Text

Final Operating Exam (Section C) (Folder 3)
	ML13066A514
Person / Time
Site:	Indian Point
Issue date:	02/27/2013
From:	; Entergy Nuclear Indian Point 3
To:	D'Antonio J; Operations Branch I
	Jackson D
Shared Package
ML12214A189	List: IR 05000286/2013301; ML12277A076; ML13036A274; ML13066A168; ML13066A177; ML13066A287; ML13066A337; ML13066A461; ML13066A514; ML13106A121; ML13106A192; ML13109A406;
References
	TAC U01866
	Download: ML13066A514 (105)
	v • d • e

Appendix 0 Scenario Outline Form ES-O-1 Facility: IpEG Unit 3 Scenario No . 1 Op-Test No.: *1 Examiners: Operators:

Initial Conditions: 100% power steady state. 32 AFW Pump is out of service for bearing repair.

Need to have 35 SWP in service.

Turnover:

32 AFW Pump is expected back in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Team has been asked to reduce power to 90%

for a Turbine StOI2 and Control Valve Test in 30 minutes.

Event Malf. Event Event No. No. Type* Description 1 N/A R (ATC) Perform power reduction.

N (BOP, CRS) 2 MAL C (CRS) 33 MFRV fails open in auto - manual available.

CFW013 E C (ATC) 33 MFRV will be placed in manual to control 33 SG level.

3 MAL C (ALL) NRHX Tube Leak.

CFW011 i 4 MAL- C (CRS. Loss of 480V Bus 3A.

EPS05B BOP) 34 or 36 SWP will be started.

TS (CRS)

CRS will determine T.8. shutdown is required due to AFW.

5 N/A R (ATC) Perform power reduction with Feed Reg Valve in Manual N (BOP, CRS) 6 MAL- C (CRS) Inadvertent main generator trip. Reactor will not automatically trip.

GENOO2 Manual trip will be required.

C (ATC) 7 MAL- M (ALL) 33 AIFW pump will not start causing a loss of heat sink. Heat sink CFWOO1 will be restored using condensate.

C 8 MAL- TS (CRS) I PORV 455C leaks by requiring isolation. CRS can be asked about

/6RSOO3 I TS requirements at end of scenario.

C (ATC)

" (N)ormal, (R)eactivitv. (i)nstrument. (C)omponent. (M)aior U3 NRC Scenano I Power ReductIOn fro 100%,33 MFRV Falls Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 1 of20

Appendix 0 Scenario Outline Form ES-D-1 The evaluation begins with the plant at 100% power steady state operation.

32 ABFP has been out-of-service for bearing oil line repair for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . It is expected back within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (TS 3.7.5 - 72 hr AOT). 31 and 33 ABFPs are protected equipment.

The team has been requested to reduce power to 90% in preparation for a turbine stop and control valve test.

After the team has begun reducing reactor power, 33 Main Feed Regulating valve (FCV-417) fails open. The team will take actions per AOP-FW-1, "Loss of Feedwater" and place the MFRV in manual to control SG level.

During subsequent actions of AOP-FW-1, a leak develops in the Non-Regen heat exchanger.

The team will respond per AOP-UCCW**1 and isolate Letdown.

While putting in Excess Letdown, an electrical fault occurs on 480V Bus 3A. The team will have to start an essential service water pump per AOP-480V-*1. The CRS will determine that two AFW Pumps are inoperable necessitating a shutdown per T.S. 3.7.5 or safety function determination per 3.0.6.

The team will commence a power reduction in accordance with POP-2.1 with 33 Main Feed Regulating Valve in Manual.

The MTG will then trip inadvertently. The reactor will not trip automatically and will require manual trip at the flight panel. After the trip, 33 AFW Pump will not start, and one of the PORVs begins to leak by creating an isolable SBLOCA. The team will respond to the PORV failure by closing its block valve. The team will initiate performance of E-O, "Reactor Trip or Safety Injection".

Since no motor-driven AFW pump is av.ailable, the team will transition to FR-H.1, "Loss of Secondary Heat Sink" due to inadequate AFW flow.

The scenario will terminate when Condensate flow is established to the SGs.

Procedure Flowpath: POP-2.1, AOP-FW-1, AOP-UCCW-1, AOP-480V-1, POP-2.1, E-O, FR-H.1 Critical Tasks are as follows:

E-O - A Manually trip reactor from the CCR before completing E-O, Step 1 E-O - M Close block MOV upstream of sb.lck-open Pzr PORV by completion of the first step in the ERG network that directs the crew to close the block MOV FR-H.1 - A Establish Condensate or Main Feed flow to at least one SG before 3 out 4 SG WR levels < 20% (or properly establish and recover from bleed and feed if required).

U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 2 of20

Appendix 0 Scenario Outline Form ES-O-1 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES IC Reset Reset Simulator to IC-11 SES Setup Insert malfunction MAL- Auxiliary Feedwater Pump 31 Failures Schedule CFW001A to TRIP Insert malfunction MAL- Auxiliary Feedwater Pump 32 Trip CFW001B Insert override SWI-ATS002A Green Lamp Aux Feedwater Pump No. 32 to Off Control Switch Module Insert override SWI-ATS002B Red Lamp Aux Feedwater Pump No. 32 Control to Off Switch Module Insert override SWI-ATS002C Trip Pas Aux Feedwater Pump No. 32 Control to On Switch Module Insert override SWI-ATS002D On Pas Aux Feedwater Pump No. 32 Control Switch Module Insert remote LOA-MSS021 MS-41 S/G 32 To AFWP Iso to a Insert remote LOA-MSS022 MS-42 S/G 33 To AFWP Iso to a Insert malfunction MAL- Auxiliary Feedwater Pump 33 Failures CFW001 C to TRIP Insert override SWI- PCV-455C Red Lamp Pressurizer Relief Valve RCS021 B to Off PCV-455C Control Switch Create event 30

..IPPLP4(1)==1 -desc Set trigger 30 to actuate after reactor trip Insert malfunction MAL- FDW CNTRL FIC-437 Auto Mode Failure CFW013E to 100.00000 on (Manual Avail) event 1 Insert malfunction MAL- Non-Regenerative Letdown Heat Exchanger CFW013E to 50.00000 on Tube Leak event 2 Insert malfunction MAL- Main Generator Trip GEN002 on event 4 Insert malfunction MAL- Loss Of 480 V Bus 3A EPS005B on event 3 Insert malfunction MAL- Pressurizer Relief Valve 455C Valve Position PRS003C after 60 to Failure 10.00000 on event 30 Insert malfunction MAL- Reactor Trip Breakers Fail To Open (Auto I RPSOO2A to ALL_FAIL . Failure) i I

U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 3 of20

Appendix 0 Scenario Outline Form ES-O-1 SES Setup ! Load Schedule and verify Schedule

malfunctions and overrides have been entered Floor Setup Perform Setup Checklist Ensure 35 Service Water Pump Operating Update Protected Equipment Hang Danger Tags on 32 AFW pump PC Risk is Yellow Hang Protected Equipment Tags For:

31 and 33 AFW eumes I

Event 1

Respond as requested by Crew performs power reduction i crew Event 2 i Activate Trigger 2 when MAL-CFW013E 33 SG MFRV Fails Open

directed i Role Play Acknowledge requests for ! I&C will develop a troubleshooting plan I&C to troubleshoot i i

i Event 3 Activate Trigger 3 i MAL-CFW013E NRHX Tube Leak Role Play Respond as requested by the i LOA-CVC031 Open/adjust CH-409, 33 charging crew pump re(;irc valve Event 4 Activate Trigger 4 MAL-EPS005B Fault on bus 3A Role Play If asked to investigate bus 3A

Bus has smell of ozone and probably tripped on actual fclUIt. More troubleshooting will be required Role Play AsSM Prompt team to continue shutdown due to T.S. i issues to have unit off line in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . !

5 Respond as requested by Power reduction due to INOPERABILITY of 2 I crew i AFW pumps Event 6 Activate Trigger 6 MAL-GEN002 Inadvertent Generator Trip MAL-RPS002A Reactor fails to automatically trip manual trip is successful.

MAL-PHS003C PORV starts to leak by can be manually isolated using block valve

! Role Play Respond as requested by the i crew

~ Event 7 erted at setup MAL-CFW001 B 33 AFW pump failure to start Role Play Respond as requested by the If asked to investigate 33 AFW pump report the crew pump is mechanically bound and will not rotate.

As Nuc NPO stand by MCC36A1B to open breakers for BFD-2s i Insert L.OA-CFW066 and LOA-CFW067 to i DEENERGIZE when requested IFa i Inserted 30 seconds after reactor trip MAL-PRS003D PORV 455C leak set to 10%

U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 4 of20

Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: _1_

Event

Description:

Power Reduction Time Position Applicant's Actions or Behavior Note:

The reactivity plan for the power reduction should be developed by the team in the briefing room prior to taking the watch. The plan could call for boration and/or rod insertion i CRS Assigns roles for power reduction ATC Reviews reactivity Qlan ATC If rods are inserted:

Places/verifies rods are in Manual

Inserts rods specified number of steps

Observes:

a Proper rod motion a Tavg a Power BOP Peer checks rQQ InsertiQn ATC If boratlon is performed:

Using SOP-CVCS-003

Places RCS Makeup control to Stop

Place RCS Makeup Mode selector to borate

Adjusts integrator to desired boration amount

Places RCS Makeup control to Start

Observes:

a Proper makeup response a Tavg 0 Power BOP Peer check boration I

U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

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Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: _1_

Event

Description:

Power Reduction Time I Position Ap~icant's Actions or Behavior Lead Evaluator When the following has been demonstrated/observed:

Sufficient load reduction .

Sufficient normal plant operations by the BOP .

Then instruct Booth to insert Event 2.

U3 NRC Scenario 1 Power Reduction fro 1000/0,33 MFRV Fails Open- Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

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Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: Event No.: -L Event

Description:

FRV fails open in auto Time Position Examinee's Actions or Behavior

, ATC Diagnose 33 MFRV failing open

Feed Flow to 33 SG increasing

33 SG Level Increasing

Steam Generator Level Control Deviation Alarm BOP Refers to ARPs for alarms ATC Places 33 MFRV in Manual Control and adjusts manual setpoint to lower feed flow to lower level CRS Directs crew to perfonT! immediate operator actions of 3-AOP-FW-1 I

ATC Performs IOAs of AOP-FW-1

Checks status of Main Boiler Flaed Pumps (MBFP)

Announce IOAs complete I Ii CRS Announces Entering 3-AOP-FW-1 and begins reading individual steps.

CRS/ATC Identify both MBFPs operating CRS Determines transition to step 4.54 CRS May perform a Crew Brief at this time May notify Shift Manager that failure has occurred.

CRS/ATC Determine Main Feed Regulating ValvE~ (MFRV) has failed open.

ATC Reports MFRV is in manual and control is functioning. SG level is returning to program.

CRS/ATC i Check status of additional feed system valves - all normal CRS Notifies the System Engineer that MFRV needs to be inspected U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open - Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

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Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: -L

. Event

Description:

FRV fails open in auto

- Time i Position I Examinee's Actions or Behavior

. CRS Notifies SM

. I Lead Examiner Direct Booth to initiate Event 3 U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open - Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 8 of20

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: _1_ Event No.: L Event

Description:

NRHX Leak Time I Position Examinee's Actions or Behavior BOP Identify Loss of Letdown/Increase in CCW Surge Tank Level I

CRS : Enter AOP-UCCW-1 (Possibly isolate leak and enter AOP-CCW-1) i Continue with Loss of Letdown I CRS/ATC Determine there is a bubble in the Pressurizer I .

BOP Close CH LCV 459 and CH*LCV-460 (Panel SFF)

CRS/ATC Determines Seal Injection exist i

Transition to S!ep 4.20 BOP/ATC Coordinate shutting CH-HCV-142 maintaining discharge header pressure < 2650 psig ATC Adjust charging pump speed to maintain seal injection approximately 6 gpm CRS Direct NPO to throttle CH-409 (33 Charging Pump Recirculation Valve) as necessary.

l Booth Operator If directed to throttle 409 LOA-CVC031 I CRS ! Determines excess letdown is desired directs BOP to perform Attachment 2

BOP I Notify HP that excess letdown will be placed in service BOP Contact Nuc NPO to verify status of RCDT I

BOP Open the following valves

AC-AOV-793 (Panel SNF)

AC-AOV-796 (Panel SGF)

AC-AOV-791 (Panel SNF) i

AC-AOV-798 (Panel SNF}

i BOP I Check CH-HCV-123 Closed (Panel SFF)

I !

U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip AvaiL, 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 90f20

Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: _1_ Event No.:

i Event Description' NRHX Leak Time Position : Examinee's Actions or Behavior

, BOP i Verify CH-AOV-215 in Divert (Panel SFF) i i

BOP I Open the following valves

CH-AOV-213A (Panel SFF)

CH-AOV-213B {Panel SFF}

BOP I Slowly Open CH-HCV-123 (Panel SFF)

BOP When sufficient warm-up (slow rise on TI-122)

Close CH-HCV-123 (Panel SFF)

Place CH-AOV-215 to NORMAL (Panel SF F)

I

Throttle Open CH-HCV-123 (Panel SFF)

Lead Examiner I Direct Booth Operator to initiate Event 4 i

U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open - Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 10 of20

Appendix 0 Scenario Outline Op-Test No.: _1_ Scenario No.: _1_ Event No.: ~

Event

Description:

Loss of Bus 3A Time Position Examinee's Actions or Behavior CRS/BOP Multiple alarms - Diagnose Loss of Bus 3A CRS Enter AOP-480V-1 CRS/BOP Determine power is lost to Bus 3A and RHR was not in service CRS/ATC Determine 33 Charging Pump is running I CRS/BOP Determine 2 CCW Pumps are running I CRS/BOP Determine Essential Service Water Header Pressure is < 60 psig and no SW pumps are operating on the Essential SW Header

Start 34 or 36 SW Pump

. CRS/ATC . Determine Turbine is on line I

i CRS/ATC Determine Power has not been lost to IRPI I

CRS/ATC . Determine Vacuum NOT decreasing BOP CRS/BOP Determine ISO PHASE BUS RETURN AIR HIGH TEMP alarm is clear on Panel SEF CRS/BOP I Determine waste release is NOT in progress BOP Dispatch operator to monitor EDGs CRS/ATC Determine IRPI is operable I

CRS Initiate Review of Tech Specs CRS i Determine that Bus 3A is inoperable and 2 AFW pumps are inoperable necessitating a shutdown per T.S. 3.7.5 U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page II 0[20

Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: ~

Event Descrietion: Power Reduction Time i

Position I Examinee's Actions or Behavior Booth Operator

If necessary call as SM and direct the crew to initiate the shutdown Immediately.

i

! The unit should be off the line in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

CRS Use Attachment 3 from POP-2.1 to continue power reduction I

CRS Record power reduction data and contact the SM to make required notifications i

I

. CRS I Direct ATC/BOP to perform a Reactivity Calculation for the power reduction ATC/BOP Prepare Reactivity Calculation using the Daily Reactivity Sheet, OPT-25 i I CRS I Assigns roles for powl:r reduction ATC Reviews reactivity plan ATC If rods are inserted:

Places/verifies rods are in Manual

Inserts rods specified number of steps

Observes:

0 Proper rod motion 0 Tavg 0 Power i BOP Peer checks rod insertion I

U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

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Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.:

Event

Description:

Power Reduct""io::..:n-'--__________________________...JI, Time Position Examinee's Actions or Behavior ATC If boration is performed:

Energize All Pressurizer Heaters

Places RCS Makeup control to Stop

Place RCS Makeup Mode selector to borate

Adjusts integrator to desired boration amount

Places RCS Makeup control to Start

Observes:

o Proper makeup response o Tavg i 0 Power I~---r----+----~

! BOP Peer check boration ATC/BOP Initiate Turbine Load Reduction at desired rate

Governor (Preferred)

Load Limit 1

Load Limit 2 ATC Maintain the manual setpoint for the MFRV Controllers Nulled.

. ATC Adjust Control Rod Position per TS and Graph-RPC-16 i

Lead Evaluator When the following has been demonstrated/observed:

Sufficient load reduction.

Sufficient normal plant operations by the BOP.

Then instruct Booth to insert Event 6.

U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open - Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 13 of20

Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: l Event Descri Generator w/o Reactor Time Position Examinee's Actions or Behavior CRS/ATC Diagnose Turbine Trip with failure of reactor to trip ATC Announce "Tripping the Reactor" then depress the reactor trip button on the Flight Panel NOTE The CRS may direct tripping the reactor before the ATC makes the

announcement.

When Unit trips, direct team to perform immediate actions of E-O

Verifies immediate actions usin!;J the procedure.

When the CRS directs "Perform the Immediate Operator Actions of E-O", the ATC and BOP will first perform the IOAs silently only announcing unexpected conditions. The crew will then re-perform i the IOAs verbalizing each item.

ATC Verifies Reactor Trip: (Panel FCF)

Reactor trip and bypass breakers open

Rod bottom lights lit

IRPls < 20 steps

Nuclear flux decreasi

. ATC Verifies Turbine Trip by observing stop valves closed (Panel FAF)

BOP Check status of 480V buses (Panel SHF)

Observe 5A, 2A, and 6A busses energized from Offsite Power ATC Check SI status Determine if SI is Actuated

SI Pum U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open - Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip AvaiL, 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 14 of20

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: ~

Event

Description:

Generator Trip wlo Reactor Trip ATC , Determines SI NOT actuated and NOT required; however, RCS pressure will be

~ decreasing.

After the "Silent Pass" through the IOAs it is permissible to perform Prudent Operator Actions. This includes closing the PORV Block valve. If the ATC and CRS have diagnosed the leaking PORV, then the PORV Block Valve should be closed at this time. This is Event 8.

If the PORV leak is NOT diagnosed then the crew will continue.

BOP/ATC I Check AFW Status

__________1 1

1f-----+------I1r---.

Observes Total of all SG flow indicators IS NOT> 686 ...

9.Lpm CRS I Transition to ES-Q, 1 r----~i-----r-----------------------------------------------__1 i I Instructor May have to announce as STA that a Red Path on Heat Sink exists.

CRS I Transition to FR-H.1 due to loss of all AFW U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 15 of20

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: _1_ Event No.: ~

Event Descri Time Position Examinee's Actions or Behavior ATC Diagnose leak by from PORV 455C

Pressurizer PORV and Safety Acoustic Monitoring Annunciator

Pressurizer Relief Line High Temp Annunciator

Acoustic Monitor ATC Announce Closing Block Valve for PORV-455C then close the valve.

The CRS may direct closing the PORV Block Valve (535) before the A TC makes the above ATC Verify PORV Block Valve closed and leakage is stopped.

U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open - Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 16 of20

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: _1_ Event No.:...1

. t" Even t Descnpllon: Loss 0 f Hea t S*In k Time !

Position Examinee's Actions or Behavior CRS/ATC Determine if Heat Sink is required

Check RCS Pressure> any non-faulted SG pressure (Panel FBF/FDF)

Check RCS Temperature> 350°F {Panel FDF)

CRS/BOP Check if Bleed and Feed is required

Average of the 3 lowest wide range SG Levels < 20% (Panel SCF)

This is NOT ex~ected at this time CRS/BOP Prepare to establish AFW flow

Check SG Blowdown isolation and sample valves closed(Panel SCF)

Check CST Level> 3 Feet

Check valves CT-6 & 64 OQen (Panel SCF}

CRS/BOP Establish AFW Flow using Motor Driven Pumps

Check 480V power available Bus 3A or 6A energized

Check Motor Driven Pups both running 0 Start motor driven AFW Pumps

If unable to start either motor driven AFW Pump, 0 Close is SG Aux Feed Reg Valves (FCV-406A-406D) i 0 If both motor driven AFW pumps are unavailable Go to Attachment 2 for 32 Pump Operation CRS/BOP Determine that 32 AFW Pump is NOT available

Determine 32 AFW Pump NOT running (Tagged Out)

Determine 32 ABW Pump Ove-rspeed Trip Valve Closed alarm (Panel SKF) is actuated due to tag out I

Return to Prclcedure Section Step 5 CRS/ATC I Stop all RCPs I I CRS/ATC Try to establish Feedwater flow to any SG BOP

Check Condensate Pump Power Supplies Available i 0 6.9 k:V buses 1, 2, 4 energized (Panel SHF)

Go To Attachment 3 to establish feedwater from secondary source.

U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 17 of20

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: _1_ Event No.:

. Event Descrigtion: Loss of Heat Sink Time Position Examinee's Ac~tions or Behavior CRS/ATC Check if a low pressune water source is available BOP

Check any condensate pumps running (Panel SCF)

Check only one condensate pump running o Secure all by one condensate pump

Check MBFPs any running o Cannot Reset and Start 1 MBFP CRS/BOP Block Automatic SI Actuation

Check SI NOT Actuated

Place SI block key switches to DEFEAT (Panel SBF-2)

CRS/BOP ! Check Condensate Pump only feed source CRS/ATC Depressurize at least ONE SG to less than 380 psig to establish feed flow.

Manually dump steam using atmospherics from at least one SG at 110)1.11 num rate

. CRS/BOP Dispatch NPO to MBFP discharge valve breakers I--_ _-+-_ _ _-+-__._-"-R.::.::o:..:.:'e=-c' play Respond CiS NPO Standing By at MCC 36A and MCC 36B CRS/ATC Prepare to Align Flowpath BOP

Place MFRVs in manual and close (Panel FBF)

Ensure Bypass FRVs Closed (Panel FBF)

Place Feedwater Isolation Defeat key switches in DEFEAT o Obtain keys from key locker o 1/FW1DA (Rack G4) 1--_ _-1--_ _ _-1--_ _ _----'--0 1/FW1DB (Rack G-6)

CRS/ATC Reset SI BOP

Check SI Actuated

Check verification of SI Automatic Actions of step 2 - 12 of RO-1 completed o If BOP available perform steps 2 - 12 of RO-1 o Press both SI Reset buttons on panel SBF-2 I I o Check SI Reset - SI Actuated lights extinguished U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open - Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip - Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 18 of20

Appendix D Scenario Outline Form ES-D-1 i Op-Test No.: _1_ Scenario No.: _1_ Event No.:

Event )",,,,,..ri,r>tir\n* Loss of Heat Sink Time Position Examinee's Actions or Behavior CRS/ATC Establish Initial FW conditions BOP

Ensure Bypass Feedwater MOVs open BFD-IVIOV-90 BFD-MOV-90-4 (Panel SCF)

Ensure Main Feedwater MOVs Open BFD-MOV-5 BFD-MOV-5-4

Crack Open Bypass Feedwater FRVs o FCV-417L o FCV-427L o FCV-437L CRS/ATC Place Steam Flow and Feed Flow Recorders to NARROW

Steam Flow switches on FBF (Red)

Feed Flow switches on FBF CRS/ATC Align Feedwater Header

Manually close MBFP Recirc Valves

Align MBFP Discharge Valves o Open BFD-MOV-2-31/32 o When valves are Open. direct NPO to open discharge valve breakers on MCC 36A and MCC 36B

. Booth Operator Insert LOA-CFW066 and LOA-CFW067 to DEENERGIZE and valves ATC Control bypass feedwater FRVs to rapidly resptore at least one SG Narrow Range Level to > 9%

Control Low Flow Bypass valves Lead Examiner Terminate the Scenario when adequate feedwater flow is established.

U3 NRC Scenario I Power Reduction fro 100%,33 MFRV Fails Open Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 19 of20

Appendix 0 Scenario Outline Form ES-D-1 Post Scenario Event Classification Event Classification - Alert EAL 1.1.1 Failure of an Automatic trip signal to reduce power range < 5%

AND Manual Trip is successful NOTE: The following event classification is possible depending on plant conditions when scenario is terminated.

Event Classification - Site Area Emergency RED PATH in FO.3 Heat Sink AND Feed and Bleed is required.

U3 NRC Scenario 1 Power Reduction fro 100%,33 MFRV Fails Open ~ Manual Control Avail. NRHX Tube Leak, Loss Bus 3A, Generator Trip, Failure Auto Rx Trip Manual Trip Avail., 33 AFW pump failure, Loss of Heat Sink, PORV 455C Leaks requiring isolation.

Page 20 of20

Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 3 Scenario No.: __ 2_ Op-Test No.:_1 Examiners: Operators:

Initial Conditions:

Reset simulator to 9% Load Simulator Schedule-Scenari02 The Plant is in Mode 1 just above 9% power preparing to come on line.

Turnover:

Raise power to approximately 12% to place MTG in service. No equipment is out of service.

Event Malf. I Event Event No. No. I Type" Descri~tion 1 N!A R(ATC) Power ascension, maintain SG levels in manual.

N(CRS)

N(BOP) 2 MOC C(CRS) 31 CCW Pump trip with failure of 32 to auto start.

SWSOO7 C(BOP)

TS(CRS) 3 XMT- I(ALL) Controlling PZR Pressure transmitter fails high.

i RCS028

'A TS(CRS) 4 MOV C(CRS) FCV-625 spurious closure.

CCWOO I 8 C(BOP) 5 MAL M(ALL) Stearn leak in the Turbine Building leading to plant trip. 33 MSIV SGNOO5 fails to close.

6 BKR C(ALL) Entered at setup, Reactor Trip Breakers will not open causing PPLOO3! team to enter FR-S. 1.

4 7 MAL C(BOP) Entered at setup, AFVlI will not auto-start requiring manual action CFWOO1 in FR-S.1 AlC 8 RLY C(CRS) Entered at setup, SI does not automatically actuate. Manual PPL487!

C(BOP) l actuation will be required.

8

. (N)ormal, (Rleactivity, (llnstrument, (Clomponent. (MJalor U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.

Page 1 of 16

Session Outline:

The scenario begins with the plant at 9% power with no equipment is out of service. The team has been instructed to raise power to approximately 12% and place MTG in service.

After taking the watch, the crew will commence raising power. After the power escalation has progressed, 31 CCW Pump will trip and 32 CCW Pump will fail to auto-start. The team will start 32 CCW pump per ARP-010.

Following the restoration of CCW, a failure high of PT -465 will occur. The team will respond using AOP-INST-1 "Instrument or Controller Failures." The channel will be removed from service.

After the channel is removed from service, FCV-625 will go closed with no apparent reason. The team should respond per ARP-01 0 or AOP-UCCW-1 and re-open the valve. If the team elects to not re-open the valve, the scenario may continue.

Prior to completion of the Subsequent Actions of AOP-CCW-1, a steam break will occur in the turbine building. The team will attempt to manually trip the plant but the reactor trip breakers will not open.

The reactor will not trip from the Control Room and the team will respond per FR-S.1, "Response to Nuclear Power Generation I A TWS," and will shutdown the reactor by manually inserting control rods and initiating Emergency Boration. The reactor trip breakers will be locally opened after an NPO is dispatched. 33 MSIV will fail to close from the control switches. The Team will also determine that SI did not automatically actuate and must manually actuate SI.

The team will proceed through FR-S.1 until transition to E-O, "Reactor Trip or Safety Injection."

After the transition to E-O is made, the team will determine that three SGs are intact and 33 SG is faulted. The team will transition to E-2, Faulted Steam Generator Isolation and isolate 33 SG.

At this point critical tasks are demonstrated and the scenario is terminated or continue to observe progression toward SI termination.

Procedure flow path: POP-1.3, ARP-010, AOP-I NST-1, ARP-01 0/AOP-UCCW-1 , AOP-UC-1 ,

E-O, FR-S.1, E-O, E-2, E-1, ES-1.1 Critical Tasks:

CT-1 Insert negative reactivity into the core by at least one of the following methods before completing FR-S.1 step 4:

De-energize the control rod drive MG sets

Place rod control in manual and insert RCCAs

Establish emergency boration flow to the RGS.

CT-2 Establish at least 686 gpm AFW flow to the SGs before completion of FR-S.1 step 3.

CT-3 Manually actuate at least one train of SIS actuated safeguards before completion of E-O step 4.

U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCY-625 Closure, Steam Line Rupture, ATWS, Faulted SG.

Page 2 of 16

Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES IC Reset I Use IC for NRC Scenario 2 ; Reset Simulator to 9% power Ie i i 9% Power Starting Up SES Setup Run Schedule and verify Loads Reactor Trip Breaker malfunction Schedule malfunctions and over-rides Loads Auto SI Failure have been entered Loads MS Isolation failure Carefully walk boards and Loads 32 CCW Pump Autostart failure check for items like Turbine Loads 31/33 AFW Pumps Autostart failures and FWH alarms that may be Loads 31 CCW Pump failure on Trigger 1 distractions to candidates. Loads PT-455 failure on Trigger 2 Loads FCV-625 failure on Trigger 3 I

! Loads Turbine Hall Steam Leak on Trigger 4 Floor Setup Perform setup checklist Event 1 Respond as requested by Crew performs power ascension Crew !

Event 2 Actuate Trigger 2 when When directed by the Lead Evaluator, directed activate Trigger 2 to cause 31 CCW Pump to trip.

MAL-CCW001A to TRIP Role Play If called to check 31 and 32 31 CCW Pump Motor has slight acrid odor.

CCW Pumps Breaker tripped on over-current. The pump that was started is operating with no issues .

I

. 32 CCW Pump, Motor, and Breaker all

---=--.. a~~ear normal Event 3 Actuate Trigger 3 when When directed by the Lead Evaluator, directed activate Trigger 3 to cause PT -455 to fail high with a 60 second ramp.

MAL-PRS005A to 2500 with 60s ramp Role Play If I&C is contacted about Report back that a troubleshooting package PT-455 failure will be prepared Event 4 Actuate Trigger 4 When directed by the Lead Evaluator, activate Trigger 4 to FCV-625 to fail closed.

At lead evaluator direction SWI-CCW010C to On Role Play When Nuclear NPO Nuke NPO reports that flow at FIC-625 is dispatched normal after valve is re-opened.

i i U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.

Page 3 of 16

Simulator Setup and Instructor Directions II Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSEIINSTRUCTOR CUES .

EventS Actuate Trigger 5 When directed by the Lead Evaluator, activate Trigger 5:

At lead evaluator Insert MAL-MSS009A to 6650000 in 600

. direction Role Play If NPO dispatched to look Ilf NPOs are dispatched to look for steam, for steam leak report back that a large steam leak exists at the north end of the turbine hall.

Role Play NPO cannot locally trip If trigger does not work, remove overrides reactor until Emergency preventing reactor trip. May have to insert Boration is commenced. manual reactor trip Remove MAL-RPS002B Actuate Trigger 30 to trip I reactor.

i III U3 NRC 2013 Scenario 2: Power escalation trom 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted sa.

Page 4 of 16

_A--'-p......

p_en_d_i_x_D______R_e_qcL-u_i_re_d_O _____p_e_ra_t_o~r_A_c_ti_o__n_s_ _ _ _ Form ES-D-2 Op-Test No.: _1_ Scenario No.: Event No.: _1_ Page_1_of Event

Description:

Power Ascension Time Position Applicant's Actions or Behavior Note:

The reactivity plan for the power ascension should be developed by team in briefing room prior to taking the watch. The plan could call for dilution and/or rod withdrawal.

CRS Assigns roles for power ascension ATC Reviews reactivity plan ATC If rods are withdrawn:

Placeslverifies rods are in Manual

Withdraws rods

Observes:

0 Proper rod motion 0 Tavg 0 Power BOP Peer checks rod withdrawal ATC If dilution is performed:

Places RCS Makeup control to Stop

Place RCS Makeup Mode selector to Dilute

Adjusts integrator to desired dilution amount

Places RCS Makeup control to Start

Observes:

0 Proper makeup response 0 Tavg 0 Power BOP Peer check dilution Adjust Low Flow Feed Reg Valves to maintain SG levels.

U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.

Page 5 of 16

Appendix 0 ____ Required Operator Actions Form ES-O-2 Lead Evaluator When the following has been demonstrated/observed:

Sufficient load ascension.

Sufficil9nt normal plant operations by the BOP.

Then instruct Booth to insert Event 2.

U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, A TWS, Faulted SG.

Page 6 of 16

Appenc:t_ix_D_ ______R_e~q'_u_ir_e_d_O_'p'_e_r_a_to_r_A_c_t_io._n_s____ Form ES-D-2 Op-Test No.: _1_ Scenario No.:..1..- Event No.: ..1..- Page _1_of ..1 Event

Description:

31 CCW Pump trip Time Position Applicant's Actions or Behavior BOP Observes CCW Pump Discharge Alarms and only 33 CCW Pump running BOP Recommends/announces starting 32 CCW Pump BOP May refers to ARP 3-ARP-10 CRS Concurs with recommendation or orders 32 CCW Pump start BOP Starts 32 CCW Pump CRS May enter AOP-CCW-1 CRS Refers to T.S. 3.7.8 and TRM 3.7.B and determines plant is in a 30 Day AOT Lead Evaluator After CRS has evaluated TRMnrS. have Booth initiate Event 3 U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV -625 Closure, Steam Line Rupture, ATWS, Faulted SG.

Page 7 ofl6

_A--,-p.L-p_e_"d_i_x_D_ _ _~__R~equired Operat_o_r_A_c_t_io<_"_s______ F_o_rm_E__S_-_D_-2_

Op-Test No.: _1_ Scenario No.: ~ Event No.: ~ Page_1_of .2.

Event

Description:

Controlling PZR Pressure transmitter fails high I

Time Position Applicant's Actions or Behavior BOP Notes PZR High Pressure Channel Trip and PZR High Pressure alarms ATC Diagnose PZR Pressure instrument failure based on above and Spray Valves opening Announces and places Master Pressure Controller in Manual CRS Instructs team to perform immediate operator actions of AOP-INST-1 ATC Checks all instrumentation listed in AOP-INST-1 for failures Announces immediate operator actions complete CRS Announces entry into AOP-INST-1 Re-checks all instrumentation with ATC Verifies PZR pressure is in Manual CRS Directs BOP to defeat PT-455 in pressure control circuit and delta-t circuit BOP In Rack B-6 places P/455A in Defeat 1 & 4 BOP In Rack B-8 places T/4111 A in Defeat Loop 1 ATC Switches recorder to an operable channel ATC Returns Master Pressure Controller to Auto CRS Refers to T. S.

Table 3.3.1-1 Function 5 and 7 Table 3.3.2-1 Function 1d and l Determines in 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AOT to trip bistables May have T.S. condition due to low PZR Pressure 3.4.1 Condition A Lead Evaluator Bistables do not have to be tripped. When T.S. evaluated instruct Booth to insert Event 4 U3 NRC 2013 Scenario 2: Power escalation trom 9%, CCW Pump Trip, PT-455 Failure, FCY -625 Closure, Steam Line Rupture, ATWS, Faulted SG.

Page 8 of 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: ~ Event No.: Page~of .2 Event

Description:

FCV-625 spurious closure Time Position A~~licant's Actions or Behavior BOP Notes CCW Thermal Barrier Return Low Flow alarm BOP Observes FCV-625 has gone closed BOP Refers to ARP-010 CRS May enter AOP-LlCCW-1 Note:

CRS should determine based on ARP ,guidance and indications that the closure was spurious and re-opening the valve is appropriclte, or the CRS will enter AOP-LICCW-1 and reopen the valve. If the valve remains closed, the scenario can continue.

BOP Re-open FCV-625 BOP Direct Nuke NPO to monitor flow at FI-625 Lead Evaluator When valve is re-opened, or it is clear it will remain closed, instruct Booth to initiate Event 5.

U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.

Page 9 of 16

Appendix 0 Required 9perator Actions Form ES-D-2 Op-Test No.: Scenario No.: Event No.: ~ Page _i_of ..1 Event

Description:

Steam leak in the Turbine Building leading to plant trip.

I~ Position I Applicant's Actions or Behavior ATC Diagnose Steam Leak:

Power increase

Tavg decrease

Steam Flow increase

SG Level increase CRS Implements AOP-UC-1 Directs crew to:

Trip Reactor (Reactor does not trip)

Close MSIVs (33 MSIV will not go closed)

Go to E-O Proceed to Event 6 when CRS gives order to trip reactor U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCY-62S Closure, Steam Line Rupture, ATWS, Faulted SO.

Page 10 of 16

Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: L Event No.: 6/7 Page _1_of .1 Event

Description:

Entered at setup, Reactor Trip Breakers will not open causing team to enter 2-FR S. 1. Entered at set AFW will not auto-start manual action in FR-S.1 Time Position icant's Actions or Behavior ATe reactor BOPIATe Will attempt to trip reactor using b/u button BOP Start 31 and 33 or 32 AFW Pumps establish 686 gpm BOPIATe Initiate Emer!Jency Boration:

Verify Charging Pump running

Open MOV-333

Close HCV-104/105

Place both boric acid pumps in high speed and restart

Place Charging Pump in manual

Maximize charging pump speed At this point the Booth will trip the reactor locally.

U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCY-625 Closure, Steam Line Rupture, ATWS, Faulted SG.

Page 1 I of 16

_A~pl.'-pe-,--n-,--d-,--i_x-,--O,--_____Req ui red Operator Actions Form ES-O-2 Note:

At this point or prior, the crew may attempt to close MSIVs. When 33 MSIV does not close, AFW should be secured to 33 SG. Also with the reactor tripped, the crew may back down on AFW flow.

Op-Test No.: Scenario No.: -L Event No.: .JL. Page_1_of A Event

Description:

Entered at setup, SI does not automatically actuate. Manual actuation will be required.

Position nt's Actions or Behavior CRS/ATC Recognize that SI should have actuated and is needed for Steamline delta-p ATC/BOP Manually actuate SI ATC May restart charging pump BOP Perform Steps 35-42 of E-O:

Verify SI Pumps Running

Verify Fan Cooler Units Running, place dampers in SI position

Open SW valves for Containment Cooling

Check Status of SI Valves, AFW, CCW, ESW, CIVs ATC Verifies reactor trip:

Reactor trip breakers open

Neutron flux decreasing

Rod bottom lights lit

IRPls all < 20 Steps U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV -625 Closure, Steam Line Rupture, ATWS, Faulted so.

Page 12 of 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: -L Event No.: -1L Page-Lof .A Event

Description:

Entered at setup, SI does not automatically actuate. Manual actuation will be required.

CRS/ATC Secure Emergency Boration

Close MOV-333

Place BATPs in slow i

Open HCV-1 04/1 05 to 25%

CRS/ATC Check RCP Seal Cooling (if charging was not started and FCV-625 was left closed, RCPs may be tripped at this point)

CRS/ATC Restore charging flow CRSI Verify SDM With SI, this is not necessary, but the team may start a boration CRS Transition to E-O ATC Verifies Reactor Trip: (Panel FCF)

Reactor trip and bypass breakers open

Rod bottom lights lit

IRPls < 20 steps ATC Verifies Turbine Trip by observing stop valves closed (Panel FAF)

BOP Check status of 480V buses (Panel SHF)

Observe ALL busses energized from Offsite Power ATC Check SI status Determine SI is Actuated

Any 81 Annunciator - Lit (Panel FDF)

SI Pumps Any Runnin!~ (Panel SBF-1, SBF-2)

ATC/BOP Manually Actuates SI I

U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.

Page 13 of 16

Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: _1_ Scenario No.: Event No.: Page~of ...4 Event

Description:

Entered at setup, SI does not automatically actuate. Manual actuation will be required.

BOP/ATC Check AFW Status Observes Total of all SG flow indicators> 365 gpm (Panel SCF)

Controls feed flow to maintain SG leve!s 9 - 50%

Adjust flow control valve potentiometers CRS Direct BOP to perform RO-1 BOP Operator Actions during use of EOPs ATC Verify Feedwater Isolation

Check Main Boiler Feed Pumps Tripped (Panel FAF)

Check MBFP Discharg43 Valves Closed (Panel FAF)

Check Feed Reg Valves and Bypasses Closedllsolated o Main and Bypass MOVs Closed (Panel SCF) o Main FRVs 2 is True (Panel SNF) o Bypass FRVs (Panel FAF)

ATC Check Blowdown Isolation Valves Closed (Panel SCF)

ATC Verify SI Flow

Check Pressure < 1700 psig (Panel FBF, or FDF)

Check High Head Pump Flow Indicators (Panel SBF-2)

Checl< Pressure < 360 psig (Panel FDF WR Press Recorder)

Checl< RHR Pumps Flow Indicators (Panel SBF-2_

ATC Verify Containment Spray NOT required

Check Containment Pressure remained < 22 psig (Panel J01 or SBF-2)

ATC Check RCP Seal Cooling

Bearing Coolant Low Flow Alarm Clear (Panel SGF)

Thermal Barrier CCW Header Low Flow alarm Clear (Panel SGF)

ATC Establish Charging Flow U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.

Page 14 of 16

Appendix 0 Required Operator Actions Form ES-O-2 ATC Check RCS Temperature ATC Check if RCPs should be stopped. RCPs may have been secured earlier.

They will not be tripped at this step.

ATC Check PORVs, Safety Valves, Sprays Closed Op-Test No.: _1_ Scenario No.: ~ Event No.: Page~of.A Event

Description:

Entered at setup, SI does not automatically actuate. Manual actuation will be required.

c~~ Determine 33 SG is faulted CRS Announce entry into E-2 NOTE:

E-2 contains the first specific steps to close MSIVs and isolate AFW flow to faulted SG.

However, there is administrative guidance to take these actions ahead of E-2 steps. It is expected that these actions would have been taken either in FR-S.1 after the reactor being tripped locally or in E-O. If these actions have not been taken at this point, the scenario may continue to allow the team to take actions per E-2.

Lead Evaluator Team should be able to quickly progress through E-2 and transition to E-1.

Foldout criteria for SI Terminati()n will be met and should be recognized.

Terminate scenario when team announces or is showing progress toward SI Termination.

U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCV-625 Closure, Steam Line Rupture, ATWS, Faulted SG.

Page 15 of 16

Post Scenario Event Classification Event Classification - Site Area EmergencyAlert EAL 1.1.2 RED path in Subcriticality and all attempts at tripping the reactor from the control room have failed to reduce power range <

U3 NRC 2013 Scenario 2: Power escalation from 9%, CCW Pump Trip, PT-455 Failure, FCY -625 Closure, Steam Line Rupture, ATWS, Faulted SG.

Page 16 of 16

Appendix D Scenario Outline Form ES-D-1 Facility: IPEC Unit 3 Scenario No.: 3 Op-Test No.: . 1 Examiners: Operators:

Initial Conditions: 50% Power IC-153 PORV 455C Leaks by seat - Block Valve 535 is closed Turnover:

Raise Power to 100%.

Event Malf. No. Event Event*

No. Type" Description R (ATC) 1 N/A N (CRS) Power Increase N (BOP)

I (ALL) 2 MAL TS (CRS) Controlling Pressurizer Level Channel fails low PRS006 B

C (ATC) 3 MAL PORV 456 leaks by seat. Close PORV Block Valve.

C (CRS)

PRS003 0

I (ALL) 4 MAL PT-4'12B failure causing AMSAC to be inoperable and requiring TS (CRS)

TUR010 tripping of bistables I B M (ALL) 5 MAL Loop Flow Transmitter penetration failure (SBLOCA)

RCS017 A

C (BOP) 6 MAL 31 AFW Pump Trip C (CRS)

CFW001 A

7 MAL M (ALL) SG Tube Leak to Rupture 32 SG SGN005 B

8 SWI IA-PCV-1228 Instrumemt Air to Containment Fails to Open C (ALL)

AIR002C

(N)ormal. (R)eactivity. (I)nstrument. {C}omeonent, {M~ajor U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 1 of33

Appendix D Scenario Outline Session Outline:

The evaluation begins with power is at 50% steady state. The crew will be directed to raise power to 100%.

After adequate power change has occurred, Pressurizer Level Channel LT-460 will fail low resulting in a loss of letdown. The crew will respond in accordance with 3-AOP-INST-1, Instrument and Controller Failures. The procedure will address both the instrumentationrrech Spec actions and restoration of charging and letdown. This is a Tech Spec for Instrumentation.

At lead examiner discretion, Pressurizer PORV 456 will start to leak past seat. The crew will attempt to close the PORV which will not be successful. The crew will then close the motor operated block valve At lead examiner discretion, PT-412B will fail low requiring bypassing AM SAC and tripping bistables. This is a Tech Spec for Instrumentation.

At lead examiner discretion, 31 Loop Flow Transmitter Penetration will fail resulting in a small break LOCA. The crew may respond using 3-AOP-LEAK-1. The crew will likely trip the reactor and manually actuate Safety Injection.

Following the Safety Injection 31 AFW pump will trip on overcurrent. This will require the crew to start 32 AFW pump to supply flow to 31 and 32 SG.

The crew will proceed through E-O to E-1. When the crew enters E-1 a SGTR will occur in 32 SG. The crew will transition to E-3 when diagnostic check for SGTR or on Foldout page based on uncontrolled level increase.

The crew will perform actions in E-3. After the cooldown, the crew will not be able to use normal spray to depressurize the RCS. The crew will depressurize the RCS using the PORV. After depressurization actions the procedure checks SI Termination Criteria and this will not be met (RCS pressure will not be stable or increasing) and transition to ECA-3.1due to LOCA with SGTR.

The scenario will be terminated when the team demonstrates they control plant Cooldown or at the lead examiners discretion.

Procedure Flowpath: POP-2.1, AOP-INST-1, ARP-FAF, AOP-INST-1, AOP-LEAK-1, E-O, E-1, E-3, ECA-3.1 Critical Tasks:

CT-1 E-O-M Close block MOV upstream of stuck-open PZR PORV by completion of the first step in the ERG network that directs the! crew to close the block valve.

CT-2 Isolate feed to 32 SG prior to completion of E-3 Step 3.

CT-3 Initiate RCS Cooldown of <100 °F/hr to prevent SG overfill in ECA-3.1 U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 2 of33

Appendix 0 Scenario Outline Form ES-O-1 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES IC Reset I Reset Simulator to IC-153 SES Setup Insert malfunction MAL PRESSURIZER LEVEL CHANNEL 460 FAILURE Schedule PRS006B to 0 on event 2 Insert malfunction MAL PRESSURIZER RELIEF VALVE 456 VALVE PRS003D to 10.00000 in 60 on POSITION FAILURE event 3 Insert malfunction MAL TURB FIRST-STAGE PRESS TRANS FAILURE TUR010B to 200.24899 on event (PT-4128) 4 Insert malfunction MAL FAILURE OF FLOW TAP PENETRATION FT-414 RCS017A on event 5 Insert malfunction MAL AUXILIARY FEEDWATER PUMP 31 FAILURES CFW001A to TRIP on Insert malfunction MAL STEAM GENERATOR 32 TUBE LEAK SGN005B to 10.00000 on event 7

Insert override SWI-AIR002C to PCV-1228 OPEN POS INSTRUMENT AIR ISOL Off on event 30 VLV NO. PCV-1228 CONTROL SWITCH Create Event 30 JPPLP4(1)==1 i Actuate Trigger 30 when the Reactor Trips (which

-desc Set Trigger 30 to actuate I will then prevent 1228 from opening when attempted) after Reactor Trip SES Setup Load Schedule and verify Schedule malfunctions and overrides have been entered Floor Setup Perform Setup Checklist Hang CTO on PORV Block Valve 535 Close PORV Block Valve and hang CTO Risk IS Green Event 1 i Respond as requested by the Crew performs power ascension I crew

p---------~--------=-----------~------------=-------------------~I I Event 2 Actuate Trigger 2 AL PRS006B LT -460 fails low isolating etdown Role Play Acknowledge requests for I&C will develop a troubleshooting plan I&C to troubleshoot Event 3 Activate trigger 3 L-PRS003D PORV 456 starts to leak by.

ole Play Respond as requested by the crew U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 3 of33

Appendix D Scenario Outline Form ES-D-1 Event 4 Activate trigger 4 I .. AI TUR10B PT-412B Fails low.

0",1",

,,, 01 ... Respond as requested by the crew Activate Trigger S MAL-RCS017A Failure of ReS flow tap. This is II a small LOCA.

'J Respond as requested by the crew Loaded at setup MAL-CFW001A Trip of 31 AFW Pump

'VI..... I ... Y Respond as requested by the crew Event 7 Activate Trigger 7 MAL-SGNOOSB Tube rupture in 32 SG Role Play Respond as requested by the crew U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 4 of33

Appendix 0 Scenario Outline Form ES*D*1 Op-Test No.: _1_ Scenario No.: L Event No.: _1_

Event

Description:

Power Escalation Time Position Applicant's Actions or Behavior Note:

The reactivity plan for the power ascension should be developed by the team in the briefing room prior to takin, the watch. The plan could call for dilution and/or rod withdrawal CRS Assigns roles for power ascension Reviews reactivity plan ATC If rods are withdrawn:

Places/verifies rods are in Manual

Withdraws rods

Observes:

o Proper rod motion o Tavg o Power BOP Peer checks rod withdrawal ATC If dilution is performed:

Places RCS Makeup control to Stop

Place RCS Makeup Mode selector to Dilute

Adjusts integrator to desired dilution amount

Places RCS Makeup control to Start

Observes:

o Proper makeup response o Tavg o Power BOP Peer check dilution U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 5 of33

Appendix 0 Scenario Outline Form ES-O-1 ATC/BOP Initiate Turbine Load Increase at desired rate

Governor (Preferred)

Load Limit 1

Load Limit 2 Lead Evaluator When the following has been demonstrated/observed:

Sufficient load ascension.

i

Sufficient normal plant operations by the BOP.

Then instruct Booth to insert Event 2.

U3 NRC Scenario 3 Power increase from 50%,L T-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 6 of33

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: L Event

Description:

Failure of Pressurizer Controlling Level Channel Time Position Examinee's Actions or Behavior ATC/BOP Diagnose Failure of LT-460 ATC Place 33 charging pump in Manual and stabilize pressurizer level.

CRS Direct Perform Immediate Operator Actions of AOP-INST-1 ATC Silently evaluates for failure of control system inputs

Rod Control 0 NIS Power Range 0 RCS Temp 0 Turbine 1sl Stage Pressure

Pressurizer Pressure

Pressurizer Level Control 0 RCS Temperature

MBFP Speed Control 0 Suction Pressure 0 Discharge Pressure 0 Steam Header Pressure

SG Level Control 0 Steam Pressure 0 Stearn Flow 0 Feedwater Flow

SG Pressure Control 0 Atmospheric Steam Dumps 0 High Pressure Steam Dum~s CRS/ATC Enter AOP-INST-1 and Re-perform IOAs verbalizing each input U3 NRC Scenario 3 Power increase from 50%,LT *460 fails low Restore Letdown; POR V 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 70f33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: --L Event

Description:

Failure of Pressurizer Controlling Level Channel Time Position Examinee's Actions or Behavior CRS/ATC Determine an Instrument failure has occurred.

CRS Identify section 4.105 of procedure CRS/ATC Determine the charging pump is in manual speed controlling pressurizer level in accordance with Graph RCS-2 CRS/ATC Determine channel has failed low CRS/BOP Place Ll460A LEVEL DEFEAT switch in DEFEAT CH 2 (RACK B-6 CRS/BOP Determine Letdown is isolated (LCV-459 is closed) (Panel SF F)

CRS/BOP Close Orifice Isolation Valve (CH-AOV**200 A - C) (Panel SFF)

CRS/BOP Place CH-PCV-135 Controller in MAN and adjust output to 50% (Panel SFF)

CRS/BOP Place AC-TCV-130 Controller in MAN and adjust output to 50% (Panel SFF)

CRS/BOP Determine CH-AOV-201 and 202 are OPEN (Panel SFF)

CRS/BOP Determine CH-LCV-459 is closed and OPEN CH-AOV-459 and return to AUTO (Panel SFF)

CRS/BOP Open ONE Orifice Isolation Valve (Panel SFF)

CH-AOV-200A

CH-AOV-200B

CH-AOV-200C BOP/ATC Coordinate to adjust charging flow as necessary

Charging pump speed (Panel FBF)

Open HCV-142(Panel SFF)

Close CH-409 {Local Action)

U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 8 of33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: ~

Event

Description:

Failure of Pressurizer Controlling Level Channel Time Position Examinee's Actions or Behavior CRS/BOP Adjust CH-PCV-135 as necessary to prevent flashing in the letdown line (Throttle closed to raise pressure to approximately 250 psig (Panel SF F)

CRS/BOP Adjust AC-TCV-130 as necessary to maintain letdown temperature 100-130°F CRSIATC I Place Modulating Heater SWITch to off for 5 seconds then Start and retu rn to AUTO CRS/ATC Place control switch for Pressurizer Backup Heaters to OFF for 5 seconds then return to auto.

CRS/ATC Place one set of Backup Heaters to ON. NOTE: Heaters were in ON for dilution for power ascension. Crew may return all heaters to ON.

CRS/ATC Determine if Pressurizer Level Recorder is selected to a Non-Affected Channel and select an operable channel if necessary CRS Refer to Technical Specifications CRS Determines 0 TS 3.3.1-1 Function 8 AOT -SHours 0 TS 3.3.3-1 Function 12 AOT 30 days 0 TS Basis 3.3.4 0 TRO 3.3.0.1 AOT 30 Days CRS/BOP Determine that NO redundant Bistable Status Lights are illuminated (Panel SO F)

CRS/BOP Trip Bistables for LT-460 Rack White A-10 Bistable LOOP 2, High Level CRS/BOP Check Bistable Status Light for failed instrument illuminated Lead Examiner Instruct the Booth to insert Event 3 Tripping bistable has no impact on the remainder of the scenario. Once Letdown is restore, the scenario can proceed.

U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 9 of33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: Event No.:

Event on: PORV 456 Leaks seat Time Position Examinee's Actions or Behavior ATC Diagnose leak by from PORV 456

Pressurizer PORV and Safety Acoustic Monitoring Annunciator

Pressurizer R.elief Line High TE~mp Annunciator

Acoustic Monitor ATC . Announce Closing Block Valve for PORV-455C then close the valve.

The CRS may direct closing the PORV Block Valve (536) before the A TC makes the above announcement ATC Verify PORV Block Vi31ve closed and leakage is stopped.

NOTE: The crew may determine that the PORV is inoperable because it will NOT close. If this occurs, the crew will:

ATC Close associated Block Valve (This should already be done)

BOP . Remove power from associated block valve (Remove fuses located inside the Flight I Panel)

CRS/BOP Direct NPO to de-energize Block Valve 536 on MCC-36A Booth Operator Insert Overrides to !;imulate de-energizing Block Valve 536 SWI-RCS024A to OFF SWI-RCS024B to OFF

SWI RCS024C to ON I

NOTE: The crew may determine that the PORV is inoperable because it will NOT close. If this occurs, the crew will U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-4128 failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 100f33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: l Event No.: ~

Event

Description:

Turbine First StaQe Pressure Transmitter Failure Low Time Position Examinee's Actions or Behavior ATC/BOP Diagnose Failure of PT-412B CRS Direct Perform Immediate Operator Actions of AOP-INST-1 ATC Silently evaluates for failure of control system inputs

Rod Control o NIS Power Range oRCS Temp st o Turbine 1 Stage Pressure

Pressurizer Pressure

Pressurizer L'9vel Control oRCS Temperature

MBFP Speed Control o Suction Pressure o Discharge Pressure o Stearn Header Pressure

SG Level Control o Steam Pressure o Stearn Flow o Feedwater Flow

SG Pressure Control o Atmospheric Steam Dumps o High Pressure SteamJJ~s CRS/ATC Enter AOP-INST-1 and Re-perform IOAs verbalizing each input CRS/ATC Determine an Instrument failure has occurred.

CRS Identify section 4.172 of procedure U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page II of33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: ...l... Event No.: ~

Event

Description:

Turbine First Stage Pressure Transmitter Failure Low Time Position Examinee's Actions or Behavior CRS/ATC Determine Channel A has NOT failed.

CRS/ATC Check Steam Dumps NOT in Pressure Mode Place Steam Dumps in Pressure Mode

Place Steam Dump Controller in Manual (Panel FCF)

Adjust Steam Dump Controller output to 0%

Place Steam Dump Control Switch to RESET and return to PRESS CONT

Place Steam Dum~ Controller in AUTO CRS/BOP Place BS/2MSS 400 block switch in AMSAC cabinet to BYPASS (LIP) position to block AMSAC system CRS Refer to Technical Specifications 0 TS 3.3.1-1 Function 17b Completion Time 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0 TS 3.3.1.1 Function 17e Completion Time 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0 TS 3.3.2-1 Function 19 AOT 6 Hours 0 TS 3.3.2-1 Function 4d AOT 6Hours 0 TS 3.3.2-1 Function 4e AOT 6Hours CRS/BOP Determine that NO redundant Bistable Status Lights are illuminated (Panel SO F)

CRS/BOP Trip Bistables for PT-412B

Rack White A-8 Bistable LOOP 2B, High SF SI

Rack White A-8 Bistable LOOP 4B, High SF SI

Rack White A-9 Bistable LOOP 1B, High SF SI

Rack White A-9 Bistable LOOP 3B, High SF SI CRS/BOP Check Bistable Status Light for failed instrument illuminated Lead Examiner Instruct the Booth to insert Event 5 Tripping bistable has no impact on the remainder of the scenario.

U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-4128 failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 12 of33

Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: L Event No.: .JL i

Event

Description:

RSC Leak/Small Break LOCA Time Position Examinee's Actions or Behavior ATC Diagnose RCS Leak

Decreasing Pressurizer Level and Pressure (Panel FBF)

PRZR LOW PRESSURE Annunciator

PRZR LOW l.EVEL Annunciator

VC SUMP PUMP RUNNING Annunciator I

C.B. COOLER COND HIGH LE:VEL Annunciator jl CRS Enter AOP-LEAK-1 CRS/ATC If At Any Time step to Isolate Leak if location is known. Determines location of leak is NOT know BOP CRS/BOP Determine plant is NOT on RHR cooling CRS/ATC If At Any Time Step to Trip the Reactor and Initiate SI if Pressurizer Pressure decreases to :s; 1930 psig.

Evaluate RCS Pressure - If < 1930

Trip the Reactor

Verify Reactor Tripped

Manually Actuate SI

Go To E-O CRS/ATC If At Any Time Step to Trip the Reactor and Initiate SI if Pressurizer Level cannot be maintained with 2 charging pumps in service and letdown flow at 45 gpm or < 14%

Evaluate PRZR Level- If conditions an~ satisfied

Trip the Reactor

Verify Reactor Tripped

Manually Actuate SI i

Go To E-O CRS/ATC As necessary:

BOP

Increase Charging Pump Speed nd

Start 2 Charging Pump

Reduce Letdown to 45 g~m CRS/ATC Determine there is NO PORV leakage.

U3 NRC Scenario 3 Power increase from 50%,LT -460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 13 of33

Appendix 0 Scenario Outline Form ES*D*1

=

CRS/ATC Determine there is NO indication of Safe~ Valve Leakage CRS/ATC Determine leak is too large. Direct Reactor Trip and Safety Injection.

U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low R,:!store Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 14 of33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: L Event No.: L Event

Description:

Reactor Trip and Safety Injection Time Position Examinee's Actions or Behavior CRS When Unit trips, direct team to perform immediate actions of E-O

Verifies immediate actions using the procedure.

When the CRS directs "Perform the ImmE!diate Operator Actions of E-O, the ATC and BOP will first perform the IOAs silently only announcing unexpected conditions. The crew will then re-perform the IOAs verbalizim each item.

ATC Verifies Reactor Trip: (Panel FCF)

Reactor trip and bypass breakers open

Rod bottom lights lit

IRPls < 20 steps I

Nuclear flux decreasing ATC Verifies Turbine Trip by observing stoe valves closed (Panel FAF)

BOP Check status of 480V buses (Panel SHF)

Observe ALL busses energized from Offsite Power ATC Check SI status

, Determine SI is Actuated

Any SI Annunciator - Lit (Panel FDF)

SI Pumps Any Running (Panel SBF-1, SBF-2)

ATC/BOP Manually Actuates SI

Depresses SI Actuation eushbutton (Panel SBF)

BOP/ATC Check AFW Status Observes Total of all SG flow indicators> 365 gpm (Panel SCF)

Controls feed flow to maintain SG levels 9 - 50%

Adjust flow control valve potentiometers CRS Direct BOP to perform RO-1 BOP Operator Actions during use of EOPs U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 15 of33

Appendix D Scenario Outline Form ES*D*1 Op-Test No.: _1_ Scenario No.: Event No.: L Event

Description:

Reactor Trip and Safety Injection II ,.:_

Position Examinee's Actions or Behavior ATC Verify Feedwater Isolation

Check Main Boiler Feed Pumps Tripped (Panel FAF)

Check MBFP Discharge Valves Closed (Panel FAF)

Check Feed Reg Valves and Bypasses Closed/Isolated 0 Main and Bypass MOVs Closed (Panel SCF) 0 Main FRVs 2 is True (Panel SNF) 0 Bypass FRVs (panel FAF}

ATC Check Blowdown Isolation Valves Closed (panel SCF}

ATC Verify SI Flow

Check Pressure < 1700 psig (Panel FBF, or FDF)

Check High Head Pump Flow Indicators (Panel SBF-2)

Check Pressure < 360 psig (Panel FDF WR Press Recorder)

ATC Verify Containment Spray NOT required

Check Containment Pressure remained < 22 psig (Panel J01 or SBF-2)

ATC Check RCP Seal Cooling

Bearing Coolant Low Flow Alarm Clear (Panel SGF)

Thermal Barrier CCW Header Low Flow alarm Clear (Panel SGF)

ATC Establish Charging Flow

Check RCS Pressure> 360 psig (Panel FDF WR Recorder)

Check CCW Available (Panel SBF-1 lights only this is adequate; Panel SGF Breakers & Flow indicators)

Check HCV 142 Fully Open (Panel SFF)

Check CH-AOV-204B Open (Panel SFF)

Open CH-LCV-112B (Panel SFF)

Then Close CH-LCV-112C (Panels SFF)

Set Speed Controller to Starting Position (Panel FBF)

Start 1 Charging Pump (Panel FBF)

Adjust Speed for Minimum Seal Injection (Panel SAF)

U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 16 of33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: L Event No.: L

Event

Description:

Reactor Trip and Safety Injection I Time POSITIon I Examinee's Actions or Behavior ATC Check RCS Average Temperature

Any RCPs Running - Tavg Trending to 54rF (Panel FDF)

No RCPs running - Tcold Trending to 547°F (Panel FDF)

If Temp < 547 0 and decreasing 0 Stop Dumping Steam 0 Control Total Feed Flow 0 Maintain> 365 until one SG > 9%

0 If cool down continues, Close MSIVS

If Temp > 547<' and increasing 0 Dump steam to condenser I 0 Dump Steam using Atmospherics ATC Check if RCPs should be stopped

At least 1 HHSI Pump running (Panel SBF-2)

Subcooling < value in table (QSPDS Monitor on desk)

Stop All RCPs ATC Check PORVs Closed (Panel FCF)

Check Safety Valves Closed

Tailpipe Temperatures Normal (Panel FBF)

Acoustic Monitors Normal (Above Door into Supervisory Panel)

Spray Valves Closed (panel FBF)

Check Aux Spray Valve Closed Panel (Panel SFF)

ATC Determine if SGs are Faulted

Any SG Pressure decreasing in uncontrolled manner (Panel FBF)

Any SG Completely depressurized (Panel FBF)

ATC Determine if SG Tubes are Ruptured

Condenser Air Ejector Radiation recorder Trend (Rad Monitor Rack)

SG Blowdown Recorder Trend (Rad Monitor Rack)

Main Steam Line Radiation Recorders (Rack D-3 behind the Flight Panel)

Any SG level increasing in an uncontrolled manner (Panel FBF)

U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 17 of33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: EventNo*:L Event

Description:

Reactor Trip and Safety Injection Time Position Examinee's Actions or Behavior ATC Check if RCS is intact

Containment Pressure Normal (Panel J-O or SBF-1)

Containment Sump Level Normal (Panel J-O)

Containment Radiation Normal 0 R-2 and R-7(Rack 0-1 Behind Flight Panel) 0 R-25 and R-26 CRS Go To E-1 Booth Operator When crew enters E-1 Activate Trigger 7 U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-4128 failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 18 of33

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: .L Event No.: 5 & 6

. Event

Description:

BOP O~erator Actions - Automatic Action Verification i

Time Position Examinee's Actions or Behavior BOP Enter RO-1 BOP Monitor Control Room Alarms

Acknowledge Supervisory Alarms

Report Unusual Alarms

Monitor High Containment Temp alarm (SCF)

Monitor 480 Safeguards Undervoltage alarm {SBF2}

BOP Verify SI Pumps running

Three SI Pumps (SBF-2) i

Two RHR Purn~s (SBF-1 or SGF)

BOP Verify Containment FCU Status

Check all FCU running

Place Damper Control Switches in Incident Mode (Panel SBF-2) 0 Damper AlB Closed 0 Damper C Closed 0 Damper D Open i

Place Control Switches for 1104 and 1105 to Open (Panel SBF-1)

Check 1104 and 11 05 O~en BOP Verify SI Valve Alignment Proper Emergency Alignment

Safeguards Valve Off Normal alarm CLEAR

Ensure following OPEN 0 BIT Discharge 1835AlB (Panel SBF-2) 0 BIT Inlet 1852AlB (Panel SBF-2) 0 High Head Stop Valves 856J, H, C, E (Panel SBF-2)

Check if MSIVS should remain OPEN 0 High Steam Flow SIIH~-Hi VC Pressure Alarm Clear (FDF)

II

IF RWST Purification Loop in service contact NPO to secure.

U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 19 of33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.:-L Event No.: 5 & 6

Event

Description:

BOP O~erator Actions - Automatic Action Verification Time Position Examinee's Actions or Behavior BOP Verify Aux Boiler Feed Pump Status

Check Motor Driven Pumps Both Running 0 Only 33AFW Pump is running

Check Turbine Pump Running 0 Raise Speed of 32 AFW PUMP (Panel SCF) 0 OPEN Aux Feed Reg Valves 405A and 405B to feed 31 and 32 SGs BOP Verify Aux Feed Valve Alignment

Motor driven AFW Pumps (Panel SCF) 0 Set 406A - D to full open (Panel SCF)

Check SG Blowdown isolation valves CLOSED (Panel SCF)

BOP Check CCW Pumps

All 3 Pumps Running i

Check RHR HX CCW Shutoff Valves O~en 822A1B (panel SGFt i BOP I Check Essential Service Water Pumps - 3 Running BOP Verify Containment Ventilation Phase A & B (Panel SNF)

Phase A actuated

Phase B Actuated

Check Phase A valve CLOSED i

Check Phase B valves CLOSED BOP Verify Containment Ventilation Isolation

Purge Valves CLOSED 0 FCV-1170 - 1173 (Panel SLF)

Pressure Relief Valves CLOSED 0 PCV-1190 -1192 (Panel SLF)

Check WCCPP Low Pressure Zone Alarms NOT Lit.

Verify IVSWS Valves OPEN 0 IV-AOV-1410, IV-AOV.*1413 i i 0 IV-SOV-6200, IV-SOV.*6201 U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low R.~store Letdown; PORV 456 leak, PT-4128 failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 20 of33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: 5 & 6 Event

Description:

BOP Operator Actions - Automatic Action Verification Time Position' Examinee's Actions or Behavior BOP Verify Emergency Diesel Generator Status

Check ALL EDGs RUNNING (Panel SBF-2)

Check EDG Outlet Flow Control Valves OPEN 1r------+------..-1---~_ _ _ _=__o FCV-1176/1776A (Panel SBF-2)

BOP Verify Control Room Ventilation

Set Control Room Ventilation Control Switch to 10% incident mode (By Supervisory Panel Entrance)

Check Damper Status o A- Dim o B- Bright o Either F1 or F2 Bright o Dampers 01 and 02 Bright

Verify AlC Compressors and fans ALL Running o ACC 31A1B ON Bright o ACC 32 AlB ON Bright o ACF 3Y32 ON Bright --'---~~-~-~'---------i BOP Verify Emergency DC Oil Pump Status

Main Turbine Emergency Bearing Oil Pump Running (Panel SEF)

Dispatch NPO to verify Main Gen Air Side Seal Oil Pump Running

MBFP DC Emergency Oil Pump Running (Alarm Panel SDFL-____

BOP Reset Safety Injection

Press both SI Reset buttons (P,anel SBF-2)

Check SI Reset 1r-____+-_____~-----o---S-'A-c-t.-ua-t-ed-lightEX-T-I-N-G-U_IS_H_E_D _ _________.__________~

BOP Reset MCCs

If RCS pressure is < 360 psig place Makeup Control Switch to stop

Dispatch NPO to secure VC Sump and RCDT Pumps on Waste Disposal Panel

Dispatch NPO to align and reset MCC per SOP-EL-15 U3 NRC Scenario 3 Power increase from 50%,LT -460 fails low Restore Letdown; PORV 456 leak, PT-4128 failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SO, Steam Generator Tube Rupture with LOCA.

Page 21 of33

Appendix 0 S(:enario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: -.L Event No.: 5 & 6

.rEvent

Description:

BOP Operator Actions . - Automatic Action Verification

Time , Position Examinee's Actions or Behavior BOP Check if additional actions should be performed

If transition to ES-1.1 0 Inform CRS of Automatic Action Verification 0 Do not perform additional steps

If Not transition to ES-1.1 0 Inform CRS of Automatic Action Verification I 0 When transition out of E-O then continue U3 NRC Scenario 3 Power increase from 50%,LT -460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SOTR 32 SO, Steam Generator Tube Rupture with LOCA.

Page 22 of33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: -L Event No.: L

. Event

Description:

Small Break LOCA Time Position Examinee's Actions or Behavior CRS Enter E-1 ATC Check if RCPs should be stopped

At least 1 HHSI Pump running (Panel SBF-2)

Subcooling < value in table (aSPDS Monitor on desk) i

. Sto~AII RCPs ATC Determine if SGs are Faulted

Any SG Pressure decreasing in uncontrolled manner (Panel FBF)

Any SG Completely depressurized (Panel FBF)

Determines NO SG Fclulted ATC/BOP Check Intact SG Levels

Check Level Response in all SGs Normal (Panel FBF)

Control Feed Flow to maintain 9 [14] - 50%

It is possible that the crew may diagnose the SGTR at this point and may transition to E-3 ATC/BOP Reset SI

Check RO-1 Steps 2 - 12 complete (report from BOP)

Press both SI Reset Push buttons (Panel SBF-2) i

Check SI Reset 0 SI Actuated Light Extinguished (Panel SBF-2)

ATC/BOP Reset Phase A and B

Place switches for 200 A, 6, C in Close (Panel SFF)

Depress Phase A Reset push buttons (Panel SNF)

I

Depress Phase 6 Reset push buttons If Actuated (Panel SNF)

U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 23 of33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: --L Event No.: ..L Event

Description:

Small Break LOCA Time Position Examinee's Actions or Behavior CRS Check Secondary Radiation ATC/BOP

Check Seismic: Event NOT occurred (Alarm on SDF Clear)

Direct Watch Chemist to Sam phS! SGs

Direct Watch HP to perform contact surveys steam lines & blowdown lines

Reset SG Sample Valves 0 Place Blowdown Switches to Close 0 Press SG Blowdown & Sample Valves Reset Push buttons 17 - 24 on Panel SMF

Check secondary radiation 0 R-15 (Radiation Monitor Control Cabinet 0 R-19 (Radiation Monitor Control Cabinet 0 R-62 A-D (Rack 03 Behind Flight Panel)

Check level in isolated SGs Stable (Panel FBF)

It is expected that the crew diagnose the SGTR at this point and may transition to E-3. If the crew continues in E-1, they will be required to transition to E-3 on foldout eage criteria.

ATC Check PRZR PORVs and Block Valve

Check Power Available to Block Valves 0 Check Breakers for MCC-36A1B closed (Panel SBF-2) 0 Check Block Valves both energized (Panel FBF)

Check PORVs Closed (Panel FCF)

Open one Block Valve~_(panel FCF)

BOP/ATC Establish Instrument Air to Containment

Check Inst. Air Low Press Alarm Clear (Panel SJF)

Press Inst. Air Reset Pushbutton 28 (Panel SMF) i

Open IA-PCV-1228 (Panel SNF) i o IA-PCV-1228 will NOT OPEN Booth Operator If necessary contact crew as HP or Chemistry to confirm elevated activity on 32 SG HP report elevated reading on contact survey for 32 Main Steam Line Chemistry report elevated activit on 32 SG Sam Ie U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 24 of33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.:--.L Event No.: L Event

Description:

Small Break LOCA Time Position Examinee's Actions or Behavior ATC/BOP Check RCP Seal Cooling

Seal Injection Established (Panel SAF)

OR

Bearing Coolant Low Flow Alarm Clear (Panel SGF)

Thermal Barrier CCW Header Low Flow alarm Clear {Panel SGFl ATC/BOP Check CCW for Charging Pump Available i

Check Pumps operating (Panels SBF-1 or SGF}

ATC Determine if Charging Flow Has Been Established

Check LCV-112B and LCV-112C both energized and one open (Panel SFF)

Check CH-AOV-204B Open (Panel SFF)

Check HCV-142 Fully Open (Panel SFF)

Check/Start a Charging Pume (panel FBF}

CRSATC Check if SI should be terminated BOP

Subcooling > 40°F [Table for Adverse] (QSPDS Monitor on Desk)

Secondary Heat Sink 0 Total Feed Flow> 365 gpm Available (Panels SCF) 0 SG LElvel > 9% [14%] (Panel FBF)

RCS Pressure 0 > 1700 psig [2000] (Panel FDF) 0 Stable or Increasing

Pressurizer LBvel > 14% [32%] (Panel FBF) i SI Termination Criteria will NOT be met I U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 25 of33

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: EventNo*:L Steam Generator Tube RI re with Small Break LOCA Time i Position Examinee's Actions or Behavior ATC Check if RCPs should be stopped

At least 1 HHSI Pump running (Panel SBF-2)

Subcooli < value in table PDS Monitor on ATC Identify Ruptured SG

Unexpected Level Increase 32 SG (Panels FBF or SCF)

High radiation from any SG Sample (Chemistry Report)

High radiation from any Steam Line (Rad Monitor Control Cabinet, QSPDS, D-Racks behind H ATC Isolate Flow From Ruptured 32 SG

Adjust Atmospheric to 1040 and check closed (Panel FBF)

32 is affected - direct NPO to isolate steam to 32 AFW Pump o Trip 32 AFW pump if at least 1 MDAFW pump running (Panel SCF) o SG-33 Close MS-42 o Restart 32 AFW Pump if necessary (Panel SCF)

Verify Blowdown Isolated (Panel SCF)

Dispatch NPO to isolate Upstream steam traps per Operator Aid

Close 32 SG MSIV (Panel SBF-1)

ATC/BOP Check Rupture SG Lj3Vei > 9% [14%]

Stop Feed Flow to ruptured SG (Panel SCF)

This nn/O.rj;:IT/"Ir action ATC/BOP Check Ruptured SG pressure> 400 psig (Panel FBF)

Transition to ECA-3.1 if < 400 psig I This is NOT U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 26 of33

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ---L Event No.: L Event

Description:

Steam Generator Tube Rupture with Small Break LOCA Time Position Examinee's Actions or Behavior CRS/ATC Determine Target Temperature for Cooldown

Determine Pressure of Ruptured SG (Panel FBF)

Using Table Determine Target Temperature ATC Dump Steam to conde*nser from intact SGs do not exceed 0.4 E6 Ibm/hr per intact SG.

Procedure actions continue until coo/down termination criteria are met.

ATC Stop cooldown when CET temp (QSPDS) is less than target temp.

Close Steam Dumps/Atmospherics (Panel FCF/FBF) 0 Null deviation meter on controller to match Auto setpoint with actual current pressure.

0 Close valves in manual 0 Place controller in automatic ATC Maintain CET temp < target temp

Monitor CET Temperature and adjust controller setpoint to control < target temp ATC/BOP Check Intact SG Levels

Level response Normal (Panel FBF and/or SCF)

Control feed flow to maintain level 13% [19%] to 50% {Panel SCF)

ATC Check PORVs and Block Valves

Check power available to block valves (lights lit) (Panel FCF)

Check PORV Closed 0 Light indicating PORVs closed (Panel FCF) 0 Tailpipe Temperatures consistent with plant conditions (Panel FBF) 0 Accoustic Monitors No lights lit. (Above door into Supervisory Panel)

Check Block Valves Open 0 Both Block Valves are CLOSED to isolate leaking PORVs.

0 The Block Valves should be left shut U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOeA.

Page 27 of33

Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: Event No.:

Event

Description:

Steam Generator Tube Rupture with Small Break LOCA Time i Position Examinee's Actions or Behavior ATC/BOP Reset SI

Check RO-1 Steps 2 - 12 complete (report from BOP)

Press both SI Reset Push buttons (Panel SBF-2)

Check SI Reset If-----_ _-+-_ _ _-+_ _ _ _ _o~_'S::.:.I...:._A_=c:.:t~u::.::a=te(j Light Extinguished (Panel SBr::_-2--'-)_ _ _ _ _ _ _-lI A TC/BOP Reset Phase A and B

Place switches for 200 A. B. C ~n Close (Panel SFF)

Depress Phase A Reset push buttons (Panel SNF)

If--------+-i_ _ _-+_ _ ._.=.D.;;:.eI:..:..::Plress Phase B Reset push buttons (Panel S::.:.N~F~)_ _ _ _ _ _ _ _-iI BOP/ATC Establish Instrument Air to Containment

Check Inst. Air Low Press Alarm Clear (Panel SJF)

Press Inst. Air Reset Pushbutton 28 (Panel SMF)

Open IA-PCV-1228 (panel SNF) o IA-PCV-1228 will NOT OPEN BOP Determine if RHR Pumps should be stopped

Check RCS Pressure> 360 psig [700] (Panel FDF or SFF)

II--_ _-I-_ _ _-r-_ _._-=S~top RHR Pumps and place in Auto (Panel SGF)

ATC/BOP Check RCP Seal Cooling

Seal Injection Established (Panel SAF)

OR

Bearing Coolant Low Flow Alarm Clear (Panel SGF)

II

Thermal Barrier CCW Header low Flow alarm Clear (Panel SGF)

U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 28 of33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: --L Event No.: L Event

Description:

Steam Generator Tube Rupture with Small Break LOCA Time Position Examinee's Actions or Behavior ATC Establish Charging Flow

Check CCW for Charging Pump Available 0 Check Pumps operating (Panels SBF-1 or SGF)

Check HCV-142 Fully Open (Panel SFF)

Check CH-AOV-204B Open (Panel SFF)

Open LCV-112B then close LCV-112C (Panel SFF)

Check/Start a Charging Pump and adjust to maximum (Panel FBF)

Expect a charging pump is already running at this point.

Actions to terminate cooldown repeated be/ow. If crew get to this step before CET < target temperature they should wait here. When CET Temps, target temp then they should continue ATC Check if cooldown should be stopped -- CET temp (QSPDS) is less than target temp.

Close Steam Dumps/Atmospherics (Panel FCF/FBF) 0 Null deviation meter on controller to match Auto setpoint with actual current pressure.

0 Close valves in manual I i 0 Place controller in automatic to maintain tem(:>

ATC Check Ruptured SG Pressure Stable or Increasing (Panel FBF)

ATB/BOP Check subcooling based on CETs > 60 c F [see table for adverse values]

i Depending on value for subcooling, the crew may transition to ECA-3.1 at this I point ATC Depressurize RCS using PRZR Spray flow S(:>ray flow is NOT available ATC Depressurize RCS Using PRZR PORV

Check PORVs available 0 PORVs indicating lights lit 0 PORV Block Valve Energized/Open

Open one PORV I

Check Pressure Decreasing (Panel FBF)

U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 29 of33

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.:.....L Event No.: L Event

Description:

Steam Generator Tube Rupture with Small Break LOCA Time Position Examinee's Actions or Behavior ATC Terminate Depressurization when:

Both oRCS Pressure < Ruptured SG Pressure (Panel FBF) o PRZR level> 14% [50] (Panel FBF)

OR

PRZR Level> 73% [58] (Panel FBF)

Subcooling < 40° [See Table for Adverse] (QSPDS)

ATC Stop Depressurization

Close PORV (Panel FCF)

ATC Check RCS Pressure Iincreasing (Panel FBF)

CRS ATC Check if SI should be terminated BOP

Subcooling > 40°F [Table for Adverse] (QSPDS Monitor on Desk)

Secondary Heat Sink o Total Feed Flow> 365 gpm Available (Panels SCF) o SG LE!Vel > 9% [14%] (Panel FBF)

RCS Pressure!

o Stable or Increasing

Pressurizer LE!Vel > 14% [32%] (Panel FBF)

If not accomplished prior to this step, the crew should transition to ECA-3.1 at this time.

CRS ATC Manually Start SI Pumps and Go To ECA-3.1 BOP U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-4l28 failure low; Loop Flow transmitter penetration leak (SB LOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 30 of33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.:_ Event No.:

Event

Description:

Time Position Examinee's Actions or Behavior CRS Enter ECA-3.1 ATC/BOP Reset SI

Check RO-1 Steps 2 - 12 complete (report from BOP)

Press both SI Reset Pushbuttons (panel SBF-2)

Check SI Reset 0 SI Actuated Light Extinguished {panel SBF-2}

BOP Reset Phase A and B

Place switches for 200 A, B, C lin Close (Panel SFF)

Depress Phase A Reset push buttons (Panel SNF)

Depress Phase B Reset ~ushbuttons If Actuated (panel SNF)

BOP Establish Instrument Air to Containment

Check Inst. Air Low Press Alarm Clear (Panel S.IF)

Press Inst. Air Reset Pushbutton 28 (Panel SMF)

Open IA-PCV-1228 (Panel SNF) 0 IA-PCV-1228 will NOT OPEN BOP Check Status of 480V buses All energized byu off site power Ensure MCC and lighting are reset per SOP-EL-15 CRS/ATC Align PRZR Heater Switches

Control Group Trip Pull Out

Backup Groups OFF CRSATC Check if Spray Pumps should be stopped BOP Containment spray was never activated CRS/ATC Check 32 SG Level> 9%

Stop Feed Flow to 32 SG CRS/BOP Determine if RHR Pumps should be stopped RHR Pumps were previousl~ sto~~ed U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 31 of33

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: _ Event No.:_

Event Time Position I-Y::amlln",,,,'c Actions or Behavior CRS/BOP Evaluate Plant Status Attachment 1 CRS/ATC Check Seal Cooling Established Seal established CRS/ATC Establish Charging Flow

Charging Flow Previously Established using one pump

Start all availab~e charging pumps

MaximumC Flow CRS/ATC Determine SGs are NOT Faulted CRS/ATC Check Intact SG Level CRS/ATC Initiate RCS Cooldown to Cold Shutdown

Verify All control rods < 20 steps

Maintain Cooldown Rate < 10Qo/hour Determine if Subcooled Recovery is appropriate

RWST Level> 24 Feet

32 SG NR levels < 95%

Lead Examiner Terminate Scenario U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-412B failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 32 of33

Appendix D Scenario Outline Form ES-D-1 Post Scenario Event Classification Event Classification - ALERT EAL 3.1.2 Primary system leakage exceeding the capacity (>75 gpm) of a single charging pump.

U3 NRC Scenario 3 Power increase from 50%,LT-460 fails low Restore Letdown; PORV 456 leak, PT-4l28 failure low; Loop Flow transmitter penetration leak (SBLOCA); 31 AFW Pump trips on start; SGTR 32 SG, Steam Generator Tube Rupture with LOCA.

Page 33 of33

Appendix 0 Scenario Outline Form ES-D-1 Facility: IPEG IJnit 3 Scenario No' 4 Op-Test No.: 1 Examiners: Operators:

Initial Conditions: 100% power steady state. 32 HHSI pump is OOS, expected to return to service in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Turnover: Maintain 100% Power Event Malt. No. Event Event No. Type* Description 1 C (ALL) VCT Level Transmitter fails Low 2 MAL- I (CRS) PT-404 failure requiring manual control of Main Boiler Feed Pumps.

MSS003 I(ATC) 3 MAL- C (ALL) Fault on 480V Bus 6A. This will require starting an ESW pump and EPS005D charging pump.

TS (CRS) 4 N/A R (ATe) T.S. load reduction.

N (CRS)

N (BOP) 5 MAL- C(ALL) Rod B-6 fails to move during power reduction (SD Bank Rod K-6 is CRFOO4AU alsl) stuck) I TS (CRS) 6 MAL- M (ALL) SBLOCA RCSOO1A

7 MAL- C (ALL) ATWS RPSOO2A1 B

8 MAL- C (BOP No Auto SI SISOO1A1B C {CRS}

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page I of36

Appendix 0 Scenario Outline Form ES-D-1 Summary The evaluation begins with the plant at 100% power steady state operation. 32 SI pump is out of service for bearing inspection. 32 SI Pump was removed from service 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ago, expected return in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

After the crew assumes the watch, VCT Level Instrument fails low. An auto makeup and charging pump suction swap will occur. CRS directs crew to perform AOP-CVCS-1.

Next, PT-404 Steam Header Pressure fails high. ATC diagnoses failure and places Main Boiler Feed Pump speed control to manual. CRS directs crew to perform AOP-INST-1, Instrument/Controller Failures.

Next, a fault occurs on Bus 6A. Team enters AOP-480V-1, Loss of 480 V Bus to stabilize the plant. The crew will start a charging pump, ESW Pump and determine that a shutdown must commence. This is a Tech Spec for the CRS.

During shutdown Control Bank 0 rod K-14 fails to move. The crew will respond using AOP-ROD-1.

Reactor Engineering will direct the crew to continue with the shutdown allowing rods to step in. This is a Tech Spec for the CRS.

After sufficient shutdown, a SBLOCA occurs. Auto reactor trip is demanded but the Reactor trip breakers do not open. The reactor will not trip from the Control Room and the team will respond per FR-S.1, "Response to Nuclear Power Generation I ATWS" and will SID the reactor by manually inserting control rods and initiating Emergency Boration via an alternate method since MOV-333 cannot be opened from the Control Room. The turbine will be manually tripped. The reactor trip breakers will be locally opened and the team will transition to E-O, "Reactor Trip or Safety Injection".

An Auto SI is required, but will not actuate. The RO will manually actuate SI. 33 SI pump cannot be powered. 32 SI pump is OOS. 31 SI pump initially starts but trips. 31 and 32 Charging Pumps are eventually started after manual action to align suction to the RWST. The team will diagnose RCS not intact and transition to EOP E-1, Loss of Reactor or Secondary Coolant As the team progresses through E-1, Reactor Vessel level will continue to lower. When level lowers to 44% RCP running range (after about 30 minutes following the ATWS), an orange path on core cooling will require a transition to FR-C.2, Response to Degraded Core Cooling.

The team will initiate depressurization of SGs per FR-C.2. The scenario is terminated after SG depressurization has been initiated.

Procedure Flowpath: AOP-INST-1, AOP-480V-1, AOP-ROD-1, FR-S.1, EOP E-O, EOP E-1, FR-C.2 Critical Tasks are as follows:

FR-S.1 - C Insert negative reactivity into the core by at least one of the following methods before step 4 of FR-S.1 is complete:

o De-energize the Rod Drive MG Sets o Manually insert the rods o Establish Emergency Boration FR-S.1 -- B Start AFW pumps and establish 686 gpm before transition out of FR-S. 1 E-O -- 0 Manually actuate at least one train of SIS actuated safeguards before completion of FR S.1 step 6 FR-C.2 -A Depressurize SGs to atmospheric pressure (at < 100°F/hr) to inject ECCS accumulators and establish low-head in}ection flow before a Core Cooling red path develops.

U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto Sf Fails; Loss of all SI Pumps results in FR-C.2 Page 2 of36

Appendix 0 Scenario Outline Form ES-O-1 Simulator Setup and Instructor Directions II Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSEIINSTRUCTOR CUES IC Reset Reset Simulator to IC-11 SES Setup PULL OUT POS SI PUMP #32 CONT SW Schedule SAFETY INJECTION PUMP 31 FAILL:RES REACTOR TRIP BREAKERS FAIL TO OPEN (AUTO FAILURE)

REACTOR TRIP BREAKERS FAIL TO OPEN (AUTO

& MANUAL)

SAFETY INJECTION FAILURE TRAIN A SAFETY INJECTION FAILURE TRAIN B VCT LEVEL FAILURE STEAM HEADER PRESSURE DETECTOR PT-404 FAILURE LOSS OF 480 V BUS 6A RCS RUPTURE (LOOP 1 COLD LEG)

STUCK RODS (CBD-B6/K6)

Local Reactor Trip Removes Malfunctions:

REACTOR TRIP BREAKERS FAIL TO OPEN (AUTO FAILURE)

REACTOR TRIP BREAKERS FAIL TO OPEN (AUTO

& MANUAL) 288 RWST TO CHARGING PUMP HEADER ISO NONE LOA TO DEENERGIZE VALVE 894A NONE LOA TO DEENERGIZE VALVE 894B NONE LOA TO DEENERGIZE VALVE 894C NONE LOA TO DEENERGIZE VALVE 894D Locally open 822B SES Setup Load Schedule and verify Schedule malfunctions and overrides bave been entered Floor Setup Perform Setup Checklist Hang Danger Tags on 32 HHSI Pump Update Protected Equipment Hang Protected Equipment Tags for 31 and 33 PC HHSI Pumps I Risk is Green U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto 81 Fails; Loss of all 81 Pumps results in FR-C.2 Page 3 of36

Appendix 0 Scenario Outline Form ES-O-1 Event 1 Activate Trigger 1 when MAL-CVC008 to 0 directed VCT Level Failure Low Role Play Respond as requested Ilf requested, running charging pump sounds normal Event 2

Activate Trigger 2 when i MAL-MSS003 PT-404 failure i

directed Role Play Respond as requested NPO may be directed to investigate PT-404 and

. MBFP I&C will prepare a Troubleshoot and Repair Package Event 3 Activate Trigger 3 when MAL-EPS005D Fault on bus 6A !

directed I Role Play I Respond as requested Report acrid smell in 480V switchgear room when asked to investigate nt 4 I No action TS 3.0.3 shutdown ole Play I Respond as requested If necessary SM direct initiate shutdown I immediately Event 5 Inserted at setup MAL-CRF004AU Rod K-14 stuck Role Play pond as requested I&C will prepare a Trouble Shoot and Repair Package

. Event 6 Activate Trigger 6 when MAL-RCS001A RCS Leak directed I Role Play Respond as requested Event 7 Inserted at setup MAL-RPS002A (Trip breakers fail to auto open) i

. MAL-RPS002B (Trip Breakers fail to man open)

ATWS Role Play When NPO directed to locally After emergency boration initiated, REMOVE trip reactor MAL-RPSOO2A and MAL-RPS002B Event 8 Inserted at Setup MAL-SIS001A Auto Failure Train A SI MAL-SIS001 B Auto Failure Train B SI

1 Role Play Respond as requested U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaJigned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all Sl Pumps results in FR-C.2 Page 4 of36

Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: Event No.: _1_

Event

Description:

VCT Level Transmitter fails Low Time Position Examinee's Actions or Behavior ATC/BOP Diagnose Failure of VeT Level Transmitter.

CRS Enters AOP-CVCS-1 BOP Opens CH-LCV-112C and closes CH-LCV-112B ATC Stops VCT makeup by placing Makeup Control Switch to Stop and Mode Selector to Manual CRS Should assess that load reduction is not necessary. Will direct load reduction if significant boration occurred.

ATC Will determine that VCT pressure is above pre-malfunction value.

BOP Direct NPO to monitor running charging pump.

CRS Request RCS Boron Sample I Lead Evaluator Instruct Booth to insert Trigger 2 U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaJigned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 5 of36

Appendix D Scenario Outline Form ES-D-1 Op~Test No.: _1_ Scenario No.: ~ Event No.:

Event

Description:

PT-404 Failure High - Manual control of Main Boiler Feed Pumps Time Position Examinee's Actions or Behavior I ATC/BOP Diagnose Failure of PT-404 ATC Place both MBFPs in Manual and stabilize plant.

CRS Direct Perform Immediate Operator Actions of AOP-INST~1 ATC Silently evaluates for failure of control system inputs

Rod Control 0 NIS Power Range 0 RCSTemp 0 Turbine 1st Stage Pressure

Pressurizer Pressure

Pressurizer LHvel Control 0 RCS Temperature

MBFP Speed Control 0 Suction Pressure 0 Discharge Pressure 0 Steam Header Pressure

SG Level Control 0 Steam Pressure 0 Steam Flow 0 Feedwater Flow

SG Pressure Control 0 Atmospheric Steam Dumps 0 High Pressure Steam Dum~s CRS/ATC Enter AOP-INST~1 and Re-perform IOAs verbalizing each input CRS/ATC Determine an Instrument failure has occurred.

U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 6 of36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: ~ Event No.: --.L Event

Description:

PT-404 Failure High - Manual control of Main Boiler Feed PumQs Time Position Examinee's Actions or Behavior I CRS Identify appropriate section 4.17 of procedure CRS/ATC i Determine Steam Dumps are in Temperature Mode - No action required. (Panel FBF)

ATC Determines Main BoilElr Feed Pumps are in Manual (Panel FAF) This should have been done as part of the Immediate Operator Actions ATC Adjust MBFP Speed to Match Steam Flow and Feed Flow.

When stable, adjust Feed Reg Valve &P Program ~er Attachment 13 graph CRS/ATC Return controls for unaffected equipment to auto as desired. The FRVs may have been placed in manual, they can be returned to auto here.

Lead Evaluator Instruct Booth to insert Trigger 3 U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Los,s of all SI Pumps results in FR-C.2 Page 7 of36

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: ~ Event 1'10.: ~

Event

Description:

Loss of 480V Bus 6A Time Position Examinee's Actions or Behavior CRS/BOP Multiple alarms - Diagnose Loss of Bus 6A CRS Enter AOP-480V-1 CRS/BOP Determine power is lost to Bus 6A and RHR was not in service CRS/ATC Determine no Charging Pump is running

Start 31 or 32 Charging Pump and match speed with previous conditions CRS/BOP Determine 2 CCW Pumps are running CRS/BOP Determine Essential Service Water Header Pressure is < 60 psig and no SW pumps are operating ,on the Essential SW Header

Start 34 or 3!5 SW Pump CRS/ATC Determine Turbine is on line CRS/ATC Determine Power has not been lost to IRPI CRS/ATC Determine Vacuum NOT decreasing BOP CRS/BOP Determine ISO PHASE BUS RETURN AIR HIGH TEMP alarm is clear CRS/BOP Determine waste release is NOT in progress BOP Dispatch operator to monitor EDGs CRS/ATC Determine IRPI is operable CRS Initiate Review of Tech Specs

TS 3.8.9 E - Inoperable train with loss of safety function

TS 3.5.2 - 2 Inoperable HHSI Pumps (Loss of safety function)

U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck !Misaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 80f36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.:.....1.... Event 1\10.: ~

Event

Description:

Loss of 480V Bus 6A Time Position Examinee's Actions or Behavior CRS Determine that 2 SIS pumps are inoperable necessitating a shutdown per T.S.

3.8.9 E CRS/BOP Determine bus 6A NOT energized by EDG CRS/BOP Determine 32 EDG is running BOP/NPO Determine white supervisory light for relay 86/6A is extinguished BOP/NPO Dispatch an operator to:

OPEN BreakHrs for o MCC**36B o MCC**36D o MCC-37

Perform visual inspection of 480V bus 6A The NPO will report NO FIRE; however an acrid smell exists in the 480 V switchgear room and bus 6A is damaged.

CRS/BOP Place Control Switches/breakers for 480V loads in pullouUoff/open 0 33 Charging Pump 0 PRZR Modulating Heaters 0 32 Boric Acid Transfer Pump 0 32 Containment Spray Pump 0 32 Recirc Pump 0 MCC36B 0 33 SI Pump 0 35 FCU 0 33ABFP 0 Turb Aux Oil Pump 0 32 RHR Pump 0 33 SW Pump 0 36 SWPmp

! 0 39 SW Pump U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 9 of36

Appendix 0 Sicenario Outline Form ES-D-1 Op-Test No.: Scenario No.: Event No.: -L Event

Description:

Loss of 480V Bus 6A Time Position Examinee's Actions or Behavior

CRS Determine indication of Fault on Bus 6A BOP Direct operator to shutdown 32 EDG U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 10 of36

Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: -.1.

Event

Description:

Power Reduction e Position Applicant's Actions or Behavior Note:

I The reactivity plan for the power reduction should be developed by the team in the briefing room prior to takin!;l the watch. The plan could call for boration and/or rod insertion CRS Obtain POP-2.1 and SM permission for power reduction CRS Use Attachment 3 from POP-2.*1 for power reduction CRS Record power reduction data and contact the SM to make required notifications CRS Direct ATC/BOP to perform a Reactivity Calculation for the power i reduction ATC/BOP Prepare Reactivity Calculation using the Daily Reactivity Sheet, OPT-25 CRS Assigns roles for power reduction ATC Reviews reactivit~ elan ATC If rods are inserted:

Places/verifies rods are in Manual

Inserts rods specified number of steps

Observes:

0 Proper rod motion 0 Tavg 0 Power i

BOP Peer checks rod insertion ATC Diagnose Rod B-6 Not inserting with the remainder of Control Bank D NOTE: <<the crew elects to use boration first, there will be some time before rod motion is required.

I CRS Suspend Power Reduction Enter AOP-ROD-1 U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page II of36

Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: ..!.

Event

Description:

Power Reduction Time Position s or Behavior ATC If boration is performed:

Energize All Pressurizer Heaters

Places RCS Makeup control to Stop

Place RCS Makeup Mode selector to borate

Adjusts integrator to desired boration amount

Places RCS Makeup control to Start

Observes:

0 Proper makeup response 0 Tavg 0 Power BOP Peer check boration ATC/BOP Initiate Turbine Load Reduction at desired rate

Governor (Preferred)

Load Limit 1

Load Limit 2 ATC Maintain the manual setpoint for the MFRV Controllers Nulled.

ATC Adjust Control Rod Position ~er TS and Gra~h-RPC-16 Lead Evaluator When the follClwing has been demonstrated/observed:

Sufficient load reduction.

Sufficient normal plant operations by the BOP.

Then instruct Booth to insert Event.

U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reac,tor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 12 of36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: --4.- Event No.: --4.

Event

Description:

Power Reduction/Stuck Rod B-6 Time Position Examinee's Actions or Behavior I CRS Enter AOP-ROD-1 I

i CRS/ATC

Determine procedure was NOT entered due to continuous rod motion I

CRS i Determine procedure section 4.42 for misaligned rod i CRS/ATC Determine rod is misaligned ATC If not already accomplished for power reduction, place rod control in Manual CRS If At Any Time step for power reduction i

0 Adjust boron concentration and turbine load CRS Refer to Tech Specs 0 TS 3.1.4 Group Alignment Limits 0 TS 3.2.3 Axial Flux Difference 0 TS 3.2.4 Quadrant Power Tilt i Depending on how (Juickly the crew diagnoses the stuck rod, actual Tech I

Spec limits may not be exceeded. The OPERABILITY of rod B-6 is in question.

I BOP I Notify I&C to investigate rod control system for the cause of miSaligned/st~ck rod.

Report as I&C there is NO obvious cause for the misaligned rod.

Lead Evaluator When sufficient load reduction and progress through AOP-ROD-1 direct booth to activate event 6 U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 13 of36

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: --+/-- Event No.:

Event

Description:

SBLOCA Time Position Examinee's Actions or Behavior ATC Diagnose rapidly decreasing Pressurize Pressure and Level.

CRS Direct ACT to trip the reactor and when verified tripped, Direct the BOP to initiate Safetll: Injection ATC Verifies Reactor NOT Tripped: (Panel FCF)

Reactor trip and bypass breakers NOT open

Rod bottom li~lhts NOT lit

IRPls NOT < 20 steps

Nuclear flux NOT decreasing I BOP Attempt to Trip the reactor using the pushbutton on Panel SBF-2 BOP Direct NPO to locally trip the reactor in the cable sereading room CRS/ATC Determine power is> 5% and transition to FR-S.1 U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto 81 Fails; Loss of all SI Pumps results in FR-C.2 Page 14 of36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: L Event Descri n: ATWSI FR-S.1 Time Position Examinee's Actions or Behavior CRS Enter FR-S.1- Direct crew to rm Immediate lnOIC<>Tnr Actions of FR-S.1 CRS/ATC Determine reactor NOT tripped Attem a manual tri ATC Insert control rods

May take manual control and insert rods

let automatic control insert control rods.

ATC Determine Turbine NOT Tripped

Manually trip Turbine BOP Check Auxiliary Feedwater Pumps Running NONE running

Start 31 AFW Pump

Start 32 AFW Pump o Increase speed and open throttle valves to feed 33 & 34 SG U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 15 of36

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: L Event nQ'.f'rintirln: ATWSI FR-S.1 Time Position Examinee's Actions or Behavior ATC Initiate Emergency Boration

Check 31/32 charging pump running

Determine MOV-333 cannot be opened.

o Place FCV-110A in Manual o Ensure FCV-110A Fully Open (Controller output = 0) o Place 111A in Manual o Ensure 111A is Fully Closed (Controller output = O) o Place Makeup Mode Selector Switch in MANUAL o Turn Makeup Control Switch to START o Transfer Charging Pump to Manual o Increase Charging Pump Speed to maximum o ClOSE! Boric Acid Storage Tank Recirc Valves BOP Verify Containment Ventilation Isolation

Purge Valves CLOSED o FCV-1170 - 1173 (Panel SLF)

Pressure Relief Valves CLOSED o PCV-1190 - 1192 (Panel SLF)

WCCPP Low Pressure Alarms NOT Lit.

BOP Check SI Status

Determine SI Not Actuated o Manually actuate SI o Perform E-O ure U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto Sl Fails; Loss of all SI Pumps results in FR-C.2 Page 16 of36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: L ATC Check Reactor Subcritical

Power Range < 5%

Intermediate Range Channels I) or negative

Check all rods < 20 steps Manual actuation of SI in previous step will strip the Rod Drive MG sets r"'~:IIITlnn in a reactor Booth Instructor Remove malfunctions for Reactor Trip Breakers and ensure reactor trip occurs.

Remove MAL-RPS002A & MAL-RPS002B CRS/ATC Secure Emergency Boration BOP

Turn Makeup Control Switch to STOP

Establish Auto Makeup per SOP-CVCS-003

Place Boric Acid Transfer Pumps in Slow Speed

to 25%

i CRS/ATC Check RCP Seal Coo Ii Established CRS/BOP Check Charging Status

Check CCW available for Charging pump

Check Charging Pump Running

Maintain seal i~i~.~'i,,_

CRS/ATC Verify Adequate Shutdown Margin BOP

Verify Control Rods < 20 Steps

Direct Chemist to Sample RCS

Check Boron> Cold Shutdown Concentration o Establish normal boration CRS Return to Procedure & Ste In Effect U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank 0 rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 17 of36

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: ~

Event

Description:

SBLOCA Time Position Examinee's Actions or Behavior CRS Return to E-O Step 1 ATC Verifies Reactor Tripped: (Panel FCF)

Reactor trip and bypass breakers open

Rod bottom lights lit

IRPls < 20 ste*ps

Nuclear flux decreasing ATC Verifies Turbine Trip by observing stop valves closed {panel FAF}

I BOP Check status of 480V buses (Panel SHF)

Observe ALL busses energized from Offsite Power

ATC Check SI status Determine SI is Actuated

Any SI Annunciator - Lit (Panel FDF)

SI Pumps An~' Running (Panel SBF-1, SBF-2)

ATC/BOP Manually Actuates SI

Depresses SI Actuation ~ushbutton (Panel SBF}

BOP/ATC Check AFW Status Observes Total of all SG flow indicators> 365 gpm (Panel SCF)

Controls feed flow to maintain SG levels 9 - 50%

Adjust flow control valve (:!otentiometers CRS Direct BOP to perform RO-1 BOP O~erator Actions during use of EOPs ATC Verify Feedwater Isolation

Check Main Boiler Feed Pumps Tripped (Panel FAF)

Check MBFP Discharge Valves Closed (Panel FAF)

Check Feed Reg Valves and Bypasses Closedllsolated 0 Main and Bypass MOVs Closed (Panel SCF) 0 Main FRVs 2 is True (Panel SNF) 0 Bypass FRVs {panel FAF)

ATC Check Slowdown Isolation Valves Closed (Panel SCF)

U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 18 of36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: ~ Event 1\10.:

Event

Description:

SBLOCA Time Position Examinee's Actions or Behavior

ATC Verify SI Flow

Check Pressure < 1700 psig (Panel FBF, or FDF)

Check High Head Pump Flow Indicators (Panel SBF-2)

Check Pressure < 360 psig (Panel FDF WR Press Recorder)

Check RHR Pumps Flow Indicators (Panel SBF-2 ATC Verify Containment Spray NOT required

Check Containment Pressure remained < 22 psig (Panel J01 or SBF-2)

ATC Check RCP Seal Cooling

Bearing Coolant Low Flow Alarm Clear (Panel SGF)

Thermal Barril~r CCW Header Low Flow alarm Clear (Panel SGF)

ATC Establish Charging Flow

Check RCS Pressure> 360 psig (Panel FDF WR Recorder)

Check CCW Available (Panel SBF-1 lights only this is adequate; Panel SGF Breakers & Flow indicators)

Check HCV 142 Fully Open (Panel SF F)

Check CH-AOV-204B Open (Panel SFF)

Open CH-LCV-112B (Panel SFF)

Then Close CH-LCV-112C (Panels SFF)

Set Speed Controller to Startin~1 Position (Panel FBF)

Start 1 Charging Pump (Panel FBF)

Adjust Speed for Minimum Seal Injection {Panel SAF}

ATC Check RCS Average Temperature

Any RCPs Running - Tavg Trending to 54]oF (Panel FDF)

No RCPs running - Tcold Trending to 547°F (Panel FDF)

ATC Check if RCPs should be stopped

At least 1 HHSI Pump running (Panel SBF-2)

Subcooling < value in table (QSPDS Monitor on desk)

Stop All RCPs U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank 0 rod will fail to insert Stuck IMisaJigned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 190f36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: EventNo*:l Event

Description:

SBLOCA Time Position Examinee's Actions or Behavior ATC Check PORVs Closed (Panel FCF)

Check Safety Valves Closed

- Tailpipe Temperatures Normal (Panel FBF)

- Acoustic Monitors Normal (Above Door into Supervisory Panel)

Spray Valves Closed (Panel FBF)

Ir------I--------r!~Check Aux Spray Valve Closed Panel (Panel SFF)

ATC I Determine if SGs are Faulted

Any SG Pressure decreasing in uncontrolled manner (Panel FBF)

- Any SG Completely depressurized (Panel FBF)

ATC Determine if SG Tubes are Ruptured

- Condenser Air Ejector Radiation recorder Trend (Rad Monitor Rack)

- SG Blowdown Recorder Trend (Rad Monitor Rack)

- Main Steam Line Radiation Recorders (Rack 0-3 behind the Flight Panel) 11-_ _-+_ _ _ _ +--_-_ Any SG level increasing in an uncontrolled manner (Panel F(3_FL--)_ _ _---I1 ATC Check if RCS is intact

- Containment Pressure Normal (Panel J-O or SBF-1)

- Containment Sump Level Normal (Panel J-O)

- Containment Radiation Normal a R-2 and R-7(Rack 0-1 Behind Flight Panel)

U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 20 of36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: ~ Event 1'110.:....2....

Event

Description:

BOP Actions during E-O (Procedure RO-1}

Time Position Examinee's Actions or Behavior BOP Monitor Control Room Alarms

Acknowledge Supervisory Alarms

Report Unusual Alarms

Monitor High Containment Temp alarm (SCF)

Monitor 480 Safeguards Undervoltage alarm {SBF2}

BOP Verify SI Pumps running

Three SI Pumps (SBF-2)

Two RHR PunnQs (SBF-1 or SGF}

BOP Verify Containment FeU Status

Check all FCU running

Place Damper Control Switches in Incident Mode (Panel SBF-2) 0 Damper AlB Closed 0 Damper C Closed 0 Damper D Open

Place Control Switches for 1104 and 1105 to Open (Panel SBF-1)

Check 1104 and 1105 OQen BOP Verify SI Valve Alignment Proper Emergency Alignment

Safeguards Valve Off Normal alarm CLEAR

Ensure following OPEN 0 BIT Discharge 1835AlB (Panel SBF-2) 0 BIT Inlet 1852AlB (Panel SBF-2) 0 High Head Stop Valves 856J, H, C, E (Panel SBF-2)

Check if MSIVS should remain OPEN 0 High Steam Flow SI/Hi-Hi VC Pressure Alarm Clear (FDF)

IF RWST Purification LooQ in service contact NPO to secure.

BOP Verify Aux Boiler Feed Pump Status

Check Motor Driven Pumps Both Running

Check Turbine PumQ Running U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 21 of36

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.:..Q...

Event

Description:

BOP Actions during E-O (Procedure RO-1)

Time Position Examinee's Actions or Behavior BOP Verify Aux Feed Valve Alignment

Motor driven AFW Pumps (Panel SCF) o Set 406A - D to full open (Panel SCF) 1f--_ _-+-_ _ _--+_ _ e_C-'--he-'-c'-k_S-'-G-'--'-B_lo'-w_d()wn isolation valves CLOSED (Pa~n-,-e_1S-"--C-"--'-F)<--_ _ _ _--iI BOP Check CCW Pumps e All 3 Pumps Hunning I

Ir---~-----+---~*

Gheck RHR HX CCW Shutoff Valves Open 822A1B (Panel SGF)

BOP Check Essential Service Water Pumps - 3 Running BOP Verify Containment VE~ntilation Phase A & B (Panel SNF)

Phase A actu;ated e Phase B Actuated e Check Phase A valve CLOSED e Check Phase B valves CLOSED BOP Verify Containment Ventilation Isolation e Purge Valves CLOSED o FCV-1170 -1173 (Panel SLF) e Pressure Relief Valves CLOSED o PCV-1190 - 1192 (Panel SLF) e Check WCCPP Low Pressure Zone Alarms NOT Lit.

Verify IVSWS Valves OPEN o IV-AOV-1410,IV-AOV-1413 o IV-SOV-6200, IV-SOV-6201 BOP Verify Emergency Diesel Generator Status e Check ALL EDGs RUNNING (Panel SBF-2) e Check EDG Outlet Flow Control Valves OPEN o FCV-1176/1776A (Panel SBF-2)

U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaJigned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 22 of36

Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: ~ Event No.:

Event

Description:

BOP Actions during E-O (Procedure RO-1)

Time Position Examinee's Actions or Behavior BOP Verify Control Room Ventilation

Set Control Room Ventilation Control Switch to 10% incident mode (By Supervisory Panel Entrance)

Check Damper Status o A- D~m o B - Bright o Either F1 or F2 Bright o Dampers D1 and D2 Bright

Verify NC Compressors and fans ALL Running o ACC :31NB ON Bright o ACC 32 NB ON Bright o ACF 31/32 ON Bright BOP Verify Emergency DC Oil Pump Status

Main Turbine Emergency Bearing Oil Pump Running (Panel SEF)

Dispatch NPO to verify Main GE~n Air Side Seal Oil Pump Running

MBFP DC Emergency Oil Pump Running (Alarm Panel SDF)

BOP Reset Safety Injection

Press both SI Reset buttons (Panel SBF-2)

Check SI Reset o SI Actuated light EXTINGUISHED BOP Reset MCCs

If RCS pressure is < 360 psig place Makeup Control Switch to stop

Dispatch NPO to secure VC Sump and RCDT Pumps on Waste Disposal Panel

Dispatch NPO to align and reset MCC per SOP-EL-15 U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto Sl Fails; Loss of all SI Pumps results in FR-C.2 Page 23 of36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: ..§..

Event

Description:

BOP Actions during E-O '~Procedure RO-1)

Time Position Examinee's Actions or Behavior BOP Check if additional actions should be performed

If transition to ES-1.1 0 Inform CRS of Automatic Action Verification 0 Do not perform additional steps

If Not transition to ES-1.1 0 Inform CRS of Automatic Action Verification I

0 When transition out of E-O then continue U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all Sf Pumps results in FR-C.2 Page 24 of36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: Event No.: 6 Continued Event

Description:

Procedure E-1 Time I Position Examinee's Actions or Behavior

'UA;",ately 30 minutes after the A TWS event RCS inventory will be low enough to require a to FR-C.2 ATC Check if RCPs should be stopped

At least 1 HHSI Pump running (Panel SBF-2)

Subcooling < value in table (QSPDS Monitor on desk)

Stop All RCPs ATC Determine if SGs are Faulted

Any SG Pressure decreasing in uncontrolled manner (Panel FBF)

Any SG Completely depressurized (Panel FBF)

Check Faulted SG Isoiated (Unless needed for cooldown)

MSIVs (Panel SBF-1)

MSIV Bypasses (Report from NPO)

Main Feed Ref Valves or MOVs (2 is True on SNF or Panel SCF for MOVs)

Bypass Feed Reg Valves or MOVs (Panel FBF or Panel SCF for MOVs)

AFW to SG (Panel SCF)

SF Atmospherics (Panel FBF)

SG Blowdown Isolation (Panel SCF)

SG Blowdown Sample Valves (Panel SNF)

SG Traps (Report from NPO)

32 SG affected Check MS-41 shut (NPO Report)

33 SG Affected Check MS-42 Shut (NPO Report)

ATC/BOP Check Intact SG Levels

Check Level Response in all SGs Normal (Panel FBF)

Control Feed Flow to maintain 9 [141- 50%

U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto Sl Fails; Loss of all Sl Pumps results in FR-C.2 Page 25 of36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: ~ Event No.: 6 Continued Event

Description:

Procedure E-1 I ATC/BOP I Reset SI

Check RO-1 Steps 2 - '12 complete (report from BOP)

Press both SI Reset Push buttons (Panel SBF-2)

Check SI Reset o SI Actuated Light Extinguished (Panel SBF-2)

ATC/BOP Reset Phase A and B

Place switches for 200 A, B, C in Close (Panel SF F)

Depress Phase A Reset pushbuttons (Panel SNF)

Depress Phase B Reset pushbuttons (Panel SNF)

CRS Check Secondary Radiation ATC/BOP

Check Seismic Event NOT occurred (Alarm on SDF Clear)

Direct Watch Chemist to Sample SGs

Direct Watch HP to perform contact surveys steam lines & blowdown lines

Reset SG Sample Valves o Place Blowdown Switches to Close o Press SG Blowdown & Sample Valves Reset Push buttons 17 - 24 on Panel SMF

Check secondlary radiation o R-15 (Radiation Monitor Control Cabinet o R-19 (Radiation Monitor Control Cabinet o R-62 A-D (Rack D3 Behind Flight Panel)

Check level in isolated SGs Stable (Panel FBF)

ATC Check PRZR PORVs and Block Valve

Check Power Available to Block Valves o Check Breakers for MeC-36NB closed (Panel SBF-2) o Check Block Valves both energized (Panel FBF)

Check PORVs Closed (Panel FCF)

Open one Block Valves (Panel FCF)

U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 26 of36

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: Scenario No.: Event No.: 6 Continued Event

Description:

Procedure E-1 BOPIATC Establish Instrument Air to Containment

Check Inst. Air Low Press Alarm Clear (Panel SJF)

Press Inst. Air Reset Pushbutton 28 (Panel SMF)

Open IA-PCV-1228 (Panel SNF)

ATCIBOP Check RCP Seal Cooling

Seal Injection Established (Panel SAF)

OR

Bearing Coolant Low Flow Alarm Clear (Panel SGF)

Thermal Barrier CCW Header Low Flow alarm Clear (Panel SGF)

ATC/BOP Check CCW for Charging Pump Available

Check Pumps operating (Panels SBF-1 or SGF)

ATC Determine if Charging Flow Has Been Established

Check LCV-112B and LCV-112C both energized and one open (Panel SFF)

Check CH-AOV-204B Open (Panel SFF)

Check HCV-142 Fully Open (Panel SF F)

Check/Start a Charging Pump (Panel FBF)

CRS ATC Check if SI should be terminated BOP

Q Subcooling > 40 F [Table for Adverse] (QSPDS Monitor on Desk)

Secondary Heat Sink o Total Feed Flow> 365 gpm Available (Panels SCF) o SG Level> 9% [14%] (Panel FBF)

RCS Pressure o > 1700 psig [2000] (Panel FDF) o Stablt3 or Increasing I

Pressurizer Lt3Vei > 14% [32%1 (Panel FBF)

U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all Sl Pumps results in FR-C.2 Page 27 of36

Appendix D ~;cenario Outline Form ES-D-1 Op~Test No.: Scenario No.: Event No.: 6 Continued Event

Description:

Procedure E~1 CRS ATC Check if Spray Pumps should be stopped BOP

Check Any spray pumps running (Panel SBF~1)

Check if Spray should be secured o 5 Fan Cooler Units Running (Panel SBF~2)

OR o Containment Pressure < 16 psig (Panel SBF~1)

Depress Containment Spray Reset push buttons (Panel SBF~1)

Check Containment Radiation Normal o R~2 and R~7 (Rack D~1 Behind Flight Panel)

Stop Containment Spray Pumps and place in auto (Panel SBF-1)

Close Pump discharge valves 866 AlB (Panel SBF~1)

BOP Determine if RHR Pumps should be stopped

Check RCS Pressure> 360 psig (Panel FDF or SFF)

Check RCS Pressure stable or increasing

Check any RHR pumps running with suction to RWST (Panel SBF~1)

Stop RHR Pumps and place in Auto (Panel SGF)

ATC Check for Faulted SG

Check pressures in all SG stable or increasing (Panel FBF)

Check RCS pressure stable or increasing

BOP Determine if Diesel Generators should be stopped

480V buses energized by offsite power (Panel SHF)

I I

Dispatch NPO to shutdown EDGs BOP Evaluate Plant Status

CRS directs BOP to perform Attachment 1 ATC Check if RCS Cooldown and Depressurization is Required

Check RCS pressure Greater than 360 (Panel FDF or SFF)

OR

Check RTHR Pump Flow Less than 300 gpm (Panel SBF~2)

CRS I Transition to ES-1.2 Post LOCA Cooldown and Depressurization U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank 0 rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 28 of36

Appendix 0 Scenario Outline Form ES-D-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: 6 Continued

Event

Description:

Procedure E-1 I ATC/BOP I Determine if Transfer to Cold Leg Recire is required.

Check RWST Level < 11.5 feet(Panel SBF-1 or SB_F-c-2c.L)_ _ _ _ _ _ _--I1 BOP Check at least one recirc flowpath using Recire Pumps Available

31 or 32 Recirc Pump Available! (Panel SBF-1)

Discharge Valves 1802A or B Open (Panel SBF-1)

31 RHR Heat Exchanger o 822A Open/Available o 638 Open/Available o 747 Open/Available o 899B Open/Available o 888A AND 888B Both Closed o 745A AND 745B Both Open

32 RHR Heat Exchanger o 822B Open/Available o 640 Open/Available o 746 Open/Available o 899A Open/Available o S88A AND 888B Both Closed

CCW System and at least 1 CCW Pump Available

At least 1 NOI1 Essential Service Water Pump Available

MCC36A or MCC36B Energized U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 29 of36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: ~ Event No.: 6 Continued Event

Description:

Procedure E-1 Check at least one rec:irc flowpath usin~1 RHR Pumps Available

31 or 32 RHR Pump Available (Panel SBF-1)

Containment Sump to RHR Pumps 885A AND 885B Open/Available (Panel SBF-1)

744 and 882 Available

31 RHR Heat Exchanger 0 822A Open/Available 0 638 Open/Available 0 747 Open/Available 0 899B Open/Available 0 888A AND 888B Both Closed 0 745A AND 745B Both Open OR

32 RHR Heat Exchanger 0 822B Open/Available 0 640 Open/Available a 746 Open/Available 0 899A Open/Available 0 888A AND 888B Both Closed

CCW System and at least 1 CCW Pump Available

At least 1 Non Essential Service Water Pump Available I

MCC36A or MCC36B Energized U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 30 of36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: Scenario No.: -+/-- Event No.: 6 Continued i Event

Description:

Procedure E-1 Check at least one recirc f10wpath using High Head SI Pumps Available

One HHSI Pump Available (Panel S8F-1)

One Recirc or RHR Pump capable of supplying HHSI Pump o 1802A or 8 Available if using Recirc o 885A AND 8858 Available If using RHR (Panel S8F-1)

31 RHR Heat Exchanger o 822A Open/Available o 638 Open/Available o 747 Open/Available o 8998 Open/Available o 888A AND 8888 80th Closed I

o 745A AND 7458 80th Open

32 RHR Heat Exchanger o 8228 Open/Available o 640 Open/Available o 746 Open/Available o 899A Open/Available o 888A AND 8888 80th Closed

High Head V'3lves Available o 744 AND 882 Available o 842 OR 843 Available o 887A AN D 8878 Available o 851A OR 8518 Available o 1810 Available o 743 OR 1870 Available o 850A AND 850C Available if 31 HHSI Pump to be used o 1852A OR 18528 Available if 32 or 33 HHSI Pump to be used o 1835A OR 18358 Available if 32 or 33 HHSI Pump to be used o 1813 Available U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown I Control Bank D rod will fail to insert Stuck IMisaJigned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 31 of36

Appendix 0 Scenario Outline Op-Test No.: _1_ Scenario No.: --1... Event No.: 6 Continued Event

Description:

Procedure E-1 I

CCW System and at least 1 CCW Pump Available

At least 1 Non Essential Service Water Pump Available

MCC36A or MCC36B Energized CRS IF unable to verify 1 low-head or 1 High-head Recirculation Flowpath Available, Transition to ECA-1.1 BOP Determine if PAB Conditions Normal

R-64, 55 Ft Elev Composite PAB

R-65, 73 Ft Elev Composite PAS

R-66, 34 Ft Elev Composite PAB

R-67, 41 Ft Elev Composite PAB

R-68, 15 Ft Elev Composite PAB

R-69, 54 Ft EI Pipe Pen Comp

PAB & TRENCH AREA HI TEMP alarm on SDF panel - NOT LIT CRS/BOP IF PAS Radiation Is NOT Normal

Try to identify and isolate leakave

If loss of RCS outside Containment is in progress, Transition to ECA-1.2 CRS/BOP Direct Watch Chemist to sample:

Ruptured SGs o Activity o Boron

RCS o Activity o Boron o Hydrogen

Containment Atmospere o Activity o Hydrogen

Recirc Sump o Boron o CI o 02 o pH U3 NRC Scenario 4. PT-404 Failure High Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 32 of36

Appendix D Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.:...i.. Event No.: 6 Continued Event

Description:

Procedure E-1 CRS/BOP Determine availability of the following:

Charging Pumps

Safety Injection Pumps

RHR Pumps

Recirc Pumps

Auxiliary Feedwater Pumps

Component Cooling Water Pumps

Service Water Pumps

Containment Spray System

Containment Isolation System

Hydrogen Recombiner

Fan Cooler Units

PAB Exhaust Fans

Diesel Generators

Offsite Power

480V Safeguards Buses

125V BatteriE!S

Instrument Air System and PORV Nitrogen Backup I BOP Place Hydrogen Monitoring System in service Emergency Director of any systems/Equipment NOT available.

U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all Sl Pumps results in FR-C.2 Page 33 of36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: ~ Event No.:-.!L Event

Description:

Degraded Core Cooling F~R-C.2 Time Position Examinee's Actions or Behavior CRS Transition to FR-C.2 BOP Verify 51 Valve Alignment Proper

Attachment 1 Injection phase 51 Valve Lineup BOP/ATC Verify 51 Flow in all Trains

Check High Head Flow Indicated 0 No Flow Indicated 0 Establish Maximllm Charging with all Available Pumps ATC Check RC5 Pressure Less Than 360 psig to check if RHR should be verified.

Pressure is greater than 360.

ATC Check RC5 Vent Path

Check Power to PORV Block Valves 0 Power is NOT available to MOV-535

Valve was open when bus de-energized

Expect valve OPEN

Check PORVs Closed

Check Block Valves at least one OPEN 0 MOV 536 is OPEN ATC Check RCP Status

All RCPs should be secured BOP Check Core Cooling

Check RVLlS Full Range NOT greater than 33%

BOP Check power to accumulator isolation valves status

Power available 0 Discharge NPO to energize valves

Discharge valves OPEN U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS n~quired shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 34 of36

Appendix 0 Scenario Outline Form ES-O-1 Op-Test No.: _1_ Scenario No.: ~ Event No.:.JL

Event I 10,.,,.,,,,'101'1 Core FR-C.2 ATC Check intact SG levels

Any greater than or equal to 9%

o IncreSlse feed flow to restore narrow range level> 9% in at least one SG

Control feed flow to maintain level between 9 and 50%

ATC Depressurize All Intact SG to 175 psig

Maintain cooldown rate in RCS cold legs < 10Qo F/hr

Dump steam to condensers o If condensers not available o Manually open SG Atmospherics

Check SG pressure < 175 and Temp < 390 0 If not i Terminate scenario when cooldown established.

U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 35 of36

Appendix 0 Scenario Outline Form ES-D-1 Post Scenario Event Classification Event Classification - Site Area Emergency EAL 1.1.2 RED path in F-O.1 Subcriticality AND ALL manual attempts at tripping the reactor from the control room have failed to reduce power range < 5%

Also possible:

EAL -1.2.1 ORANGE or RED path in F-O.2 CORE COOLING U3 NRC Scenario 4. PT-404 Failure High - Manual control MFW Pumps; Fault on Bus 6A; TS required shutdown; During Shutdown 1 Control Bank D rod will fail to insert Stuck IMisaligned Rod; SBLOCA; Reactor will not trip, ATWS Local trip successful; Auto SI Fails; Loss of all SI Pumps results in FR-C.2 Page 36 of36

v t e Letter Sequence Other
TAC:U01866, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML13066A337, ML13066A354, ML13066A461, ML13066A514, ML13109A406
MONTHYEAR2013-02-27 [Table View]

ML13066A514

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