Text

Initial Exam 2010-301 Final Simulator Scenarios
	ML101520379
Person / Time
Site:	Oconee
Issue date:	05/04/2010
From:	; NRC/RGN-II
To:	; Duke Energy Carolinas
References
	50-269/10-301, 50-270/10-301, 50-287/10-301
	Download: ML101520379 (78)
	v • d • e

Appendix D 0 Scenario Outline Scenario Outline Form Form ES-D-1 ES-D-1 3/10 3/10 Facility: Oconee Facility: Oconee Scenario No.:

Scenario No.: 1I Op-Test No.:

Op-Test No.: 1 Examiners:

Examiners: Operators:

Operators: SRO OATC BOP Initial Conditions:

. 65% Reactor Power Turnover:

. Place the 11AA Main FDW Pump on Handjack Event Maif. No.

Malf. Type*

Event Type* Event No. Description Oa Pre-lnsert Pre-Insert Switch will not stop 11B2 B2 RCP when directed by Rule 2 AOR Ob Pre-Insert 11 HP-3 fails to close on ES AOR Oc Pre-lnsert Pre-Insert All turbine trips bypassed AOR 1

1 Override N, BOP, SRO Place 11A Handjack A Main Feedwater Pump on Handiack 2 MSS 200 C, BOP, SRO Vacuum Leak 3 MPS 247 C, BOP, SRO 1 B1 1 Bi RCP lower seal fails (Requires pump shutdown) 4 MPI 281 MPI281 I, OATC, SRO ICS fails to re-ratio Feedwater 5 MPS 248 C, ALL C,ALL RCS Leak (1 B1 RCP middle and upper seals fail) (TS)

MPS 249 6 R, OATC, SRO Manual plant shutdown 7 Pre-Insert C, OATC, SRO Turbine fails to trip requiring EHC pumps lockout 8 MPS 400 M, ALL SBLOCA (LOSCM to LOCA CD) 11HP-3 fails to close on ES Switch will NOT stop 1B2 1B2 RCP when directed by Rule 22

(N)ormal, (R)eactivity, (I(I)nstrument

)nstrument, (C)omponent, (C)omponent (M)ajor Page Page 11 ofof 19 19

Appendix 0D Scenario Outline Scenario Outline Form Form ES-O-2 ES-D-2 Op-Test No.:

Op-Test No.: 11 Scenario No.:

Scenario No.: 1I Event No.:

Event No.: 1I Page Page 11 of of 11 Event

Description:

Event

Description:

Place 1A Place IA Main Main Feedwater Feedwater Pump Pump on Handjack: (N; on Handjack: (N; BOP, BOP, SRO)

SRO)

Time Position Applicants Actions or Behavior Applicant's Crew response:

BOP OP/I/Ni 106/002 B Enclosure 4.10 (Placing 1A OP/1/A/1106/002 IA FDWPT On Handjack)

Ensure 1A1A MAIN FDW PUMP (ICS) in "HAND".

HAND.

NOTE:

Control of 1A FDWPT with 1A FDWPT Motor Speed Changer indicated when 1A FDWPT speed and/or suction flow decreases.

Two successful decreases should be achieved to ensure control.

Run 11A A FDWPT Motor Speed Changer down to control 11A A FDWPT.

NOTE:

Handjack "ON" ON simulates Motor Gear Unit at high speed stop.

When Handjack switch is placed to on FDWPT speed may increase -40 40 rpm.

Turn FDWPT 1A HANDJACK switch to "ON". ON.

1A FDWPT speed now controlled with 1A FDWPT Motor Speed Changer.

Record on Turnover Sheet control of 1 1A A FDWPT on Motor Speed Changer.

Tb SHEET" Place "T/O SHEET CR tag on 1A MAIN FDW PUMP (ICS) station.

When the IA 1A Main Main FDW FDW pump is on pump is on Handjack Handjack or or when when directed directed by by the the Lead Lead Examiner Examiner this this event event is is completed.

completed.

Page2ofl9 Page 2 of 19

Appendix DD Scenario Scenario Outline Outline Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 11 Scenario No.:

Scenario No.: 1I Event No.:

Event No.: 22 Page 11 of Page of 11 Event

Description:

Event

Description:

Leak: (C; Vacuum Leak: BOP, SRO)

(C; BOP, SRO)

Time Position Applicants Actions or Behavior Applicant's Plant response:

- 1SA-031A-6, COND VACUUM LOW 1SA-03/A-6,

OAC alarm, Main Condenser Vacuum LOW Crew response:

AP127, Loss of Condenser Vacuum.

Refer to the ARG and AP/27, BOP Refer to AP/27:

SRO BOP

Announce AP entry using PA system.

IAAT condenser vacuum is s; 22" 22 Hg, THEN trip RX.

Dispatch operators to perform Enc!. End. 5.1 (Main Vacuum Pump Alignment) and look for vacuum leaks.

Booth cue: Notify CR that USING TIME COMPRESSION, Main Vacuum Pumps are aligned per Encl.End. 5.1.

Start all Main Vacuum Pumps.

Ensure 1V-186 is closed.

Ensure Stm to Stm Air Eject A, B, C > > 255 psig.

Verify Stm Seal Hdr Press> 1.5 1 .5 psig.

Start 1 1D D CCW pump to ensure all CCW pumps operating.

Booth cue: Call Control Room as the NED NEO and report that a leak was found on the 1 lB B Main FDW Pump pumping trap sight glass and has been isolated.

Verify Condensate flow flow;:: 2300 gpm.

WHEN condenser vacuum is stable, AND End Encl 5.1 (Main Vacuum Pump Alignment) is complete, THEN EXIT this procedure.

When vacuum has has been been recovered or or when when directed directed by by the Lead Lead Examiner, Examiner, the event event is is complete.

Page Page 33 of of 19 19

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 1I Event No.: 3 Page 11 of 2 Event

Description:

1IBI B1 RCP lower Seal Failure: (C, BOP, SRO)

Time Position j Applicants Actions or Behavior Applicant's Plant response:

1SA-06/C-5, RC PUMP 1B1 IBI CAVITY PRESS HI/LOW

1SA-06/C-6, RC PUMP 1B1 SEAL RETURN FLOW HI/LOW Crew response:

BOP AP/1 6 Refer to the ARGs; Refer to AP/16 AP/1 6 , Abnormal RCP Operations Refer to AP/16 ,

SRO

Check if any RCP Immediate Trip Criteria (ITC) met. RNO- (Go to step 4.12)

SRO

Announce AP entry on plant page BOP

Notify OSM to request evaluation by RCP Component Engineer.

IAAT the failure is identified, THEN GO TO the applicable section: (GO TO Section 4A- Seal Failure)

IAAT - Check for ITC. RNO- (Go to step 12 of Section 4A)

any of the following indicate external RCP seal leakage:

IAAT fly

~ RB RIAs increasing or in alarm (RIA-4, 43 - 46)

~ RCS Tave constant with LOST LDST level decreasing more than normal

~ Quench Tank level rate increasing

~ RB Normal Sump rate increasing THEN initiate AP/02 (Excessive RCS Leakage).

Verify the following are open:

~ 1HP-20

~ 1HP-21

Verify 11HP-232 HP-232 is open

IAAT Based on #1 seal delta P; Go To Step 16 to shutdown 1B1 RCP.

Verify Mode 1 1 or 2

Verify three RCPs will remain operating after affected RCP is tripped Page4ofl9 Page 4 of 19

Appendix D Appendix D Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:

No.: _ _ Scenario No.:

Scenario No.: 1I Event No.:

Event No.: 3 Page 22 of Page of 22 Event

Description:

Event

Description:

1IBI RCP lower B1 RCP lower Seal Seal Failure:

Failure: (C, BOP!SRO)

(C, BOP/SRO)

Time Position Applicants Actions or Behavior Applicant's BOP

Verify Rx power is ~ <70%

70%

Verify any jy SG not on Low Level Limits

Verify FDW masters in Auto

StopIBIRCP Stop 1B1 RCP

- Verify ICS re-ratios feedwater

End 4.3 (Special Instructions for <

Initiate Encl < 4 RCP Operation) of OP/i/Ni 102/004 OP/1/A/1102/004

IAAT RCP has been shut down for >30 minutes, THEN close the associated RCP motor cooler inlet/outlet valve (1 LPSW-9 & 10)

When the I1BI B1 RCP has been securedsecured or when directed by the Lead Examiner, Examiner, the event is is complete.

Page Page 55 of of 19 19

Appendix D Appendix D Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:

No.: _ _ Scenario No.:

Scenario No.: 1I Event No.:

Event No.: 44 Page 11 of Page of 22 Event

Description:

Event

Description:

ICS fails to re-ratio les re-ratio Feedwater Feedwater (I, (I, OATC, OATC, SRO)

SRO)

Time Position Applicants Actions or Behavior Applicant's Plant response:

When the 11 B Bi1 RCP is secured the ATC TC controller will fail at - +3.5

+35 Feedwater flow will continue to increase to the 1A SG and decrease to the 1I B SG causing the actual ATc \Tc to become increasingly negative.

Crew response:

OATC/SRO OATCISRO API16 (Continued)

AP/16 (Continued) establish O°F

Verify ICS re-ratios feedwater to establish::::: 0°F b.Tc.

NOTE: ATC controller will fail in auto aHa flUll'tlal~

Place DELTA Tc station in HAND.

achieve 0° b.

Manually adjust DELTA Tc station to achieve::::: k Tc.

2 i

CAUTION:

Total feedwater flow should be maintained constant to prevent changes in core reactivity.

IF DELTA Tc station does NOT control, THEN perform the following:

o Place 1AlAand and 1lBB FDW MASTERs in HAND:

Manually adjust FDW masters to achieve:::::

achieve 0° b.Tc.

tiTc.

o Initiate AP128 (lOS Instrument Failure).

AP/28 (ICS Note: FDW Master toggle switches will have to be used to adjust ATc. aTc.

Decrease the 1A IA and Increase the 18 lB

Initiate End Ene! 4.3 (Special Instructions for << 4 RCP Operation) of OP/i/All 102/004 (Operation at Power).

OP/1/A/1102/004

IAAT any of the following indicate external RCP seal leakage:

o RB RIAs increasing or in alarm ooRCS RCS Tave constant with LDST level decreasing more than normal o Quench Tank level rate increasing o RB Normal Normal Sump Sump rate increasing oo Visual confirmation THEN initiate AP/02 (Excessive RCS Leakage).Leakage).

Verify 11HP-20 HP-20 and and 11HP-21 HP-21 are open:

1HP-232 is

Verify 1HP-232 is open.

open.

Page Page 66 of of 19 19

Appendix D Scenario Outline Scenario Form ES-D-2 No.: _ _

Op-Test No.: No.: 1I Scenario No.: Event No.:

Event No.: 4 Page 22 of 2 Page Event

Description:

Event

Description:

les ICS fails to re-ratio Feedwater (I,(I, OATC, SRO)

SRO)

Time Position Applicants Actions or Behavior Applicant's Crew response: (Continued)

OATC/SRO AP128 AP/28 BOP

AP128:

Verify entry into AP/28:

Power>3%

o Power> 3%

o PTR actions taken and TPB :s; the pre-transient power level AND Delta Tc has failed.

Verify that current thermal power best is :s; pre-transient thermal power best and that the plant is stable.

Notify Rx Engineering to provide Control Room with a maneuvering plan.

GO TO the applicable section (4F - Delta Tc) per the following table:

4F - Delta Tc

~ Ensure the following in HAND:

11AFDW A FDW MASTER

11BFDWMASTER B FDW MASTER

DELTATc DELTA Tc

~ establish OaF Re-ratio feedwater flow, as required, to establish:::: 0°F DELTA Tc while maintaining total feedwater flow constant.

~ Notify SPOC to perform the following:

Investigate and repair the failed Delta Tc controller.

~ WHEN notified by SPOC that Delta Tc controller has been repaired, THEN GO TO Ene! End 5.1 (Placing ICS lCS in AUTO).

When the plant is stable and SPOC has been notified, or when directed by the Lead Examiner this event is completed.

Page 77 of 19 19

Appendix 00 Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 1I Event No.: 5 Page 11 of 2 Event

Description:

RCS Leak RCS Leak - 1I B1

- BI RCP RCP middle and upper upper seals fail, (C, All) (TS)

Time Position Applicants Actions or Behavior Applicant's Plant response:

11 SA-6/C-5, RC Pump 11 B1 Bi Seal Cavity Press Hi/Low

11SA-6/C-6, SA-61C-6, RC Pump 11 B1 Seal Return Flow Hi/Low

11 B1 BI RCP lower pump cavity pressure will equal upper seal cavity pressure.

LDST level will decrease as - 80 gpm will leak out of the RCS through the failed pump seals.

Reactor Building Normal Sump level will increase.

Crew response:

AP16

Per IAAT (Section 4A - Step 12), indication of external seal leakage, SRO/

OATC/ BOP OATC/BOP THEN initiate AP/2 (Excessive RCS Leakage).

AP2

Verify HPI operating.

IAAT RC makeup flow is is>> 100 gpm, AND Pzr level is decreasing, THEN close 1 1HP-5.

HP-5.

IAAT RCS leakage> NORMAL MAKEUP CAPABILITY with letdown isolated, AND Pzr level decreasing, THEN trip Rx.

Initiate makeup to LDST using EOP Encl (Pzr and LDST Level End 5.5 (pzr Control), as necessary EOP Encl End 5.5 (pzr LDST Level Control)

(Pzr and LOST BOP

Utilize the following as necessary to maintain Pzr level >100 >100" [180

[180" acc]:

o Standby HPI pump o 1 1HP-26 HP-26 o 1 1HP-7 HP-7 o IHP-5 1HP-5 o 11HP-i 20 setpoint or valve demand HP-120

IAAT> 1 1 HPI pump is operating, AND additional HPI pumps are NO longer needed, THEN perform the following:

o Obtain SRO concurrence to reduce running HPI pumps.

o Secure the desired HPI pumps.

o Place secured HPI pump switch in AUTO, if desired.

IAAT LDST level CANNOT be maintained, o Open 1 1HP-24.

HP-24.

o Open 1HP-25.

1HP-25.

o Close 1HP-16.

Page 88 of 19 19

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ No.: 1I Scenario No.: Event No.: 5 Page 2 of 2 Page Event

Description:

RCS Leak - 1I B1

- BI RCP middle and upper seals fail, (C, All) (TS)

Time Position Applicants Actions or Behavior Applicant's Crew response:

AP2 (Continued)

BOP/SRO

Announce AP entry using the PA system.

Make notifications to OSM, STA, & RP

Monitor OAC for leak trends/data

- End 5.1 (Leak Rate Determination).

Initiate Ene!

Calculation of RCS Volume Loss:

LeakRate=

Leak Rate = +

+ - ___ - ___

- - =___

=

MU SI LD TSR Where: MU = Makeup Flow

=

SI = Seal Inlet Hdr Flow LD = Letdown Flow TSR = = Total Seal Return Flow

Go To Step 4.145 based on leakage from RCP seal failure

Discontinue pumping RBNS since leak> 10 gpm

IAAT leak rate>rate > TS, THEN initiate shutdown by one of the following:

AP/29 (Rapid Unit Shutdown)

OP/11A111021004 (Operation At Power)

OP/1/A/1102/004

OP/i/All 102/010 OP/1/A/11 02/01 0 (Controlling Procedure For Unit Shutdown).

NOTE: Crew will use AP/29 AP129 NOTE: LCO 3.4.13 (RCS operational LEAKAGE)

RCS operational LEAKAGE shall be limited to:

No pressure boundary LEAKAGE;

1I gpm unidentified LEAKAGE;

10 10 gpm identified LEAKAGE; and

150 150 gallons per day primary to secondary LEAKAGE When plant shutdown has been directed or when directed by the Lead Examiner this event is completed.

Page Page 99 of 19 19

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 1 I Event No.: 6 Page 11 of 2 Event

Description:

Manual Reactor power decrease: (R, OATC, SRO)

Time Position Applicants Applicant's Actions or Behavior Crew response:

AP/29 (Rapid Unit Shutdown)

NOTE SRO The CR SRO should read this procedure and it should NOT be used when EOP entry conditions exist.

BOP BOP

End 5.1 (Support Actions During Rapid Unit Shutdown).

Initiate Encl

Announce AP entry using the PA system.

Verify ICS in AUTO.

NOTE: ICS is in MANUAL. The OATC will use the Reactor Diamond and the FDW masters to reduce power.

OATC RNO: Initiate manual power reduction to desired power level.

Verify both Main FDWPs operating.

Verify 1 1B B FDWP to be shut down first.

Adjust the FWP bias counterclockwise to lower 11 B B FDWP suction flow -

1 1066 Ib/hr 1 x 10 lb/hr < 1A

< 1A FDWP suction flow.

WHEN core thermal power is < <65%

65% FP, THEN continue.

IAAT any of the following statalarms are received:

1SA-16/A-1 (FWP (FWPA A FLOW MINIMUM)

1SA-16/A-2 (FWP A FLOW BELOW MIN)

1SA-16/A-3 (FWP B B FLOW MINIMUM)

1SA-16/A-4 1 SA-16/A-4 (FWP B FLOW BELOW MIN),

THEN trip the 1 lB B Main FDWP.

Verify Turbine-Generator shutdown is required.

Start the TURBINE TURNING GEAR OIL PUMP.

Start 1A through 1 1 E TURBINE BRNG OIL LIFT PUMPS.

Start the TURBINE MOTOR SUCTION PUMP.

WHEN NI power::;

power 18%,

THEN depress turbine TRIP pushbutton.

Page 10 of 19

Appendix DD Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:

Op-Test No.: _ _ Scenario No.:

Scenario No.: 1I Event No.:

Event No.: 66 Page 22 of Page of 22 Event

Description:

Event

Description:

Manual Reactor Manual Reactor power power decrease:

decrease: (R,(R, OATC, OATC, SRO)

SRO)

Time Position Applicants Actions or Behavior Applicant's Crew response:

End 5.1 (Support Actions During Rapid Unit Shutdown).

Encl BOlD BOP

WOO SRO to initiate Encl Notify WCC End 5.2 (WCC (WOO SRO Support During Rapid Unit Shutdown).

Start the following pumps:

1A and 1lB B FDWP SEAL INJECTION PUMP

1A and 1lB B FDWP AUXILIARY OIL PUMP

Stop 11 E1 El and 1I E2 HTR DRN PUMPs. (already off)

Verify Turbine-Generator shutdown is required.

Place the following transfer switches to MAN:

11TA TA and 1 1TB TB AUTO/MAN

ITA SU 6.9 KV FOR Close 1TA FDR and verify 1TA NORMAL 6.9 KV FOR FDR opens.

Close 1TB SU 6.9 KV FOR FDR and verify 1TB NORMAL 6.9 KV FOR FDR opens.

Place the following transfer switches to MAN:

MFB1 and MFB2 AUTO/MAN

1 MFB1 STARTUP FOR El Close E11 FDR and verify N11 1 MFB1 NORMAL FOR Ni FDR opens.

Close E2 1

E21 MFB2 STARTUP FDR FOR and verify N2 1

N21 MFB2 NORMAL FDRFOR opens.

Notify OR CR SRO that Unit auxiliaries have been transferred.

WHEN CTP :s; 65%,

THEN place 11FDW-53 and 11FDW-65 in MANUAL and close:

Ensure lA1A and lB1B MSRH DRN PUMP is stopped.

Place 11HD-37 and 11HD-52 HD-52 in DUMP.

DUMP.

WHEN CTPis60%,

CTP is:s; 60%,

THEN ensure 1SSH-9 1SSH-9 closed.

When the OATC has reduced power - 10%, 10%, or when directed directed by the Lead Examiner this event is is completed.

Page Page 11 11 of of 19 19

Appendix D Outline Scenario Outline Form ES-D-2 ES-D-2 No.: _ _

Op-Test No.: No.: 1I Scenario No.: Event No.:

Event No.: 7 Page 11 of of 11 Event

Description:

Event Main Turbine Fails to trip (Lockout EHC Pumps) Pumps) (C, OATC)

Note: Reactor will trip as a result of the SBLOCA in event 8.

Time Position Applicants Actions or Behavior Applicant's Plant response:

Plant

11 SA-9/A-6, RB Reactor Building Normal Sump Level High/Low

1iSA-i/A-i, B-i, C-1, SA-1/A-1, B-1, C-i, D-1, RP Channel Trip

11 SA-2/D-3, RC Press High/Low

A SBLOCA will result in a reactor trip.

The Main Turbine should trip but does not. This will result in a reduction of steam pressure in both SGs until actions are taken to trip the turbine. This will result in RCS overcooling until the turbine is tripped.

Crew response:

- SRO will enter the EOP.

SRO

OATC will perform Immediate Manual Actions

Depress REACTOR TRIP pushbutton OATC

Verify reactor power < < 5% FP and decreasing

Depress turbine TRIP pushbutton.

Verify all turbine stop valves closed Note: The OATC should diagnose that the turbine did not trip and then perform the RNO step which will stop and lock out both EHC pumps. This will cause the turbine to trip. (CT-18)

Verify RCP seal injection available.

BOP will perform a symptom check.

BOP Event is complete when EHC pumps have been tripped or when directed by the Lead Examiner.

12 of 19 Page 12 19

Appendix D Appendix D Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: _ _ Scenario No.:

Scenario No.: 1I Event No.:

Event No.: 88 Page Page 11 of of 66 Event

Description:

Event

Description:

Small Break Small Break LOCA:

LOCA: (M, (M, ALL)

ALL)

Time Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior Plant response:

Plant response:

- Statalarms:

Statalarms:

- 1SA-91A-6, RB 1SA-9/A-6, RB Reactor Reactor Bldg Bldg Norm Norm Sump Level High/Low Sump Level High/Low

- 11SA-81B-9, Process Radiation SA-8/B-9, Process Radiation Monitor Monitor High High

- Control board Control board indications:

indications:

- RBNS level RBNS level increases increases

PZR level will decrease very slowly PZR level slowly due to the the leak leak and 11 HP-5 HP-5 being being closed.

closed.

Crew response:

SRO The SRO will refer to EOP Subsequent Actions; Parallel Actions page.

The SRO will receive Symptoms Check/Report from one of the ROs.

The SRO will direct one of the ROs to perform EOP Enc!. End. 5.1 (ES Actuation)

Note: The RCS will eventually saturate with all HPI injecting.

The SRO will provide concurrence to the other RO to perform Rule 2 - Loss of Subcooling Margin.

Verify all control rods fully inserted.

Verify Main FDW in operation.

Verify Main FDW controlling properly.

Verify TBVs controlling SG pressurepressure::::: 1010 psig.

Verify 11RIA-40 operable.

Dispatch an operator with End End 5.29 (MSRV (MSRV Locations) to verify all MSRVs MSRVs have reseated.

- Verify Verify ES ES is is required.

required.

Ensure Ensure ES ES 5.15.1 (ES (ES Actuation) is is in in progress Page Page 13 13 of of 19 19

Appendix 0D Scenario Outline Scenario Outline Form Form ES-O-2 ES-D-2 Op-Test No.:

Op-Test No.: _ _ Scenario No.:

Scenario No.: 1I Event No.:

Event No.: 88 Page 22 of Page of 66 Event

Description:

Event

Description:

Small Break Small Break LOCA:

LOCA: (M, ALL)

(M, ALL)

Time Position Applicants Actions or Behavior Applicant's Behavior OATC/

- When ES Channels 11 and 2 actuate, an operator should inform the SRO that ES BOP Channels 11 and 2 have actuated.

- End. 5.1, ES Actuation per the Parallel The SRO should direct initiation of EOP Encl.

SRO Actions page of Subsequent Actions section or of the LOSCM Tab.

- End. 5.1, the operator will:

When running Encl.

OATC/

BOP ** Determine which ES channels should have actuated and verify all "Blue Blue Lights" Lights White Lights" and White Lights are lighted for the appropriate channels.

- Place HPI in Manual.

- Verify Rule 2 in progress or complete.

- Determine NO RCPs operating and GO TO Step 8.

Note: ES Channels 1-thru-6 may actuate due to High Reactor Building Pressure; therefore the ES Actuation Checklist may be performed in a staggered fashion as the various ES Channels are actuated.

- Place LPI pumps and 11LP-17/18 LP-17/18 in manual control.

CAUTION LPI pump damage may occur if operated in excess of 30 minutes against a shutoff head.

- IAAT y any LPI pump is operating against a shutoff head, THEN at the CR SROs discretion, stop affected LPI pumps SRO's

- Ensure A & Band B and 3A & 3B Outside Air Booster Fans are operating. (CT-27)

- Verify 1CF-1/2 ICF-1/2 open.

- Verify IHP-410 1HP-41 0 closed.

- Secure makeup to the LDST.

- Verify all ES Channel 1 4 components are in the ES position.

Note: I1 HP-3 will not close. The operator should diagnose this and perform the RNO and close IHP-I 1 HP-1 located on IUBI.

1 UB1.

- Close 1LPSW-139 1LPSW-139

- Fail Open 1LPSW-251/252 1LPSW-251/252

- Open I1LPSW-4/5 LPSW-4/5

- Dispatch Dispatch anan operator operator to perform perform End.

Encl. 5.2 5.2 (Placing RB Hydrogen Hydrogen Analyzers Analyzers InIn Service)

Service)

- Notify Notify U2 U2 CR CR SRO SRO that that SSF SSF is is inoperable inoperable due due to OTS1-1 open.

open.

- The operator operator must must get get SRO SRO approval approval toto exit exit this enclosure.

Page Page 1414 of of 19 19

Appendix DD Scenario Scenario Outline Outline Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: _ _ Scenario No.:

Scenario No.: 1I Event No.:

Event No.: 88 Page Page 33 of of 66 Event

Description:

Event

Description:

Small Break Small Break LOCA:

LOCA: (M, ALL)

(M, ALL)

Time Position Position Applicants Actions or Behavior Applicant's Behavior Plant response:

RCS subcooling margin (§!JY)

(y) will = 0°F.

= OaF.

Crew response:

SRO SRO

The BOP/OATC should inform the SRO that the RCS has saturated and obtain SRO concurrence to perform Rule #2, Loss of SCM.

BOP/

Verify that reactor power is < 11 %.

OATC

mm of LOSCM)

Stop all RCPs (within 2 min (CT-I)

(CT-1)

Note: 11B2 B2 RCP will not trip from the switch. RNO will be performed to de- de energize 1T ITA A and 1TB ITB (6.9KV switchgear).

Step 2 RNO

Place 1TA AUTO/MAN switch in MAN.

Place 1TB AUTO/MAN switch in MAN.

Open 1TA SU 6.9 KV FDR.

HA

Open 1TB 1 TB SU 6.9 KV FDR.

Notify CR SRO of RCP status.

Verify that HPI is performing as required and notify CR SRO of HPI status.

Verify that LPI flow in both headers is < <3400 3400 gpm.

Verify that TBVs are available.

Select OFF for both digital channels on AFIS HEADER A and B.

Start both MD EFDW pumps and establish 300 gpm to each SG. Feed to LOSCM SP per Rule 77 (SG Feed Control). (CT-b)

(CT-10)

Verify both MDEFDWPs operating.

Ensure TDEFDWP is in PULL TO LOCK.

Trip both MFDWPs and close the FDW block valves (FDW-33, 31, 31,42,40) 42, 40)

Notify SRO of SG feed status.

Maintain SG pressure << RCS pressure using TBVs.

Ensure Rule 33 is in progress or complete.

Page Page 15 15 of of 19 19

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 1I Event No.: 8 Page 4 of 6 Page Event

Description:

Small Break LOCA: (M, ALL)

Time Position Applicants Actions or Behavior Applicant's Crew response:

Rule 3:

BOP/

IAAT NO SGs can be fed with FDW (Main/CBP/Emergency),

OATC OATe AND any of the following exist:

o RCS pressure reaches 2300 psig OR NDT limit oRCS o Pzr level reaches 375"375 [340"

[340 acc]

THEN PERFORM Rule 4

Start EFDW pumps to feed all intact SGs.

Verify any EFDW pump operating.

IAAT Unit 1 I EFDW is in operation, THEN initiate Ene!End 5.9 (Extended EFDW Operation).

End 5.9 (Extended EFDW Operation Encl

Monitor EFDW parameters on EFW graphic display.

Perform the following as required to maintain UST level> level > 7.5':

7.5:

o Makeup with demin water.

o Place CST pumps in AUTO.

IAAT all the following exist:

o Rapid cooldown NOT in progress o MD EFDWP operating for each available SG o EFDW flow in each header << 600 gpm THEN place 1 1 TD EFDW PUMP switch in PULL TO LOCK.

Notify CR SRO to set priority based on the NOTE above and EOP activities.

Page 16 16 of 19 19

Appendix D0 Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 1I Event No.: 8 Page 5 of 6 Event

Description:

Small Break LOCA: (M, ALL)

Time Position Applicants Actions or Behavior Applicant's SRO

The SRO should GO TO the LOSCM Tab per the Parallel Actions page of the EOP Subsequent Actions section. LOSCM Tab will:

Ensure that Rule #2 is in progress or complete.

Verify that station ASW is NOT feeding any SG.

Verify that the LOSCM is NOT caused by excessive heat transfer.

Verify transfer to LOCA CD tab not required due to no LPI flow.

Verify that the SSF is NOT activated.

Verify all the following conditions exist:

~ NO RCPs are operating

~ HPI flow exists in both HPI headers

~

> Adequate Total HPI flow per figure 1 1 (Total Required HPI Flow)

Open 11AS-40 AS-40 while closing 1 I MS-47.

Control steaming and feed rates on all intact SGs to maintain cooldown rate within Tech Spec limits:

~

> Tc ~ 280°F Tc>280°F <5O°F/4hour

50°FI y; hour

~ Tc<280°F Tc < 280°F <25°F/1/4

25°FI Y; hour

Utilize TBVs

GO TO Step 92.

Close 1 1 RC-4 (No HPI forced cooling in progress)

Close 1GWD-17, 1HP-1, 1 1HP-2, 1RC-3.

HP-2, 1 RC-3.

Maintain SG pressure < RCS pressure utilizing either TBVs or ADVs (TBVs).

Verify primary to secondary heat transfer exists.

End 5.16 (SG Tube-to-Shelll1 Initiate Encl Tube-to-Shell iT T Control).

Verify CETCs increasing.

Verify required RCS makeup flow NOT within normal makeup capability.

GO TO LOCA CD tab.

Page 17 of 19

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 1I Event No.: 8 Page 6 of 6 Event

Description:

Small Break LOCA: (M, ALL)

Time Position

[ Crew response:

Applicant's Applicants Actions or Behavior SRO LOCA LOCACD CD tab:

Ensure all RBCUs in low speed.

Open 1LPSW-18.

Open 11 LPSW-21.

Open 11 LPSW-24.

End 5.35 (Containment Isolation).

Initiate Ene!

Start all RB Aux fans.

End 5.36 (Equipment Alignment For Plant Shutdown).

Initiate Ene!

Select OFF for both digital channels on AFIS HEADER A and B.

Notify Chemistry to sample the RCS boron hourly

Initiate determination of minimum required boron concentration for MODE 5 5 using either of the following:

Reactor Engineer

PT/i/A/i 103/015 (Reactivity Balance Procedure)

PT/1/A/1103/015

Initiate steaming all intact SGs to cooldown to cooldown plateau at ~ 50°F/Yz 2 hr 50°F/Y using either of the following:

TBVs

ADVs Event and exam is complete when directed by the Lead Examiner.

Page 18 of 19

Appendix D D Scenario Outline Form ES-D-2 CRITICAL TASKS 1.

1. CT-18, Turbine Trip CT-1, Trip All RCPs

2. CT-I, CT-10, Establish FW Flow and Feed SGs

3. CT-b,

4. CT-27, Implementation of Control Room Habitability Guidance Page 19 of 19

Simulator BrieflTurnover SAFETYIPRA RISK (OSM)

SAFETY/PRA 3Ar~"1 : Take a Minute I SAFETY:

I PRA Risk Status: GREEN F UNIT 0 (OSM (OSM)

SSF 0Operable: '"Yes II KHUs II UI - OH, U2 - UG

's Operable: U1 - - LOTs Operable: 2 LeTs II Fuel Handling: None II L UNIT STATUS (CR SRO)

Unit 1 I Simulator Other Units Mode: 1 1 Unit 2 Unit 33 Reactor Power: 65% Mode: 11 Mode: 1 1 Gross MWE: 586 100% Power 100% Power RCS Leakage: .025 gpm EFOW EFDW Backup: Yes EFOW EFDW Backup: Yes SpecificationslSLC Items (CR SRO)

Technical Specifications/SLC Component/Train Corn ponentlTrain OOS Restoration Required TSISLC #

TS/SLC Date/Time DatelTime Date/Time DatelTirne Shift Turnover Items (CR SRO)

Primary

. 492 EFPO EFPD

. Two hours ago power was decreased from 100% for possible work on the 1A Main FOW FDW pump.

. Rx Engineering is developing a maneuvering plan to maintain current power level.

Secondary

. 1 SSH-1, 1 1SSH-1, SSH-3, 1 1SSH-3, SO-2, 1 1SD-2, SO-5, 1SO-140, 1SO-303, 1SO-355, 1SO-356 and 1 1SD-5,1SD-140,ISD-303,1SD-355,ISD-356 SO-358 are closed with ISD-358 power supply breakers open per the Startup Procedure for SSF Overcooling Event. 1 1 PR-1, PR-i, 1 1 PR-6, 1

1 LPSW-1, LPSW-i, 1 1 LPSW-2, 1 I LPSW-3, 1I FOW-80, FDW-80, 1 I CF-5, 1 1 CF-6, 1 I LP-1 LP-i and 1 1 LP-2 breakers open per the appropriate system operating procedures.

. Unit 3 has the Aux Steam Header

. OP/i/Ni 102/004 Operation at Power in progress. Enc. 4.2 is complete up through step 2.19.

OP/1/A/1102/004

. After shift turnover, place the 1A IA Main FDW pump on Handjack per OP/1/Al1106/002 0P111A111061002 B Enclosure 4.10 (Placing 1A IA FDWPT On Handjack)

Reactivity Management (CR SRO)

RCS Boron: 30 ppm ppmB B I Gp 7 Rod Position: 79%

I I Batch additions as required for volume control.

1/

Human Performance Emphasis (OSM)

Procedure Use and Adherence 1 RO Scenario 1

Appendix D Appendix D Scenario Outline Scenario Outline Form Form ES-D-1 ES-D-1 3/10 3/10 Facility: Oconee Facility: Oconee Scenario No.:

Scenario No.: 22 Op-Test Op-Test No.:

No.: 1I Examiners:

Examiners: Operators:

Operators: SRO OATC BOP Initial Conditions:

Initial Conditions:

. 1100% Reactor power 00% Reactor power Turnover:

. SASS inin Manual Manual

- ICS CS in in manual ready to return manual and ready return to Auto Event Maif. No.

Malf. Type*

Event Type* Event No. Description Oa Pre-Insert SASS in Manual Ob ICS in Manual 11 N, OATC, SRO Place ICS in Auto 2 Override C, BOP, SRO Operating LPSW Pump trips and Standby fails to start (TS)

Updater MPIO21 MPI021 C, BOP, Inadvertent ES Channels 2 actuation (TS) 3 OATC, SRO 4 MCS 004 I, OATC, SRO Controlling Tave fails hiQh ControllinQ high 5 Override C, BOP, SRO 1A 1A CBP Trip and 1 lB B CBP fails to Auto Start.

MSS 460 6 MSS 010 M, ALL M,ALL Loss of Main and Emergency Feedwater MSS 020 MSS 260 LOHT Tab MSS 270 CBP feed 77 Override ALL CBPs trip I/ HPI Forced Forced cooling I1HP-26 HP-26 fails to open open HPI HPI CD CD Tab

(N)ormal, (N)ormal (R)eactivity, (R)eactivity, (l)nstrument, (I)nstrument, (C)omponent, (C)omponent, (M)ajor (M)ajor

Appendix D Appendix D Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 1I Scenario No.:

Scenario No.: 22 Event Event No.:

No.: 1I Page Page 11 of of 22 Event

Description:

Place Event

Description:

Place ICS ICS in in AUTO:

AUTO: (C; (C; OATC, OATC, SRO)

SRO)

Time Time Position Position Applicants Actions or Applicant's or Behavior Behavior response:

Crew response:

Crew OATC/SRO OATC/SRO OP/1/A/1102/004 OP/i/Ni 102/004 A End. 4.4 will direct the OATC to:

A Encl.

RATE SET" Ensure "RATE SET thumbwheels at 0.0.

IF MASTER is IF TURBINE MASTER is in HAND, perform in "HAND", perform Section Section 3 (Placing (Placing Turbine To Auto).

Turbine is in AUTO

HAND, perform Section 4 (Placing TBV To Auto).

IF either TBV is in "HAND",

TBVsareinAUTO

TBVs are in AUTO

IF REACTOR MASTER OR DIAMOND is in manual, perform Section 5 (Placing Rx To Auto).

HAND, perform the following:

IF Rx Master is in "HAND",

MANUAL.

Ensure DIAMOND is in "MANUAL".

Place REACTOR MASTER to "AUTO". AUTO.

IF selected Tave (01 E2086) is different from Tave setpoint (01 E2087) by more than +/- 0.3°F, perform the following:

o Simultaneously ensure 1A and 11 B FDW MASTER in "HAND" HAND o On REACTOR MASTER adjust Tave setpoint (01 E2087) towards selected Tave (01 E2086).

o Verify selected Tave is within +/-+/- 0.3°F of Tave setpoint.

o Place DIAMOND in AUTO.

"AUTO".

o Return to Section 2 (Procedure).

IF DELTA Tc is in HAND, "HAND", perform Section 66 (Placing DELTA Tc To Auto).

DELTA Tc is in AUTO "AUTO" Page of 16 Page 22 of 16

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1I Scenario No.: 2 Event No.: 1I Event Page 2 of 2 Page Event

Description:

Place ICS ICS in AUTO: (C; OATC, SRO)

Time Position Applicants Actions or Behavior Applicant's Crew response:

OATC/SRO

IF STM GENERATOR MASTER or either FDW MASTER is in "HAND", HAND, perform Section 7 (Placing FDW To Auto).

HAND, perform the following:

IF SG Master is in "HAND",

SG Master is in AUTO.

IF either 1A OR 1 lB AUTO, perform the following:

B FDW Master is NOT in "AUTO",

1A Select 1A and 1 lBB FDW MASTER to "MEAS VAR MEAS VAR"

IF both 1A and 1BlB FDW Master Measured Variables are on the caret:

o Select 1A and 1 lB POS B FDW MASTER to "POS" o Simultaneously ensure 1A and 1 lB B FDW MASTER in "AUTO" AUTO

HAND, perform Section 8 (Placing FDW IF any FDW valves are in "HAND",

Valves To Auto).

All FDW valves are in AUTO

HAND, perform Section 9 (Placing Main IF either Main FDW Pump is in "HAND",

FDW Pumps To Auto).

Both FDW pumps are in AUTO.

NOTE: ICS 105 must be in full auto before adjusting any setpoint to minimize possible CTP changes. (R.M.)

The SRO will verify ICS lOS in full Auto.

When the ICS has been placed in AUTO, or when directed by the Lead Examiner this event is is completed.

Page3of Page 3 of 16 16

Appendix DD Appendix Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 1I Scenario No.:

Scenario No.: 22 Event No.: 22 Event No.: Page Page 11 of of 11 Event

Description:

Event

Description:

Operating LPSW Operating LPSW pumppump trips, trips, Standby Standby fails fails to to auto auto start:

start:

(C, BOP, (C, BOP, SRO)

SRO) (TS)(TS)

Time Time Position Position ApplicanVs Actions Applicant's Actions oror Behavior Behavior Plant response:

Plant response:

- 11 SA-9/A-9 SA-91A-9 (LPSW (LPSW Header Header AA Press Press Low)

Low)

- LPSW Header LPSW Header AlB Pressure Low A/B Pressure Low - gauge

- gauge

- BB LPSW LPSW pumppump trips trips Crew response:

Refer to ARG for 11 SA-9/A-9 Refer SA-9/A-9 (LPSW (LPSW Header Header AlB Press Low)

A/B Press Low)

~ AP124 (Loss of LPSW)

Refer to AP/24 AP/24 (Loss of LPSW)

SRO/BOP

Verify Unit 11 is going to handle LPSW system operations.

Verify

Determine no LPSW pump is cavitating

Start available (NOT previously cavitating) LPSW pumps, as necessary, to raise LPSW header pressure.

Verify normal LPSW System operation is restored.

SRO SRO Note: The SRO should direct a call to SPOC SP~C to troubleshoot the reason for the LPSW pump tripping and the Auto Start failure.

The SRO should refer to TS:

TS 3.7.7 (Low Pressure Service Water System) Condition A "A" applies.

Restore required LPSW pump to operable status. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time.

time.

TS 3.3.28 (LPSW pump Auto-Start Circuitry) Condition A. "A". Restore Auto-Start Circuitry to operable.

operable. 77 day day completion time.

Event Event is is complete complete whenwhen SROSRO hashas referred referred toto TS TS or or when when directed directed by by the Lead the Lead Examiner.

Examiner.

Page4ofl6 Page 4 of 16

Appendix D Appendix D Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 1I Scenario No.:

Scenario No.: 22 Event No.:

Event No.: 33 Page 11 of Page of 33 Event

Description:

Event

Description:

Inadvertent Inadvertent ES Channels 22 actuation:

ES Channels actuation: (C, (C, OATC/BOP/SRO)

OATC/BOPISRO)

Time Position Position j Applicants Actions or Applicant's Behavior or Behavior Plant response:

Plant response:

Statalarms:

iSA-i/B-iC, ES CHANNEL 2 TRIP 1SA-1/B-10, Control Board indications:

ES Channel 2 actuate

HPI Injection in "B" B header

Letdown isolated

Keowee emergency start Crew response:

Determine that ES actuation was NOT valid and inform the SRO.

BOP

Crew may perform Plant Transient Response.

ALL

The SRO should enter AP/42 (Inadvertent ES Actuation)

SRO

AP/42 (Inadvertent ES Actuation) Actions:

Place HPI in MANUAL on RZ Modules BOP

- Throttle HPI

Secure the 1C1C HPI pump

Close 1HP-25 1HP-25

Direct the BOP to perform End. End. 5.1 (Side Board Board Action)

Notify Notify the OSM and STA

Direct Direct the the OATC OATC toto perform perform End.

End. 5.2 5.2 (Letdown (Letdown Restoration)

Restoration)

Page Page 55 of of 16 16

Appendix DD Appendix Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 1I Scenario No.:

Scenario No.: 22 Event No.:

Event No.: 33 Page 22 of Page of 33 Event

Description:

Event

Description:

Inadvertent Inadvertent ES ES Channels Channels 22 actuation:

actuation: (C, (C, OATC/BOP/SRO)

OATCIBOP/SRO)

Time Time Position Position Applicants Actions or Applicant's or Behavior Behavior Crew response:

Crew response:

BOP BOP

perform Enc!.

BOP will perform BOP End. 5.1 (Side Board Action)

(Side Board

Open 11 HP-20 and 11 HP-21 HP-21 (Seal Return)

Return)

Open 11 HP-228, 226, 232, and 230 (Seal Return Stop)

Place the following in MANUAL on the RZ Module and OPEN:

11 PR-7, 11 PR-9 (RB RIAs)

11PR-8, PR-8, 11PR-10 PR-1 0 (RB RIAs)

Start the 11 RIA-47 RB RIA sample pump from the ENABLE CONTROLS screen on the RIA View Node.

NOTE: Must select "OFF" OFF on sample pump before it can be restarted.

OATC

End. 5.2 (Letdown Restoration)

Encl.

Verify CC pump operating

Verify letdown is isolated

Close 1HP-5 (LETDOWN ISOLATION)

Open 1HP-1, 1HP-1, 1HP-2, 1HP-2, 1HP-3, 1HP-3, and 1HP-4 1HP-4 (lAand (1Aand lB1B Letdown Cooler Inlet and Outlet)

Close 1HP-6 1HP-6 (LETDOWN ORIFICE STOP)

Close 1HP-7 (LETDOWN CONTROL)

Close *1HP-7 CONTROL)

Open 1HP-5 1HP-5 (LETDOWN ISOLATION) ISOLATION)

Adjust 11HP-7 HP-7 for for::::: 20 20 gpm gpm letdown letdown

Open Open 1HP-6 1HP-6 (LETDOWN ORIFICE ORIFICE STOP)

STOP)

Adjust Adjust 11HP-7 HP-7 toto control control desired desired letdown letdown flow (75 (75 gpm) gpm)

Page Page 66 of of 16 16

Appendix D Appendix D Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:

Op-Test No.: 1I Scenario No.:

No.: 2 Event No.:

Event No.: 3 Page 33 of Page of 33 Event

Description:

Event

Description:

Inadvertent Inadvertent ES Channels 22 actuation:

ES Channels actuation: (C,(C, OATC/BOP/SRO)

OATCIBOPISRO)

Time Position Applicants Actions or Behavior Applicant's Crew response:

SRO

AP142 (Inadvertent ES Actuation) Actions (Continued)

AP/42

Verify ICS inin AUTO

Initiate a power decrease to maintain control rods within the desired band by adjusting rate set as necessary and decrease CTP demand setpoint.

Notify Chemistry for RCS and LDST boron sample

Notify Rx Engineering to develop a maneuvering plan

Place LOAD SHED & STBY BKR 11 and 2 in MANUAL on the RZ Module

Dispatch an operator to perform End. 5.3 (SSF Restoration)

Notify SPOC to investigate and repair the failed ES components

IAAT Rx power is stable THEN initiate evaluation of NI operability in accordance with OP/1/A/11 OP/1/AJ1IO2/004 02/004 (Operation At Power) Limits and Precautions.

Initiate logging TS/SLC Entry/Exit as applicable, lAW Encl. End. 5.4 (TSISLC Requirements)

(TS/SLC (TS) 3.3.7 ESPS Digital Automatic Actuation Logic Channels o TS 3.3.7-Condition A; Place associated component(s) in ES configuration OR Declare the associated component(s) inoperable within 1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

o TS 3.3.6 - ESPS Manual Instrumentation Condition A; Restore channel to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months o TS 3.4.15 - RCS Leakage Detection Instrumentation Condition B; Analyze grab samples of the containment atmosphere once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . (can be exited once End. 5.1, Side Board Actions completed) o TS 3.4.9 - Pressurizer Condition A; Restore level within limit within 11 hour1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months Note:

Note: Should enter ONLY if if Pzr Pzr level level exceeds exceeds 260 260 inches inches

WHEN all the following exist:

o Cause of inadvertent ES ES resolved o ES ES Channel reset is is desired desired o OSM concurs THEN continue.

THEN When plant plant isis stable stable and and Letdown Letdown has has been restored, or or when when directed directed by by the Lead Lead Examiner the event event isis completed.

completed.

Page Page 77 of of 16 16

Appendix DD Appendix Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 1I Scenario No.:

Scenario No.: 22 Event No.:

Event No.: 44 Page Page 11 ofof 11 Event

Description:

Event

Description:

Controlling Controlling Tave Tave fails fails HIGH (I, OATC, HIGH (I, OATC, SRO)SRO)

Time_j Time Position Position Applicants Actions or Applicant's or Behavior Behavior Plant response:

Plant response:

- 1SA-02/A-12, ICS 1SA-02/A-12, lOS Tracking, will actuate actuate due due to neutron neutron and and feedwater cross-limits.

cross-limits.

- Controlling Tave will indicate Controlling indicate == 596.4° F.F. (Failed (Failed HIGH)

HIGH)

- Actual loop A A & B Tave will decrease until operator stops transient.

RCS pressure and temperature will decrease.

Crew response:

Statalarms; candidates perform "Plant Plant Transient Response" Response process to stabilize the plant.

>-> Verbalize to the SRO reactor power level and direction of movement.

>-> Place the Diamond and both FDW Masters in manual and adjust.

FDW should be decreased to below pre-transient level and Control SRO/OATC SROIOATC Rods may be inserted to stop RCS pressure increase

The SRO should:

>- Refer to AP/28, AP!28, ICSCS Instrument Failures

>-> Contact SP~CSPOC to repair controlling Tave.

Note: The ICS remains in manual for the rest of scenario.

AP128 AP/28 (ICS(lOS Instrument Failures)

Verify plant conditions are controlled or stable as indicated by the SRO following:

NI power change < <2%

2% from current NI power indication AND thermal OATC best pre-transient power level power best::;

Tave change < < 2°F from current Tave indication

THP/SG Outlet Press. change <30 < 30 psig from current THP/SG Outlet Press.

RCS pressure change << 150 150 psig from current RCS pressure

Provide control bands - see Placard (OMP 1-18) 1-18)

Make notifications (OSM, (OSM, STA)

Verify aa power power transient has has occurred

Notify Rx Engineering Engineering to discuss need for aa power maneuvering plan BOP

GO TO section 4A (RCS Temperature Failure)

Notify Notify SPOC SP~C to to repair failed instrument instrument

PERFORM PERFORM an an instrumentation surveillance surveillance using using applicable applicable table table in in End Encl 5.3 5.3 (ICS (ICS Instrument Instrument Surveillances)

Surveillances) for for the the failed instrument.

instrument.

When When The The SRO SRO Directs Directs Performing Performing End. Encl. 5.3 Or At 5.3 Or At The The Discretion Discretion Of Of The The Lead Lead Examiner Examiner this this event event is is completed.

completed.

Page Page 88 of of 16 16

Appendix DD Appendix Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.: 1I Op-Test No.: Scenario No.:

Scenario No.: 22 Event No.:

Event No.: 55 Page Page 11 of of 22 Event

Description:

Event

Description:

IA CBP 1A CBP TripTrip and and 1B lB CBP CBP fails fails to AUTO Start:

to AUTO Start: (C,(C, BOP/SRO)

BOPISRO)

Time Position Position Applicants Actions Applicant's Actions or Behavior Behavior

Response

Plant Response:

Plant

- 11SA-2/A-11 SA-2/A-11 ICSICSRUNBACK RUNBACK BOPISRO BOP/SRO ** 11SA-8/A-1 SA-8/A-1 FDW SUCTION PRESSURE LOW LOW

Powdex Bypasses at 360 psig FDWP FDWP Suction Pressure.

Pressure.

11 C-61 opens bypassing the Hydrogen Coolers @ © 235 psig (on either FDWP/ 2 out of 3 logic) FDWP Suction Pressure FDWP/2 Crew Response:

Crew will take one of two paths:

Path #1

Crew will manually start the 1 1 B CBP SRO!BOP SRO/BOP

/OATC

Refer to ARG Path #2

Crew will perform Plant Transient Response (PTR)

BOP should determine that a valid ICS runback signal is present but the runback is NOT in progress (for C/FDW suction pressure) due to ICS in MANUAL.

SRO will enter AP/1 (Unit Runback) and go to section 4D

Direct the OATC to manually reduce power with FDW and the Diamond until the runback clears. ( (=== 85%)

When the plant is stable/controllable OR as directed by ARG 11SA-8/A-1 SA-8/A-1 FDW SUCTION PRESSURE LOW the team should elect to manually start the lB

'1 B' CBP (standby).

Manual Actions

IF IF standby Condensate Booster Pump has NOT NOT started, start any available CBP manually Note: If Note: If the unit trips the unit trips initiate initiate event event 6.

6.

The event The event isis complete when the complete when the reactor reactor trips, trips, thethe plant plant is is stabilized stabilized atat 85% power,

- 85% power, oror when when determined determined by by the the Lead Lead Examiner.

Examiner.

Page Page 99 of of 16 16

Appendix D Appendix D Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:

Op-Test No.: 1I Scenario No.:

Scenario No.: 22 Event No.:

Event No.: 55 Page 22 of Page of 22 Event

Description:

Event

Description:

IA CBP 1A CBP Trip and and 1BlB CBP CBP fails to Start: (C, to AUTO Start: (C, BOP/SRO)

BOPISRO)

Time Position Applicants Actions or Behavior Applicant's Crew Response:

Note: If the plant does NOT trip, the crew may reset 1I C-61 and restore the SRO/BOP Powdex as described below.

/OATC

Reset 110-61 C-61 when FDWP suction pressure ;::235 235 psig (OP/1/A/11 (OP/i/Ni 106/002 06/002 Condensate and Feedwater, Enclosure 4.22- Resetting 110-61 C-61 Controller) as follows:

10-61 is in Manual Ensure 1C-61

Manually adjust 11C-6i C-61 controller demand to 85-95%

Verify 0101417 01D1417 (Generator Water Cooler Condensate Diff) Duff) value FALSE "FALSE"

Throttle closed 110-61 LP C-61 to establish 5-16 ft H20 L\P

Ensure adjusted 110-61 AP C-61 setpoint to match actual L\P

Ensure 110-61 AUTO C-61 to "AUTO"

(OP/I/Ni 106/002 Restore Powdex to service per (OP/1/A/11 06/002 Condensate and Feedwater; Enclosure 4.19- Placing Powdex In/Out of Service)

When FDWP suction pressure is > > 360 psig place the Powdex In iC-14/15 while maintaining CBP Service by slowly throttling closed on 1C-14/15 pressure 70 psig.

suction pressure;::

Note: If the unit trips initiate event 6.

The event event isis complete when the reactor trips, the plantplant is is stabilized at at

- 85%

85% power, power, oror when when determined determined byby the Lead Lead Examiner.

Examiner.

Page Page 1010 of of 16 16

Appendix DD Appendix Outline Scenario Outline Scenario Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 1I Scenario No.:

Scenario No.: 22 Event No.:

Event No.: 66 Page Page 11 of of 33 Event

Description:

Event

Description:

Loss of Main Loss of Main and and Emergency FDW, LOHT, Emergency FDW, LOHT, CBP CBP Feed Feed (M, (M, ALL)

ALL)

Time Position Position Applicants Actions or Behavior Applicant's Behavior Plant Response:

Plant Response:

When directed by the Lead Examiner, a Loss Loss of Main Main and Emergency Emergency Feedwater will occur.

Feedwater Crew Response:

Perform Immediate Manual Actions (IMAs)

Depress REACTOR TRIP pushbutton.

Verify reactor power < < 5% FP and decreasing.

Depress turbine TRIP pushbutton.

SRO/OATC

Verify all turbine stop valves closed.

Verify RCP seal injection available.

BOP will perform a Symptom Check and initiate Rule 3 (Loss of Main and /I or Emergency Feedwater)

SRO will transfer to the Loss Of Heat Transfer Tab BOP Rule 3 (MainlCBPlEmergency), AND any

IAAT NO SGs can be fed with FDW (Main/CBP/Emergency),

of the following exist:

o RCS pressure reaches 2300 psig OR NOT oRCS NDT limit o Pzr level reaches 375 [340 acc]

375" [340" THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).

Start EFDW pumps to feed all intact SGs.

Place the following in MANUAL and close:

1FDW-315 1FDW-315

1FDW-316 1FDW-316

Verify both of the following:

Any CBP CBP operating

TBVs available on an an intact SG

Select OFF for both digital digital channels on AFIS HEADER HEADER A.

Select OFF for both Select OFF digital channels both digital channels on on AFIS HEADER HEADER B. B.

Page 11 of Page 11 of 16 16

0 Appendix D Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:

Op-Test No.: 1I Scenario No.:

Scenario No.: 2 Event No.: 6 Event No.: Page 2 of Page of 3 Event

Description:

Loss of Main and and Emergency FDW, FDW, LOHT, CBP Feed Feed (M, ALL)

Time Position Applicants Actions or Behavior Applicant's Crew Response:

Rule 3 (Continued)

BOP

Place 11 FDW-33 and 1I FDW-42 control switches in OPEN:

- Simultaneously position Startup Control valves (1 FDW-35 11 FDW-44) 10

- 20% open on §l!

- all intact SGs:

Perform the following:

Place 11 FDW-31 switch in CLOSE.

Place 11 FDW-40 switch in CLOSE.

Close 11 FDW-32.

Close 1FDW-41.

Lower SG pressure in available SGs to:::::to 500 psig.

Control FDW flow to stabilize RCS PIT P/T by throttling the Startup Control valves and TBVs as necessary:

Place 11 FDW-38 and 11 FDW-47 switches to OPEN

Place 11 FDW-36 and 11 FDW-45 switches to CLOSE

Dispatch an operator to perform Ene!End 5.26 (Manual Start of TDEFDWP).

Verify cross-tie with Unit 2 is desired.

Dispatch an operator to open 2FDW-313 and 2FDW-314

Dispatch an operator to 11 FDW-313 FDW-31 3 and have them notify the CR when in position.

NotifyUnit2to:

Notify Unit 2 to:

Manually Close 2FDW-315 & 316.

Start their U2 TDEFWP

WHEN, either of the following exists: 11 FDW-313 FDW-31 3 Operator in position OR Unit 1 1 TDEFWP has been manually started; THEN continue.

Page 1212 of 16 16

Appendix DD Appendix Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 1I Scenario No.:

Scenario No.: 22 Event No.: 66 Event No.: Page Page 33 of of 33 Event

Description:

Event

Description:

Loss Loss of of Main Main and Emergency FDW, and Emergency LOHT, CBP FDW, LOHT, Feed (M, CBP Feed ALL)

(M, ALL)

Time Position Position Applicants Actions or Applicant's Behavior or Behavior Crew Response:

Crew Response:

Loss Of Heat Transfer Tab

IAAT NO SGs can be IAAT be fed with FDW FDW (Main/CBP/Emergency), AND any jy SRO of the following exist:

o RCS pressure reaches 2300 psig OR NDT limit oRCS o Pzr level reaches 375" 375 [340"

[340 acc]

THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).

NOTE: 1A1 IAI RCP provides the best Pzr spray.

Reduce operating RCPs to one pump/loop.

WHEN y any of the following exists:

o Unit 1 1 EFDW available BOP o EFDW aligned from another unit THEN GO TO Step 48 EOP Enclosure 5.5 BOP/OATC

Utilize the following as necessary to maintain Pzr level >1OQ[18Qacc]:

>10Q"[18Q"acc]:

o Standby HPI pump o 1 1HP-26 HP-26 o 1HP-7 1HP-7 o 1HP-5 1HP-5 o 11HP-i HP-12020 setpoint or valve demand

IAAT> 11 HPI pump is operating,

AND additional HPI pumps are NO longer needed, needed,

THEN perform the following:

oo Obtain SRO concurrence concurrence to reduce running HPI HPI pumps.

o Secure the desired HPI HPI pumps.

oo Place secured HPI HPI pump switch in AUTO, if desired.

desired.

IAAT IAAT LDST LDST level CANNOT be level CANNOT be maintained, maintained,

. Open 1HP-24.

oo . Open 1HP-24.

oo . Open 1HP-25

. 1HP-25 oo Close Close 1HP-16.

1HP-16.

When When RCS RCS temperature temperature is is stabilized stabilized on on Condensate Condensate Booster Booster Pump Pump feed, or when feed, or when directed directed by the Lead by the Lead Examiner Examiner this this event event is is completed.

completed.

Page Page 13 of 16 13 of 16

Appendix DD Appendix Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:

Op-Test No.: 1I Scenario No.:

Scenario No.: 22 Event No.:

Event No.: 77 Page Page 11 of of 22 Event

Description:

Event

Description:

CBPs CBPs Trip, HPI Forced Trip, HPI Forced Cooling, Cooling, Spray Spray Valve Valve Fails Fails Closed Closed (ALL)

(ALL)

Time Position Position Applicants Actions or Behavior Applicant's Behavior Plant Response:

Plant Response:

- CBPs CBP5 trip trip

Feedwater flow decreases

RCS temperature increases Crew Response:

SRO SRO SRO may direct RO to re-perform Rule 3 psig RCS pressure, direct performance of Rule 4 (HPI Forced At 2300 psiq Cooling).

BOP/OATC Rule 4 (CT-14) (Within 5 minutes of meeting criteria)

Open 11HP-24 HP-24 and 11HP-25.

HP-25.

Start ill!

aM available HPI pumps.

Open 1 1HP-26 HP-26 and 1 1HP-27 HP-27 IHP-26 will NOT open (1HP-410 Note: 1HP-26 (IHP-4I0 must be opened; per Step below)

Open 1 1RC-4.

RC-4.

Verify flow exists in y any HPI header.

Open PORV. (Switch to OPEN, depress OPEN permit)

least two HPI pumps operating.

Verify at ast

Verify flow in both HPI headers is in the acceptable region of Figure 11

Open IHP-410 1HP-410 (Flow is unacceptable in IA 1A HPI Header)

Stop all but one RCP (1A1 (1A 1 RCP provides the best Spray Spray flow)

De-energize all Pzr heaters.

Close 1HP-5.

1HP-5.

Verify HPI HPI Forced Forced Cooling Cooling initiated due to initiated due to aa loss loss of of CBP CBP feed.

Close Close TBVs, TBVs, 11FDW-35 FDW-35 andand 11FDW-44.

FDW-44.

Page 14 of Page 14 of 16 16

Appendix D Outline Scenario Outline Form ES-D-2 Op-Test No.: 1I No.: 2 Scenario No.: Event No.: 7 Page 2 of 2 Event

Description:

CBPs trip, HPI HPI Forced Cooling, Spray Valve Fails Fails Closed (ALL)

Time Position j Applicants Actions or Behavior Applicant's Crew Response:

SRO LOHT tab

PERFORM Rule 4 (Initiation of HPI Forced Cooling).

Verify all the following:

At least two HPI pumps operating

Acceptable HPI flow exists in both HPI headers per Rule 4

PORVopen PORV open

1 1RC-4 RC-4 open

GO TO HPI CD tab.

SRO/OATC/

SROIOA TCI HPI CD tab BOP

Verify all of the following exist:

Verify.§ll PORV open

PORVopen 1 RC-4 open

1RC-4

Two HPI trains injecting

CETCs 640°F :s

Ensure all RBCUs in low speed.

Open 1LPSW-18, 1 1LPSW-21 LPSW-21 and 1 1LPSW-24.

LPSW-24.

End 5.35 (Containment Isolation)

Initiate Ene!

Start A & B B Outside Air Booster Fans (CT-27)

Notify Unit 3 to start 3A and 3B Outside Air Booster Fans When SRO transfers to HPI CD tab, or when directed by the lead examiner this event is completed.

Page 15 15 of 16 16

0 Appendix D Scenario Outline Form ES-D-2 CRITICAL TASKS

1. CT-14, Initiate HPI Cooling 1.

2. CT-27, Implementation of Control Room Habitability Guidance (Optional if crew progresses this far)

Page 16 16 of 16 16

BrieflTurnover Simulator Brief/Turnover Simulator SAFETYIPRA RISK SAFETY/PRA RISK (OSM)

(OSM)

SAFETY: Take aa Minute I y: Take Minute PRA

. .r Risk

,~" 'Status: GREEN

... a .... S: GREEN UNIT 0 (OSM UNITO (OSM)

SSF SSF Operable:

Operable: Yes II KHUs Operable:

KHU's Operable: U1UI - OH,

- OH, U2 U2 - UG

- UG I LeTs Operable: 22 II LCTs Operable: Fuel Handling:

Fuel Handling: None None UNIT UNIT STATUS STATUS (CR (CR SRO)

SRO)

Unit 1I Simulator Unit Other Other Units Units Mode: 11 Mode: Unit Unit 2 Unit 3 Reactor Power:

Reactor Power: 100% 100% Mode:

Mode: 1I Mode:

Mode: 11 Gross MWE: 897 100% Power 100% Power RCS Leakage: .01 gpm EFOW EFDW Backup: Yes EFOW EFDW Backup: Yes RBNS Rate: 0 gpm Technical Specifications/SLC Items (CR SRO)

ComponentlTrain Component/Train OOS Restoration Required TSISLC #

TS/SLC DatelTime Date/Time Date/Time DatelTime Shift Turnover Items (CR SRO)

Primary

. 420 EFPO EFPD

- SASS in Manual Secondary

- 1SSH-1, 1SSH-3, 1SD-2, 1SSH-1, 1SSH-3, 1S0-2, 1SD-5,1SD-140,1SD-303,1SD-355,ISD-356 1S0-5,1S0-140,1S0-303,1S0-355,1S0-356 and 1SD-358 1S0-358 are closed with power supply breakers open per the Startup Procedure for SSF Overcooling Event. 11PR-i, PR-1, 11PR-6, 1LPSW-i, 1LPSW-1, 1LPSW-2,1LPSW-2, 1LPSW-3, 1LPSW-3, 1FDW-80, 1FOW-80, 1CF-5, 1CF-5, ICF-6, 1CF-6, 1LP-1 1LP-1 and ILP-2 1LP-2 breakers open perthe per the appropriate system operating procedures. procedures.

- Unit Unit 33 has has the the Aux Steam Steam Header Header

- Last Last shift shift ICS ICS waswas placed placed in in MANUAL MANUAL for l&E I&E testing testing

- After shift shift turnover, place place ICS ICS in in AUTO perper 0P111A111021004 OP/1/Al1102/004 A End. Encl. 4.4.

4.4.

o0 Initial Initial Conditions Conditions are are complete complete Reactivity Reactivity Management Management (CR (CR SRO)

SRO)

RCS RCS Boron: Boron: 30 30 ppmBppmB I I Gp Gp 77 Rod Rod Position:

Position: 87%

87% III Batch Batch additions additions as as required required for for volume volume control.

control.

Human Human Performance Performance Emphasis Emphasis (OSM) (OSM)

Procedure Procedure Use Use and and Adherence Adherence Scenario 22 RO Scenario RO

Appendix D Appendix D Scenario Scenario Outline Outline Form ES-D-1 Form ES-D-1 3/10 3110 Oconee Facility: Oconee Facility: No.: 33 Scenario No.:

Scenario Op-Test Op-Test No.:

No.: 1 Examiners:

Examiners: Operators:

Operators: SRO OATC BOP Initial Conditions:

Initial Conditions:

Reactor

. Reactor power power == 1100%

00%

Turnover:

. Intermittent Intermittent LPSW LPSW leakleak in RB RB requires frequent RBNS RBNS pumping Event Maif. No.

Malf. Type*

Event Type* Event No. Description Oa Pre- SASS in Manual Insert 11 MPS 290 C, BOP, SRO 1A CC pump trips and 1lB B CC pump fails to auto start Override Override C, OATC, SRO 1HP-120 1 HP-120 (RC Volume Control) fails Closed 2

3 Override I, BOP, SRO Pump RBNS and RBNS Pumps do not auto stop at 6" 6 4 Override C, OATC, SRO 1A HPI Pump trips and standby HPI pump fails to start (TS) 5 Override C, BOP, SRO 1A RBCU cooler rupture (TS) 6 Override I, ALL Turbine trips to hand for unknown reason MCRO21 MCR021 C, OATC, SRO Dropped Control Rod and manual Power Reduction (TS) 7 MCRO22 MCR022 88 MEL 120 120 M, ALL 1TA 1TA Lockout - causes Rx trip due to loss of 22 RCPs

- RCP's MEL 8

eLr,d 180 Override CT-1 Lockout I/ Keowee Unit 11 ELO (Blackout)

CT-i Regain power manually from CT-5.

9 MSS 380 All SGTR requires transfer to SGTR tab to end scenario TDEFWP fails requiring MDEFWPs MDEFWP's

(N)ormal, (N)ormal (R)eactivity, (l)nstrument, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-2 No.: 1I Op-Test No.: Scenario No.:No.: 3 Event No.: 1I Event No.: Page Page 11 of 3 Event

Description:

1A IA CC Pump trips, 1B lB CC Pump Pump Fails Fails to Auto Start: (C; BOP, BOP, SRO)

Time Position__I Position Applicants Actions or Behavior Applicant's Plant response:

11SA-9/B-1, SA-9/B-1, CC CRD RETURN FLOW LOW

11SA-9/C-1, SA-9/C-1, CC COMP COOLING RETURN FLOW LOW

1SA-2/C-1, 1SA-21C-1, LETDOWN TEMPERATURE HIGH

1I HP-5 (Letdown Isolation) will close due to high letdown temperature

CC Total Flow Low

Component Cooling Pressure Low Crew Response:

1 SA-9/B-1 OR 1SA-9/C-1 Refer to ARG 1SA-9/B-1 I SA-9/C-1 BOP

Determine low flow is due to CC Pump failure AND Standby CC Pump did NOT start and perform the following:

Verify CC Surge Tank level> 12" 12

Start Standby CC Pump SRO Note: The SRO may not initiate AP/20 API2O if the Standby Pump is started per the ARG.

Initiate AP/20 (Loss of Component Cooling)

IAAT ~ two CRD stator temperatures ~ 180°F, BOP THEN trip RX. (- ( 4 minutes)

Open 1 1CC-7 CC-7 and 1 1CC-8 CC-8

level 12".

Verify CC Surge Tank level;:: 12.

Manually start the Standby CC Pump

Verify CC TOTAL FLOW> FLOW > 575 gpm

If Letdown> 130 °F, of, THEN:

Close 1 1HP-5, HP-5,

Initiate AP!032 AP/032 (Loss of Letdown)

Page 22 of of 21 21

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1I Scenario Op-Test Scenario No.:

No.: 3 Event No.: 1I Page 2 of 3 Event

Description:

1A IA CC Pump trips, 1B lB CC Pump Pump Fails to Auto Start: (C; BOP, BOP, SRO)

Time Position Applicant's Applicants Actions or Behavior Crew Response:

SRO SRO Directs AP/32 (Loss of Letdown) entry; AP/32 will:

BOP/

BOPI

Place 11 HP-120 in HAND and reduce demand to zero.

OATC

LDST as required (EncI.5.5 or OP/1/A/11 Initiate makeup to LOST OP/i/Ni 103/004.

03/004.

Notify Chemistry of the following:

BOP

Current RCS boron sample is needed for possible unit shutdown.

Normal letdown line is isolated.

IAAT Pzr level ~ 260",

260, AND letdown CANNOT be established, THEN initiate unit shutdown at:::::

at 20%/min 20%/mm per AP/29 (Rapid Unit Shutdown).

IAAT Pzr level ~ 375",

375, THEN trip Rx.

Position the standby HPI pump switch to OFF.

IHP-31 to establish 12 Throttle 1HP-31 12--1515 gpm SEAL INLET HDR FLOW.

Verify HPI pump flow ~ ( gpm Recirc ++ _

65 gpm. (30 SI +_

+ MU)

L/D temperature high and then GO TO Step 4.29.

Verify loss of letdown is due to LID

Notify SPOC to initiate repairs on failed equipment.

IAAT letdown can be re-established, THEN perform Steps 4.31 - 4.46.

Place CC system in operation

Close 1 1HP-6 HP-6 and 1 1HP-7.

HP-7.

Open the following:

- 1 IHP-i HP-1

- 1HP-2 1 HP-2

- 1HP-3 1 HP-3

- 1HP-4 1HP-4 Page 33 of Page of 21 21

Appendix 00 Scenario Outline Form ES-O-2 ES-D-2 Op-Test No.: 1I Scenario No.: 3 Event No.: 1I Page 3 of 33 Event

Description:

Event

Description:

1A IA CC Pump trips, 1lB CC Pump B CCCC Pump Fails to Auto Start: (C; Pump Fails (C; BOP, BOP, SRO)

Time Position Applicants Actions or Behavior Applicant's Crew Response:

SRO!

SRO/

Verify letdown temperature < RNO Step 4.34)

< 135°F (it is not; RNa BOP

Open 11HP-13.

HP-13.

Close the following:

1IHP-8 HP-8

11HP-9&11 HP-9&11

Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.

Open 1I HP-5.

Throttle open 1 1 HP-7 to establish'"

establish 20 gpm.

WHEN letdown temperature < 130°F, THEN place LETDOWN HI TEMP INTLK BYP switch in NORMAL.

Open 11HP-6.

HP-6.

Adjust 11 HP-7 to control desired (75 gpm) letdown flow.

Re-establish normal makeup through 1 1HP-120.

HP-120.

Re-establish normal RCP seal injection flow.

Position the standby HPI pump switch to AUTO.

NOTE: If pressurizer level exceeds 260 inches, TS 3.4.9 Condition A should be entered requiring level be restored within 1 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months This event is complete when Seal Flow is returned to normal (32 gpm) or when directed by the Lead Examiner.

Page4of2l Page 4 of 21

Appendix D Outline Scenario Outline Form ES-D-2 No.: _ _

Op-Test No.: Scenario No.:

Scenario No.: 3 Event No.:

Event No.: 2 Page 11 of 2 Page Event

Description:

Event

Description:

1IHP-120 OATCISRO)

Fails closed (C, OATC/SRO)

HP-120 (RC Volume Control) Fails Time Position Applicants Actions or Behavior Applicant's Plant response:

OATC ** RCS makeup flow goes to -10 10 gpm (HP Injlnj Warming Flow)

PZR level begins to decrease.

LDST level begins to increase.

LOST

Valve position demand for 1HP-120 begins to increase to the 100%

demand value and valve position indication will indicate closed (green light).

The OATC should diagnose the failure and notify the SRO.

Crew response:

APII4 (Loss of Normal Makeup and/or RCP Seal Injection.

Refer to AP/14

IAAT Determine Seal Injection is lost...

indicated...

IAAT loss of suction to HPI pumps is indicated ...

SRO

Announce AP entry using PA system.

OATC

Verify y any HPI pump operating

Verify RCP seal injection or HPI makeup line leak is NOT indicated.

Report of line leak

Abnormal LOST LDST level decrease

11 RIA-32 (AUX BLDG GAS)

1 1RIA-45 RIA-45 (NORM VENT GAS)

RB RIAs in alarm

Abnormal RBNS level increase

Abnormal LAWT or HAWT level increase

Verify RCP seal injection flow exists.

1HP-120 has failed in AUTO and perform the RNO and determine Verify 1HP-120 it will also not work in MANUAL. GO TO Step 4.129.

Perform the following as necessary to maintain Pzr level > 200:

level> 200":

Close 1 1HP-6 HP-6 (Letdown Orifice Stop)

Throttle 1HP-7 1HP-7 (Letdown Control)

Throttle 1HP-26 1HP-26 (1A HP Injection)

Place 1HP-120 1HP-120 to HAND HAND and closed

Contact SPOC to repair 1HP-120.

1HP-120.

Note: IHP-120 1HP-120 will remain failed for the duration of the scenario.

When PZR level is being controlled manually or when directed by the Lead Examiner this event is completed.

Page 55 of 21 21

Appendix DD Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.: _ _ Scenario No.: 33 Event No.: 2 Page 2 of 2 Event

Description:

1IHP-120 Event

Description:

Control) Fails (RC Volume Control)

HP-120 (RC Fails closed (C, (C, OATC/SRO)

OATCISRO)

Time Position Applicants Actions or Behavior Applicant's Crew response:

BOP/OATC Crew may use EOP Enclosure 5.5 (pzr (Pzr and LDST Level Control) for primary inventory control

>100 [180" Utilize the following as necessary to maintain Pzr level >100" [180 acc]:

Standby HPI pump

11HP-26 HP-26

11HP-7HP-7

11HP-5 HP-5

1I HP-120 HP-I 20 setpoint or valve demand

IAAT>> 1I HPI pump is operating, IAAT AND additional HPI pumps are NO longer needed, THEN perform the following:

Obtain SRO concurrence to reduce running HPI pumps.

Secure the desired HPI pumps.

Place secured HPI pump switch in AUTO, if desired.

IAAT LDST level CANNOT be maintained,

THEN Open 1 IHP-24 HP-24 and Open 1 IHP-25; IHP-I6.

HP-25; Close 1 HP-16.

IAAT 1 1C C HPI PUMP is required, THEN Open 1 I HP-24 and 11 HP-25 Start 1 IC C HPI Pump

Throttle 1 1HP-26 HP-26 and 1 HP-27 as required to maintain desired Pzr level:

1HP-27

IAAT makeup to the LOST LDST is desired, THEN makeup from 1A BHUT.

IAAT additional makeup flow to LOST LDST is desired, AND 1A BLEED TRANSFER PUMP is operating, THEN dispatch an operator to close 1CS-48 ICS-48 (1A BHUT RECIRC)

IAAT it is desired to secure makeup to LDST, THEN secure makeup from 1A IA BHUT.

When PZR level is being controlled manually or when directed by the Lead Examiner this event is completed.

Page 6of21 6 of 21

Appendix 0D Scenario Outline ES-D-2 Form ES-O-2 Op-Test No.: _ _

Op-Test Scenario No.: 3 Event No.: 3 Page 11 of 11 Event

Description:

Event

Description:

Pump RBNS, RBNS Pump RBNS, RBNS pumps pumps do NOT NOT auto stop at 6 inches BOP, SRO) inches (I, BOP, Time Position Applicants Actions or Behavior Applicant's Plant response:

Statalarms:

11SA-9/A-6 SA-9/A-6 (REACTOR BUILDING NORMAL SUMP LEVEL HIGH/LOW)

Crew response:

BOP/SRO Refer to 1 1 SA-9/A-6 SA-91A-6 ARG.

High Level:

Align normal sump pump and lower level in sump per OP/1/A/1104/007 (Liquid Waste Disposal System), Encl. End. 4.1 (U1 (Ui RBNS Transfer Mode 1)

Verify MWHUT level adequate to receive waste volume.

Open 1 1LWD-i LWD-1 and 1 1LWD-2 LWD-2 (RB NORMAL SUMP ISOLATION)

Start one or both of the following:

1A RB NORM SUMP PUMP.

1lBB RB NORM SUMP PUMP.

OP/0/B/1 106/033 Investigate possible RCS leakage per OP/0/B/11 06/033 (Primary PT/1/A/0600/0i00 (Reactor Coolant System Leak Identification) or PT/1/A/0600/01 Leakage). (Leakage is known from turnover-LPSW)

Monitor RB RIAs, CC Surge Tank level, CFT Level and LPSW flow to and from RB and sample RB Normal Sump to determine source.

Calculate RB Normal Sump Rate from Digital Trend (Use 15 gal/inch conversion factor).

Refer to AP/11A11700/002 AP/1/A/1700/002 (Excessive RCS Leakage). (Not needed due to knowing the source of the leakage into the RB).

Low Level:

Verify sump pump(s) stopped, and realign valves per OP/1/A/1104/007 OP/i/A/l 104/007 (Liquid Waste Disposal System), Encl. End. 4.1. (U1 (Ui RBNS Transfer Mode 1)

Note: The RBNS pumps will not stop on the low level cutoff. The BOP should recognize this and stop the pumps per procedure.

WHEN RBNS level is at desired level or at 6 6" (low level alarm),

THEN ensure pump(s) stopped.

- Close 1LWD-1 1LWD-1 and 1LWD-2(RB 1LWD-2(RB NORMAL NORMAL SUMP ISOLATION)

Contact SPOC to repair RBNS pump low level cutoff.

When RBNS pumps have been stopped or when directed by the Lead Examiner this event is completed.

Page7of2l Page 7 of 21

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 3 Event No.: 4 Page 11 of 2 Event

Description:

HPI Pump trips and the Standby HPJ A HPJ "A" HPI pump fails to auto start:

(C, OATC, SRO) (TS)

Time Position Applicants Actions or Behavior Applicant's Plant response:

Statalarms:

11SA-2/B-2 SA-2/B-2 (HP RCP Seal Injection Flow High/Low)

11SA-2/C-2 SA-2/C-2 (HP Injection Pump Disch. Header Pressure High/Low)

Board indications:

RC Makeup Flow =

= 0 gpm

1A HPI Pump OFF

PZR level will begin to decrease and LOST LDST level will begin to increase.

BOP Crew response:

SRO ** Refer to ARG for above Statalarms

SRO should refer to APII4 AP/14 (Loss of Normal Makeup and/or RCP Seal Injection)

BOP

IAAT RCP seal injection flow is lost...

IAAT loss of suction to operating HPI pumps is indicated indicated...

Announce AP entry using PA system.

Verify NO HPI pump operating

Close 1 1HP-5 HP-5 (Letdown Isolation)

Place 1 1HP-120 HP-120 (RC Volume Control) in HAND and closed

Place 1 1HP-31 HP-31 (RCP Seal Flow Control) in HAND and closed

Start standby HPI pump (1 (lB B HPI pump)

Place in HAND and slowly open 1 1 HP-31 in small increments until :::::

8 gpm/RCP is achieved.

Re-establish normal makeup through 1 HP-120. (failed closed) 1HP-120.

Ensure proper operation of the CC system.

Reduce 1 1 HP-7 demand to 0%.

Close 1 1HP-6 HP-6

Ensure the following open:

~ 1 1HP-1, HP-1, 11HP-2, 1HP-3, HP-2, 1 HP-3, 1 1HP-4 HP-4 Page 8 of 21

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 3 Event No.: 4 Page 2 of 2 Event

Description:

A HPI Pump trips and the standby HPI pump fails to auto start:

"A" OATCISRO)

(C, OATC/SRO)

Time Position Applicants Actions or Behavior Applicant's

Open 1HP-5

Throttle open 11 HP-7 for:==

for 20 gpm letdown flow.

Open 1 IHP-6 HP-6

Adjust 11 HP-7 for desired letdown flow (75 gpm).

Open 1 1HP-228, HP-228, 11HP-226, HP-226, 1 1HP-232, HP-232, 1 1HP-230.

HP-230.

Open 1 1HP-21 HP-21

Place 11HP-31 HP-31 in auto.

. Refer to Tech Spec 3.5.2 High Pressure Injection SRO

Condition "A" A

Required Action: Restore HPI pump to OPERABLE status

Completion Time: 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Note: Due to sequence of events, SRO may not review the TS during the scenario. Follow-up questions may be required to ensure knowledge of this competency.

Event is complete when normal makeup and letdown is established or when directed by the Lead Examiner.

Page 99 of 21

Appendix D Scenario Outline Form ES-D-2 No.: _ _

Op-Test No.: Scenario No.:

Scenario No.: 3 Event No.:

Event No.: 5 Page 11 of Page of 11 Event

Description:

IA RBCU rupture (C, BOP, SRO) (TS) 1A Time Position Applicants Actions or Behavior Applicant's Plant Response:

11SA-9/B-9, SA-9/B-9, LPSW RBCU A Cooler Rupture

11SA-91A-6, SA-9/A-6, RB Normal Sump Level High/Low

RB normal sump level will increase Crew Response:

BOP BOP ARG for 11 SA-9/B-9 SA-91B-9

Verify alarm is valid by checking RBCU 1A Inlet Flow and RBCU 1A delta flow (327 gpm Delta Flow).

Verify 1LPSW-18 (RBCU 1A Outlet) open

Verify adequate LPSW flow is available; check LPSW pump operation and 11LPSW-16 LPSW-16 (1A RBCU INLET PENE) is open.

Monitor RBNS Level for any unexplained increase

Diagnose a Cooler Rupture is indicated and Isolate the 1A RBCU Cooler.

Close 1LPSW-16 (1A RBCU INLET PENE).

Close 1 1LPSW-18 LPSW-18 (RBCU 1A OUTLET).

Perform TS 3.6.3 Condition C for closed containment system.

SRO

Requires isolating penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

Enter TS 3.6.5 for RBCU inoperable. (TS 3.6.5 Condition B).

Requires restoring RBCU to OPERABLE within 7 days

Refer to SLC 16.9.12 16.9.12 (Additional LPSW and Siphon Seal Water System Operability Requirements) (Not applicable after 1 ILPSW-16 LPSW-16 is closed)

When the RBCU has been isolated, or at the direction of the Lead Examiner this event is completed.

Page 10 of 21 10 of

Appendix D Appendix D Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:

Op-Test No.: _ _ Scenario No.:

Scenario No.: 33 Event No.:

Event No.: 66 Page 11 of Page of 11 Event

Description:

Event

Description:

Turbine Turbine trips trips to to HAND HAND (I, (I, ALL)

ALL)

Time Position Applicants Actions or Behavior Applicant's Plant Response:

Statalarms:

SRO

1SA-2/A-12, ICS 1SA-2/A-12, lOS Tracking

1 SA-2/C1 2, ICS 1SA-2/C-12, los H/A Station on Man Crew Response:

BOP

Refer to ARG for above alarms.

IF Turbine Master Trips to Hand for unknown reason, refer to AP/lIAJl700/028 (ICS AP/1/A/17001028 (105 Instrument Failure).

SRO

AP128 AP/28

GO TO Section 40

Simultaneously place the 1A and 1 1B B FDW MASTERs to HAND:

OATC

Place the DIAMOND in MANUAL.

SP~C to investigate the cause of the Turbine Master tripping Notify SPOC to Hand.

When FDW Masters and Diamond are in MANUAL, or when directed by the Lead Examiner this event is completed.

Page 11 Page 11 of of 21 21

Appendix DD Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: _ _ Scenario No.:

No.: 3 Event NO.:7 Event No. :7 Page 11 of Page of 2 Event

Description:

Event

Description:

Dropped Dropped Control Control Rod,Rod, Manual Manual Power Power Reduction Reduction (C, (C, OATC, SRO) (TS)

(TS)

Time_J Time Position Applicants Actions or Behavior Applicant's Plant Response:

Stat alarm 1ISA2IA1O SA2/A 10 (CRD GLOBAL TROUBLE) 1SA2/B1O (CRD ASYMMETRIC ROD ALARM)

Stat alarm 1SA2/B10 Stat alarm 11SA2/D9 SA2/D9 (CRD OUT INHIBIT)

Crew Response:

SRO SRO SRO should enter AP/1 APII (Unit Runback)

APII Section 4H AP/1

IAAT more than one control rod is dropped or misaligned >6% (> (>9) 9")

from the group average, THEN trip the Rx.

Verify Rx is critical.

Verify Rx runback to 55% FP in progress.

Note: Runback will not be occurring due to ICS in MANUAL.

RNO: Initiate manual power reduction to 55% CTP at ~ 1%/min.

1%Imin.

R OATC R,OATC

OATC will reduce power with FDW Masters, Diamond, and Turbine BOP

End 5.1 (Control of Plant Equipment During Shutdown).

Initiate Encl

Notify SPOC to investigate cause of dropped or misaligned control rod and rreare prepare to reduce the following trip setpoints:

o RPS Flux/Flow-Imbalance o RPS High Flux

Notify the OSM to ensure the requirements of the following Tech Specs are met:

o TS 3.1.4 (Control Rod Group Alignment Limits)

Previously discussed o TS 3.1.5 3.1.5 (Safety (Safety Rod Position Limits)

Condition Condition A - 11 hr

- hr Completion Time o TS 3.2.3 3.2.3 (Quadrant Power Power Tilt)

IF IF QPT exceeds steadysteady state limit, limit, Condition A required. First First action has has 22 hr hr Completion Time NOTE:

NOTE: OSM will be unavailable to make make the TS determination determination and itit will be the responsibility of of the SRO SRO Page Page 12 12 of2l of 21

Appendix DD Appendix Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.: _ _

Op-Test No.: Scenario No.:

Scenario No.: 33 Event No.:

Event No.: 77 Page 22 of Page of 22 Event

Description:

Event

Description:

Dropped Dropped Control Control Rod, Manual Power Rod, Manual Power Reduction Reduction (C, (C, OATC/SRO)

OATCISRO) (TS) (TS)

Time e Position Position Applicants Actions Applicant's Actions or or Behavior Behavior Crew Response:

Crew Response:

SRO should SRO should refer refer to to TS for the dropped TS for dropped control control rod.

rod.

SRO SRO Enter TS 3.1.4 (Control Enter (Control Rod Rod Group Alignment Limits)

Limits) Condition A: (One(One inoperable or not aligned to within 6.5% of its group average trippable CR inoperable height or height or both).

both).

1. Restore Control Rod Alignment within 11 hour1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months OR

2. Verify SDM within 11 hour1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months OR Initiate Boron to restore SDM within 11 hour1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months AND Reduce Thermal Power to ~

< 60% of allowable thermal power within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND (flux/flow/imb) to ~ 65.5%

Reduce nuclear overpower trip setpoints (fluxlflow/imb) of the allowable thermal power within 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months AND Verify the potential ejected rod worth is within assumptions of rod ejection analysis within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months BOP BOP ** Verify> 1 1%

% SDM with allowance for the inoperable control rod per PT/i IA/i 103/015 PT/1/A/11 031015 (Reactivity Balance Calculation).

USE COLR curve for 4 RCPs and 11 inoperable rod.

Ensure requirements of TS 3.1.5 (Safety Rod Position Limits) ofTS

Ensure requirements of TS 3.2.3 (Quadrant Power Tilt) are met.

Reduce power and ensure <55% on all Nls when the power decrease is complete.

When When TS TS have been addressed, have been addressed, or or when when directed directed byby the the lead lead examiner examiner this this event event is is completed.

completed.

Page Page 13 13 of of 21 21

Appendix DD Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.:

No.: _ _ Scenario No.:

Scenario No.: 33 Event No.:

Event No.: 88 Page 11 of Page of 55 Event

Description:

Event

Description:

1TA ITA Lockout Lockout and and Unit Unit Blackout:

Blackout: (M,(M, ALL)

Time j Position J Applicants Actions or Behavior Applicant's Plant response:

ITA Lockout (6900 Volt Switchgear) 1TA

IAI and 1B1 1A1 I BI RCPs trip causing a reactor trip

KHU #1 Emergency Lockout

CT-i CT -1 Lockout

MFBs will de-energize Crew response:

Perform Immediate Manual Actions (IMAs)

OATC/SRO

Depress REACTOR TRIP pushbutton.

Verify reactor power < < 5% FP and decreasing.

Depress turbine TRIP pushbutton.

Verify all turbine stop valves closed.

Verify RCP seal injection available.

IF CC is unavailable, THEN immediately perform the following:

Stop all RCPs.

Notify CR SRO to "initiate initiate AP125 AP/25" (Standby Shutdown Facility Emergency Operating Procedure).

BOP AP125 AP/25 Obtain the Vital area access key ring, Flashlight and Proceed to the SSF.

NOTE: Examiner should stop the BOP before leaving the control room and informed that Unit 2 RO will perform SSF actions.

OATC/BOP Perform Symrtom Symptom Check

Power Range Nis Nls ARE <5%< 5% and decreasing

NOSCMs<0°F NO SCMs < O°F

Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW) - TDEFWP is oeratinq

- operating

Uncontrolled Uncontrolled Main Steam line(s) pressure decrease is is NOT occurring

SGTR does NOT NOT exist

CSAE Offgas alarms

Process monitor monitor alarms (RIA-40, (RIA-40, 59, 59, 60)

Area monitor alarms (RIA-i 6/17)

(RIA-16/17)

Page Page 14 14 of of 21 21

Appendix DD Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.: _ _

Op-Test No.: Scenario No.:

No.: 3 Event No.:

Event No.: 8 Page 2 of Page of 5 Event ITA Lockout Event

Description:

1TA Lockout and Unit Unit Blackout:

Blackout: (M, ALL)

Time Position Applicants Actions or Behavior Applicant's Crew response:

Rule 3 (Loss of Main or Emergency Feedwater)

BOPIOATC BOP/OATC

- IAAT NO SGs can be fed with FDW (Main/CBP/Emergency),

(Main/CBP/Emergency), AND any of the following exist:

RCS pressure reaches 2300 psig OR NDT limit

Pzr level reaches 375" [340 acc]

375 [340" THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).

Start EFDW pumps to feed all intact SGs. (Only the TDEFDFW pump will be operating)

Verify any SCM ~O°F.

0°F. RNO - IF overcooling, THEN throttle EFDW as necessary.

IAAT Unit 11 EFDW is in operation, End 5.9 (Extended EFDW Operation).

THEN initiate Ene!

BOP/OATC BOP/OA TC End 5.9 (Extended EFDW Operation)

Encl

Monitor EFDW parameters on EFW graphic display.

level > 7.5':

Perform the following as required to maintain UST level> 7.5:

Makeup with demin water.

Place CST pumps in AUTO.

Verify 1I TD EFDW PUMP operating and Start TD EFDWP BEARING OIL COOLING PUMP.

Notify CR SRO to set priority based on the NOTE above and EOP activities.

SRO SRO will transfer to the BLACKOUT tab.

Page 15 15 of 21

Appendix D Scenario Outline ES-D-2 Form ES*D*2 Op-Test No.: _ _ Scenario No.: 3 Event No.:

Event No.: 8 Page 3 of 5 Page ITA Lockout and Unit Blackout: (M, ALL)

Event

Description:

1TA Time ime Position Applicants Actions or Behavior Applicant's Crew response:

SRO will transfer to the BLACKOUT tab.

SRO/BOP

/OATC IOATC

Direct an RO to announce plant conditions using the plant page and notify the OSM to reference EP and NSD 202 (reportability).

Verify two ROs available to perform Control Room activities.

End. 5.38 (Restoration of Power)

SRO will direct an RO to perform Encl.

Position the following to OFF:

1A 1AMDEFDWP MD EFDWP

1B 1BMDEFDWP MD EFDWP

Feed and steam available SGs as necessary to stabilize RCS PIT. P/T.

NOTE:

Feeding SGs with EFDW is desired above HPI Forced Cooling. Step 6 should be performed prior to re-performing Rule 3.

IAAT NO SGs are being fed, AND any source of EFDW (Unit 1 1 or another unit) becomes available, THEN perform the following:

Establish 100 gpm to each intact SG. (Feeding to 240" 240 XSUR)

Perform one of the following:

Tc> 550°F- Initiate cool down to Tc 540°F - 550°F by feeding and steaming intact SGs at a rate that prevents RCS saturation.

Tc ~< 550°F - Feed and Steam intact SGs SG's to stabilize Tc ~

< 550°F

IAAT EFDW from any source is insufficient to maintain stable RCS PIT, P/T, THEN notify SSF operator that feeding SGs with SSF ASW is required.

IAAT power is restored to jy any of the following:

1TC.1TD,1TE 1TC. 1TD, 1TE THEN Initiate AP/1 AP/111 (Recovery from Loss of Power).

GO TO Subsequent Actions Tab SRO NOTE: Once power is restored to any 41 60V bus, the SRO will transfer 4160V to the Subsequent Actions tab per the above IAAT step.

Verify all control rods fully inserted.

Verify Main FDW in operation.

Verify Main FDW controlling properly.

IAAT IAAT Main FDW is operating...

operating ...

Verify TBVs controlling SG pressure at desired setpoint.

Verify 11RIA-40 operable with CSAE OFF-GAS BLOWER operating.

Page 16 16 of 21

Appendix D Outline Scenario Outline Form ES-D-2 No.: _ _

Op-Test No.: Scenario No.: 3 Event No.: 8 Page 4 of 5 Page Event

Description:

1TA ITA Lockout and Unit Blackout: (M, ALL)

Time Position Applicants Actions or Behavior Applicant's Crew response:

AP/1 1 (Recovery from Loss of Power). - to be performed after completion of AP/11 OATC/BOP End. 5.38 (Restoration Of Power; from CT-5)

EOP Enc!.

Announce AP entry using the PA system.

Verify load shed has initiated

Verify load shed is complete as indicated by LOAD SHED COMPLETE on any ES Module (Channel 11 or 2).

Close the following breakers:

1TC INCOMING FOR FDR BUS 1/2 lTD INCOMING FOR

1TD FDR BUS 1/2

1TE INCOMING FOR FDR BUS 1/2

Verify a 230KV Switchyard Isolation has occurred. (It has NOT)

Verify ES has occurred. (It has NOT)

Simultaneously press RESET on both of the following pushbuttons to reset Main Feeder Bus Monitor Panel Load Shed Circuitry:

UNDERVOLTAGE MFB UNDERVOL TAGE CHANNEL 1/2 RESET

Verify all condensate flow has been lost for < < 25 minutes and condensate operation is desired.

Place all HWP control switches to OFF.

Place all CBP control switches to OFF.

Place 11 FDW-53/65 in MANUAL and close.

Place 1C-10 iC-iC FAIL SWITCH in MANUAL.

Close iC-b.

1C-10.

Using a plant page, clear TB Basement and TB third floor of non- non essential personnel.

Start one HWP.

Throttle 11C-iC C-1 0 controller 10%

10% open to satisfy 25 minute restart criteria.

WHEN FWP SUCT HDR PRESS is is;::: 100 100 psig, THEN open iC-iC.

1C-10.

Page 17 17 of 21

Appendix DD Scenario Outline Form ES-D-2 Form ES-D-2 Op-Test No.: Scenario No.: 3 Event No.: 8 Page 5 of 5 Event

Description:

1TA Event

Description:

ITA Lockout Lockout and Unit Unit Blackout:

Blackout: (M, (M, ALL)

Time Position Applicants Actions or Behavior Applicant's Crew response:

OATe/BOP OATC/BOP RO will perform End. 5.38 (Restoration of Power) (CT-8) (Not met if Enc!.

End.

5.38 completed with power NOT restored.)

Place 11HP-31 HP-31 in HAND and reduce demand to O. 0.

Close 11HP-21.

HP-21.

Verify MFB1/2 energized (NOT)

CT-i indicates 4160v Verify CT-1 4i60v (NO)

Verify both Standby Bus #1 and Standby Bus #2 are de-energized.

Emergency start Keowee units

Notify Keowee Operator to place all operating Keowee units in Oconee Control.

CT-S indicates == 4160 volts, IAAT CT-5 THEN GO TO Step 50. (It does; from Central Swyd)

Place the following switches in MAN:

MFB1 and MFB2 AUTO/MAN

STANDBY 1 I and STANDBY 2 AUTO/MAN

Open the following breakers:

1 and N21 Ni

N11 1 MFB1 NORMAL FOR N2 FDR

E11 1 and E21 El 1 MFB1 STARTUP FOR E2 FDR

Place the following switches in MAN:

CT4 BUS 1 1 and CT4 BUS 2 AUTO/MAN

CT5 BUS 1 I and CT5 BUS 2 AUTO/MAN

Open the following breakers:

Ski SK1 and SK2 CT4 STBY BUS 1 i FEEDER

Close SL SL11 and SL2 CT5 STBY BUS 1 1 FEEDER

Place the following switches in AUTO:

CT5 BUS 1 i and CT5 BUS 2 AUTO/MAN

Verify Standby Bus #1 energized.

Notify CR SRO in each unit where aa blackout exists that Standby Bus #1 is energized.

Close Si S1 1 and 1 1 S2 S2 1 STBY BUS 22 TO MFB2 (power is restored)

Verify iTC, 1TC, 1TD, or 1TEiTE energized.

Notify Unit i1 CR SRO of status of 4i60V 4160V SWGR.

When the SRO has transferred to Subsequent Actions tab, or when directed by the Lead Examiner this event is completed.

Page 18 18 of 21

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: _ _ Scenario No.: 3 Event No.: 9 Page 11 of 2 Event

Description:

SGTR: (M, ALL)

Time Position Applicants Actions or Behavior Applicant's After the SRO transfers to the Subsequent Actions tab and when directed by the Lead Examiner a SG tube rupture will occur in the 1 I B SG.

Plant Response:

I SA-8/8-9 1 SA-8/B-9 RM Process Monitor Radiation High

1SA8/D10 (RM CSAE EXHAUST RADIATION HIGH)

PZR level decreasing Crew response:

SRO The SRO should use the Parallel Actions page and transfer to the SGTR tab.

SGTR tab will:

14Q- 180"

Maintain Pzr level 14Q"- [17- 21Q"acc]

180 [17Q"- 21acc] by initiating Encl End 5.5 (pzr (Pzr and LDST Level Control).

Start A and B OUTSIDE AIR BOOSTER FAN (CT-27)

Notify Unit 3 to start the 3A and 3B OUTSIDE AIR BOOSTER FAN

Monitor RIAs 16 and 17 to identify all SGs with a tube rupture.

Dispatch an operator to open A and B TURB BLDG SUMP PUMP BKR)

Notify RP to survey both MS lines for radiation.

OATC/BOP Note: When RP is directed to survey MS lines the TD EFDW pump will trip; requiring either Rule 3 to be performed OR performing a symptoms check to start the MDEFWP's. MDEFWPs. (CT (CT-b)

-10)

Secure any unnecessary offsite release paths. (Main Vacuum Pumps, TDEFDWP, Emergency Steam Air Ejector (1MS-46),

(1 MS-46), etc.).

Verify Main FDW or EFDW controlling properly.

Open 11HP-24 HP-24 and 11HP-25 HP-25

Secure makeup to LDST. (Close 1HP-16, if open)

Maintain both SG pressures << 950 psig using either of the following:

- TBVs TBVs

Dispatch two operators to perform End Encl 5.24 (Operation of the ADV5)

ADVs)

Page 1919 of 21

Appendix D Appendix D Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: _ _ Scenario No.:

Scenario No.: 33 Event No.:

Event No.: 99 Page Page 22 of of 22 Event

Description:

Event

Description:

SGTR:

SGTR: (M,(M, ALL)

ALL)

Time Time Position Position Applicants Actions Applicant's Actions or Behavior or Behavior Crew response:

Crew response:

......SGTR

. continued:

SGTR tab continued:

ALL

- IAAT all the following exist:

all the exist:

SCMs>

- All SCMs 0°F

> OaF

ES Bypass Permit satisfied

RCS pressure controllable THEN bypass ES as necessary.

Verify any RCP operating. (NOT)

Minimize core SCM using any/all of the following methods:

De-energize all Pzr heaters

Use Pzr spray

Maintain Pzr level 140" 140 - 180"

- 180 [175"

[175 - 215"

- 215 acc]

NOTE: With no RCP's RCPs operating, the above methods will be unsuccessful at reducing SCM.

IAAT RCS de-pressurization methods are inadequate in minimizing core SCM, THEN perform Step 36 - 38. (CT-?) - (CT-7)

a. Verify Pzr spray nozzle liT LlT;::: 410°F.

b. Close 1 1LWD-1 LWD-1 and 1 1LWD-2 LWD-2

c. Cycle PORV as necessary.

When When crew crew takes takes action to minimize action to minimize SCM SCM oror when when directed directed by by the the Lead Lead Examiner, Examiner, the the scenario scenario is is complete.

Page Page 20 20 of of 21 21

Appendix 00 Scenario Outline ES-D-2 Form ES-O-2 CRITICAL TASKS CT-8,

1. CT -8, Electrical Power Alignment

2. CT-27, Implementation of Control Room Habitability Guidance

3. CT-7, Minimize SCM (optional)

CT-1O, Establish FDW Flow and Feed Steam Generators

4. CT-10, Page 21 of 21 21

BrieflTurnover Simulator BriefITurnover I SAFETYIPRA RISK (OSM)

SAFETY/PRA (OSM) I SAFETY: Take a Minute Minute PRA Risk Status: GREEN UNITO(OSM)

UNITO (OSM SSF Operable: Yes II L<'UI KHUs Operable: U1 I'" f"l""""hl,,: UI - OH, U2 - UG

- - UG Operable:. ..,2 LCTs Op LeTs II cFuel Handling:

ndling: None II UNIT STATUS (CR SRO)

Unit 1I Simulator Other Units Mode: 11 Unit 2 Unit 3 Reactor Power: 100% Mode: 1I Mode: 11 Gross MWE: 897 100% Power 100% Power RCS Leakage: .01 gpm RC8 EFDW Backup: Yes EFOW EFDW Backup: Yes EFOW RBNS Rate: 0 gpm RBN8 SpecificationslSLC Items (CR SRO)

Technical Specifications/SLC ComponentlT rain Component/Train OOS Restoration Required TSISLC #

TS/SLC DatelTime Date/Time DatelTime Date/Time Shift Turnover Items (CR SRO)

Primary

. 492 EFPOEFPD

. Intermittent LP8W LPSW leak in RB requires frequent RBN8 RBNS pumping Secondary

. 1SSH-1, 188H-3, 188H-1, ISD-2, 180-5,180-140,180-303,180-355,180-356 1SSH-3, 180-2, 1SD-5,1SD-140,1SD-303,1SD-355,1SD-356 and 180-358 1SD-358 are closed with power supply breakers open per the Startup 8tartup Procedure for SSF 88F Overcooling Event. 1 PR-1, 1 1 PR-i, 1 PR-6, 1 LPSW-1, 1 LP8W-1, 1 1 LPSW-2, LP8W-2, 1 1 LPSW-3, LP8W-3, 1 1 FOW-80, FDW-80, 1 1 CF-5, 1CF-6, 1 CF-6, 1 1 LP-1 and 11 LP-2 breakers open per the appropriate system operating procedures.

Unit 33 has the Aux Steam 8team Header Reactivity Management (CR SRO)

CRSRO)

RCS Boron: 30 ppmB RC8 Gp 7 Rod Position: 91% 91 % III Batch additions as required for volume control.

I Two Human Performance Emphasis (OSM)

Procedure Procedure Use and Adherence Scenario 33 RO

Appendix 0D Appendix Scenario Outline Scenario Outline Form Form ES-D-1 ES-D-1 3/10 3/10 Facility: Oconee Facility: Oconee No.: 44 Scenario No.:

Scenario Op-Test No.:

Op-Test No.: 1 Examiners:

Examiners: Operators:

Operators:

Initial Conditions:

.* Reactor power == 0.02%;

Reactor power 0.02%; below below POAH POAH Turnover:

Turnover:

.* Unit Unit I1 Startup Startup in in progress; progress; BOL; BOL; not after refueling not after refueling

.* LDST LDST pressure pressure low, low, requires requires HH2 addition 2 addition

.* Startup Startup procedure procedure atat step step 3.29 (1102/02 3.29 (1 102/02 End Encl 4.7) 4.7)

. Event Malf. No.

Malf.No. EventType*

Event Type* Event No.

No. Description Description Oa Override AFIS does not auto actuate Ob Override Override 1FDW-316 failed closed 1FDW-316 11 Override N, BOP, SRO H-1) fails OPEN Pressurize LDST with H2, H2 supply valve (1 H-i)

(TS) 2 R,OATC,SRO R, OATC, SRO Increase power to 3% and place ICS in AUTO 3 MPS 1101 10 C, BOP, SRO 1 1 HP-5 (Letdown Isolation) fails CLOSED (TS) 4 Override C, OATC, SRO 1 1 RC-1 (Pzr Spray Valve) fails open RC-i (pzr 5 MCS012 MCSO12 M, ALL 1 1AA Turbine bypass valve and its block valve fail open due to instrument failure Excessive Heat Transfer 11FDW-316 FDW-316 failed closed requiring feed through the startup header FCDtab Transfer to FCD tab

- N)ormal, (N)ormal, (R)eactivity, (R)eactivity, (I)nstrument, (I)nstrument, (C)omponent, (C)omf'onent, (M)ajor

Appendix D Appendix 0 Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: 1I Scenario No.:

Scenario No.: 44 Event No.:

Event No.: 1I Page Page 11 of of 22 Event

Description:

Event

Description:

Pressurize Pressurize LDST LDST with with H2, H2, H2 H2 supply supply valve valve (1(IH-1)

H-1) fails fails OPEN OPEN (N, (N, BOP, BOP, SRO)

SRO)

(TS)

Time Time Position Position Applicants Actions Applicant's Actions or Behavior or Behavior Crew response:

Crew response:

SRO SRO Direct the

- Direct BOP to the BOP to add add H2 H2 to to the the LOST LDST using using OP/1/A/11 06/017 OP/i/A/1106/017 (Hydrogen System)

(Hydrogen System) Enclosure Enclosure 4.54.5 (Unit 11 LOST LDST H2 H2 Addition).

Addition).

- Enclosure 4.5 (Unit 11 LOST Enclosure LDST H2 Addition) will:

BOP Chemistry of hydrogen addition

Notify Chemistry addition prior prior to adding hydrogen.

hydrogen.

NOTE:

OP/C/All 108/001 (Curves And General Information) and computer may

OP/O/A/1108/001 LDST Pressure vs. Level curve.

be referred to for LOST

LOST LDST Maximum Pressure vs Indicated Level Curve should NOT be exceeded when pressurizing LOST. LDST.

Immediately prior to pressurization determine lowest reading of diverse LDST level indications:

LOST inches.

LDST level determine LOST For existing LOST LDST Pressure allowable per LOST LDST Pressure vs. Level curve: psig.

Notify Operator at H2 Cage to pressurize primary hydrogen.

NOTE: Operator should be in constant communication with CR to close 1H-26 1 1H-l H-26 if 1H-1 fails open.

Direct Operator to open 1 1 H-26 (LDST (LOST Block).

Direct Operator to monitor explosive detector.

Cycle 11 H-i (LOST SUPPLY) as required to pressurize LDST H-1 (LDST LOST per LDST LOST Pressure vs Level curve.

1 H-1 (LDST SUPPLY) will fail open.

Note: IH-I

WHEN Hydrogen addition complete, ensure closed 11H-1(LDST H-1 (LOST SUPPLY).

Page of 15 Page 22 of 15

Appendix 0D Scenario Scenario Outline Outline Form ES-D-2 Form ES-D-2 Op-Test No.:

Op-Test No.: I1 Scenario No.: 44 Scenario No.: Event No.: I1 Event No.: Page 22 of Page of 22 Event

Description:

Event

Description:

Pressurize LDST with Pressurize LDST with H2, H2 supply H2, H2 supply valve (1H-1) fails valve (IH-I) fails OPEN OPEN (N, BOP, SRO)

(N, BOP, SRO)

(TS)

Time Position Applicant's Actions or Behavior Applicants Plant response:

Plant

LDST pressure will continue to increase.

11SA-02/D-2, HP HP Approaching LDST Operating Limits, actuates Crew response:

BOP ** BOP should determine that 11H-iH-1 has failed open and direct the NLO to close 11H-26.

Refer to the ARG.

Verify LDST pressure/level are within the acceptable operating region of the LDST PRESSURE vs. LEVEL enclosure in OP/C/Ni 108/001 (Curves and General Information).

OP/0/A/1108/001 SRO SRO IF necessary, vent LDSTt0 OP/1/A/1104/002 (HPI System).

LDST to GWD per OP/1!N1104/002

LDST PRESSURE vs. LEVEL enclosure in OP/O/N1 OP/0/A/11108/001 081001 (Curves and General Information) directs the following:

If LDST Pressure vs. Level is above and to the left of Curve 1, then declare BOTH trains of HPI INOPERABLE.

o Immediately depressurize LDST below Curve 1.

o Refer to TS 3.0.3 for shutdown requirements.

o Make notifications as required by OMP 1-14 (Notifications).

BOP

OP/i/Ni 104/002 (HPI Direct the ROs to vent LDST to GWD per OP/1/A/1104/002 End. 4.16, (Lowering LDST Pressure)

System), Enc!.

Review Limits and Precautions

Direct Operator to Close 11 GWD-20 (LDST Vent Blk). Bik).

IGWD-i9 (LDST VENT).

Open 1GWD-19

Direct Operator to throttle open 1I GWD-20 (LDST Vent Blk) BIk) until LDST pressure begins to slowly decrease and GWD system can maintain vent header.

WHEN desired LDST pressure obtained, close 1GWD-19 1GWD-i9 (LDST VENT)

Event is complete when vent of LDST is complete or when directed by the Lead Examiner.

15 Page 3 of 15

D Appendix D Scenario Outline Form ES-D-2 I

Op-Test No.: 1 Scenario No.: 4 Event No.: 2 Page 11 of 11 Event

Description:

Increase reactor power to 3% and place ICS in AUTO: (R, OATC, SRO)

Time Position Applicants Actions or Behavior Applicant's Crew response:

OP/i/Ni 102/001 (Controlling Procedure for Unit Startup)

OP/1/A/1102/001 NOTE:

POAH is normally achieved from 0.05 to 0.15% power on Wide Range Indications.

When POAH is achieved: TBVs will begin to open, 1HP-120 will begin to close, TAVE will increase, & SUR will decrease with negative Moderator SRO/OATC SROIOATC Temperature Coefficient.

BOP

Begin reactor power increase to 0.5% - 1.0% at :5 0.5 DPM SUR.

WHEN above POAH, begin reactor power increase to 2.5 -3.5%.

WHILE power increases, begin increasing 1HP-120 (RC VOLUME 215 to 225" CONTROL) setpoint to establish 215" 225 PZR Level

WHEN at 2.5% - 3.5% Power, perform the following:

AUTO.

Place REACTOR MASTER to "AUTO".

AUTO.

Place DIAMOND to "AUTO".

to 880 - 890 psig.

Ensure TURBINE MASTER Setpoint to::::: -

Event is complete when ICS is placed in AUTO or when directed by the Lead Examiner.

Page 44of15 of 15

0 Appendix D Scenario Outline Form ES-D-2 I

Op-Test No.: 1 Scenario No.: 4 Event No.: 3 Page 11 of 2 IHP-5 (Letdown Isolation) fails CLOSED (TS) (C, BOP, SRO)

Event

Description:

1HP-5 Time Position Applicants Actions or Behavior Applicant's Plant Response:

OATC

1HP-5 1 HP-5 green closed light is lit

Pzr Level slowly increases

LDST Level slowly decreases LOST Crew Response:

Enters AP/32, AP/32 , Loss of Letdown

- HP-120 in HAND and reduce demand to zero.

Place 11HP-120 OATC/S RO ** Initiate makeup to LOSTLDST as required.

Initiate notification of the following:

OSM to reference OMP 1-14 (Notifications) and Emergency Plan STA

Notify Chemistry of the following:

Current RCS boron sample is needed for possible unit shutdown.

Normal letdown line is isolated

IAAT either of the following exist:

260, level > 260",

Pzr level>

AND letdown CANNOT be established Plant conditions exist such that letdown will NOT be restored at 20%/min THEN initiate unit shutdown at::::: 20%/mm per AP/29 (Rapid Unit Shutdown).

IAAT Pzr level;::: 375, level 375",

THEN trip Rx.

Position the standby HPI pump switch to OFF.

Step 4.8, Throttle 1 1HP-31 12-- 15 gpm SEAL INLET HDR HP-31 to establish 12 FLOW.

flow 65 gpm. (If less than 65 gpm, log beginning time for Verify HPI pump flow;:::

HLP pump flow below minimum).

GO TO Step 4.11 per Table in AP/32

Close 1 1HP-6.

HP-6.

Close 1 1HP-7.

HP-7.

Open 1 1 HP-5. (will not open from control room)

Page 5 of 15

D Appendix D Scenario Outline Form ES-D-2 Op-Test No.:

Op-Test No.: I1 Scenario No.: 4 Event No.:

No.: 33 Page 22 of 22 1HP-5 (Letdown Isolation) fails CLOSED (TS) (C, BOP, SRO)

Event

Description:

IHP-5 Time Position Applicant's Actions or Behavior Applicants BOP/SRO ** Open 1 1 HP-5 RNO actions as follows:

BOPISRO o Dispatch NEO in continuous communications with control room to manually open 1 1 HP-5 Booth cue: Using TIME COMPRESSION report that IHP-5 1HP-5 is manually open.

Note: Continuous communication can be accomplished using either plant radio or telephone o IF 11 HP-5 is manually open, THEN enter TS 3.6.3 (Condition A, 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months completion time)

Note: 1 I HP-5 is allowed to be manually opened by Note 1. I.

WHEN 11 HP-5 is open, THEN continue.

Place CC system in operation.

Verify letdown temperature << 135°F.

Throttle 1 20 gpm 1 HP-7 to establish -20

WHEN letdown temperature < 130°F, THEN place LETDOWN HI TEMP INTLK BYP switch in NORMAL.

Open 11HP-6 HP-6

Adjust 1 1 HP-7 to control desired letdown flow.

Re-establish normal makeup through 1 1HP-120.

HP-120.

Notify SPOC to initiate repairs on 1 I HP-5.

Verify seal injection flow reduced in Step 4.8.

Re-establish normal RCP seal injection flow.

Position the standby HPI pump switch to AUTO.

WHEN repairs are complete on 1HP-5 (LETDOWN ISOLATION)

THEN perform the following:

o Locally turn 11 HP-5 HP-S handwheel fully clockwise.

o EXITTS3.6.3.

EXIT TS 3.6.3.

HP-5 will not be repaired during this scenario Note: 1IHP-5 Note: If Pzr level exceeds 260 inches, TS 3.4.9 Conditions A should be entered requiring level to be restored within 11 hour1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months .

When 1I HP-5 is manually opened and NEO is stationed locally or when directed by Lead Examiner then this event is complete.

Page 6 of 1515

Appendix D Appendix D Scenario Scenario Outline Outline Form Form ES-D-2 ES-D-2 Op-Test No.:

Op-Test No.: I1 Scenario No.:

Scenario No.: 44 Event Event No.:

No.: 44 Page of 11 Page 11 of Event

Description:

Event

Description:

PZR PZR Spray Spray Valve Valve Fails Fails OPEN:

OPEN: (C, (C, OATCISRO)

OATC/SRO)

Time Position Applicant's Actions or Behavior Applicants Behavior Booth cue: Call as RP and ask BOP to report the pressure in the GWD gas tanks.

Plant response:

RCS pressure will decrease 1SA-21D-3, RC PRESS HIGH/LOW

1SA-21D-3, HIGH/LOW Crew response:

Refer to ARG SRO/OATC ** 1AP/44, Abnormal Pzr Pressure Control Refer to 1AP/44, Note: If the block valve is not closed, the reactor will trip on variable low pressure and ES actuation will occur.

If the operator identifies 1 1 RC-1 has failed open, he should immediately close the block valve (1 RC-3) per IMAs of AP/44

Evaluate reducing or isolating letdown flow

Increase makeup flow as required

SRO enters to 1AP/44, Abnormal Pzr Pressure Control

IAAT all of the following conditions exist:

RC pressure < 2155 psig

RC pressure decreasing without a corresponding decrease in PZR level

PZR heaters are on THEN close the following:

11RC-1 RC-1

1RC-3 1RC-3

Verify Pzr heaters maintaining RCS pressure w/in bands

Notify SPOC to repair failed 11 RC-1

Ensure TS requirements met

WHEN repairs are complete, THEN place 11 RC-1 and 11 RC-3 in the desired positions.

Note: The PZR spray valve will remain failed for the remainder of the scenario.

When RCS pressure decrease has been stopped, or when directed by the Lead Examiner this event is completed.

Page 77of15 of 15

D Appendix D Scenario Outline Form ES-D-2 Op-Test No.:

Op-Test No.: I1 Scenario No.:

No.: 4 Event No.:

No.: 5 Page 11 of 77 1A TBV fails OPEN (I: OATC, SRO)

Event

Description:

IA Time Position Applicants Applicant's Actions or Behavior Plant response:

OAC alarm

1A1A Turbine Bypass Valve fails open.

1A1A Main Steam line pressure decreases

Reactor Coolant Temperature decreases causing reactor power to increase.

SRO/OATC SRO/OATC Crew response "Plant Transient Response.

Crew will perform Low Power Plant Response".

lCS Diamond Panel to MAN Place ICS

Place ICS Feedwater Loop Masters 1A &1 B to HAND 1A &1B OATC

Insert Control Rods to reduce power to below pre-transient level

1A SG pressure continues to decrease, the OATC should trip the As "1A" reactor due to the anticipated affects of the excessive heat transfer.

When the reactor is tripped or when directed by the Lead Examiner, this event is completed Page 8 of 15

Appendix D Appendix D Scenario Outline Scenario Outline Form Form ES-D-2 ES-D-2 Op-Test No.:

No.: 1I Scenario No.:

Scenario No.: 4 Event No.:

Event No.: 55 Page 22 of Page of 77 Event

Description:

Event

Description:

Excessive Heat Excessive Heat Transfer (M, (M, ALL)

Time Position Applicants Actions or Behavior Applicant's Plant response:

Reactor is manually tripped

- 11A A SG pressure continues to decrease

AFIS fails to initiate automatically Crew response:

OATC/S RO OATC/SRO

Perform Immediate Manual Actions (IMAs)

Depress REACTOR TRIP pushbutton.

Verify reactor power < < 5% FP and decreasing.

Depress turbine TRIP pushbutton.

Verify all turbine stop valves closed.

BOP

Verify RCP seal injection available.

- Perform Symptom Check

Power Range N NIs <5%

Is < 5%

Power Range Nls Nis decreasing

SCMs are>

are > O°F 0°F

NO Loss of Main and Emergency FDW (including unsuccessful BO P/OATC BOP/OATC manual initiation of EFDW) exists

Uncontrolled Main steam line(s) pressure decrease

- NONOSGTR SGTR

CSAE Offgas alarms

Process monitor alarms (RIA-40, 59, 60)

Area monitor alarms (RIA-16/17)

An RO will recognize indications of a steam line break on the 1A 1A MS Line and initiate Rule 55 (Excessive Heat Transfer).

Rule 55 (CT-17)

(CT -17)

On AFIS HEADER A, depress CH. 11 IN IT.

INIT.

On AFIS HEADER A, depress CH. 2 INIT.

NOTE: AFIS will not work

Select OFF for 1A 1A MD EFDWP.

Trip both Main FDWPTs.

Close 1FDW-315.

1FDW-315.

Place 11FDW-33 switch switch to CLOSE.

CLOSE.

Place 11FDW-31 switch to CLOSE.

Page9ofl5 Page 9 of 15

Appendix D Scenario Outline Form ES-D-2 I

Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page 3 of 7 Event

Description:

Excessive Heat Transfer (M, ALL)

Position Applicants Applicant's Actions or Behavior Crew response:

BOP/OATC ** Rule 5 Continued.

Verify 11 TO TD EFDW PUMP operating.

Verify 11 TO TD EFDW PUMP is feeding affected SGs. (NOT)

IF MD EFDWP for the intact SG is operating, THEN GO TO Step 5.

lB Verify 1 B SG is an affected SG. (NOT)

WHEN overcooling is stopped, THEN adjust steaming of unaffected SG to maintain CETCs constant using either of the following:

o TBVs o Dispatch two operators to perform Encl End 5.24 (Operation of the ADVs).

CAUTION Thermal shock conditions may develop if HPI is NOT throttled and RCS pressure NOT controlled.

WHEN ill! aM the following exist:

~ Core CoreSCM>OF SCM> 0 F

~

> RxRxpowerl%

power:::;; 1%

> Pzr level

~

THEN perform the following to stabilize RCS PIT: P/T:

BOP/OATC

~ Throttle HPI.

~

> Reduce 11HP-120 setpointto HP-120 setpoint >100 [180"acc].

to control at >100" [180acc}.

~

> Adjust steaming of unaffected SG as necessary to maintain CETCs constant.

- Ensure Rule 3 (Loss of Main or Emergency FDW) is in progress or complete.

Rule 3 (Loss of Main or Emergency Feedwater)

IAAT NO SGs can be fed with FDW (Main/CBP/Emergency), AND y any of the following exist:

o RCS pressure reaches 2300 psig OR NOT oRCS NDT limit o Pzr level reaches 375" 375 [340"

[340 acc]

THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).

Page 10 of 15

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 11 Scenario No.: 4 Event No.: 5 Page 4 of 7 Event

Description:

Excessive Heat Transfer (M, ALL)

I Time Position Applicants Actions or Behavior Applicant's Crew response:

BOP/OATC ** Rule 3 continued

Start EFDW pumps to feed all intact SGs.

Verify y any EFDW pump operating.

IAAT both of the following exist:

>-> An EFDW valve will NOT control in AUTO

>-> The same EFDW control valve will NOT respond in MANUAL THEN perform Steps 33 and 34.

Notify CR SRO that Encl. End. 5.27 (Alternate Methods for Controlling EFDW Flow) is being initiated due to 1 IFDW-316 FDW-316 failed closed.

End. 5.27, (Alternate Methods for Controlling EFDW Flow)

Initiate Encl.

BOP/OATC

End. 5.27 Encl.

Identify the failure: (CHART; 1 1 FDW-316 FDW-31 6 - CLOSED) Step 39

Stop 1lB B MD EFDWP.

Verify 1A IA MD EFWP is operating. (RNO)

>-> Close 11 FDW-369; GO TO Step 43.

Place 1 1 FDW-44 in HAND and set demand to 0%.

OATC/SRO

Close 1 1 FDW-42

Verify 1 1BB MD EFDWP will be used.

Open 11 FDW-384.

Verify the following:

>-> 1 FDW-45 closed 1

>- 1FDW-47 1 FDW-47 open

Start1BMDEFDWP.

Start 1B MD EFDWP.

Throttle 1 1FDW-44 FDW-44 to establish 100 gpm. (100 gpm is the Rule 7 limit for initial feeding a dry SG. After heat transfer is established the limit is 600 gpm per rule 7).

Throttle 1 1 FDW-44 to obtain desired SG level per Rule 7 (SG Feed (CT-b)

Control). (CT-10)

IAAT proper SG level is reached (25") (25) and level permits auto level control, THEN place 11 FDW-44 in AUTO.

Page 11 of 15

Appendix D D Scenario Outline Form ES-D-2 I

Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page 5 of 7 Event

Description:

Excessive Heat Transfer (M, ALL)

Time Position ]

Applicants Applicant's Actions or Behavior Crew response:

SRO Transfer to EOP Subsequent Actions tab then to the Excessive Heat Transfer tab per the Parallel Actions page of Subsequent Actions

Verify any SG pressure < 550 psig.

Ensure Rule 5 (Main Steam Line Break) in progress or complete.

Place the following in HAND and decrease demand to zero on ill! ji affected SGs:

1FDW-32 1 FDW-32

1FDW-35 1 FDW-35 SRO/BOP

Close the following on all affected SGs:

/OATC IOATC

- 1 FDW-372 1FDW-372

1MS-17

1MS-79 1 MS-79

1MS-35

1M5-82 1 MS-82

1FDW-368

Verify level in both SGs < <96%

96% O.R.

SRO/BOP

IAAT core SCM is > 0°F,

> OaF,

/OATC IOATC

Throttle HPI per Rule 6 (HPI).

Verify letdown in service.

Verify any SG has an intact secondary boundary (intact SG).

Open the following on all intact SGs:

11FDW-382 FDW-382

11 FDW-369

Start1BMDEFDWP Start 1B MDEFDWP

Feed and steam ill!aM intact SGs to stabilize RCS PIT P/T using either of the following:

- TBV5 TBVs

Dispatch two operators to perform EnclEnd 5.24 (Operation of the ADVs).

Page 12 of 15

Appendix D Scenario Outline Form ES-D-2 Op-Test No.: 1 I Scenario No.: 4 Event No.: 5 Page 66 of 7 Event

Description:

Excessive Heat Transfer (M, ALL)

Time Position Applicant's Actions or Behavior Applicants Crew response:

OATC/SRO Excessive Heat Transfer tab of the EOP (Continued)

/BOP IBOP

Verify y

any of the following:

HPI has operated in the injection mode while NO RCPs were operating

A cooldown below 400 °F of at> °FIhr has occurred 100 °F/hr at > 100

Verify both of the following are closed:

11MS-24 MS-24

11MS-33 MS-33

Open 1AS-8.

Close the following 1 1 SSH-9.

Notify Chemistry to determine RCS boron concentration

IAA T all the following exist:

IAAT

ES Bypass Permit satisfied

AIISCMs>OLIF All SCMs > ODF

RCS pressure controllable THEN bypass ES as necessary.

Verify any SG is dry.

Minimize SCM using the following methods as necessary:

De-energize all Pzr heaters

Use Pzr spray 1OQ[18Qacc]

Throttle HPI to maintain Pzr level 10Q"[18Q"acc]

Use PORV

Verify any RCP operating. Maintain RCP NPSH.

- OAC OAC (P/T Curves)

End 5.18 (PIT

Encl

Initiate Encl Tube-to-Shell T End 5.16 (SG Tube-to-Shelll1 T Control).

IAAT all the following exist:

RBS actuated

RB pressure < 10 psig

1 1 RIA-57 NOT in alarm

1 1 RIA-58 NOT in alarm THEN stop both RBS pumps.

Page 13 of 15

Appendix D Scenario Outline Form ES-D-2 I

Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Page 7 of 7 Event

Description:

Excessive Heat Transfer (M, ALL)

Time Position Applicants Applicant's Actions or Behavior Crew response:

OATC/SRO Excessive Heat Transfer tab of the EOP (Continued)

/BOP IBOP

Verify any RCP operating. Maintain RCP NPSH.

- OAC OAC

End 5.18 (PIT Ene! (P/T Curves)

End 5.16 (SG Tube-to-Shell f1 Initiate Ene! TT Control).

IAAT all the following exist:

RBS actuated

RB pressure < 10 psig

11 RIA-57 NOT in alarm

1 1 RIA-58 NOT in alarm THEN stop both RBS pumps.

350° F, IAAT Tcold approaches 350°F,

AND all RCPs are operating,

THEN ensure < <four four RCPs are operating.

IAAT BWST level is::; is 19',

19, End 5.12 (ECCS Suction Swap to RBES).

THEN initiate Encl

SCMs>> OaF.

Verify all SCMs 0°F.

Verify indications of SGTR exist.

Verify required RCS makeup flow within normal makeup capability

Verify either of the following:

Any SG isolated

Any SG has an unisolable steam leak

GO TO FCD tab.

When transfer to the FCD tab is made or when directed by the Lead Examiner this event is completed Page 14 of 15

0 Appendix D Scenario Outline Scenario Outline Form ES-D-2 Form ES-D-2 CRITICAL TASKS CRITICAL 1 CT-17,

1. CT-i 7, Isolate Isolate Overcooling 10, Establish FDW Flow and Feed SGs

2. CT- 10, Page 15 15 of 15 15

Simulator Simulator BrieflTurnover BrieflTurnover SAFETYIPRA RISK SAFETY/PRA RISK (OSM)

(OSM)

Take aa Minute SAFETY: Take SAFETY: Minute PRA Risk PRA Risk Status:

Status: GREEN GREEN UNIT UNIT 00 (OSM)

(OSM)

~~~ ~

SSF Operable: Yes :: KHUs I1na."hla:

/0 ." Operable: U1 UI - OH,

- OH, U2 U2 - UG

- UG LCTs Oper~~.~.

II LeTs Operable: -2 j:.-.Fuel Handling: None

.. ~: Mone UNIT STATUS STATUS (CR SRO) SRO)

Unit 1I Simulator Unit Other Units Units Mode:22 Mode: Unit Unit2 2 Unit Unit3 3 Reactor Power: .02%02% Mode: 11 Mode: 11 Gross MWE: 0 100% Power 100% Power RCS Leakage: 0.1 gpm EFDW Backup: Yes EFDW Backup: Yes RBNS Rate: 0 gpm Specifications!SLC Items (CR SRO)

Technical Specifications/SLC ComponentlTrain Component/Train OOS Restoration Required TS/SLC TSISLC #

DatelTime Date/Time DatelTime Shift Turnover Items (CR SRO)

Primary

- Unit 1 1 was started up following a RFO and operated at power for 1 1 week. Turbine vibration problems required the unit to be shutdown. Turbine vibration problems have been fixed.

- LDST LOST pressure is low and requires H2 make up. After turnover is complete, perform a H2 make up to the LOST LDST using OP/1OPII/A11106/017,

/A/11 06/017, Encl.

End. 4.5.

- Unit 1 OP/i/Ni 102/001 Enclosure 4.7 (Unit Startup From 1 Startup procedure in progress. OP/1/A/1102/001 532°F and 2155 psig) is complete up through step 3.28.

- OP/i/Ni105/0 OP/1/A/11 05/019 i9 (Control Rod Drive)

Orive) in progress. Initial Conditions completed

Rx power 0.01%; = 0.01 %; below the POAH. After turnover is complete continue with the startup at step 3.29.

Secondary

- 11SSH-i, SSH-1, 11SSH-3, SSH-3, 11SD-2,SO-2, 11SD-5, SO-5, 11SD-i 40,11SD-303, SO-140, SO-303, 11SD-355,1 SO-355, 1SD-356 SO-356 and and 11SD-358 SO-358 are closed closed with with power power supply supply breakers open per the Startup Startup Procedure Procedure for SSF SSF Overcooling Event. iPR-i, Event. 1PR-1, iPR-6, 1PR-6, 1LPSW-1, 1 LPSW-1, 1LPSW-2, 1LPSW-2, 1LPSW-3, 1LPSW-3, 1FDW-80, 1FOW-80, 1CF-5, 1CF-5, 1CF-6, 1CF-6, 1LP-i 1LP-1 and I1LP-2 breakers open per the appropriate system operating procedures.

Reactivity Reactivitv Management Management (CR (CR SRO)

SRO)

RCS Boron:

RCS Boron: 11 64ppmB I Gp 1164ppmB Gp 66 Rod Rod Position: 48% II Batch Position: 48% Batch additions additions as as required for for volume volume control.

control.

Human Human Performance Performance Emphasis Emphasis (OSM)

OSM)

Procedure Procedure Use Use and and Adherence Scenario 44 RO Scenario RO

ML101520379

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