ML030560837

Nov/Dec 2002-301 Exam Final Simulator Scenarios

ML030560837
Person / Time
Site:	Vogtle
Issue date:	01/10/2003
From:	Ernstes M Operator Licensing and Human Performance Branch
To:	Gasser J Southern Nuclear Operating Co
References
50-424/02-301, 50-425/02-301 50-424/02-301, 50-425/02-301
Download: ML030560837 (116)

Text

Final Submittal (Blue Paper)

Actions ES As Given Simulator Scenario Operator D-2 VOGTLE EXAM 2002-301 50-424 AND 50-425 NOVEMBER 26, &

DECEMBER 2 - 13, 2002

Facility: VOGTLE Scenario No.: 1 Op-Test No.: 1 Examiners: Operators:

Initial Conditions: The plant is at 95%. RCS boron concentration is at 1308 ppm, BOL conditions. B Train equipment in service.

Turnover:

1. _ Plant Startup is in progress.

2. _ Rx power is 95%.

3. __ Train "A"MDAFW Pump is OOS due to mechanical seal failure. It has been OCOS for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> and is expected to return to service in 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />. (T.S. 3.7.5 Condition "B") LCO has been written.

4. The NCP has just been returned to service following maintenance PM's.

5. The Aux Bldg SO has been dispatched to the NCP and the pre-start checks have been performed. When you assume the shift the SS has directed the NCP be placed in service for engineering.

7. After the NCP has been placed in service you are to continue the power increase to 98% per 12004-C. (step 4.1.50) All prerequisites for the power increase were met on the previous shift. The Load Dispatcher has been notified of the power increase.

8. The last shift entered AOP 18009-C due to a 20 GPD tube leak on Steam generator #1. All actions of Section "B" have been completed with the exception of the radiation monitors which still need to be reset by Chemistry.

9. In addition a tornado alert has been issued for Burke and Richmond Counties.

There are heavy thunderstorms occurring at this time. The severe weather checklist (11889-C) has been completed in the last hour.

1 of 30

Event Malf. No. Event Event No. Type* Description 1 N-RO Place NCP in service 2 RO-R Increase power to 98%

3 SG03a BOP-I SG Pressure Transmitter fails low 4a EL13 SRO-C Loss of 120 VAC vital power 1AYIA (channel I 4b BOP-C instrumentation), (N41 failure, Steam Generator Control 4c RO-C Instrument failure letdown isolation) 5 Panel RO-C Following the loss of power to 1AYIA CVCS letdown Draw isolation valve 1LV-0459 will not reopen when normal O/R letdown is being restored. The RO will be required to place CVCS excess letdown in service to allow control of Pressurizer level.

6 FW16 SRO-l Feedwater Heater 4 level transmitter failure & Feedwater RO-I Heater 5A Hi-Hi level loss of extraction steam (AOP 18016 BOP-l C) 7 COO5b ALL-M Condensate Pump "B"trips with the failure of Condensate Cond Pump "C" to start. Crew enters AOP-18016-C; Rapid Pump insertion of control rods, Borate as necessary. Operating O/R Crew recognize the need to manually trip the Reactor due to AF03b the feedwater conditions. RO attempts to trip the Reactor however it cannot be tripped from the Control Room.. Crew enters 19211 -C start manual rod insertion, trip the Turbine, initiate emergency boration. Reactor is locally tripped and crew transition to 19000-C after completion of 19211 -C.

Upon entry into 19000-C the TDAFW pump will trip on overspeed and the Train "B"MDAFW pump will have a broken pump coupling resulting in a loss of heat sink. The Crew will enter 19231 to perform actions for recover of secondary heatsink, after progressing through the procedure the TDAFW Pump will be repaired and the plant will recover.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (P)RA, (L)ow Power 2 of 30

PREINSERTS:

Initial Conditions:

• Reset to IC #_ (NRC #1 snap)

• _Insure Information Board in Control Room is updated

• _Shift sign in and reactivity briefing sheets provided

• _RO & BOP Name plates on Panel D

• _Check EOP's, AOP's, UOP's, SOP's used in the last scenario clear of red marks

• _ IPC is Mode 1

• _Check Control Rod Group Step Counters

• _Unit 2 supplying the Aux Steam Header

• Correct AFD sheet is at the control board Select to following QMCB positions:

• Steam Seals System "Caution Tag" supplied from Aux Stm Hdr

• Hotwell Makeup Controller "Caution Tag" in manual at 50%

• Train "B" CCP in service

• All Controlling channels selected to channel #1

• All Train "B" Equipment Running

• Align plant for operation with minor S/G tube leak per AOP-18009-C section "B"

• _Ensure all QPCP and QHVC recorders running in auto

• __Place Clearance Tag on Train "A"AFW Pump (PTL Position)

• _Place Clearance Tag on AFW Train "A" Discharge valves (Closed position)

(1HS-5139A & 1HS-5137A) 3 of 30

Insert simulator malfunctions:

WY

• _(Malfunction SGO1 e at 20%) 20 GPD tube leak on Steam Generator #1 malfunction (Let run for 11 minutes to stabilize)

• _(ES01) Failure of the Automatic Reactor Trip

• _(ES02) Failure of the Manual Reactor Trip

• _(RD07) Control Rods Fail to move in Automatic

• _(AF03b) Broken Pump coupling on Train "B" MDAFW Pump Simulator Overrides & Remote Functions:

• _Condensate Pump "C" fails to start malfunction Panel Drawings-B1 -AFW-Cond Pump "3"-STOP

• _Override Train "A" AFW Pump to off position Panel Drawing-B1-AFW-HS5131A-STOP

• _Override discharge Valves for Train "A" AFW Pump to shut position Remote Function ( AF20, AF18 in LOCAL ; AF19, AF21 to 0%)

Panel Drawings-B1-AFW-HS5131A-Green light-OFF ALB50 (CR HI/LO AP)

Panel Drawings-HV1-ALB50-CR Hi/Lo Diff Press-OFF ALB20 (Turbine/Gen Trouble)

Panel Drawings-B2-ALB20-EO1 -OFF ALB62 (Gen Gas Non Sys Alarm)

Panel Drawings-QPCP2-ALB62-F02-OFF ALB36 (1ABB Trouble)

Panel Drawing-EAB3-ALB36 C02-OFF 4 of 30

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

Description:

Swap CVCS Charging Pumps (Start NCP; Stop CCP "B")

Time Position Applicant's Actions or Behavior SRO Actions:

• Gives direction for RO to start NCP and stop CCP "B"per SOP 13006-1 RO Actions:

"* Refers to SOP-1 3006-1 "Section 4.2.1"

"* Verifies Boron concentration in CCP "B"using control status board

"* Verifies 1HV-81 10 OPEN

"* Places 1FIC-0121 in manual control

-.,,j-

"* Starts NCP (1HS-0275)

"* Observe increase in charging flow

"* Stops CCP "B" (1HS-0274A)

"* Adjust RCP seal injection between 8-13 GPM

"* Returns CVCS System controls to automatic after conditions stabilize BOP Actions:

• Assists RO in Monitoring plant parameters during pump swap 5 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Event

Description:

Increase Power to 98%

Time Position Applicant's Actions or Behavior SRO Actions:

"* Gives crew briefing on the power increase

"* Directs Operators to increase power to 98%

"* Refers to UOP 12004-C, Power Operation RO Actions:

"* Commences dilution

"* Maintains rods above insertion limits

"* Maintains Tave within 2 deg Tref

"* Maintains AFD within target band BOP Actions:

• Loads Turbine per SOP.

6 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Event

Description:

Steam Generator #1 Controlling Pressure Channel Fails Low Malfunction: SG03a at 0% (1PT-514) input upon Examiner CUE Simulator Operator Notes:

7 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Event

Description:

Steam Generator #1 Controlling Pressure Channel Fails Low Time Position Applicant's Actions or Behavior BOP Actions:

"* Take manual control of Steam Generator #1 MFRV and MFP AP Critical controllers to stabilize Steam Generator #1 level and match steam Task and feed flows. (Immediate Operator Action)

"* Maintain S/G #1 level between 60-70% NR

"* Swap controlling channel per USS direction Take 1FS-512C from the 512 position to 513 position

"* Returns the Feedwater System to automatic SRO Actions:

"* Enter AOP-18001-C Section "F" for failed Steam Generator Pressure channel.

"* Direct (BOP) to select unaffected controlling channel per Table F2 Take 1FS-512C from the 512 position to 513 position

"* Return MFRV and MFPs to auto

"* Notify Operations duty manager

"* Have Maintenance Work order written

"* Refer to Technical Specifications

• 3.3.2 (SI) Functional Unit 1.e condition D Place channel in trip condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

• 3.3.2 (SLI) Functional Unit 4.d(1) condition D Place channel in trip condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

• 3.3.4 (Remote S/D) Functional Unit 13 Condition A Restore to operable status within 30 days 8 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event

Description:

Loss of vital AC Bus 1AYlA Simulator operator CUE: When SO or maintenance is dispatched report back, 1AYlA normal incoming breaker (02) is tripped and the flag for the ground relay is actuated. Maintenance recommends 1AYIA be inspected because they are unsure where the fault originated.

Malfunction: EL13A on Examiner CUE Simulator operator: Override 1LV-459 CLOSED following the loss of power to 1AY1 A to force operating crew to place CVCS Excess Letdown in service.

• Panel Drawing-A2-LTD-HS459-CLOSED Time Position Applicant's Actions or Behavior RO/BOP Actions:

"* Identify loss of 1AYlA.

• ARP on electrical panel (RO/BOP)

• Recognize failed channel 1 instruments. (RO/BOP) 18032-C

• Manually Control Steam Generator Levels and MFP speed Actions (RO/BOP)

"* Swap Steam Generator Controlling channels per USS direction (RO/BOP)

• Return Steam Generator Level Control to automatic when conditions are stabilized (RO/BOP)

"* Recognize CVCS letdown has isolated. (RO/BOP)

"* Select Non affected controlling channel per USS direction for Pressurizer level control (RO/BOP)

"* Recognize Train A pressure instrument failure 1-PT-455.

(RO/BOP) 9 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event

Description:

Loss of vital AC Bus 1AYIA RO/BOP Actions: (PT-455) 0 Sprays in manual control (RO/BOP) 18001-C 0 1HS-455A in close (RO/BOP)

Section C & Operate heaters and spray to maintain Pressurizer Actions pressure between 2220-2250 psig.(RO/BOP) 0 1PIC-455A in manual at 25% demand (RO/BOP)

• Swap controlling channels(457/456). (RO/BOP)

• Return control system to automatic.(RO/BOP)

• Place recorder 1PS-455G to channel 457 position (RO/BOP

• Verify P-11 status light (RO/BOP)

"* Defeat failed channel for Tavg and AT as directed by the USS 18032-C (RO)

Actions

"* When RO attempts to restore Normal CVCS letdown flow 1LV 0459 will not reopen, refer to event 5 for actions relate to this failure.

Return Point following Actions of 18007-C to place excess letdown in service 18001-C Actions (PT-505)

Section H

• Block Channel 1 rod stop (RO/BOP)

Actions

• Place Steam Dumps in "Steam Pressure Mode" per USS direction (RO/BOP) (may reference 13601-1)

• Verify P-1 3 BPLP Status light per USS direction (RO/BOP)

Next Event Option for Examiner to move on 18032-C

• Maintain Stable Plant Conditions (RO/BOP)

Actions 0 RCS Temperature

• Pressurizer Level

• Pressurizer pressure 0 S/G levels 10 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event

Description:

Loss of vital AC Bus 1AYlA RO/BOP

• Verify NI-41 Interlocks per Tech Spec required actions for T.S.3.3.1-1 Functions (16)a,b,c,d,e,f and 3.3.2-1 function 8b All are 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> actions

"* Dispatch Control Building SO and Maintenance to investigate problem (SRO/RO/BOP)

"* Shutdown any standby CCW, NSCW or ACCW pump that automatically started due to the power loss per USS direction (RO/BOP)

"* Block failed NI channel.

"* Rod stop bypass for failed channel (RO/BOP)

"* Comparator channel defeat for failed channel (RO/BOP)

"* Power mismatch bypass for failed channel (RO/BOP)

"* Upper section for failed channel (RO/BOP)

"* Lower section for failed channel (RO/BOP)

Actions:

S Enter AOP 18032-C Section "A" "Loss of vital instrument panel 1AY A".

• Direct manual control of S/G levels Direct BOP is selecting unaffected controlling channel for S/G level control

• Direct BOP to return S/G level control to automatic Attachment A Table 1

• Enter AOP 18001-C Section "C" "Due to 1PI-455 controlling channel failing low on the power loss".

• Direct RO to verify 0CS pressure stable or rising

• Direct RO to place sprays in manual control 11 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event

Description:

Loss of vital AC Bus IAYlA SRO 0 Direct RO to place 1HS-455A in close 0 Direct RO to control operate heaters and spray to maintain Pressurizer pressure between 2220-2250 psig.

• Direct RO to place 1PIC-455A in manual at 25% demand

• Direct RO to swap controlling channels(457/456).

Direct RO to return control system to automatic Sprays, Heaters, PORV Check P-11 status light (I hour Tech Spec Action)

NOT illuminated is correct indication Return to AOP 18032-C Section "A" "Loss of vital instrument panel 1AY1A".

"* Dispatch operator/maintenance to investigate 120 VAC instrument panel 1AY1A power loss. (Do Not Restore Power until maintenance has investigated cause of the power loss)

"* Direct RO to defeat Failed loop 1 Tavg and AT.

" Direct RO to restore CVCS letdown flow to service per SOP 13006-1 When RO attempts to restore Normal CVCS letdown flow 1LV-0459 will not reopen, refer to event 5 for actions relate to this failure.

S SS.*WSS SS W......SN

• SMS*U Return

• Point following Actions of 18007-C to place excess letdown in service

• Enter AOP 18001-C "Section H" due to 1PT-505 failure.

• Direct BOP to Block Channel 1 rod stop 12 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Event

Description:

Loss of vital AC Bus 1AY1A SRO

• Direct BOP to place Steam Dumps in "Steam Pressure Mode" (may reference 13601-1)

• Verify P-1 3 BPLP Status light per USS direction Next Option for Examiner to move on Event O

"* Verify TS interlocks.

• Tech Spec 3.3.1-1 functions 16a,b,c,d,e, and 3.3.2-1 function 8b. (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Tech Spec Actions)

" Enter AOP-18002-C for failed NI.

• Direct SOP to block failed NI channel.

<-A Notify Operations duty manager.

" Have Maintenance Work order written.

" Refer to Technical Specifications.

• Apply TS 3.8.7 Condition A Restore Inverter to service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or shutdown required, mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />

• Apply TS 3.8.9 Condition B Restore power to 1AY1A within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or shutdown required, mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />

______ I __________ 4 13 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 5 Event

Description:

Following the loss of power to 1AYIA 1LV-459 will not reopen when the RO is restoring CVCS normal letdown flow. This will require the RO to place Excess Letdown flow in service to control Pressurizer level.

Malfunction: Panel Drawing-A2-LTD-HS459-CLOSED Simulator Operator: Override 1LV-0459 closed following the loss of power to 1AY1A.

Simulator Operator Notes:

14 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 5 Event

Description:

Following the loss of power to 1AYIA 1LV-459 will not reopen when the RO is restoring CVCS normal letdown flow. This will require the RO to place Excess Letdown flow in service to control Pressurizer level.

Time Position Applicant's Actions or Behavior RO Actions:

"* Ro will attempt to place normal letdown flow in service using SOP 13006-1

"* Recognizes the 1LV-0459 will not reopen.

• Refers to SOP-1 3008-1 to place Excess Letdown in service "Section 4.1"

• Notes maximum reactor power with excess letdown in service is limited to 3562 Mwt

• Verifies 1HV-8098 Closed

• Verifies 1HIC-0123 Closed

& Verifies 1HV-8100 & 1HV-8112 Open

• Verifies 1HV-8143 is in the VCT Position

• Open 1HV-8153

• Open 1HV-8154

• Notes indication on 1PI-0124 & 1TI-0122 on main control board

• Slowly raises Excess flow while monitoring temperature and pressure rise on indication.

• Limits pressure rise to 50 pisg (added to pressure noted when

• 1HV-8153 & 1HV-8154 were opened)

• Limits temperature to 165 F 15 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 5 Event

Description:

Following the loss of power to 1AYIA 1 LV-459 will not reopen when the RO is restoring CVCS normal letdown flow. This will require the RO to place Excess Letdown flow in service to control Pressurizer level.

RO

• Lowers Pressurizer level to normal (requires RO to lower total charging flow to minimum)

Return to event 4 at arrow marking spot.

SRO Actions:

"* Refers to AOP 18007-C Section "A" and directs crew operations

"* Directs RO to isolate normal letdown flow path when 1LV-0459 fails to open

"* Directs RO to lower charging flow

"* Notifies Chemistry Department of CVCS Letdown isolation

"* Directs (RO) to place excess letdown flow in service

"* Directs RO to restore Pressurizer level to normal

"* Initiate maintenance.

"* Notify Operations duty manager.

"* Have Maintenance Work Order written.

Return to event 4 at arrow marking spot.

16 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

Loss Of Feedwater Heaters results in Reactor Power increase Malfunction: FW16A on Examiner CUE Simulator Operator: Override 1HS4302A Feedwater Heater 5A Extraction Steam Stop Valve to the closed position Panel Drawing-B2-TUR-HS4302A-CLOSED (5A)

Panel Drawing-B2-TUR-HS4343A-CLOSED (4A)

Simulator Operator Notes:

17 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 6 Event

Description:

Loss Of Feedwater Heaters results in Reactor Power increase Time Position Applicant's Actions or Behavior RO/BOP Actions:

"* Reference annunicators received of feedwater heater #4A

"* Recognizes Reactor Power is increasing due to the lower main feedwater temperature (RO/BOP)

"* Manual Control rod insertion to lower Reactor Power below 100% as required (RO/BOP)

"* Lower Main Turbine Load to maintain Reactor Power below 100% (RO/BOP)

"* Restore Tavg to program. (RO/BOP)

"* Verify plant parameters are within normal operating range; Pressurizer Level / Pressure, Steam Generator Levels.

SRO Actions:

"* Refers to AOP 18016-C Section "C" and directs crew operations

"* Directs (RO/BOP) to maintain Reactor Power below 100% by all indications

" Determine that power reduction is required due to the loss of feedwater heating

"* Initiate maintenance.

"* Notify Operations duty manager.

"* Have Maintenance Work Order written.

18 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event

Description:

Condendate pump "B" will trips and pump "C" fails to start automatically or manually.

Malfunction: C005b on Examiner CUE Simulator Operator: Insure malfunctions are in place to prevent automatic, manual reactor trip & automatic rod movement Simulator Operator Notes:

19 of 30

<-7

Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event

Description:

Condendate pump "B" will trips and pump "C" fails to start automatically or manually.

Time Position Applicant's Actions or Behavior RO/BOP Actions:

"* Recognizes Condensate Pump "B" has tripped and the standby Condensate Pump "C" has failed to start. (RO/BOP)

"* Attempts to manually start Condensate Pump "C" (RO/BOP)

"* Recognizes that Condensate Pump "C" failing to start will require a manual reactor trip due lowering S/G levels.

(RO/BOP)

"* Informs the USS of the problem SRO Actions:

"* Refers to AOP 18016-C Section "C" and directs crew operations

"* Direct RO to start Condensate Pump "C"

"* Recognizes due to lowering S/G levels the reactor should be manually tripped

"* Directs RO to manually trip the reactor

_______________________________ J 20 of 30

No.: 1 Event No.: 7 Op-Test No.: 11 Scenario No.:

Scenario 1 Event No.: 7 Event Description Condensate pump "B" will trip with the failure of Condensate pump "C" to start automatically or manually. This will require to operating crew to manually trip the Reactor, it will fail to trip. The crew will enter 9211-C (ATWT) for required actions to shutdown the plant. Following the Reactor trip the crew will transition to back to 19000-C at which time the TDAFW Pump will trip on overspeed (MDAFW Pump "B" will be running with a broken pump coupling).

Simulator Operator: Allow crew to progress past step 7 in 19211-C and if a reasonable amount of time has elapsed, insert Reactor trip.

"* Remove malfunction (ES01) Failure of the Automatic Reactor Trip.

"* TDAFW Pump trips on overspeed (AF02C)

"* Remove (AF02C) following TDAFW evaluation to allow operation.

"* Remote Function (AF22) will be used to reset the T&TV.

Cue: Time Dispatched Report Back

• The Train "B" MDAFW pump motor is running but the pump coupling is broken.

• Maintenance engineering report the TDAFW Pump tripped due to a slug of water in the steam line and can be operated after reset.

Simulator Operator Notes:

21 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event Description Condensate pump "B" will trip with the failure of Condensate pump "C" to start automatically or manually. This will require to operating crew to manually trip the Reactor, it will fail to trip. The crew will enter 9211-C (ATWT) for required actions to shutdown the plant. Following the Reactor trip the crew will transition to back to 19000-C at which time the TDAFW Pump will trip on overspeed (MDAFW Pump "B" will be running with a broken pump coupling).

Time j Position Applicant's Actions or Behavior Entrance into 19211-C - Critical Task RO/BOP Actions: (19211-C)

"* Attempt to manually trip the Reactor using BOTH Control Room Handswitches (RO/BOP)

"* Dispatches the Control Building SO to Locally Manually trip the Unit 1 Reactor (USS/RO/BOP)

" Manually insert Control Rods (RO/BOP) Note: When the (RO/BOP) places the Rod Control System in Automatic they must recognize the failure of the system to automatically insert the Control Rods and return to manual insertion

"* Manually Trip the Main Turbine (RO/BOP)

"* Verify/Start AFW System (RO/BOP)

"* Identify that Reactor Power is >5% (RO/SRO)

"* Initiate Emergency Boration (RO/BOP)

"* Align CVI per USS direction (RO/BOP)

"* Dispatch Auxiliary Building SO to locally shut 1-1208-U4-183 (USS/RO/BOP)

"* Verify Core Exit TC's less than 1200 degrees F.(RO/BOP)

"* Perform first 16 steps of 19000-C as time permits if Safety Injection is automatically actuated (RO/BOP)

Actions: (19000-C) (RO/BOP) will be required to manually align "A" train components due to the loss of 1AY1A)

Following the Reactor trip and completion of 19211 -C the crew will transition back to 19000-C.

22 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event Description Condensate pump "B" will trip with the failure of Condensate pump "C" to start automatically or manually. This will require to operating crew to manually trip the Reactor, it will fail to trip. The crew will enter 9211-C (ATWT) for required actions to shutdown the plant. Following the Reactor trip the crew will transition to back to 19000-C at which time the TDAFW Pump will trip on overspeed (MDAFW Pump "B" will be running with a broken pump coupling).

ROIBOP

• Verify Rx Trip (RO/BOP)

E-0

• Verify turbine trip. (RO/BOP) 19000-C Actions

• Verify power to AC emergency busses. (RO/BOP)

• Check if SI Actuated. (RO/BOP)

• Verify Feedwater isolation. (RO/BOP)

• Verify MLB indications for both trains of ECCS equipment aligning for injection phase. (RO/BOP)

• Verify containment isolation Phase A actuated. (RO/BOP)

• MDAFW Pumps running. ( NOTE: operator should recognize the MADFW Pump "B" has no discharge pressure and dispatch an operator to check locally) (RO/BOP)

• SG blowdown isolated (RO/BOP) 19231-C Actions: (19231-C)

Actions

"* Verifies RCS pressure >350 and RHR flow <500 (RO/BOP)

"* Check CCP status (RO/BOP)

No CCP requires feed & bleed

"* Check RCS pressure <2335 psig (RO/BOP)

Pressure >2335 due to loss of heat sink requires feed & bleed

"* Check S/G levels (RO/BOP)

Any 3 S/G levels <29% requires feed & bleed 23 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event Description Condensate pump "B" will trip with the failure of Condensate pump "C" to start automatically or manually. This will require to operating crew to manually trip the Reactor, it will fail to trip. The crew will enter 9211-C (ATWT) for required actions to shutdown the plant. Following the Reactor trip the crew will transition to back to 19000-C at which time the TDAFW Pump will trip on overspeed (MDAFW Pump "B" will be running with a broken pump coupling).

RO/BOP Path #1 if any of the conditons above are satisfied then feed &

bleed criteria will be required go to step 11 and:

Feed &

• Stop All RCPs (RO/BOP)

Bleed Actions 0 Manually actuate SI (RO/BOP)

• Verify feed path (RO/BOP)

• CCP at least 1 running OR

"* SI pump at least 1 running

"* Verify ECCS valve alignment using MLBs

• Establish bleed path (RO/BOP)

"* Turn off Pressurizer heaters

"* ARM both trains of COPs

"* Open both Pressurizer PORVs Planned End Point for feed & bleed Path #2 if TDAFW pump is returned to service prior to meeting feed & bleed criteria:

"* Try to establish AFW flow (RO/BOP)(Check alignment)

"*SGBD valves shut (RO/BOP)

"*S/G sample valves shut (RO/BOP)

"*Check suction to AFW pumps (RO/BOP)

"*Check AFW discharge throttle valve open (RO/BOP)

"* Check TDAFW Pump:

"* 1HV-5106 open (RO/BOP)

"* 1PV-15129 is Closed (due to the overspeed)

"* Governor Valve operating properly.

"* The (RO/BOP) directs the Outside Building SO to locally reset the T&TV when ready 24 of 30

LventINo.: /

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

Scenario No.: 11 Event No.: 7 K-> Event Description Condensate pump "B" will trip with the failure of Condensate pump "C" to start automatically or manually. This will require to operating crew to manually trip the Reactor, it will fail to trip. The crew will enter 9211-C (ATWT) for required actions to shutdown the plant. Following the Reactor trip the crew will transition to back to 19000-C at which time the TDAFW Pump will trip on overspeed (MDAFW Pump "B" will be running with a broken pump coupling).

nO/sO3P "* Trips RCPs (RO/BOP)

"* Starts TDAFW Pump (RO/BOP)

• PLACE TDAFW Pump Steam Admission Valve 1 -HV-5106 Handswitch 1-HS-5106A to CLOSE and HOLD (BOP)

• PLACE Handswitch 1-HS-15111 to OPEN, then RELEASE (RO/BOP)

• When Trip and Throttle Valve 1-PV-15129 is full open, RELEASE Handswitch 1-HS-5106A (RO/BOP)

• Establish >570 gpm AFW flow (RO/BOP)

• Transition to 19000-C Planned End Point if AFW flow is established

.1 25 of 30 C

Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event Description Condensate pump "B" will trip with the failure of Condensate pump "C" to start automatically or manually. This will require to operating crew to manually trip the Reactor, it will fail to trip. The crew will enter 9211-C (ATWT) for required actions to shutdown the plant. Following the Reactor trip the crew will transition to back to 19000-C at which time the TDAFW Pump will trip on overspeed (MDAFW Pump "B" will be running with a broken pump coupling).

SRO Actions:

"* Directs/Insures the RO has manually tripped the Reactor Using BOTH Control Room Handswitch.

S.1 "* Enters 19211-C (ATWT).

"* Directs/Insures the BOP has manually tripped the Main Turbine

"* Ensures the Control Building Operator Has been dispatched to locally manually trip the Unit 1 Reactor.

"* Insure AFW in service

"* Direct the (RO/BOP) to initiate Emergency Boration

"* Direct BOP to align CVI

"* Direct isolation of dilution paths

"* Directs RO to check Reactor Power <5%

E-O Actions: (19000-C)

"* Following the Reactor trip and completion of 19211-C the crew will transition back to 19000-C.

"* Directs RO to Verify Rx Trip

"* Directs BOP Verify turbine trip.

"* Directs BOP Verify power to AC emergency busses.

"* Directs RO Check if SI Actuated.

26 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event Description Condensate pump "B" will trip with the failure of Condensate pump "C" to start automatically or manually. This will require to operating crew to manually trip the Reactor, it will fail to trip. The crew will enter 9211-C (ATWT) for required actions to shutdown the plant. Following the Reactor trip the crew will transition to back to 19000-C at which time the TDAFW Pump will trip on overspeed (MDAFW Pump "B" will be running with a broken pump coupling).

SRO

• Directs BOP verify Feedwater isolation.

• Verify MLB indications for both trains of ECCS equipment aligning for injection phase.

NOTE: The USS must have the RO/BOP manually align Train "A" equipment due to the power loss on 1AYlA.

"* Direct RO to verify proper CIA

"* Directs BOP to verify MDAFW Pumps running.

"* Directs BOP to verify SG blowdown isolated H-i Actions: (19231-C)

• Verifies RCS pressure >350 and RHR flow <500 (RO/BOP)

• Check CCP status (RO/BOP)

No CCP requires feed & bleed

• Check RCS pressure <2335 psig (RO/BOP)

Pressure >2335 due to loss of heat sink requires feed & bleed

• Check S/G levels (RO/BOP)

Any 3 S/G levels <29% requires feed & bleed Path #1 if any of the conditons above are satisfied then feed &

bleed criteria will be required go to step 11 and:

"* Stop All RCPs (RO/BOP)

"* Manually actuate SI (RO/BOP)

" Verify feed path (RO/BOP)

• CCP at least 1 running OR

"* SI pump at least 1 running

"* Verify ECCS valve alignment using MLBs

______ .1__________ 1 27 of 30

Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event Description Condensate pump "B" will trip with the failure of Condensate pump "C" to start automatically or manually. This will require to operating crew to manually trip the Reactor, it will fail to trip. The crew will enter 9211-C (ATWT) for required actions to shutdown the plant. Following the Reactor trip the crew will transition to back to 19000-C at which time the TDAFW Pump will trip on overspeed (MDAFW Pump "B" will be running with a broken pump coupling).

SRO

• Establish bleed path (RO/BOP)

"* Turn off Pressurizer heaters

"* ARM both trains of COPs

"* Open both Pressurizer PORVs (Planned End Point for feed & bleed)

• Try to establish AFW flow (BOP)(Check alignment)

• Direct the Outside Operator to reset the T&TV when conditions allow

• When >570 GPM AFW is established transition to 19000-C (Planned End Point if AFW flow is established)

Examiner: Have the SRO (USS) classify the event. The answer key for event classification is on page 29.

28 of 30

Classify the Event answer:

Red path on heat sink is a potential loss of both the clad & RCS barrier which is a SITE AREA EMERGENCY.

29 of 30

Initial Conditions: The plant is at 95%. RCS boron concentration is at 1308 ppm, BOL conditions. B Train equipment in service.

Turnover:

1. Plant Startup is in progress.

2. Rx power is 95%.

3. Train "A" MDAFW Pump is COS due to mechanical seal failure. It has been OOS for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> and is expected to return to service in 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />. (T.S. 3.7.5 Condition "B") LCO has been written.

4. The NCP has just been returned to service following maintenance PM's.

5. The Aux Bldg SO has been dispatched to the NCP and the pre-start checks have been performed. When you assume the shift the SS has directed the NCP be placed in service for engineering.

6. After the NCP has been placed in service you are to continue the power increase to 98% per 12004-C. (step 4.1.50) All prerequisites for the power increase were met on the previous shift. The Load Dispatcher has been notified of the power increase.

7. The last shift entered AOP 18009-C due to a 20 GPD tube leak on Steam generator #1. All actions of Section "B" have been completed with the exception of the radiation monitors which still need to be reset by Chemistry.

8. In addition a tornado alert has been issued for Burke and Richmond Counties.

There are heavy thunderstorms occurring at this time. The severe weather checklist (11889-C) has been completed in the last hour.

30 of 30

Facility: VOGTLE Scenario No.: 2 Op-Test No.: 1 Examiners: Operators:

Initial Conditions: The plant is at 45% ramping to 100% at 8%/hr. RCS boron concentration is at 363 ppm, EOL conditions. After shift turnover have the RO complete the "B"MFP startup. All activities have been completed in SOP-1 3615-1 up to step 4.1.4.20. "A" Train equipment in service. CCW train B in PTL.

Turnover:

1. -Plant Startup is in progress.

2. _ Rx power is 45%.

3. 1PV-0456 is in the shut position due to seat leakage.

4. 1HV-8000B is shut to comply with Technical Specification 3.4.11 Condition "A".

5. ___ CCW train B pumps in PTL, clearance has just been released. Functional testing scheduled approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> from now for response time testing. Tech Spec action of 3.7.7 have been completed.

6. SGBD is OOS due to HIGH failure on 1RE-021. Will be returned to service of the next shift.

7. The last shift entered AOP 18009-C due to a 20 GPD tube leak on Steam generator #1. All actions of Section "B" have been completed with the exception of the radiation monitors which still need to be reset.

8. In addition a tornado alert has been issued for Burke and Richmond Counties.

There are heavy thunderstorms occurring at this time. The severe weather checklist has been completed in the last hour.

1 of 23

Event Malf. Event Event No. No. Type* Description 1 N-RO Place the "B" Main Feedwater Pump in service 2 PR-02A RO-I PRZR pressure channel fails high 100% PORV-455A fails partially open on transient PR-05 5%

CC01A BOP-C 3 O/R Loss of CCW train B pmp5 4 FW14 BOP-l MFP discharge pressure fails low 0%

5 CV07 RO-C NCP trips 6 RP06A ALL-R RCP #1 seal #1 failure (5.2 gpm) mgmt says S/D in 30 min 15% SRO directs rapid power reduction per 18013-C 7 RO-N Operating Crew reduces power to be in mode 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 8 RP06a M-ALL RCP seal LOCA 100% B train CVA failure RC05a SIP-1A fails to start 1.5% PV-507C fails open (steam Dump)

MS01 Stop scenario when 19012-C is entered 100%

ES19B SI06a

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (P)RA, (L}ow Power 2 of 23

PREINSERTS:

Initial Conditions:

• Reset to IC # (NRC #2 snap)

• _Insure Information Board in Control Room is updated

• _Shift sign in and reactivity briefing sheets provided

• _RO & BOP Name plates on Panel D

• _Check EOP's, AOP's, UOP's, SOP's used in the last scenario clear of red marks

• _IPC is Mode 1

• _Check Control Rod Group Step Counters

• _Unit 2 supplying the Aux Steam Header

• _MFP "B" running on GE pot

• _Start second condensate pump

• _Ensure C-7 is reset Select to following QMCB positions:

& 1 PV-0456 in shut position with "Caution Tag"

• 1 HV-8000B in shut position with "Caution Tag" 0 Steam Seals System "Caution Tao" supplied from Aux Stm Hdr 0 Hotwell Makeup Controller "Caution Taq" in manual at 50%

0 All Controlling channels selected to channel #1 0 All Train "A"Equipment Running

• _Align plant for operation with minor S/G tube leak per AOP-18009-C section "B"

• _Ensure all QPCP and QHVC recorders running in aut 3 of 23

Insert simulator malfunctions:

• (Malfunction SGO1E at 20%) 20 GPD tube leak on Steam Generator #1

• _(ES19B) CVI Train "B" failure

• _(SI06A) SI Pump "A" fails to automatically start on the SI signal

• _(RM05G) 1RE-021 failed high causing SGBD to isolate Simulator Overrides & Remote Functions:

• CCW pump #5 - STOP Panel Drawings-AL-CCW-HS1856A-STOP

• ALB50 (CR HI/LO AP)

Panel Drawings-HV1-ALB50-CR Hi/Lo Diff Press-OFF

• ALB20 (Turbine/Gen Trouble)

Panel Drawings-B2-ALB20-E01 -OFF

• ALB62 (Gen Gas Non Sys Alarm)

Panel Drawings-QPCP2-ALB62-F02-OFF 4 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Event

Description:

Complete the actions using SOP-13615-1 for placing the "B" Main Feedwater Pump in service Time Position Applicant's Actions or Behavior RO Actions:

SOP 13615-1 Section 4.1.4 selected:

"* Open 1HV-5209 "B" MFP discharge valve

"* Verify 1HS-5208 & 1HS5209 are in automatic

"* Verify MFPT-B TURNING GEAR MOTOR, 1-HS-3164, is in the AUTO/PULL-TO-LOCK position

" 1-SIC-0509C, in MAN and set to minimum speed TRANSFER Pump Speed Control to 1-SIC-0509C as follows:

a. MONITOR MFPT-B AUTO/MAN Transfer Deviation, 1-SI-3154.

b. Slowly ADJUST Motor Speed Changer potentiometer, 1-SC-3152 to obtain zero deviation on 1-SI-3154.

c. TRANSFER control by placing MFPT-B Motor Speed Changer, 1-HS-3152, to AUTO.

"* Verify MFP-A is in AUTO.

"* OBSERVE the "A"Main Feed Pump's speed and feed water flow rate to verify load sharing while performing the following:

(1) Slowly ADJUST MFPT-B Speed controller, 1-SIC-0509C, output to match Master MFPT Speed controller, 1-SIC-0509A, output.

(2) PLACE MFPT-B Speed controller, 1-SIC-0509C, in AUTO.

______ I _______ .1 5 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Event

Description:

PRZR pressure PT-455 fails high and PORV 455A fails partially open. Also PORV 455A block valve will not automatically close on the 2185 pressure interlock.

Malfunctions: PR02A @ 100%, PR05 @ 10% on Examiner CUE Override block valve 1 HV-8000A open remove override when RO places the handswitch to close.

Simulator operator: (Remote Function) PR03 When requested to remove power from 1 HV8000A Simualtor Operator Notes:

6 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Event

Description:

PRZR pressure PT-455 fails high and PORV 455A fails partially open. Also PORV 455A block valve will not automatically close on the 2185 pressure interlock.

RO Actions:

Immediate actions:

"* Close Spray valves

"* Close PORV-455A

"* Energize PZR Heaters

"* Control Pressurizer pressure between 2220-2250 psig

"* Master Controller placed in manual @ 25%

"* Select 457/456 for control

"* Return heaters, spray valves, and PORV, master controller to AUTO

"* Select unaffected channel for panel recorder (457)

"* Verify P-11 in proper state for plant conditions (1 hr LCO action)

PORV Actions: (PORV-455A failing to fully shut) 455 Fails F Observes dual indication for PORV-455A Critical Task

• Shuts PORV Block Valve 1HV-8000A SRO Actions:

18001-C Section C referenced (PT-455 failure)

• Directs RO to close spray valves, PORV-455A, Energize Heaters

& Directs RO to Master Controller placed in manual @ 25%

• Directs RO to select 457/456 as controlling channels 7 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Event

Description:

PRZR pressure PT-455 fails high and PORV 455A fails partially open. Also PORV 455A block valve will not automatically close on the 2185 pressure interlock.

"* Directs RO to return heaters, spray valves, and PORV-455A to automatic

"* Directs RO to verify P-11 BPLP (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action)

PORV Actions: (PORV-455A failing to fully shut) 455 Fails

• Directs RO the close PORV-455A Critical

• Directs RO to close PORV-455A block valve 1HV-8000A Task Tech Notifies duty manager of AOP entry Spec Contacts maintenance to initiate repairs Actions Refers to Tech Specs:

" LCO 3.3.1 Functional Unit 6 - Condition E Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Functional Unit 8a - Condition M Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Functional Unit 8b - Condition E Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

"* LCO 3.3.2 Functional Unit id -Condition D Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Functional Unit 8b - Condition L Verify P-11 BPLP status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

"* LCO 3.4.11 Condition B Close block valve and remove power within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

• Request SSS to remove power from 1HV-8000A

.1 L 8 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Event

Description:

Loss of CCW train B (pump 1 trips,pump 5 fails to start)

Malfunction: CC01A on Examiner Cue Simulator Operator CUE: Report Back when dispatched to CCW Pump #1:

Time Called:

Report back time:

Control Building SO and Maintenance: Phase A,B,C (150 device) Overcurrent Flags are present and the 186 lockout is tripped for CCW Pump

1. 1.

Auxiliary Building SO: There are no obvious problems noted locally at the CCW Pump #1 Simulator Operator CUE: Report Back when dispatched to CCW Pump #5:

Control Building SO and Maintenance: The Breaker to CCW Pump #5 appears to not be racked in completely and the racking mechanism may be damaged.

Simulator Operator Notes:

9 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Event

Description:

Loss of CCW train B (pump 1 trips,pump 5 fails to start)

BOP Actions:

"* Diagnose only CCW pump #3 is running

"* Attempt manual start of pump #5

"* Stop CCW train A

"* Place CCW train B in service using SOP-13715-C

"* Verifies NSCW operation

"* Dispatch SO to place SFPC train B in service

"* Dispatch SO to investigate CCW pumps/breakers SRO Actions:

"* Enters 18020-C Loss of CCW

"* Directs RO to manually start CCW Pump #5

"* Directs RO to stop CCW Pump #3

"* Directs RO to place Train "B" CCW in service

"* Notifies duty manager of AOP entry

"* Contacts maintenance to initiate repairs

"* Tech Spec:

0 LCO 3.7.7 condition B (72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> shutdown) 10 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event

Description:

MFP Discharge pressure indication (PT-508) fails low on Examiner CUE Malfunction: FW14 @ 0% (set ramp time at 11 seconds) on Eximiner Cue Simulator Operator Notes:

11 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event

Description:

MFP Discharge pressure indication (PT-508) fails low on Examiner CUE BOP Actions:

"* Diagnose PT-508 failed low

"* Verify MFPs operating "adjust speed as required to maintain S/G levels using 1SIC-507A/B/C

• Restore Tavg to program (RO/BOP)

"* Take manual control of MFP master controller

"* Match steam and feed flows on all 4 SGs

"* Verify Pressurizer pressure and level trending on program (RO/BOP)

"* Check all feedwater heaters extraction valves open

"* Operate Main Feedwater Pump AP in manual SRO Actions:

"* Reference 18016-C section "A"

"* Verifies BOP is takes manual control of MFP master controller

"* Directs BOP to adjust MFP speed as required to maintain S/G levels using 1SIC-507A/B/C

"* Directs operators to restore Tavg to program

"* Verifies BOP controlling S/G levels within normal bands

"* Has the BOP maintain manual control of the MFP until repaired

"* Direscts operators to verify Pressurizer pressure and level trending on program

"* Notifies duty manager of AOP entry

"* Contacts maintenance to initiate repairs 12 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event

Description:

MFP Discharge pressure indication (PT-508) fails low on Examiner CUE SRO

• Inform BOP of responsibilities regarding manual control of Main Feedwater Pump AP 13 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Event

Description:

NCP Trips Malfunction: CV07 on Examiner Cue Simulator Operator CUE: Report Back when dispatched to NCP Time Called:

Report back Auxiliary Building SO and Maintenance: The NCP Pump appears to be OK. Maintenance suspects a faulty relay caused the problem.

Simulator Operator Notes:

14 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Event

Description:

NCP Trips RO Actions:

"* Isolate CVCS letdown (Due to flashing in letdown line)

"* Verify Charging Pump lineup

"* OPEN 1-HV-8471A (1-HV-8471B) CCP-A(B) SUCTION

"* OPEN 1-HV-8111A (1-HV-8111B) CCP-A(B)

MINIFLOW,

"* OPEN 1-HV-81 10 CCP A & B COMMON MINIFLOW,

"* CLOSE 1-HV-0190A (1-HV-0190B) CHARGING THROTTLE,

"* OPEN 1-HV-8485A (1-HV-8485B) CCP-A(B)

DISCHARGE ISOLATION,

"* If starting CCP-B, OPEN 1-HV-8438 CCP DISCHARGE HEADER CROSS-CONNECT

"* SET 1-HIC-182 for MAXIMUM Seal Flow (0%

demand).

"* ENSURE 1-FIC-0121 CHARGING FLOW in MAN and SET to minimum

"* ENSURE 1-LI-0185 VCT level indicates between 30 and 80%.

"* Dispatch SO to investigate NCP and perform CCP prestart checks

"* Start CCP 1A or 1B

"* Raise charging to 80-90 GPM

"* RCP seal injection flow 8-13 GPM/pump

"* Go to section 4.4.2 to restore letdown flow

• CLOSE 1-HV-8149A, 1-HV-8149B, and 1-HV-8149C LETDOWN ORIFICE 45 & 75 gpm,

• CLOSE 1-LV-0460 AND 1-LV-0459 LETDOWN ISOLATION VLV UPSTREAM and DOWNSTREAM

• CLOSE 1-HV-8145 PZR AUX SPRAY VALVE, 0 OPEN 1-HV-15214 CVCS LETDOWN PIPE BREAK PROT ISOLATION 0 OPEN 1-HV-8160 RCS LETDOWN LINE ISO VLV IRC, 15 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Event

Description:

NCP Trips RO OPEN 1-HV-8152 RCS LETDOWN LINE ISO VLV ORC 0 1-PIC-0131 LETDOWN PRESS in MANUAL and output adjusted to 50% to 75%,

• 1-TIC-0130 LETDOWN HX OUTLET TEMP in 0 MANUAL and output adjusted to 50%,

• 1-LR-0459 PRESSURIZER LEVEL greater than 17%,

OPEN one of the following 1HV-8146 or 1HV-8147 S ýOPEN 1-HV-8106 and 1-HV-8105 CHARGING TO RCS ISOLATIONs

• Adjust charging flow to between 80-90 gpm

• Maintain RCP seal flow between 8-13 gpm

& Open 1LV-459 & 1LV-460

- Open 75 gpm orifice isolation valve

• When 1-PI-0131A LETDOWN PRESS stabilizes between 360 and 380 psig, PLACE 1-PIC-0131 in AUTO Place 1TIC-130 in automatic and verify temperature is maintained <115 degrees F.

Actions:

SRO

• Enters 18007-C "Section B" 0 Have RO isolate CVCS letdown flow

• Check ACCW System in service 0 Check indication that NCP did not trip due to gas binding 0 Direct starting of CCP (A or B) per SOP-13006-1

"* Dispatches Operator and maintenance to investigate problem

"* Notifies duty manager of AOP entry

"* Has SSS initiate work order

"* (Note Only INFO LCOs for this failure) 16 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

RCP #1 seal #1 failure (5.2 gpm)

Malfunction: RP06A @ ramp slowly @ 15% (watch indication) on Examiner Cue Simulator operator Cue: Duty Manager instructs USS to shutdown unit in next hour and secure RCP #1 when contacted by USS about problem.

Load Dispatcher will be notified by duty manager Simualtor Operator Notes:

17 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

RCP #1 seal #1 failure (5.2 gpm)

RO Actions:

Seal Failure:

• Diagnose RCP seal failure (Controlled leakage hi/Io flow alarm)

• SOP 13003-1 RCP operation with seal abnormality

• Use figures 1&2 to determine RCP must be stopped in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

• Monitors RCP data on the IPC SRO Actions:

Seal Failure:

"* Using 13003-1 confirm decision tree

"* Seal injection >8 gpm & <130 deg F

"* Seal leakoff outside normal ops band (figure 2)

"* Contacts duty manager about problem 18 of 23

Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event

Description:

Reduce Reactor Power per operations Duty Manager to mode 3 within the next hour and remove RCP #1 from service.

Simulator Operator Notes:

19 of 23

Op-Test No.: 1 Scenario No.: 1 Event No.: 7 Event

Description:

Reduce Reactor Power per operations Duty Manager to mode 3 within the next hour and remove RCP #1 from service.

Time Position Applicant's Actions or Behavior SRO Actions:

"* Gives crew briefing on the power decrease to be off line within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

"* Refers to UOP 12004-C, Power Operation

• Direct RO to energize Pressurizer B/U heaters RO Actions:

"* Energize Pressurizer B/U heaters

"* Commences boration per SOP-13009-1

"* Direct BOP of load reductions

"* Maintains rods above insertion limits

"* Maintains Tave within 2 deg Tref

"* Maintains AFD within target band BOP 18013-C Actions:

"* Reduce turbine load

"* Maintain S/G in normal control band 20 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Event

Description:

RCP seal LOCA Malfunction: (1) RP06A 100% "RCP #1 seal failure" (2) RC05A @ 1.5% "Hot Leg Break at 450 GPM" (3) MS01 @ 100% "Steam Dump Valve 1PV-507C fails fully open" Simulator Operator Notes:

21 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Event

Description:

RCP seal LOCA TimeI Position Applicant's Actions or Behavior RO/BOP Actions: (As seal leak increases)

"* Diagnose leak increasing

"* Increases charging flow to maintain PZR level

"* Determine that Pressurizer level and pressure cannot be maintained.

"* Manually trips reactor

"* Manual SI 19000-C Actions: (19000-C)

Actions

"* Verify Rx Trip (RO/BOP)

"* Verify turbine trip. (RO/BOP)

"* Verify power to AC emergency busses.(RO/BOP)

"* Check if SI Actuated. (RO/BOP)

"* Verify Feedwater isolation. (RO/BOP)

"* Verify MLB indications ECCS equipment aligning for injection phase. (RO/BOP)

"* Verify containment isolation Phase A actuated. (RO/BOP)

"* Verify AFW Pumps running. (RO/BOP)

"* SG blowdown isolated (RO/BOP)

"* TDAFW pump running. (RO/BOP)

"* Verify ECCS pumps running: CCP, SI, RHR. ( Manually starts SI Pump "A") (RO/BOP)

"* Verify 2 CCW pumps running on each Train. (RO/BOP) 22 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Event

Description:

RCP seal LOCA RO/BOP , Verify 2 NSCW pumps running on each Train. (RO/BOP)

"* Verify containment ventilation isolation (CVI). (RO/BOP)

"* Check if MSIV should be isolated (RO/BOP)

"* Check containment spray not required. (RO/BOP)

"* Verify DG running. (RO/BOP)

"* Verify ECCS flows. (RO/BOP)

"* Verify total AFW flow greater than 570 GPM. (RO/BOP)

"* Verify ECCS alignment on MLBs. (RO/BOP)

"* Verify RCS temperatures. (Should find 1PV-507C failed open and actuate MSLI )(RO/BOP)

"" Verify PORVs/sprays working correctly (RO/BOP)

"* Check if RCPs should be stopped (RO/BOP)

"* Check ACCW pump running (RO/BOP)

" Place Hydrogen Monitors in service per SOP-13130-1 Section 4.2.1 & 4.2.2 (RO/BOP)

• OPEN the H2 MONITOR A SPLY ISO IRC:1 -HV-2792A,1 -HV-2792B

• OPEN H2 MONITOR A SPLY ISO ORC 1-HV-2791 B

• OPEN H2 MONITOR A RTN ISO ORC 1-HV-2793B

• PLACE Mode Switch 1-HS-22900 in ANALYZE

• ENSURE Function Selector Switch 0 1-HS-22904 in Sample position

& Momentarily DEPRESS Remote Control Selector Pushbutton 1-HS-22944 and VERIFY Sample Light LIT

• Same Actions for "B"train monitor 23 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Event

Description:

RCP seal LOCA RO/BOP 0 Check for secondary fault (RO/BOP)

• Check for SGTR (RO/BOP)

• Direct chemistry sample

• Use IPC to trend secondary radiation data Path If the crew transitions to 19030-C due to high secondary 19030-C radiation go to page 25 for the actions.

19010-C Actions: (19010-C)

"* Check if RCPs should be stopped (RO/BOP)

"* Verify ACCW operation (RO/BOP)

"* Place Hydrogen monitors in service (may have been already completed in 19000-C) (RO/BOP)

"* Check for secondary fault (RO/BOP)

"* Check for SGTR (RO/BOP)

"* Check PORV operation (RO/BOP)

• Check if SI can be terminated (RO/BOP)

• Verify RCS subcooling >24 F

• Check for secondary heat sink

"* SG levels >10%

"* AFW flow >570 gpm 0 Verify RCS pressure stable or rising

• Verify Pressurizer level >9%

"* Check if Containment spray actuated (RO/BOP)

"* Check if RHR pumps can be stopped (RO/BOP) 24 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Event

Description:

RCP seal LOCA RO/BOP

• Dispatch outside SO to shutdown D/Gs (RO/BOP)

• Evaluate RHR system (RO/BOP) (both trains)

• Power to HV-881 1, HV-8809, RHR pumps

• RHR HX available

• Check for LOCA outside Containment (RO/BOP)

• Transition the 19012-C

• Planned end point 19030-C Actions:

Path

• Determine if RCPs should be stopped (RO/BOP)

• CCP or SI Pumps at least 1 running

& RCS pressure <1375 psig

" Identify the ruptured S/G (RO/BOP)

• Uncontrolled level rise High radiation in S/G from chemistry sample High radiation from radiation monitors

" Isolated the ruptured S/G when identified (RO/BOP)

• ARV (1PV-3000) pot set to 7.73 (1160 psig)

• TDAFW steam supply valve 1HV-3009 closed

• SGBD isolation valve closed (1HV-7603A/B/C/D)

• MSIV & Bypass valves for loop 1

"* Check ruptured S/G level >10% (then stop all feed flow)

(RO/BOP)

"* Check ruptured S/G pressure >290 psig(RO/BOP)

I 25 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Event

Description:

RCP seal LOCA RO/BOP

• Initiate RSC cooldown to target core exit TC temperature of 518 degrees F. (RO/BOP) 0 Place steam dumps in steam pressure mode (RO/BOP)

• Block steam line isolation/SI when below P-11 (RO/BOP)

• Slowly raise cooldown rate to maximum (Note if steam lines isolate the ARVs on loops 2,3 & 4 will be used)

(RO/BOP)

• Stabilize core exit TCs at or below target temperature.

(RO/BOP)

• Control intact S/G levels between 10 to 65% (RO/BOP)

• Check for proper PORV operation (RO/BOP)

• Reset Sl signal (RO/BOP)

• Reset CIA signal (RO/BOP)

• Establish instrument air to containment (RO/BOP)

"* Stop both RHR pumps (RO/BOP)

"* Check ruptured S/G pressure at least 250 psig > intact S/Gs (RO/BOP)

May Exit to 0 Check RCS subcooling at least 44 degrees F. (RO/BOP) 19131-C

"* Depressurize the RCS to refill the Pressurizer(RO/BOP)

• Open loop #4 spray valve to maximum until:

"* Pressurizer level >9% AND RCS pressure < ruptured S/G pressure

"* RCS subcooling <24 degrees F.

"* Pressureizer level >69%

" When one of the above criteria is met close loop #4 spray valve (RO/BOP)

" Check if ECCS flow can be reduced

• RCS subcooling >24 degrees F. (RO/BOP) 26 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Event

Description:

RCP seal LOCA RO/BOP Heat sink available (RO/BOP)

AFW flow >570 gpm 1 S/G level >10%

RCS pressure stable or rising (RO/BOP)

Pressurizer level >9% (RO/BOP)

"* Stop 1 CCP (RO/BOP)

"* Stop both SI pumps (RO/BOP)

"* Establish normal charging (RO/BOP)

• Open normal miniflow valves (1HV-81 11A/B, 1HV-81 10)

• Closed RWST miniflow valves (1HV-8508A/B)

• White lights off on (1HV-8508A/B)

• Close BIT valves (1HV-8801 A/B)

• Set 1HC-0181 to maximum seal flow (0% demand)

• Open 1HV-8105 & 1HV-8106 (normal charging)

"* Control normal charging flow to maintain Pressurizer level (RO/BOP)

"* Verify ECCS flow not required: (RO/BOP)

• RCS subcooling >44 degrees F.

• Pressurizer level >9%

Ifthis path is taken the crew should transition at this point to 19131 C "SGTR with loss of reactor coolant: subcooled recovery desired" Planned End Point 27 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Event

Description:

RCP seal LOCA SRO Actions:

"* Directs RO to maintain PZR level

"* Directs RO to manually trip reactor and initiate manual SI

"* Enters 19000-C, Reactor trip/Si E-0 Actions: (19000-C)

"* Directs RO to verify Rx Trip

"* Directs BOP to verify turbine trip.

"* Directs BOP to verify power to AC emergency busses.

• Directs RO to check if SI Actuated.

"* Direst BOP to verify proper Feedwater isolation.

"* Direct RO to verify MLB indications ECCS equipment aligning for injection phase.

"* Directs RO to verify containment isolation Phase A actuated.

"* Directs BOP to verify AFW Pumps running.

"* Direct BOP to verify SG blowdown isolated

"* Directs BOP to verify TDAFW pump running.

"* Directs RO to verify ECCS pumps running: CCP, SI, RHR.

(Has RO manually starts SI Pump "A")

"* Directs RO to verify 2 CCW pumps running on each Train.

"* Directs RO to verify 2 NSCW pumps running on each Train.

"* Directs RO to verify containment ventilation isolation (CVI).

Train "B" CVI Will need to be manually aligned due to failure.

"* Directs RO/BOP to check if MSIV should be isolated

"* Directs RO to check if containment spray is required.

28 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Event

Description:

RCP seal LOCA SRO

• Directs BOP to verify DG running.

"* Directs RO to verify ECCS flows.

"* Directs BOP to verify total AFW flow greater than 570 GPM.

• Directs RO to verify ECCS alignment on MLBs.

"* Directs RO/BOP to verify RCS temperatures. (Directs actions to restore RCS temperature to 557 F. Should find 1PV-507C failed open and actuate MSLI )

"* Verify PORVs/sprays working correctly

"* Determine if RCPs should be stopped

• CCP or SI Pumps at least 1 running

• RCS pressure <1375 psig

& Check ACCW pump running

"* Have BOP place Hydrogen Monitors in service per SOP13130-1

"* Check for secondary fault

"* Check for SGTR Path 19030-C If the crew transitions to 19030-C due to high secondary S/G Tube radiation go to page 31 for the actions.

Rupture 19010-C

• Diagnose Primary LOCA Primary LOCA Actions: 19010-C

"* Enter 19010-C, Response to LOCA

" Determine if RCPs should be stopped

• CCP or SI Pumps at least 1 running

• _ _RCS pressure <1375 psig 29 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Event

Description:

RCP seal LOCA SRO

• Directs RO to verify ACCW operation

"* Directs BOP to place Hydrogen monitors in service (may have been already completed in 19000-C)

"* Check for secondary fault

"* Check for SGTR

"* Check PORV operation

"* Check if SI can be terminated

• Verify RCS subcooling >24 F

• Check for secondary heat sink

"* SG levels >10%

"* AFW flow >570 gpm

• Verify RCS pressure stable or rising

• Verify Pressurizer level >9%

"* Check if Containment spray actuated

"* Check if RHR pumps can be stopped

"* Direct BOP to shutdown D/Gs

"* Evaluate RHR system (both trains)

• Power to HV-8811, HV-8809, RHR pumps

• RHR HX available

"* Check for LOCA outside Containment

"* Transition to 19012-C Post LOCA cooldown/depressurization Planned end point SRO Examiner: Have the SRO (USS) classify the event. The answer Classify key for event classification is on page 34.

Path #1

_______ .1___________ 1 30 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Event

Description:

RCP seal LOCA SRO Actions:

19030-C

• Determine if RCPs should be stopped Actions

• CCP or SI Pumps at least 1 running

• RCS pressure <1375 psig

"* Identify the ruptured S/G

• Uncontrolled level rise

• High radiation in S/G from chemistry sample

• High radiation from radiation monitors

"* Isolated the ruptured S/G when identified

• ARV (1PV-3000) pot set to 7.73 (1160 psig)

• TDAFW steam supply valve 1HV-3009 closed

• SGBD isolation valve closed (1HV-7603A/B/C/D) 0 MSIV & Bypass valves for loop 1

"* Check ruptured S/G level >10% (then stop all feed flow)

"* Check ruptured S/G pressure >290 psig

"* Initiate RSC cooldown to target core exit TC temperature of 518 degrees F.

• Place steam dumps in steam pressure mode

• Block steam line isolation/SI when below P-11 0 Slowly raise cooldown rate to maximum (Note if steam lines isolate the ARVs on loops 2,3 & 4 will be used)

• Stabilize core exit TCs at or below target temperature.

"* Control intact S/G levels between 10 to 65%

"* Check for proper PORV operation

"* Reset SI signal

"* Reset CIA signal 31 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Event

Description:

RCP seal LOCA SRO & Establish instrument air to containment

• Stop both RHR pumps

• Check ruptured S/G pressure at least 250 psig > intact S/Gs May go To

• Check RCS subcooling at least 44 degrees F.

19131-C

• Depressurize the RCS to refill the Pressurizer Open loop #4 spray valve to maximum until:

• Pressurizer level >9% AND RCS pressure < ruptured S/G pressure

• RCS subcooling <24 degrees F.

• Pressureizer level >69%

• When one of the above criteria is met close loop #4 spray valve

• Check if ECCS flow can be reduced

• RCS subcooling >24 degrees F.

• Heat sink available

• AFW flow >570 gpm

• 1 S/G level >10%

RCS pressure stable or rising R

• Pressurizer level >9%

• Stop 1 CCP

• Stop both SI pumps

• Establish normal charging

• Open normal miniflow valves (1HV-8111A/B, 1HV-8110)

• Closed RWST miniflow valves (1HV-8508A/B)

• White lights off on (1 HV-8508A/B)

• Close BIT valves (1HV-8801 A/B)

• Set 1HC-01 81 to maximum seal flow (0% demand) 32 of 23

Op-Test No.: 1 Scenario No.: 2 Event No.: 8 Event

Description:

RCP seal LOCA SRO & Open 1HV-8105 & 1HV-8106 (normal charging)

"* Control normal charging flow to maintain Pressurizer level

"* Verify ECCS flow not required:

• RCS subcooling >44 degrees F.

• Pressurizer level >9%

Ifthis path is taken the crew should transition at this point to 19131 C "SGTR with loss of reactor coolant: subcooled recovery desired" SRO Planned End Point Classify Examiner: Have the SRO (USS) classify the event. The answer Path #2 key for event classification is on page 34.

33 of 23

Classify the Event answer:

Path 1# for the RCP seal LOCA is an ALERT EMERGENCY due to, non isolable RCS leak greater than the capactity of one charging pump in the normal charging mode.

Path 2# SGTR with LOCA in progress is an ALERT EMERGENCY due to, non isolable RCS leak greater than the capactity of one charging pump in the normal charging mode.

34 of 23

Crew Turnover Sheet Initial Conditions: The plant is at 45% ramping to 100% at 8%/hr. RCS boron concentration is at 363 ppm, EOL conditions. After shift turnover have the RO complete the "B"MFP startup. All activities have been completed in SOP-1 3615-1 up to step 4.1.4.20. "A" Train equipment in service.

Turnover:

1. Plant Startup is in progress.

2. Rx power is 45%.

3. 1PV-0456 is in the shut position due to seat leakage.

HV-8000B is shut to comply with Technical Specification 3.4.11 Condition "A".

4. CCW train B pumps in PTL, clearance has just been released. Functional testing scheduled approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> from now for response time testing. Tech Spec action of 3.7.7 have been completed.

5. SGBD is COS due to HIGH failure on 1RE-021. Will be returned to service of the next shift.

6. The last shift entered AOP 18009-C due to a 20 GPD tube leak on Steam generator #1. All actions of Section "B" have been completed with the exception of the radiation monitors which still need to be reset.

7. In addition a tornado alert has been issued for Burke and Richmond Counties. There are heavy thunderstorms occurring at this time. The severe weather checklist has been completed in the last hour.

35 of 23

Facility: VOGTLE Scenario No.: 3 Op-Test No.: 1 Examiners: Operators:

Initial Conditions: The plant is at 95%. RCS boron concentration is at 1194 ppm, BOL conditions. Shutdown in progress due to Tech Spec action requirement.

Shift Turnover:

1. Plant Shutdown is in progress.

2. __ Current Reactor power is 95%.

3. Train "A" MDAFW Pump is OOS due to mechanical seal failure. It has been 0OS for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and not expected to return to service within the remaining LCO time due to parts unavailability, LCO has been written.

4. Also affecting AFW is a severe packing leak has occurred on the high pressure side of 1-1301-U4-051, a chemical cleaning isolation valve on the Steam Header from S/G #1 to the TDAFW Pump. As a result, 1HV-3009, steam supply to the TDAFW Pump from S/G #1 is tagged shut and power has been removed from the valve. The manual upstream isolation valve, 1- 1304-U4-005 is also tagged shut to allow maintenance to repack the valve.

5. As a result of this work, Unit 1 is in a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> shutdown requirement per Tech. Spec.

3.7.5 Condition "C" due to 2 inoperable AFW Trains.

6. Air Compressor #2 is tagged out for motor replacement.

7. -Plant Management has directed Unit 1 be in Mode 3 within the next 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

8. --- The System Operator has been notified of the pending power reduction.

9. The SS has directed you to have the RO increase CVCS letdown flow to 120 GPM per chemistry department request.

10. The last shift entered AOP 18009-C due to a 20 GPD tube leak on Steam generator #1. All actions of Section "B" have been completed with the exception of the radiation monitors which still need to be reset.

11. In addition a tornado alert has been issued for Burke and Richmond Counties.

There are heavy thunderstorms occurring at this time. The severe weather checklist has been completed in the last hour.

1 Of 24

Event Malf. Event Event No. No. Type* Description 1 RO-N Increase CVCS letdown flow to 120 GPM per chemistry request (SS direction during shift turnover) 2 RO-R Decrease power to Mode 3 3 OR BOP-C Air Compressor #1 Trips 4 CV13 RO-I VCT level transmitter 1LT-185 fails HIGH, with auto M/U CV01 failure 5 FW02b BOP-l Controlling feedwater flow channel fails low on S/G #2 0% (1FT-520) 6 PR02a RO-I Controlling Pressurizer level channel fails high (1LT-459) 100%

3/4ý--- 7 SG01a ALL-M 500 GPM S/G #2 tube rupture 50%

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (P)RA, (L)ow Power 2 Of 24

PREINSERTS:

Initial Conditions:

• __ Reset to IC # Snap for NRC .)

• _Insure Information Board in Control Room is updated

• _Shift sign in and reactivity briefing sheets provided

• _RO & BOP Name plates on Panel D

• _Check EOP's, AOP's, UOP's, SOP's used in the last scenario clear of red marks

• _ IPC is Mode 1

• _Check Control Rod Group Step Counters

• _Unit 2 supplying the Aux Steam Header

• _Correct AFD sheet Select to following QMCB positions:

All Controlling channels selected to channel #1 Align plant for operation with minor S/G tube leak per AOP-18009-C section "B"

Ensure all QPCP and QHVC recorders running in auto Place Clearance Tag on Train "A"AFW Pump (PTL Position)

Place Clearance Tag on AFW Train "A"Discharge valves (Closed position)

(1HS-5139A & 1HS-5137A)

Place Clearance Tag on Air Compressor #2 (Stop position)

Panel Drawing-AL-NSW-HS9383-stop(Also turn off RED/AMBER/GREEN light indication for NC #2.

• Place Clearance Tag on TDAFW Pump steam supply isolation Valve 1HV-3009 (Closed position)

• _Steam Seals System "Caution Tag" supplied from Aux Stm Hdr Hotwell Makeup Controller "Caution Tag" in manual at 50%

3 Of 24

Insert simulator Malfunctions:

• (Malfunction SGO1e at 20%) 20 GPD tube leak on Steam Generator #1 malfunction

• _(ES01) Failure of the Automatic Reactor Trip

• _(CV01) VCT automatic makeup failure

• _(AF05B) MDAFW Pump "B" fails to automatically start Simulator Overrides & Remote Functions:

Reactor Trip Handswitch on "C" to CLOSE position Panel Drawings-C-NIM-HS40007-CLOSE Air Compressor #4 Handswitch to Stop Panel Drawings-Al-NSW-HS9381-STOP Override 1 HV-3009 shut and remove light indication Panel Drawings-B1 -AFW-HS3009-CLOSE (Use Panel Drawings to turn off RED & GREEN light indication)

Override Train "A" AFW Pump to off position Panel Drawing-B1-AFW-HS5131A-STOP Override discharge Valves for Train "A" AFW Pump to shut position Remote Function (AF20, AF18 in LOCAL; AF19, AF21 to 0%)

Panel Drawings-B1-AFW-HS5131A-Green light-OFF ALB50 (CR HI/LO AP)

Panel Drawings-HV1-ALB50-CR Hi/Lo Diff Press-OFF ALB20 (Turbine/Gen Trouble)

Panel Drawings-B2-ALB20-E01 -OFF ALB62 (Gen Gas Non Sys Alarm)

Panel Drawings-QPCP2-ALB62-F02-OFF 4 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 1 K-> Event

Description:

Increase CVCS letdown flow to 120 GPM Time Position Applicant's Actions or Behavior RO Actions:

"* SOP-13006-1 Section 4.2.4

"* Raise charging flow to between 120-130 GPM

"* Main RCP seal injection flow between 8-13 GPM

"* Place 1-PIC-0131 in manual and lower pressure between 100-120 psig

"* Open 45 GPM orifice valve

"* Adjust 1-PIC-0131 to between 360-380 psig

"* Return system to automatic 5 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event

Description:

Decrease Reactor Power (Mode 3 in 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />)

Time Position Applicant's Actions or Behavior SRO Actions:

"* Gives crew briefing on the power decrease

"* Directs Operators to decrease power (Mode 3 in 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />)

"* Refers to UOP 12004-C, Power Operation RO Actions:

"* Commences boration per 13009-1

"* Maintains rods above insertion limits

"* Maintains Tave within 2 deg Tref

"* Maintains AFD within target band BOP Actions:

• Loads Turbine per SOP.

6 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event

Description:

Air Compressor #1 Trips (Air Compressor #4 fails to automatically start)

Malfunction/Override: Trigger the following: on Examiner CUE

1. Panel Drawings-Al-NSW-HS19338-STOP

2. Panel Drawings-Al -NSW-AIC #1 RED light OFF

3. Panel Drawings-Al-NSW-A/C #1 GREEN light ON

4. Panel Drawings-Al-NSW-ANC #1 AMBER light ON

5. Panel Drawings-EAB1-ALB33-A06-ON

6. Note: must remove Panel Drawings-A1-NSW-HS9381 STOP, when BOP places AC #4 handswitch to start.

Simulator Operator Notes:

7 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event

Description:

Air Compressor #1 Trips (Air Compressor #4 fails to automatically start)

Time Position Applicant's Actions or Behavior SRO Actions:

"* Reference ARP for low service air ALB01 C06

"* Enters AOP-1 8028-C Section "A'

"* Directs RO to Start Air Compressor #4

• Dispatches operator to locally investigate problem

• Dispatch Operator & Maintenance to investigate

• Have SSS write Work Order and make notifications BOP Actions:

"* Reference ARP for low service air ALB01 C06

"* Trend air pressure on IPC

"* Starts Air Compressor #4

"* Dispatch Operator to investigate problem 8 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event Description VCT level transmitter 1LT-185 fails high. Result in letdown flow being diverted to the RHUT. VCT level will lower to the automatic makeup setpoint of 30% if not noticed by the operators.

Malfunction: Check (CV01) active then insert (CV12) on Examiner Cue Simulator Operator Note 9 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event Description VCT level transmitter 1LT-185 fails high. Result in letdown flow being diverted to the RHUT. VCT level will lower to the automatic makeun setnoint of 30% if not noticed by the operators.

Time Position Applicant's Actions or Behavior SRO Actions:

"* Directs operator to place 1-LV-01 12A to the VCT position

"* Directs operator to Monitor VCT level using 1-LT-01 12 (IPC)

"* Alerts operator that the automatic swap-over on low VCT level is not functional.

"* Caution the operators of the possible loss of suction to the CCP's

"* Have Maintenance Work order written.

RO Actions:

"* Identify failed VCT level channel (1-LT-185)

"* Trend 1-LT-115 on the IPC computer.

"* Place 1-LV-0112A to the VCT position.

"* Be aware of the possible loss of suction potential to the CCP's.

Critical Critical that the CCP do not lose suction during scenario Task 10 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 5 Event

Description:

Controlling Feedwater Flow channel fails low on S/G #2 (1FT-520)

Malfunction: FW02b at 0% on Examiner Cue Simulator Operator Notes:

11 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 5 Event

Description:

Controlling Feedwater Flow channel fails low on S/G #2 (1FT-520)

Time Position Applicant's Actions or Behavior SRO Actions:

"* Enters AOP-18001-C Section "G"

"* Directs BOP to control S/G #2 flow in manual

"* Directs BOP swap controlling channel

"* Directs BOP to return to automatic when system stabilizes

"* Have SSS notify Maintenance to investigate

"* Have SSS write Work Order and make notifications BOP Actions:

• Determine failure of 1LT-520 (controlling channel)

Immediate actions:

• Take manual control of S/G #2 MFRV and MFP control level between 60-70%

"* Select non affected controlling channel

"* Return system to automatic 12 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Event

Description:

Controlling Pressurizer level channel fails high (LT-459)

Malfunction: PR03A at 100% on Eximiner Cue Simulator Operator Notes:

13 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Event

Description:

Controlling Pressurizer level channel fails high (LT-459)

Time Position Applicant's Actions or Behavior SRO Actions:

"* Enters 18001-C section "D"

"* Directs RO to control CVCS charging flow in manual

"* Directs RO to select new controlling channel (461/460)

"* Verify letdown in service

"* Verify Pressurizer heater operation

"* Direct RO to restore to automatic when conditions allow

"* Notifies duty manager of AOP entry

"* Contacts maintenance to initiate repairs

"* Refers to Tech Specs:

• LCO 3.3.1 Functional unit 9 - Condition M Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> o LCO 3.3.2 Function unit 5c - Condition I Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Function unit 6b - Condition D Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> o LCO 3.3.3 Info LCO No required action

& LCO 3.3.4 Function 8 condition A Restore within 30 days 14 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 6 1/2>

Event

Description:

Controlling Pressurizer level channel fails high (LT-459)

RO Actions:

"* Determine 1 LT-459 has failed high

"* Place CVCS changing flow in manual and restore flowrate to normal

"* Select unaffected controlling channel (461/460)

"* Return Pressurizer level control to automatic I I 15 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 7 Event

Description:

500 GPM Tube Rupture On S/G #1 Malfunction: SGO1a @ 50% on Examiner Cue Simulator Operator Notes:

16 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 7 Event

Description:

500 GPM Tube Rupture On S/G #1 Time Position Applicant's Actions or Behavior SRO Actions:

"* Identifies from indications of high radiation on secondary and lowering Pressurizer level & Pressure that a S/G tube rupture is in progress

"* Directs operator actions to maintain Pressurizer level & pressure

"* May enter 18009-C if time allows for actions relate to the loss of RCS inventory

"* Directs operator the manually trip the Unit One Reactor due to the decreasing Pressurizer Level & pressure 19000 Actions: (19000-C)

Actions Ato 0 Directs RO to verify Rx Trip E-0

• Directs BOP to verify turbine trip.

• Directs BOP to verify power to AC emergency busses.

• Directs RO to check if SI Actuated.

• Direst BOP to verify proper Feedwater isolation.

• Direct RO to verify MLB indications ECCS equipment aligning for injection phase.

• Directs RO to verify containment isolation Phase A actuated.

• Directs BOP to verify AFW Pumps running.

• Direct BOP to verify SG blowdown isolated

• Directs BOP to verify TDAFW pump running.

• Directs RO to verify ECCS pumps running: CCP, SI, RHR.

• Directs RO to verify 2 CCW pumps running on each Train.

• Directs RO to verify 2 NSCW pumps running on each Train.

17 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 7 Event

Description:

500 GPM Tube Rupture On S/G #1 SRO

• Directs RO to verify containment ventilation isolation (CVI).

"* Directs RO/BOP to check if MSIV should be isolated

"* Directs RO to check if containment spray is required.

"* Directs BOP to verify DG running.

"* Directs RO to verify ECCS flows.

"* Directs BOP to verify total AFW flow greater than 570 GPM.

"* Directs RO to verify ECCS alignment on MLBs.

"* Directs RO/BOP to verify RCS temperatures.

"* Verify PORVs/sprays working correctly

"* Check if RCPs should be stopped

"* Check ACCW pump running

"* Have BOP place Hydrogen Monitors in service per SOP13130-1

"* Check for secondary fault

"* Check for SGTR 19030 Transition the 19030-C based on high secondary radiation Actions Actions: 19030

"* Check if RCPs should be stopped

"* CCP or SI pumps at least 1 running

"* RCS pressure <1375 psig

"* Identifies SG #1 as ruptured

• Uncontrolled level rise

______ ________ I 18 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 7 Event

Description:

500 GPM Tube Rupture On S/G #1 SRO Directs the isolation of S/G #2 per 19030-C

"* ARV (PV-301 0) pot set at 7.73 and in automatic controlling at 1160 psig

"* Directs BOP shut 1HV-3009

"* Directs BOP to verify SGBD is isolated

"* Directs BOP to shut MSIVs & Bypass valve for loop #2

"* Directs BOP to maintain S/G #2 level >10% (should isolate flow if level is above 10% NR)

" Verifies S/G #2 pressure >290 psig

" Directs RSC cooldown to target core exit TC temperature of 518 degrees F. (RO/BOP)

• Place steam dumps in steam pressure mode (RO/BOP)

• Block steam line isolation/Si when below P-1 1 (RO/BOP)

• Slowly raise cooldown rate to maximum (Note if steam lines isolate the ARVs on loops 2,3 & 4 will be used)

(RO/BOP)

"* Stabilize core exit TCs at or below target temperature.

Planned end point SRO Examiner: Have the SRO (USS) classify the event. The answer key Classify for event classification is on page 23.

RO/BOP Actions: (19000-C)

"* Identifies from indications of high radiation on secondary and 19000-C lowering Pressurizer level & Pressure that a S/G tube rupture is in Actions progress (RO/BOP)

"* Increases Charging (start additional charging pump if time permits) to maintain Pressurizer level and pressure. (RO/BOP)

Critical

• Actuates manual Reactor Trip ( NOTE: QMCB panel "C" Task Handswitch will not function and the RO will be required to us Panel "A" Handswitch) (RO/BOP)

"* Verify Rx Trip (RO/BOP) 19 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 7 Event

Description:

500 GPM Tube Rupture On S/G #1 RO/BOP

• Verify turbine trip. (RO/BOP)

• Verify power to AC emergency busses. (RO/BOP)

• Check if SI Actuated. (RO/BOP)

• Verify Feedwater isolation. (RO/BOP)

• Verify MLB indications for both trains of ECCS equipment aligning for injection phase. (RO/BOP)

• Verify containment isolation Phase A actuated. (RO/BOP)

• MDAFW Pumps running. ( NOTE: operator must manually start MDAFW Pump "B") (RO/BOP)

• SG blowdown isolated (RO/BOP)

• TDAFW pump running. (RO/BOP)

• Verify ECCS pumps running: CCPs, SI, RHR. (RO/BOP)

• Verify 2 CCW pumps running on each train. (RO/BOP)

• Verify 2 NSCW pumps running on each train. (RO/BOP)

• Verify containment ventilation isolation (CVI). (RO/BOP)

• Check if MSIVs should be isolated. (RO/BOP)

• Check containment spray not required. (RO/BOP)

• Verify DG running. (RO/BOP)

• Verify ECCS flows. (RO/BOP)

• Verify total AFW flow greater than 570 GPM. (RO/BOP)

• Verify ECCS alignment on MLBs. (RO/BOP)

• Verify RCS temperatures. (RO/BOP) 20 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 7 Event

Description:

500 GPM Tube Rupture On S/G #1 RO/BOP 0 Verify PORVs/sprays working correctly

"* Check if RCPs should be stopped

"* CCP or SI pumps at least 1 running

"* RCS pressure <1375 psig

" Check ACCW pump running

• Place Hydrogen Monitors in service per SOP-13130-1 Section 4.2.1

& 4.2.2 (RO/BOP)

• OPEN the H2 MONITOR A SPLY ISO IRC:1 -HV-2792A,1 -HV-2792B

• OPEN H2 MONITOR A SPLY ISO ORC 1-HV-2791 B

• OPEN H2 MONITOR A RTN ISO ORC 1-HV-2793B

• PLACE Mode Switch 1-HS-22900 in ANALYZE

• ENSURE Function Selector Switch

• 1-HS-22904 in Sample position

• Momentarily DEPRESS Remote Control Selector Pushbutton 1-HS-22944 and VERIFY Sample Light LIT

• Same Actions for "B"train monitor

"* Check for secondary fault

"* Check for SGTR 19030-C

• Identify ruptured S/G on uncontrolled level rise or secondary high Actions radiation (RO/BOP)

Actions:

• Determine if RCPs should be stopped (RO/BOP)

"* CCP or SI pumps at least 1 running

"* RCS pressure <1375 psig

• CCP or SI Pumps at least 1 running 21 Of 24

Op-Test No.: 1 Scenario No.: 3 Event No.: 7 Event

Description:

500 GPM Tube Rupture On S/G #1 RO/BOP 0 RCS pressure <1375 psig

"* Identify S/G #2 ruptured based on uncontrolled level rise (RO/BOP)

"* Isolated the ruptured S/G when identified (RO/BOP)

• ARV (1PV-3000) pot set to 7.73 (1160 psig)

• TDAFW steam supply valve 1HV-3009 closed

• SGBD isolation valve closed (1HV-7603A/B/C/D)

• MSIV & Bypass valves for loop 2

"* Check ruptured S/G level >10% (then stop all feed flow) (RO/BOP)

"* Check ruptured S/G pressure >290 psig(RO/BOP)

"* Initiate RSC cooldown to target core exit TC temperature of 518 degrees F. (RO/BOP)

", Place steam dumps in steam pressure mode (RO/BOP)

• Block steam line isolation/SI when below P-11 (RO/BOP)

• Slowly raise cooldown rate to maximum (Note if steam lines isolate the ARVs on loops 1,3 & 4 will be used)

(RO/BOP)

Stabilize core exit TCs at or below target temperature.

Planned end point I I --

22 Of 24

Classify the Event answer:

SGTR in progress is an ALERT EMERGENCY due to, non isolable RCS leak greater than the capactity of one charging pump in the normal charging mode.

23 Of 24

Initial Conditions: The plant is at 100%. RCS boron concentration is at 1194 ppm, BOL conditions. Shutdown in progress due to Tech Spec action requirement.

Shift Turnover:

1. Plant Shutdown is in progress.

2. Current Reactor power is 100%.

3. Train "A"MDAFW Pump is 0OS due to mechanical seal failure. It has been 0OS for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and not expected to return to service within the remaining LCO time due to parts unavailability, LCO has been written.

4. Also affecting AFW is a severe packing leak has occurred on the high pressure side of 1-1301-U4-051, a chemical cleaning isolation valve on the Steam Header from S/G #1 to the TDAFW Pump. As a result, 1HV-3009, steam supply to the TDAFW Pump from S/G #1 is tagged shut and power has been removed from the valve.

The manual upstream isolation valve, 1- 1304-U4-005 is also tagged shut to allow maintenance to repack the valve.

5. As a result of this work, Unit 1 is in a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> shutdown requirement per Tech. Spec. 3.7.5 Condition "C" due to 2 inoperable AFW Trains.

6. Plant Management has directed Unit 1 be in Mode 3 within the next 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

7. Air Compressor #2 is tagged out for motor replacement.

8. The System Operator has been notified of the pending power reduction.

9. The SS has directed you to have the RO increase CVCS letdown flow to 120 GPM per chemistry department request.

10. The last shift entered AOP 18009-C due to a 20 GPD tube leak on Steam generator #1. All actions of Section "B" have been completed with the exception of the radiation monitors which still need to be reset.

11. In addition a tornado alert has been issued for Burke and Richmond Counties.

There are heavy thunderstorms occurring at this time. The severe weather checklist has been completed in the last hour.

24 Of 24

Facility: VOGTLE Scenario No.: 4 Op-Test No.: 1 Examiners: Operators:

Initial Conditions: The plant is at 95%. RCS boron concentration is at 1308 ppm, BOL conditions. B Train equipment in service.

Turnover:

1 ___Plant Startup is in progress.

2- Rx power is 95%.

3 1PV-0456 is in the shut position due to seat leakage.

4 1HV-8000B is shut to comply with Technical Specification 3.4.11 Condition "A".

5 ECCS Accumulator #2 level is low due to a minor leak. After assuming the shift raise the accumulator level per SOP-13105-C 6 __ After Accumulator #2 has been filled you are to continue the power increase to 98% per 12004-C. (step 4.1.50) All prerequisites for the power increase were met on the previous shift. The Load Dispatcher has been notified of the power increase. The SS has requested that Control Rods be placed in automatic when reactor power is at 98% for engineering testing, notify him.

7 The last shift entered AOP 18009-C due to a 20 GPD tube leak on Steam generator #1. All actions of Section "B" have been completed with the exception of the radiation monitors which still need to be reset.

8 ___ In addition a tornado alert has been issued for Burke and Richmond Counties.

There are heavy thunderstorms occurring at this time. The severe weather checklist has been completed in the last hour.

1 of 26

Event Malf. Event Event No. No. Type* Description 1 RO-N Raise #2 accumulator level 2 RO-R Increase power to 98%

Letdown HX temperature controller fails resulting in high 3 RO-I letdown flow temperature. The demin divert valve 1TV-129 will fail to operate, requiring the RO to take manual action to protect the demin resin and RCS chemistry.

4 RC10c RO-I Loop #3 NR Tavg fails high (TE-431 B) 100%

5 SG02h BOP-C Controlling S/G #4 level transmitter (1LT-549) fails high 100%

6 MS03b BOP-C ARV #2 (1 PV-301 0) fails open due to controlling pressure 100% transmitter failure 7 GE01 M-ALL 0 Loss of offsite power EL02,

• DG 1B trips after starting 03

• Faulted S/G #3 (IRC)

ELOla 15Sec/

TD MS04c 100%

SY01A, B, D, E, G, H, J, K,M

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (P)RA, (L)OW rower 2 of 26

PREINSERTS:

Initial Conditions:

• Reset to IC # (NRC #4 snap)

• _Insure Information Board in Control Room is updated

• _Shift sign in and reactivity briefing sheets provided

• _RO & BOP Name plates on Panel D

• _Check EOP's, AOP's, UOP's, SOP's used in the last scenario clear of red

• marks

• • IPC is Mode 1

• _Check Control Rod Group Step Counters

• _Unit 2 supplying the Aux Steam Header Select to following QMCB positions:

• __1 PV-0456 in shut position with "Caution Tag"

• _ 1 HV-8000B in shut position with "Caution Tag"

• _All Controlling channels selected to channel #1

• All Train "B" Equipment Running

• Align plant for operation with minor S/G tube leak per AOP-1 8009-C section

• _Ensure all QPCP and QHVC recorders running in auto 3 of 26

Insert simulator malfunctions:

• _(Malfunction SG01e at 20%) 20 GPD tube leak on Steam Generator #1

• _ SI02B at 100% until low level is received for accumulator #2 alarm then remove malfunction Simulator Overrides & Remote Functions:

• _ALB50 (CR HI/LO AP)

Panel Drawings-HV1-ALB50-CR Hi/Lo Diff Press-OFF 0 _ALB20 (Turbine/Gen Trouble)

Panel Drawings-B2-ALB20-E01 -OFF

• _ALB62 (Gen Gas Non Sys Alarm)

Panel Drawings-QPLP2-ALB62-F02-OFF

• _DRPI aligned to ABE 4 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: 1 Page 3 of 9 Event

Description:

Raise #3 ECCS accumulator Level Time Position Applicant's Actions or Behavior RO Actions:

"* SOP 13105-1 Section 4.2.1 selected:

"* Check miniflow path for SI pump aligned

"* Start SI pump

"* Open 1HV-8888

"* Open I HV-8871

"* Open 1HV-8878B

"* Monitor Accum #2 level

"* When desired level is reached close valves Tech Spes required level is between 29.2 to 70.7%

<7 5 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: 2 Page 3 of 9 Event

Description:

Increase Reactor Power to 98%

Time Position Applicant's Actions or Behavior SRO Actions:

"* Gives crew briefing on the power increase

"* Directs Operators to increase power to 98%

"* Refers to UOP 12004-C, Power Operation RO Actions:

"* Commences dilution per SOP-13009-1

"* Maintains rods above insertion limits

"* Maintains Tave within 2 deg Tref

"* Maintains AFD within target band BOP Actions:

• Loads Turbine per SOP.

6 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: :3 Event

Description:

Letdown HX temperature controller fails resulting in high letdown flow temperature. The demin divert valve 1TV-129 will fail to operate, requiring the RO to take manual action to protect the demin resin and RCS chemistry.

Malfunction: Pot fails to 10 on 1TIC-0130 and override 1TV-129 to the VCT position on Examiner Cue Simulator Operator Notes:

7 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: 3 Event

Description:

Letdown HX temperature controller fails resulting in high letdown flow temperature. The demin divert valve 1TV-129 will fail to operate, requiring the RO to take manual action to protect the demin resin and RCS chemistry.

Time Position Applicant's Actions or Behavior SRO Actions:

"* Recognize that letdown flow temperature is increasing

"* Direct the RO the take manual control of 1TIC-0131 and lower temperature to normal

"* Realize that 1TC-129 failed to operate

"* Direct RO to place 1TV-129 to the VCT position

"* Call chemistry and alert them of the problem

"* Call SSS to initiate maintenance work order RO Actions:

"* Recognize that letdown flow temperature is increasing

"* Take manual control of 1TIC-0131 and lower temperature to normal

"* Realize that 1TC-1 29 failed to operate Critical

• Place 1TV-129 to the VCT position Task

• Reference ARPs and insure all actions are completed.

8 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: 4 Event

Description:

Loop #3 NR temperature instrument fails high. Control rods would move in if controls were in automatic, however with power ramp in progress they should be in manual control.

Malfunction: RC1Oc @ 100% on Examiner Cue Simulator operator: Ensure Control Rods have been placed in automatic prior to This failure.

Simutlator Operator Actions:

9 of 26

SL I.I

• Op-Test No.: 1 Scenario No.: 4 Event No.: 4 Event

Description:

Loop #3 NR temperature instrument fails high. Control rods would move in if controls were in automatic, however with power ramp in progress they should be in manual control.

Time Position Applicant's Actions or Behavior SRO Actions:

"* Enters AOP 18001-C Section "B"

"* Has operator place rod control in manual

"* Have operator verify Tavg is on program

"* Defeat failed channel

• Place Tavg defeat switches (1TS-412T & 1TS-411 F) to Loop #3 position

"* Notify Operations duty manager.

"* Have Maintenance Work order written.

Tech 0 Refer to Technical Specifications.

Spec

• 3.3.1 Function 6 Condition E Actions Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 3.3.1 Function 7 Condition E Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 3.3.2 Function 5b Condition I Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> RO Actions:

"* Identify the failed channel is Loop #3

"* Place control rods in manual control (immediate action)

"* Adjust Tavg to Tref if required

"* Place Tavg defeat switches (1TS-412T & 1TS-41 1F) to Loop #3 position 10 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: .5 Event

Description:

Controlling SIG #4 level transmitter (1 LT-554) fails high. Results in the Loop #4 MFRV going in the shut direction to lower feedwater flow.

Malfunction: SG02D @ 100% on Examiner Cue Simulator Operator Notes:

11 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Event

Description:

Controlling S/G #4 level transmitter (1LT-554) fails high. Results in the Loop #4 MFRV going in the shut direction to lower feedwater flow.

Time Position Applicant's Actions or Behavior SRO Actions:

"* Enters AOP 18001-C Section "E"

"* Has operator control S/G #4 MFRV in manual to restore level between 60-70%

"* Have operator select unaffected controlling channel

"* Directs operator to restore system to automatic when conditions have stabilized.

"* Notify Operations duty manager.

"* Have Maintenance Work order written.

"* Refer to Technical Specifications.

• 3.3.1 Function 13 Condition E Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

• 3.3.2 Function 5c Condition I Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 0 3.3.2 Function 6b Condition D Place channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

• 3.3.3 Info LCO BOP Actions:

• Identify the failed channel is Loop #4 (11LT-549)

Critical

• Place MFRV on Loop #4 in manual control and control level Task between 60-70%

12 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: 5 Event

Description:

Controlling S/G #4 level transmitter (1LT-554) fails high. Results in the Loop #4 MFRV going in the shut direction to lower feedwater flow.

BOP "* Select an unaffected controlling channel

"* Restore system to automatic when conditions allow

______ I 13 of 26

A W i I ---- _-I Nl-- .

• Op-Test No.: 1 Scenario No.: 4 Event rio.: 6 Event

Description:

ARV on Loop #3 (1PV-3020) fails open due to controlling transmitter failing high. The operate should identify the condition when the alarm is received on high tailpipe temperature and Reactor Power is observed to be increasing with Main Turbine Load lowering.

Malfunction: MSO3b @ 100% on Examiner Cue Insert Steam leak MS02C start at 3% and increase until Operators are required to lower reactor power below 100%

Simulator Operator Notes:

14 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: 6 Event

Description:

ARV on Loop #3 (1PV-3020) fails open due to controlling transmitter failing high. The operate should identify the condition when the alarm is received on high tailpipe temperature and Reactor Power is observed to be increasing with Main Turbine Load lowering.

Time Position Applicant's Actions or Behavior SRO Actions:

"* May enters AOP 18008-C for secondary leakage

"* Alert operator keep Reactor Power below 100% by all indications

"" Directs operator that manually shut 1PV-301 0 (using 1PIC-3020)

"* When 1PV-301 0 fails to respond contact SSS to dispatch SO to locally isolate the failed ARV.

"* Notify Operations duty manager

"* Have Maintenance Work order written

"* Refer to Technical Specifications.

• 3.3.4 (Info only)

• 3.3.4 (info only)

BOP Actions:

"* Identify the failed open ARV on Loop #3

"* Keep Reactor Power below 100% by all indications

"* Place 1PIC-3020 in manual control and attempt to lower output (ARV will fail to respond) 15 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: 7 Event

Description:

Main Generator Trip results in automatic reactor trip, following fast bus transfer power is lost to RAT A, DIG 1A will start tie on to 1AA02 and then trip on overspeed during load sequencing followed by a major secondary fault outside Containment on S/G #3.

Malfunction: List:: On Examiner Cue

1. GE01 (Main Generator Trip)

2. EL02, (Loss of RAT "A")

3. MS04c @ 100% (S/G #3 faulted IRC)

4. EL01A @ 15 second time delay (DIG 1A Trip on OS)

Simulator Operator Notes:

16 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: 7 Event

Description:

Main Generator Trip results in automatic reactor trip, following fast bus transfer power is lost to RAT A, DIG 1A will start tie on to 1AAO2 and then trip on overspeed during load sequencing followed by a major secondary fault outside Containment on S/G #3.

Time Position Applicant's Actions or Behavior SRO Actions:

• Identifies Automatic Reactor Trip 19000-C Enters 19000-C Actions Actions: (19000-C)

"* Directs RO to verify Rx Trip

"* Directs BOP to verify turbine trip.

"* Directs BOP to verify power to AC emergency busses. (Notes that 1AA03 is de-energized)

"* Directs RO to check if SI Actuated.

"* Direst BOP to verify proper Feedwater isolation.

"* Direct RO to verify MLB indications ECCS equipment aligning for injection phase.

"* Directs RO to verify containment isolation Phase A actuated.

"* Directs BOP to verify AFW Pumps running.

"* Direct BOP to verify SG blowdown isolated

"* Directs BOP to verify TDAFW pump running.

"* Directs RO to verify ECCS pumps running: CCP, SI, RHR.

"* Directs RO to verify 2 CCW pumps running on each Train.

"* Directs RO to verify 2 NSCW pumps running on each Train.

"* Directs RO to verify containment ventilation isolation (CVI).

"* Directs RO/BOP to check if MSIV should be isolated 17 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: __7 Event

Description:

Main Generator Trip results in automatic reactor trip, following fast bus transfer power is lost to RAT A, DIG 1A will start tie on to 1AA02 and then trip on overspeed during load sequencing followed by a major secondary fault outside Containment on S/G #3.

SRO "* Directs RO to check if containment spray is required.

"* Directs BOP to verify DG running.

"* Directs RO to verify ECCS flows.

"* Directs BOP to verify total AFW flow greater than 570 GPM.

"* Directs RO to verify ECCS alignment on MLBs.

"* Directs RO/BOP to verify RCS temperatures.

"* Verify PORVs/sprays working correctly

"* Check if RCPs should be stopped

"* CCP or SI pump at least 1 running

"* RCS pressure <1375 psig

"* Check ACCW pump running

"* Place Hydrogen Monitors in service per SOP-13130-1 Section 4.2.1

& 4.2.2 (RO/BOP)

• OPEN the H2 MONITOR A SPLY ISO IRC:1-HV-2792A,1-HV-2792B

• OPEN H2 MONITOR A SPLY ISO ORC 1-HV-2791 B

• OPEN H2 MONITOR A RTN ISO ORC 1-HV-2793B

• PLACE Mode Switch 1-HS-22900 in ANALYZE

• ENSURE Function Selector Switch

• 1-HS-22904 in Sample position

• Momentarily DEPRESS Remote Control Selector Pushbutton 1-HS-22944 and VERIFY Sample Light LIT

• Same Actions for "B" train monitor

______ ________ I 18 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: 7 Event

Description:

Main Generator Trip results in automatic reactor trip, following fast bus transfer power is lost to RAT A, DIG 1A will start tie on to 1AA02 and then trip on overspeed during load sequencing followed by a major secondary fault outside Containment on S/G #3.

SRO

• Check for secondary fault

• Transitions to 19020-C due to S/G #3 low pressure 19020-C Actions: 19020-C Actions

• Verifies MSIVs & Bypasses are closed

"* Identifies that S/G # 3 is faulted (the other 3 are not faulted)

"* Verify all feedwater is isolated to S/G#3

"* Verify SGBD and S/G sample valve is isolated for S/G #3

"* Verify CST level >15%

"* Have BOP check for secondary radiation

"* Check if SI can be terminated

• Verify RCS subcooling >24 F

& Check for secondary heat sink

"* SG levels >10%

"* AFW flow >570 gpm

& Verify RCS pressure stable or rising

• Verify Pressurizer level >9%

"* Transitions to either 19011-C or 1901 0-C depending on conditions at the time (how fast the crew moves through the procedures compared to how fast S/G #3 depressurizes)

"* When time permits should dispatch personnel to 1AA03 and RAT "A"to invertigate problem.

Path #1 Actions: 19010-C 19010-C

• Check if RCPs should be stopped Actions

• CCP or SI pump at least 1 running

• RCS pressure <1375 psig

• Verify ACCW operation

______ .3_______ .3 19 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: __7 Event

Description:

Main Generator Trip results in automatic reactor trip, following fast bus transfer power is lost to RAT A, DIG 1A will start tie on to 1AA02 and then trip on overspeed during load sequencing followed by a major secondary fault outside Containment on S/G #3.

SRO

• Place Hydrogen monitors in service (may have been already completed in 19000-C)

"* Check for "another" secondary fault

"* Check for SGTR

"* Check PORV operation

• May required COPs to be placed in service

"* Check if SI can be terminated

& Verify RCS subcooling >24 F

• Check for secondary heat sink

"* SG levels >10%

"* AFW flow >570 gpm 0 Verify RCS pressure stable or rising

• Verify Pressurizer level >9%

19011-C Actions Actions: 19011-C

"* Direct RO to reset SI

"* Direst RO to reset CIA

"* Direct RO to align instrument air to containment

"* Direct RO to stop 1 CCP

• Verify RCS pressure stable or rising

_j_I__ _ _ _ I 20 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: 7 Event

Description:

Main Generator Trip results in automatic reactor trip, following fast bus transfer power is lost to RAT A, D/G 1A will start tie on to 1AA02 and then trip on overspeed during load sequencing followed by a major secondary fault outside Containment on SIG #3.

SRO Direct Ro to place normal charging in service

"* Open 1HV-8111A/B & 1HV-8110

"* Close 1HV-8508A/B

"* Close 1HV-8801 A/B

"* Set 1HC-01 82 to maximum seal flow

"* Open 1HV-8105 & 1HV-8106

"* Control RCP seal injection between 8-13 gpm

"* Check RCS pressure trend

"* Stop SI & RHR pumps Planned end point SRO key Classify Examiner: Have the SRO (USS) classify the event. The answer for event classification is on page 25.

RO/BOP Actions: (19000-C)

"* Verify Rx Trip (RO/BOP) 19000-C Actions 9 Verify turbine trip. (RO/BOP)

"* Verify power to AC emergency busses. (alert the operating crew on the loss of power to 1AA03) (RO/BOP)

"* Check if SI Actuated. (RO/BOP)

"* Verify Feedwater isolation. (RO/BOP)

"* Verify MLB indications "B" Train ECCS equipment aligning for injection phase. (RO/BOP)

"* Verify containment isolation Phase A actuated. (RO/BOP)

"* Train "B" MDAFW Pump running. (RO/BOP)

"* SG blowdown isolated (RO/BOP)

_ I___ _ _ _

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Op-Test No.: 1 Scenario No.: 4 Event No.: 7 Event

Description:

Main Generator Trip results in automatic reactor trip, following fast bus transfer power is lost to RAT A, DIG 1A will start tie on to 1AA02 and then trip on overspeed during load sequencing followed by a major secondary fault outside Containment on S/G #3.

RO/BOP

• TDAFW pump running. (RO/BOP)

• Verify ECCS pumps running: Train "B" CCP, SI, RHR. (RO/BOP)

• Verify 2 CCW pumps running on "B" Train. (RO/BOP)

• Verify 2 NSCW pumps running on "B" Train. (RO/BOP)

• Verify containment ventilation isolation (CVI). (RO/BOP)

• Check if MSIVs should be isolated. (BOP should recognize that S/G

1. 3 is faulted and isolate all AFW flow to that S/G) (RO/BOP)

& Check containment spray not required. (RO/BOP)

• Verify DG Train "B"running. (RO/BOP)

• Verify ECCS flows. (RO/BOP)

• Verify total AFW flow greater than 570 GPM. (RO/BOP)

• Verify ECCS alignment on (Train "B") MLBs. (RO/BOP)

• Verify RCS temperatures. (RO/BOP)

• Verify PORVs/sprays working correctly (RO/BOP)

• Check if RCPs should be stopped (RO/BOP)

• Check ACCW pump running (RO/BOP) 22 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: 7 Event

Description:

Main Generator Trip results in automatic reactor trip, following fast bus transfer power is lost to RAT A, DIG 1A will start tie on to 1AA02 and then trip on overspeed during load sequencing followed by a major secondary fault outside Containment on S/G #3.

RO/BOP Place Hydrogen Monitors in service per SOP-1 3130-1 Section 4.2.1

& 4.2.2 (RO/BOP)

• OPEN the H2 MONITOR A SPLY ISO IRC:1 -HV-2792A,1 -HV-2792B

• OPEN H2 MONITOR A SPLY ISO ORC 1-HV-2791 B 0 OPEN H2 MONITOR A RTN ISO ORC 1-HV-2793B 0 PLACE Mode Switch 1-HS-22900 in ANALYZE

• ENSURE Function Selector Switch 1-HS-22904 in Sample position 0 Momentarily DEPRESS Remote Control Selector Pushbutton 1-HS-22944 and VERIFY Sample Light LIT

• Same Actions for "B"train monitor 1/2>- Check for secondary fault (RO/BOP) 19020-C Actions 19020-C Actions

"* Verifies MSIVs & Bypasses are closed (RO/BOP)

"* Identifies that S/G # 3 is faulted (the other 3 are not faulted)

(RO/BOP)

"* Verify all feedwater is isolated to S/G#3 (RO/BOP)

"* Verify SGBD and S/G sample valve is isolated for S/G #3 (RO/BOP)

"* Verify CST level >15% (RO/BOP)

"* Checks for secondary radiation (RO/BOP)

_____ I ______ I 23 of 26

Op-Test No.: 1 Scenario No.: 4 Event No.: 7 Event

Description:

Main Generator Trip results in automatic reactor trip, following fast bus transfer power is lost to RAT A, DIG 1A will start tie on to 1AA02 and then trip on overspeed during load sequencing followed by a major secondary fault outside Containment on S/G #3.

RO/BOP Check if SI can be terminated (RO/BOP) 0 Verify RCS subcooling >24 F (RO/BOP)

• Check for secondary heat sink (RO/BOP)

• SG levels >10% (RO/BOP)

• AFW flow >570 gpm (RO/BOP)

• Verify RCS pressure stable or rising (RO/BOP)

• Verify Pressurizer level >9% (RO/BOP)

• Transitions to either 19011-C or 19010-C depending on conditions at the time (how fast the crew moves through the procedures compared to how fast S/G #3 depressurizes) 19011-C Actions 19011-C Actions

"* Reset SI (RO/BOP)

"* Reset CIA (RO/BOP)

"* Align instrument air to containment (RO/BOP)

"* Stops 1 CCP (RO/BOP)

• Verify RCS pressure stable or rising (RO/BOP)

Places normal charging in service (RO/BOP)

"* Opens 1HV-81 11A/B & 1HV-81 10

"* Closesi HV-8508A/B

"* Closes 1HV-8801A/B

"* Sets 1HC-0182 to maximum seal flow

"* Opens 1HV-8105 & 1HV-8106

"* Controls RCP seal injection between 8-13 gpm

"* Checks RCS pressure trend

"* Stops SI & RHR pumps Planned end point

______ J________ I 24 of 26

Classify the Event answer:

Uncontrolled depressurization of one or more steam generators is an NOUE EMERGENCY 25 of 26

Initial Conditions: The plant is at 95%. RCS boron concentration is at 1308 ppm, BOL conditions. B Train equipment in service.

Turnover:

1. Plant Startup is in progress.

2. Rx power is 95%.

3. 1PV-0456 is in the shut position due to seat leakage.

4. 1HV-8000B is shut to comply with Technical Specification 3.4.11 Condition "A".

5. ECCS Accumulator #2 level is low due to a minor leak. After assuming the shift have the RO raise the accumulator level per SOP-1 3105-C

6. After Accumulator #2 has been filled you are to continue the power increase to 98% per 12004-C. (step 4.1.50) All prerequisites for the power increase were met on the previous shift. The Load Dispatcher has been notified of the power increase. The SS has requested that Control Rods be placed in automatic when reactor power is at 98% for engineering testing, notify him.

7. The last shift entered AOP 18009-C due to a 20 GPD tube leak on Steam generator #1. All actions of Section "B" have been completed with the exception of the radiation monitors which still need to be reset.

8. In addition a tornado alert has been issued for Burke and Richmond Counties.

There are heavy thunderstorms occurring at this time. The severe weather checklist has been completed in the last hour.

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