verify Alarm window G-5 "Actuation Sys SIAS Trip" is in Ensure 11 & 13 HPSI pumps started on 1CO8 & 1C09 Ensure Main

& Aux HPSI Header Valves Open on 1C08 & 1 C09 If SIAS actuated then:

o Verify following pumps running: 11 HPSI on 1C08 13 HPSI on 1C09 1 1 LPSI on 1CO8 . 12 LPSI on 1C09 . All charging pumps on 1C07 o Verify HPSI flow per EOP Attachment 10 when RCS temp < 1270 psia Direct RO to perform Step F Commence RCS Boration RO CRS Page 22 of 25 Commence RCS Boration Verify boration in progress as follows: o o o VCT Makeup Valve 1-CVC-512 is shut on 1C07 Boric Acid Direct Makeup Valve 1-CVC-514 is open on 1C07 BAST Gravity Feed Valves are open on 1C07 1-CVC-508-MOV

' 1-CVC-509-MOV o o 11 & 12 Boric Acid Pumps are running on 1C07 RWT Charging Pump Suction Valve 1-CVC-504 is shut on 1 C07 VCT Outlet Valve 1-CVC-501-MOV is shut on 1C07(May direct local operation to shut) All Charging Pumps running on 1C07 o o Record time RCS boration commenced Direct CRO to perform Step G Commence RCS Cooldown CRO Commence RCS cooldown . Block SGIS when SGIS Block Permitted alarms C-53

& C-54 on 1C03 are received Record Open and Close times for 11 ADV for dose calculations Open ADV's to 100% using 1-HIC-4056 on IC03 When Thot reaches 515"F, adjust ADV controller to

-:40-50% Establish AFW flow using 13 AFW pump . . o Place AFW motor train block valve handswitches to open 1-AFW-4522-CV on 1C04 1-AFW-4523-CV on 1C04 1-AFW-4532-CV on 1C04 . 1-AFW-4533-CV on 1C04 o Start 13 AFW Pump o Restore and maintain S/G Level between

(-)24 to (+)30 inches using: = 1-AFW-4525-CV on 1C04 . 1-AFW-4535-CV on 1C04 Secure the Main Feed System o o Trip both SGFP using pushbuttons on 1C03 Place all Condensate Booster Pump handswitches in PTL on 1C03 Place all Condensate Pump handswitches in PTL on IC03 Place both Heater Drain Pump handswitches in PTL on 1C03 Shut S/G Feedwater Isolation valves . 1 -FW-45 16-MOV on 1 C03 . 1-FW-4517-MOV on 1C03 o o o o Place Hotwell Level controller l-LIC"4405 in manual with 50% output Protect S/G BD against waterhammer by shutting the following:

o . 1-BD-4010-CV on IC03 . 1-BD-4011-CV on 1C03 . 1-BD-4012-CV on 1C03 1-BD-4013-CV on 1C03 1-CD-410 in Turbine Bldg 1-CD-411 in Turbine Bldg Page 24 of 25 Direct CRO to perform Step J Identify, Isolate and Confirm Affected S/G 1111 Direct RO to perform Step I Depressurize the RCS to reduce subcoolin CRS RO CRS Page 25 of 25 Maintain subcooling as low as possible with these limits:

Subcooling between 25 and 140'F using CET's RCS pressure < 900 psia RCS pressure approximately equal to S/G pressure Lower subcooling by: Initiate Aux Spray De-energize all PZR Heaters on 1C06 o Record PZR water temperature and Charging temperature from indicators on 1C06 & 1C07 Open Aux Spray Valve 1-CVC-517-CV on 1C07 o o Shut Loop Charging Valves 1 -CVC-5 18-CV on 1 C07 = 1-CVC-519-CV on 1C07 o Shift P'ZR Spray Controller 1-HIC-100 to manual with 0% output on 1C06 Depressurize RCS to =: 25" Subcooling (minimize RCS leak rate) Secure Scenario after 11 S/G isolated Determines EAL H.A.5.1.2

• Shading indicates critical task Page 1 of 22 Appendix D Scenario Outline Form ES-D-1 Downpower NIOOl1-01 CVCSOO4-01 FWO 18-02 CD008 S WY DO02 4KV001-01 AFWOOI-01 Scenario No.: 4 Facility: Calvert Cliffs 1 & 2 Scenario No.: 4 Op-Test No.: 2008 R (RO N (CRO/SRO) 1 (RO) C (RO) I (CRO) C (CRO) M (ALL) C (CRO) C(CR0) Examiners: Operators: Tarqet Quantitative Attributes [Per Scenario:

See Section D.5.d) Actual Attributes Turnover: Unit 1 is at 100% power, MOC, Equilibrium Conditions.

12 ARN pump tagged out for repair of overspeed trip device linkage (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> into 18 hour2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> maintenance window).

-_ __ -_ Event 1 2 3 4 5 6 7 8 1. Total malfunctions (5-8) 2. 3. Abnormal events (2-4) Malfunctions after EOP entry (1-2) I1 7 It 2 I1 3 Event Description TSO-SO directed downpower

4. Major transients (1-2) 5. EOPs enteredlreauirina substantive actions (1-2) Channel A NI Power Summer Failure 11 Charging Pump coupling failure 12 FXV Controller Failure Condensate header rupture Loss of Offsite Power 11 4KV bus fault I1 1 I1 1 11 AFW Pump Failure

6. 7. Critical tasks (2-3) EOP contingencies requiring substantive actions (0-2) * (N)orrnal, (R)eactivity, (I)nstrurnent, (C)ornponent, (M)ajor 11 0 11 2 Page 2 of 22 Op-Test No.: 2008 Scenario No.: 4 SCENARIO OVERVIEW NI POWER SUMMERLOSS OF ALL FEED Initial Condition is steady state at 100% power with 12 AFW pump tagged out for repair of overspeed trip device linkage (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> into 18 hour2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> maintenance window). 12 Charging pump is the running charging pump. Scenario starts with a call from TSO-SO that a transformer problem requires U-1 gross electrical output be reduced to 600 MWE as soon as possible.

This will cause the crew to perform a rapid downpower IAW OP-3. During the downpower a NI channel A power summer amp fails causing multiple alarms.

Once crew identifies failed power summer amp NO-1-200 should be referenced and LCO's 3.3.1.A & 3.3.1.D should be entered. CRO will bypass channel A trip units 1,2,7,8,10.

The downpower should be continued.

11 Charging pump coupling breaks causing PZR level to lower, when failed coupling is discovered the crew will select 12 charging pump as the running pump and place 11 Charging Pump WS in PTL. A failure of the 12 S/G Main FRV controller will cause the FRV to fail to the D/P controller in manual. AOP-3G should be implemented.

After verifying a good setpoint signal the CRO will commence auto operation with the Main Feed Bypass valve. Once Feedwater is auto a condensate header rupture will occur causing AOP-3G entry and trip of reactor and securing main feed & condensate.

Once reactor is tripped a loss of offsite power will occur concurrent with a fault on the 11 4KV bus. This will cause a loss of all A train components. During EOP-0 the CRO will need to start 12 CC pp to prevent a RCS leak from the RCP seals. During the wrap up brief for EOP-0 the 11 AFW pump will trip causing a loss of all feedwater.

CRS should implement EOP-3. During EOP-3 the crew will cool down the primary using available S/G inventory and commence once through core cooling when S/G level reaches -350". CRS should direct tying MCC 114 to MCC 104 to maximize PORV flow. Scenario ends when crew has determined OTCC will be successful IAW EOP Attachments.

CRS will declare Alert based on either A.A.7.1.2 or H.A.2.1.2

1. 2. 3. 4. 5. 6. - - - 7. - 8. 9. - Page 3 of 22 INSTRUCTOR SCENARIO INFORMATION Reset to IC-24 Perform switch check. Place simulator in CONTINUE, advance charts and clear alarm display. Place simulator in FREEZE. Enter Trigger

a. None Enter Malfunctions

a. b. C. d. e. f. g. h. Channel A NI Power Summer Failure NI0011-01 on F1 11 Charging Pump coupling failure CVCSOO3-01 on F2 12 FRV Controller Failure FW018-02onF3 Condensate Header Rupture CD008 on F4 Loss of Offsite Power SWYD002 on F5 11 4KV bus fault 4KV001-01 on F6 11 AFW Pump Failure AFWOO1-01 on F7 12 AFW Pump Failure AFWOO1-02 at Time Zero Enter Panel Overrides

a. None Enter Remote Functions

/ Administrative

a. Place yellow tag on 12 AFW Pump trip pushbutton. Set simulator time to real time, then place simulator in CONTINUE.

Page 4 of 22 - 10. Give crew briefing. a. Present plant conditions:

b. Power history:

C. Equipment out of service: d. Abnormal conditions:

e. Surveillances due:

f. Instructions for shift:

100% load at MOC 10500 MWD/MTU 100% for 6 months 12 AFW Pump 00s (repairing overspeed trip linkage 6 hrs into 18 hr window) None None Maintain 100% power - 1 1. Allow crew 3-5 minutes to acclimate themselves with their positions.

12. Instructions for the Booth Operator.

a. Activate F1 Channel A NI Power Summer Failure when cued by the lead evaluator.

b. Activate F2 11 Charging Pump coupling failure when cued evaluator.

c. Activate F3 12 FRV Controller Failure when cued by lead evaluator.

d. Activate F4 Condensate header rupture when cued by lead evaluator.

e. Activate F5 & F6 Loss of Offsite Power & 11 4KV bus fault at same time when cued by lead evaluator after reactor trip.

f. Activate F7 11 AFW Pump Failure when cued by lead evaluator Op-Test No.: 2008 Scenario No.: 4 Page 5 of 22 RESPONSES TO CREW REQUEST If a request and response is not listed, delay response until reviewed with the examiner.

If one request is dependent upon completion of another, then subsequent actions should not be responded to until the appropriate time delay has been observed. Responses to routine requests, which have no effect the scenario, do not require examiner clearance.

1. 2. 3. 4. 5 6. 7. 8. 9. 10. 11. 12. 13. REQUEST OWC contact IM for assistance for NI Power Summer AB0 check 11 charging pump AB0 check suction pressure oscillation on 12 charging pump OWC contact Engineering

& IM for FRV Controller Failure TBOPPO check location of condensate header rupture PWS tie 1Y09 to lY10 with lY10 supplying IAW local plaque TBO shift13 charging pump to 14 480V Bus ABOPPO check SWGR Ventilation in service ABOPPO operate ADV's locally with chain operator OWC/TBO check 11 AFW pp U2 CRO align 23 AFW pp to supply U-1 OWC expedite return of 12 AFW pp to service ABOPPO/PWS tie MCC-114 to MCC-104 RESPONSE Acknowledge Request Acknowledge Request, after 2 minutes report broken coupling Acknowledge Request, after 1 minute report no pressure oscillations Acknowledge Request Acknowledge request, after 2 minutes report leak is at common discharge of condensate booster pumps Acknowledge Request, after 4 minutes tie 1Y09 to 1Y10 Acknowledge Request, after 1 minute shift power supply Acknowledge Request, after 2 minutes report SWGR Ventilation in service Acknowledge Request, after 2 minutes open ADV's to requested position.

Acknowledge Request, after 2 minutes report 11 AFW pp appears seized.

Acknowledge Request, after 2 minutes report cross-connect valve will not open, OWC informed Acknowledge Request Acknowledge Request, after 5 minutes tie MCC's using Remote Function Page 6 of 22 Critical Tasks 1. 2. Starts 12 Component Cooling Pump prior to exceeding RCP temperature limits. (thrust bearing 195", CBO 200"). Commence OTCC within 5 minutes of both S/Gs <-350" or Tcold rising 5"uncontrollably (must be commenced prior to CET temperature reaching 560°F)

Page 7 of 22 Appendix D Required Operator Actions Form ES-D-2 Posit ion CRS RO CRO RO RO CRS RO Applicant's Actions or Behavior Direct RO

& CRO to perform rapid Downpower IAW OP-3 to 600 MWe gross Borate the RCS 1. 2. Start 12 charging pump 3. 4. 5. 6. Open BA Direct MAJ Valve 1-CVC-5 14-MOV on IC07 Start 11 or 12 BA Pump for 30 seconds then secure pump started Shut BA Direct h4RJ Valve 1-CVC-514-MOV on 1C07 Open RWT CHG PP Suction valve 1-CVC-504-MOV on 1C07 Shut VCT Outlet Valve 1-CVC-501-MOV on 1C07 Adjust turbine load to maintain Tcold within 5°F of program (not to exceed 548°F) using manual adjust switch 1-CS-80 or using auto on Mk6 Turbine Control Computer flat panel display on 1C02 Insert CEA's as needed by selecting Manual Sequential control at 1C05 and operating the In-Hold-Out switch to the insert direction.

CEA's should be operated in 15 inch increments not to exceed transient insertion limits. Initiate Pressurizer Spray flow to help equalize PZR boron concentration.

1. 2. Energize all PZR Backup heaters on 1C05 Adjust setpoint of Pressurizer Pressure controller 1-PIC-1OOX

& Y to = 2200 psia to maintain RCS pressure =: 2250 psia. When 600 We gross output is reached, direct securing from rapid downpower Restore Charging pump suction to VCT: 1. 2. Open VCT Outlet Valve 1-CVC-501-MOV on 1C07 Shut RWT CHG PP Suction valve 1-CVC-504-MOV on 1C07 Page 8 of 22 Appendix D Required Operator Actions Form ES-DQ Position CRORO CRS RO CRO CRS CRO CRS RO Cue) Applicant's Actions or Behavior Announce alarm D-22 on IC06 per management expectations CRS directs RO to monitor primary Monitor the primary Check Reactor Power Check RCS temperatures Check RCS pressure Check PZR level Report primary is stable Recognize power summer failure on channel A and informs CRS ~ ~~ Reference NO-1-200 matrix for T.S. applicability Direct CRO to bypass RPS A Trip Units 1,2,7,8,10 Bypass Trip Units Channel A IAW 01-6. Ensure CRS checking Tech Specs Insert bypass key and turn clockwise to Bypass for following T/U's: o 1 HiPower o 2 Hi Rate o 7 TMnPPress o 8 LossofLoad o 10 Axial Power Enter RPS Instrumentation Tech Spec Action Statements LCO 3.3.1.A . LCO 3.3.1.D Evaluate Alarm Manual for compensatory actions Page 9 of 22 Appendix D Required Operator Actions Form ES-DP Position RO RO CRS Applicant's Actions or Behavior Announce and acknowledge alarm F-45 "CHG HDR FLOW LO PRESS LO' on 1 C07 Recognize failure of 11 charging pump coupling . . . Charging header flow 0 gpm on 1C07 11 Charging Pump red light lit on 1C07 11 Charging Pump indicating low amps on 1C07 Inform CRS Direct RO to shift to 12 Charging Pump IAW 01-2A RO Shift to 12 Charging Pump 4 . . . Notify Radiation Safety of new charging pump lineup Place 12 Charging Pump handswitch to start on 1C07 Direct AB0 to check suction pressure oscillations e 4 psig Place 13 Charging Pump in PTL on 1C07 Place Backup Charging Pump Select handswitch in the "13 & 11" position on 1C07 Stop 11 Charging Pump on 1C07 Place 13 Charging Pump handswitch in normal on 1C07 . =

Page 10 of 22 Appendix D Required Operator Actions Form ES-DQ ~ Position Applicant's Actions or Behavior CRORO Acknowledge and announce 1C06 E-43 Selected Computer Point Alarm CRO I Reports 12 FRV controller failed, and now in manual control using the DP controller on IC03 CRS 1 CRS directs RO to monitor primary RO Monitor the primary . Check Reactor Power Check RCS temperatures Check RCS pressure . Check PZR level Report primary is stable CRS Implement AOP-3G CRS Direct RO to monitor for trip criteria . . Tcold lowers to 515°F S/G level approaching

(+)50 inches CRO CRO Place 1-HS-45 17C in Main Fail position on 1C03 Adjust 1-PDI-4517 in manual control on 1C03 to maintain 12 S/G level approximately zero inches CRO Verify S/G FW Main & Bypass Valve Controllers are in Manual on 1C03 CRO Page 11 of 2 Shift the S/G FW Bypass Valve Controller to Bypass Override Operation (may decide not to perform) . . . . . Verify Plasma Display at 1C36 is activated Select "Menu" option on plasma display Select "4 Display" (Channel Bypass) on plasma display Press "Disabled' on plasma display Verify plasma display displays "ENABLED' Verify BYP OVERRIDE light on 1C03 is lit for 12 FRV Adjust the 12 S/G FW Bypass Valve and Main Valve using controllers in manual: o o 12 S/G FW Bypass Controller output =: 70% 12 S/G FW Main FRV (using PDI Controller) for

=: zero inches . When above conditions are met and it is desired then place the 12 S/G Bypass Valve Controller to Auto Page 12 of 22 Appendix D Required Operator Actions Form ES-D-2 Position CRO/RO CRS CRO CRS RO CRO CRS Amlicant's Actions or Behavior Announce multiple alarms per management expectations CRS directs CRO to check RPS calling for a trip Check RPS calling for a trip . Checks RPS for active trips (any 2 sets of red lights on same Trip Unit means trip condition)

Checks RPS power supplies (2 RPS channels w/o power indicates trip condition)

Checks RPS Matrix Relays (any combination of right side lights out with left side lights out (6 groups of 4 lights) . Report RPS not calling far a trip CRS directs RO to monitor primary Monitor the primary . Check Reactor Power . Check RCS temperatures . Check RCS pressure . Check PZR level. Report primary is not stable Recognize condensate header rupture and report to CRS Implement AOP-3G, directs RO to trip reactor and CRO to secure condensate and feed IAW AOP-3G Section VI11 Step A RO CRO Page 13 of 2 Depress Reactor trip pushbuttons on 1C05 and perform EOP-0, Reactivity Control . . . Depress Manual Reactor Trip Pushbutton on 1C05 Check Reactor tripped using NI power indications on 1C05 Verifies all CEAsf ully inserted Verify DI Water Makeup is secured o o o Check 11 & 12 RC makeup Pumps secured on 1C07 Check VCT M/U 1-CVC-512-CV is shut on 1C07 If aligned for direct makeup to RCS then shut RWT Charging Pump Suction 1-CVC-504-MOV on 1C07 Reports Reactivity Control Complete Secure Feed and Condensate IAW AOP-3G 1. Trip both SGFP's 2. Secure following pumps and place handswitches in PTL 9 Condensate Pumps on 1C03 . 3. Shut SG FW Isolation Valves: . 1-FW-4516-MOV on 1C03 . 1-FW-4517-MOV on 1C03 4. Start an AFW Pump (1 1 or 13) on 1C04 Condensate Booster Pumps on 1C03 Heater Drain Pumps on 1C03 Page 14 of 22 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008 Scenario No.: 4 Event No.: 5 Event

Description:

Loss of Offsite Power & 11 4KV bus fault, EOP-0 (Evaluator's Cue)

Time Position RO CRO Applicant's Actions or Behavior Places 13 Charging pump in PTL on 1C07 and directs TBO to shift 13 charging pump to 14 480v Bus When power supply is shifted for 13 Charging Pump then start 13 Charging Pump Performs Turbine Trip Check Reactor tripped then: Depress both Turbine Trip Pushbuttons on 1C02 Check Main Turbine stop Valves shut on MK VI screen Check Turbine Speed drops on MK VI screen Checks Turbine Generator Output Breakers open 11 GEN BUS BKR 0-CS-552-22 on lC01 11 GEN TIE BKR 0-CS-552-23 on lCOl Check Generator Field Breaker open on lCOl Check Generator Exciter Field breaker open on lCOl Ensure MSR 2nd Stage Steam source Valves are shut . 1-MS-4025-MOV on 1C02 cannot be verified due to loss of power effects 9 Direct TBO to manually shut o 1-MS-4018-MOV o 1-MS-4017-MOV 9 Direct TBO to verify MSR Panel Loader Panels are set to zero . 1-MS-4026-MOV on IC02 Reports Turbine Trip Complete CRO CRO CRS RO Page 15 of: Performs Vital Aux . . . Check 11 or 14 4KV bus energized.

(14 4KV Bus is energized)

Depress OC DG Emergency Start Pushbutton 0-HS-0707 on 1C20A Check ALL 125V DC BUS VOLTS greater than 105 volts on 1C24: 11 . 12 21 22 . Check at least THREE 120V AC Vital Buses are energized on 1C24: . 11 . 12 13 14 Check EITHER 1YO9 OR 1Y 10 energized on 1C24. (1Y 10 is energized) . Direct AB0 to verify switchgear ventilation in service IAW 01-22H Reports Vital Auxiliaries Complete Direct OS0 to locally trip 1A D/G due to running without auxiliaries Direct OWC to contact E&C to investigate loss of 11 4KV Bus Performs Press & Inventory Checks pressurizer pressure at 1C06 between 1850 and 2300 psia and trending to 2250 PSIA on 1C06 Checks pressurizer level at 1C06between 80 an 180 inches and trending to 160 inches on 1CO6 Checks subcooling is greater than 30°F by PAMs display on 1C05 0 0 Reports Press & Inventory is complete Page 16 of 22 CRO CRS CRO Performs Core

& RCS Heat Removal TBV and ADV Controllers have lost power o Directs AJ30PPO to manually open 11 & 12 ADV's to 40-50% open using chain operator Maintains S/G pressures between 850 and 920 psia and Tcold between 525 and 535°F o 0 Checks S/G level (-)170" to (+) 50" on 1C03 o o Start an AFW pump: Main Feedwater lost due to loss of power effects Open 1-MS-4070-CV

& 1-MS4071-CV at 1C04 to start 11 AFW pump o o Trip the SGFP's by depressing trip pushbuttons on 1C03 Shut the S/G FW Isolations using handswitches on IC03 . 11 S/G Feedwater isolation does not have power, direct an extra AB0 to shut manually o Operate AFW System to restore S/G levels to between (-)170 and (+)30 inches (AFW flow control setpoint between 150 gpm and 300 gpm on 1C04) Checks RCP not operating green lights illuminated on 1C06 Reports Core and RCS Heat Removal cannot be met due to no operating RCP's Contact PWS to tie 1Y09 to 1Y 10 IAW local plaque Perform Containment Environment including verifying alt actions 0 Checks Containment Pressure c 0.7 psig using narrow range pressure on lClO Verifies Containment Temperature c 120°F using cavity and dome temperature indicators on 1C10. (Loss of power effects prevents) o Verifies 13 & 14 Containment Air Coolers operating in Fast Speed on lClO Opens 13 & 14 Containment Air Coolers Emergency Outlet Valves on lClO o 0 Verifies Containment Gaseous RMS at 1C22 not in alarm with no abnormal rising trend (Loss of power effects prevents) o No valid alarm received, no Iodine Filter Units should be started on lC10 teports Containment Environment complete (May call cannot be met due to loss )f power effects)

CRO Perform Rad Levels External to Containment Check the following RMS alarms are clear with no unexplained rise: (Due to loss of power effects, cannot verify alarms clear) U-1 Wide Range Noble Gas Monitor U-1 Condenser Off Gas @ 1C22 0 U-1 S/GBlowdown

@ 1C22 U-1 Main Vent Gaseous @ 1C22 Reports Rad Levels External to Containment cannot be met due to loss of power effects Direct PWS to tie 1YO9 to 1Y 10 IAW local plaque After 1Y09 tied to 1Y 10, control of ADV's can be returned to 1C03. . Place ADV controller to desired output Direct AEiOPPO to remove mechanical gag on ADV's I I

• Shading indicates Critical Task Page 18 of 22 Appendix D Required Operator Actions Form ES-D-2 No.: 4 Event AFW Pump / Still pump started) Position CRO CRO CRO CRS CRS CRS No.: 6 in EOP-0 (Evaluator's Cue, = 3 minutes after Applicant's Actions or Behavior Recognize 11 AFW Trip and report to CRS Contact TBO to investigate failure of 11 AFW Pump Re-evaluate Core and RCS Heat Removal Safety Function Report Core

& RCS Heat Removal cannot be met due to no Feedwater and no operating RCP's Contact OWC to expedite repairs to 12 AFW Pump Perform EOP-0 brief . Ensure all are attentive . Review Safety Functions not met o Core and RCS Heat Removal due to no Feedwater and no operating RCP's Containment Environment due to loss of power effects Rad Levels External to Containment due to loss of power effects o o Review Safety system Actuations o None (Chance of AFAS depending on timing) . Solicit Input Conclude the brief Refer to EOP-0 flowchart . Heat Removal not met due to no Feedwater, consider EOP-3 Implements EOP-3 due to loss of all feedwater Page 19 of 22 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2008 Scenario No.: 4 Event No.: 5 Event

Description:

EOP-3 Time Position CRS CRS CRO CRS RO CRS Applicant's Actions or Behavior Hold EOP-3 Entry Brief using EOP-3 placekeeper Direct CRO to perform step E "Minimize S/G Inventory Loss" Verify S/G Blowdown Valves shut on 1C03 1 -BD-40 1 0-CV 1-BD-4011-CV 1 -BD-40 12-CV 1 -BD-4013-CV

__~ ~ Direct RO to perform Step F "Commence RCS Boration" Commence RCS Boration Verify boration in progress as follows: VCT Makeup Valve 1-CVC-512 is shut on 1C07 Boric Acid Direct Makeup Valve 1-CVC-514 is open on IC07 BAST Gravity Feed Valves are open on 1C07(Action may be delayed due to loss of power) 1-CVC-508-MOV 1-CVC-509-MOV Verify M/U Mode Selector Switch 1-HS-210 in Manual on 1 C07 Start 12 Boric Acid Pump on 1C07 VCT Outlet Valve I-CVC-501-MOV is shut on lC07(Action may be delayed due to loss of power) 12 & 13 Charging Pumps running on 1C07 Record time RCS boration commenced Record BAST Levels Direct CRO to perform step G "Commence Natural Circulation Cooldown to Tcold < 465°F" CRO CRS CRS Commence rapid cooldown to 465°F If at any time both S/G Levels reach

(-)350 inches or Tcold rises uncontrollably by 5"F, then initiate Once Through Core Cooling per Step J . Block SGIS o When SGIS A Block Permitted alarm is received on 1C03 then block SGIS A using keyswitches on 1C03 When SGIS B Block Permitted alarm is received on 1C03 then block SGIS B using keyswitches on 1C03 o Block SIAS o When PZR Pressure Block A Permitted alarm is received on 1C08 then block SIAS A using keyswitches on lC10 When PZR Pressure Block B Permitted alarm is received on 1C08 then block SIAS B using keyswitches on lCl0 o Shut both MSIV's due to loss of offsite power Open ADV's fully using controller at IC03 while maintaining the following:

o o Cooldown less than 100°F in any one hour Subcooling between 30 and 140"based on CET temperatures on 1 C05 Pressurizer level between 50 and 180 inches o Direct OWC to contact maintenance for AFW pp's & 1A DG(if not done during EOP-0) Direct RO to peform step J "Initiate Once Through Core Cooling"

Page 22 of 2: CRS I Direct CRO to perform step Q "Restore from Loss of Power" CRS I Direct PWS to tie MCC 114 to MCC 104 IAW Step Q.5.b on page 50 of EOP-3 Secure Scenario when OTCC initiated and crew recognizes need to restore power to MCC 114 to be successful CRS EAL A.A.7.1.2 or H.A.2.1.2

• Shading indicates Critical Task