Text

Final - Section C Operating (Folder 3)
	ML051240145
Person / Time
Site:	Beaver Valley
Issue date:	01/15/2005
From:	Hynes C; FirstEnergy Nuclear Operating Co
To:	Conte R; NRC/RGN-I/DRS/OSB
	Conte R
References
	Download: ML051240145 (108)
	v • d • e

-~

RTL# A5.670.M 2

1/2-ADM-1357.F11 Page 1 of 1 Revision 0 2-8-05 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:

License Operator TraininglLicensed Requalification Training SUBDIVISION:

Simulator SCENARIO TITLWNO.:

COMPUTER CODE FOR L.P.:

2005 NRC Initial License Exam 1 LOT6 Scenario No. 1 INSTRUCTIONAL SETTING:

Simulator APPROXIMATE DURATION:

1.5 Hours PREPARED BY:

REVIEWED BY:

APPROVED FOR IMPLEMENTATION:

Date Date Date BVPS-1 NRC Scenario 1 Page 1 of 29

INITIAL CONDITIONS:.

IC-1 81, PW = NRC1; 100% Power, RCS Boron 1205 ppm, CB D at 227 steps, Rods in Auto.

1 CH-P-1 C, HHSVCharging Pump 00s.

PCV-1 RC-456, PORV leakage. MOV-1 RC-536, Block Valve closed with power maintained.

Flood warnings from heavy rains.

Maintenance investigating 1 RW-P-1 A, River Water Pump abnormal vibrationhoise.

PCV-1 RC-456 Control Switch in Close MOV-1 RC-536 Control Switch in Close I

ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS I

I I

YCT - Both CH-P-1 C Switches YCT - PCV-1 RC-456 Control Switch YCT - MOV-1 RC-536 Control Switch OM Fig. 7-1, 3E: CH-27, 161 Shut OM Fig. 7-1, 5E: CH-21, 148 Shut EQUIPMENT STATUS DATE/TIME 00s I

TECHNICAL SPECIFICATION(S)

I I

N/A I

2 days ago I

I 1CH-P-1C I

3.4.1 1.a I

Yesterday 1500 I

I PCV-1 RC-456 SHIFT TURNOVER INFORMATION

1.

2.

3.

4.

5.

6.

1 CH-P-1 C is 00s for pump shaft and coupling replacement and is expected to return within the next 24 - 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

PCV-1 RC-456 seat leakage. MOV-1 RC-536 is closed with power maintained per T.S. 3.4.1 1.a.

1 WR-P-1 A is operable, but investigation of abnormal vibrationhoise by Maintenance is ongoing.

AOP-1/2.75.2, Acts of Nature - Flood is in effect. River water level is currently 671 feet and stable. Cooling Tower Pump House level is being logged on the Outside Operator Tour.

Train B is the Protected Train.

Reduce reactor power to 75% at 12Yhr.

to remove a condenser waterbox from service for cleaning.

SCENARIO SUPPORT MATERIAL REQUIRED 1 OM-52.4.8, Load Following Reactivity Plan for 12%/hr. Load Reduction Protected Train B Wall Plaque

INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #1 Reduce power to 75% at 12% per hour Turbine load and reactor power decreasing at 12%/hr.

US directs load reduction in accordance with Reactivity Plan.

BOP initiates load reduction per 1 OM-52.4.8, Step 1V.A.

Set the desired terminal load on the SETTER.

Set the desired rate on the LOAD RATE thumbwheel (5%/min.

maximum).

As the turbine load reduces, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.

Depress the GO pushbutton.

BVPS -1 NRC Scenario 1 4 of 29

I I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Turbine Load and Reactor Power lowering at 12% per hour After the governor valves are off the limiter, transfer the turbine control to the 1 stage pressure feedback mode by depressing the lST STG IN pushbutton AND verify the following:

1. The IST STG OUT lamp is OFF.

2. The lST STG IN lamp is ON.

After transfer to the 1 ST stage pressure feedback mode, set the desired terminal load on the SETTER.

Set the desired rate on the LOAD RATE thumbwheel (5%/min.

maximum).

As the turbine load reduces, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.

Depress the GO pushbutton.

BVPS -1 NRC Scenario 1 5 of 29

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I RO initiates RCS boration as necessary to maintain Tavg - Tref per 1 OM-7.4.L, Step 1V.A and reactivity plan.

Estimate the volume of boric acid to be added to the RCS using any of the following:

a.

b.

C.

1 OM-7.5, Figure 7.7, Boron Addition, AND Table 1, Nomograph Correction Factors WAG tables Reactor Engineer approved computer based methods Estimate the rate of boron concentration change as a function of boric acid flow rate using 1 OM-7.5, Figure 7-8, Boron Addition Rate, AND Table 1, Nomograph Correction Factors.

Place the 1 MU control switch to Stop for greater than 1 second to allow the blender to unarm.

BVPS -1 NRC Scenario 1 6 of 29

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Place 43/MU control switch to Borate.

Set FCV-1 CH-l13A, Boric Acid to Blender FCV to the desired boric acid flowrate.

Set Boric Acid Integrator YIC-1 CH-113 for the desired quantity.

a. Reset Boric Acid Integrator YIC-1 CH-113.

Start the Reactor Makeup Control System by placing 1 MU control switch to Start.

Verify boric acid to blender flow on FR-1 CH-113, Boric Acid Flow.

Operate the pressurizer spray as required to limit the difference between boron concentration in the pressurizer and that of the RCS to less than 50 PPm-BVPS -1 NRC Scenario 1 7 of 29

[ INSTRUCTIONAL GUIDELINES 1

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Verify boration automatically stops when Boric Acid Integrator YIC-1 CH-113 reaches the setpoint.

When boration is complete, perform the following:

a.

b.

C.

d.

e.

Place the 1 MU control switch to Stop for greater than 1 second.

Place 43/MU control switch to Auto.

Reset Boric Acid Integrator Adjust makeup controls for the new RCS boron concentration.

Place the 1 MU control switch to Start.

YIC-1 CH-113.

BVPS -1 NRC Scenario 1 8 of 29

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I

EVENT #2 Valve Position Limiter Failure; Control Rods Fail In Auto When directed, insert the following command:

IMF TUR15 (0 0) 60 (Other malfunctions pre-loaded)

Load rejection occurs and control rods fail in Auto after stepping in.

Annunciators:

[A4-461, Tavg Deviation from Tref

[A4-1241, Rod Control Bank D Low Low

[A4-121, Pressurizer Control Low Pressure Deviation

[A4-521, Delta Flux Out of Target Band Control rods stop moving after 10 seconds (preloaded).

Control rods stepping in.

Tavg increasing.

Steam dump valves opening.

RCS pressure increasing.

MW decreasing.

Control rods not inserting.

Rods in Manual and inserting.

Boration flow indicated.

Crew acknowledges alarms, notifies US and investigates loss of load.

Crew informs US of the loss of electrical load.

US refers to AOP-1.35.2, Load Rejection RO verifies control rods in Auto.

. Inserts control rods in Manual RO initiates RCS boration.

BVPS -1 NRC Scenario 1 9 of 29

I INSTRUCTIONAL GUIDELINES 1

PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Crew sounds Standby alarm and announces Unit 1 load rejection.

US requests SM to evaluate EPP.

BVPS -1 NRC Scenario 1 EHC system normal except for valve position limiter.

1 LO-M-SA running.

EHC pressure > 1550 psig.

Valve position limiter failure; vibration and load satisfactory for condition.

Generator load stable.

10 Of 29 BOP verifies normal EHC operation.

. VPL not consistent with pre-event value BOP checks at least one EHC pump is running.

BOP checks EHC fluid pressure greater than 1550 psig.

Crew checks if governor valves have closed in sequence, checks turbine vibration recorders.

Crew monitors for subsequent load reductions > 90 Mwe.

I INSTRUCTIONAL GUIDELINES 1

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]

Generator load > 270 Mwe.

Vacuum < 5.5 inches HgA.

Generator volts, amps, and power factor satisfactory.

Tavg lowering to Tref value.

Steam dump valves closed.

Steam dumps reset.

Bistable lights extinguished.

V P L malfunctioning.

Crew checks if reactor or turbine should be tripped.

Generator load > 270 MWe

. Vacuum -c 5.5 inches HgA BOP checks main generator parameters.

RO checks Tavg-Tref within k 2".

BOP resets steam dump controller:

Verifies steam dump valves closed Places steam dump control mode selector switch to reset Allows switch to spring return to Tavg position Verifies load rejection bistables NOT lit Crew determines VPL reference setting not at pre-event value.

BVPS -1 NRC Scenario 1 11 of 29

[ INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I FE System and Duquesne Light Controllers acknowledge notification of load rejection.

At SM direction, do not lower turbine load.

Continue with scenario when VPL problem is identified and Tavg-Tref are matched, or at Examiners discretion.

BVPS -1 NRC Scenario 1 TV-1 CN-100 closed.

Reactor power > 25%.

12 of 29 US notifies Wadsworth (FE) System Control Center and Duquesne Light System Control Center of load rejection.

US directs I&C to investigate problem with VPL.

US checks for load reduction of > 15%

and informs Chemistry, if necessary.

Crew checks TV-1 CN-100 closed.

Crew checks if 1 CCT-13 should be opened.

US may review T.S. 3.2.1, 3.2.5 and 3.1.3.6 for compliance.

US reviews T.S. 3.4.8 for RCS sampling requirements, if power changed by >1 5°/0.

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #3 Pressurizer Pressure Transmitter Fails High PT-1 RC-445 fails high slowly.

When directed, insert the following command:

Annunciators:

IMF PRS08E (0 0) 2500 120

[A4-51, Pressurizer Power Oper Relief Valve Open

[A4-9], Pressurizer Control Press High

[A4-121, Pressurizer Control Press Deviation

[A4-1 31, Pressurizer Control Press High Pwr Relief Act PCV-1 RC-455D closed.

RO notes alarm and informs US. Crew refers to ARPs, if necessary.

US refers to 1OM-6.4.IFI Instrument Failure Procedure, Attachment 2.

RO closes PCV-1 RC-455D.

PCV-1 RC-456 blocked closed.

US refers to Technical Specifications.

. T.S. 3.2.5 may apply if RCS pressure is below DNB setpoint.

T.S. 3.4.1 1.a may be referenced, but PORV remains operable in manual, capable of being cycled.

BVPS -1 NRC Scenario 1 13 of 29

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #4 SG Pressure Transmitter Failure PT-1 MS-485 fails low.

When directed, insert the following command:

Annunciators:

IMF MSS16E (0 0) 0

[A7-491, Loop 2 Steamline Pressure Low or Press Rate Hi Crew responds to indications and alarms.

[A7-50], Loop 2 Feedwater Flow >

Steam Flow

[A7-53], Aux Feed to Stm Gen Valves Not Fully Open Train A SG 16 Channel 3, PT-1 MS-485 fails low.

SG 1 B Channel 3 steam flow drops (density compensation input).

SG 1 B feed flow, NR level drops.

FCV-1 FW-488 modulates closed in automatic.

BOP notes problem with SG 16 level control, takes manual control of FCV-1 FW-488 and informs US.

BVPS -1 NRC Scenario 1 14 of 29

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1

NOTE:. Level deviation is dependent on time of establishing normal MFRV control to restore SG level.

SG 1 B level deviation.

NR level returning to 44%.

FM-485 selected.

FCV-1 Fw-488 in Auto.

Crew determines that steam pressure channel PT-1 MS-485 failed low.

US refers to 1 OM-24.4.IF, Instrument Failure Procedure, Attachment 4.

US directs BOP to restore SG 1 B level to program level.

BOP selects redundant SG steam flow signal on FC-1 Fw-488.

US directs BOP to return feedwater control to automatic when SG level is within normal range.

US refers to T.S. 3.3.2.1 and Table 3.3-3, Items 1.e and 4.d.

US identifies 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months requirement to place channel in the tripped condition.

BVPS -1 NRC Scenario 1 15 of 29

I INSTRUCTIONAL GUIDELINES 1

PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 US directs crew to trip associated bistables per 1 OM-24.4.IF, Attachment 4, Table 1.

US directs I&C to investigate failure of steam pressure channel.

Prior to next event, insert the following command:

IMF MSS07 (0 0)

Condenser Steam Dump Failure When bistables have been directed to be tripped and malfunction is inserted, continue with the next event.

BVPS -1 NRC Scenario 1 16 of 29

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENTS #5.6, & 7 Turbine Trip; Condenser Steam Dump Failure; Auto and Manual Reactor Trip Failure; SG ADV Fails Open When directed, insert the following command:

Spurious turbine trip leads to ATWS event followed by faulted SG due to stuck open atmospheric dump valve.

IMF TURO1 (0 0)

ATWS Crew enters FR-S.l.

RCS pressure and Tavg rising.

Turbine tripped.

Crew determines that the turbine has tripped.

US directs a manual reactor trip.

RO places reactor trip switch to Trip.

RO identifies that reactor failed to trip.

RO depresses BB-A reactor trip pushbutton to attempt reactor trip.

US transitions to FR-S.l, and informs crew.

BOP verifies turbine is tripped.

BVPS -1 NRC Scenario 1 17 of 29

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Crew verifies TREF is decreasing.

CRITICAL TASK #1:

Crew inserts negative reactivity into the core by inserting RCCAs before transitioning from FR-S.l.

Control rods inserting.

FW-P-3A and 38 running.

TV-IMS-105A and 1056 open.

MOV-1 FW-l51A, 6, C, D, E, and F open.

CH-P-1 A running.

SI not actuated.

MOV-1 CH-350 open ICH-P-2A(B) running in fast speed.

RO places control rod group selector in Auto and verifies rods are inserting.

RO drives rods in manual after automatic rod motion stops.

BOP verifies AFW status.

. Motor-driven pumps running

. Turbine-driven AFW pump steam supply valves open A W throttle valves - full open RO initiates emergency boration.

Verify at least one charging pump running

. Check SI actuated

. Open MOV-1CH-350

. Start in-service Boric Acid Transfer Pump in FAST speed BVPS -1 NRC Scenario 1 18 of 29

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Boration flow > 30 gpm.

FI-1 CH-122A indicates > 75 gpm.

PRZR pressure < 2335 psig.

Verify emergency boration flow -

greater than 30 gpm Adjust FCV-1 CH-122 to establish charging flow greater than 75 gpm RO checks PRZR pressure < 2335 psig.

Crew sounds Standby alarm and announces Unit 1 ATWS.

When directed to locally trip reactor, insert:

TRG! 3 RTB A open (2 minute delay).

Crew dispatches operator to locally trip the reactor.

RTB B open (2 minute delay).

Control rods drop.

Power decreasing.

BOP verifies turbine trip and reheat steam isolation.

MOV-1 MS-1 OOA, B closed.

All reheat stop and interceptor valves closed.

Reset reheater controller Verify MOV-1 MS-1 OOA, B closed BVPS -1 NRC Scenario 1 19 of 29

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 BOP places both steam dump control interlock selector switches in Off.

Crew returns to E-0.

SI not actuated.

Power range indicates < 5%.

Intermediate Range SUR negative.

US determines SI has not actuated.

US directs performance of first 10 steps of E-0, as time permits.

RO checks reactor is subcritical.

. Power range channels < 5%.

. Intermediate range channels negative startup rate.

RO continues boration, as necessary.

US transitions to E-0, and informs crew.

US directs STA to monitor CSF Status Trees.

BVPS -1 NRC Scenario 1 20 of 29

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I RO verifies reactor trip.

Reactor trip and bypass breakers open.

Rod bottom lights lit.

Rods at bottom.

Rx trip and bypass breakers are open Rod bottom lights are lit Rod position indication at zero Neutron flux decreasing.

. Neutron flux is dropping Throttle and governor valves closed.

Main generator output breakers open.

Exciter circuit breaker open.

1 AE and 1 DF busses energized.

E-0 immediate actions complete.

NOTE: Pre-emptive action may have been previously performed.

SI actuated.

BOP verifies turbine trip.

BOP verifies generator trip.

BOP verifies power to AC emergency busses.

RO verifies SI actuated.

. Depresses manual SI actuation pushbuttons (both trains).

Crew sounds Standby Alarm and announces Unit 1 reactor trip and safety injection.

BVPS -1 NRC Scenario 1 21 of 29

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 1 VS-F-4A running.

CH-P-1 A and CH-P-1 B running.

BIT flow indicated.

SI-P-1 A and 16 running.

MD and TD ARN pumps running.

All SG AFW throttle valves open.

A M flow > 355 gpm.

BOP verifies leak collection exhaust fan is running.

US directs starting CNMT hydrogen analyzers.

RO verifies SI status.

. Two charging pumps running BIT flow indicated

. LHSl pumps both running BOP verifies AFW status.

. AFW pumps running

. SG AFW throttle valves full open

. Total ANV flow > 355 gpm BOP performs Attachment 1 -K, Verification of Automatic Actions (Steps listed at end of scenario guideline.)

BVPS -1 NRC Scenario 1 22 of 29

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 PCV-1 MS-101 A stuck open.

TAVG decreasing.

Condenser steam dumps closed.

MOV-1 MS-1 OOA, B closed.

Total A M I flow > 355 gpm.

Main steam trip and bypass valves closed.

Recirc spray pumps not running.

PCV-1 RC-456 closed, but leaking.

Spray valves closed.

Safety relief valves closed.

PRT conditions normal.

All PORV MOVs open (except MOV-1 RC-536 previously closed).

D/P between RCS and highest SG pressure > 200 psid.

RO check RCS TAVG stable at or trending to SPF.

Stop dumping steam.

Verify reheat steam isolation.

Reduce total feed flow to minimize cooldown.

Close main steam trip and bypass valves.

RO checks recirc spray pump status.

RO checks PRZR isolated.

PORVs closed Spray valves closed Safety relief valves closed PRT conditions at expected values Power to at least one block valve and at least one open Crew checks if RCPs should be stopped.

BVPS -1 NRC Scenario 1 23 of 29

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Crew checks if any SGs are faulted.

BOP determines SG 1 A pressure decreasing in uncontrolled manner.

SG 1A faulted.

Crew enters E-2.

Control Room dampers shut and timers running.

When requested as Unit 2 Operator, report CREVS actuation.

CRITICAL TASK #2:

Crew isolates the faulted SG and directs operator to close isolation valve before transition out of E-2.

All yellow SLI marks lit.

Pre-nonreturn valves closed.

SG 1 B and 1 C pressures stable.

US transitions to E-2, and informs crew.

BOP initiates CREVS and verifies system actuated.

Crew requests Unit 1 CREVS status.

Crew verifies steam line isolation.

BOP closes steamline pre-nonreturn drain valves.

BOP checks for any non-faulted SG.

BVPS -1 NRC Scenario 1 24 of 29

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 SG 1 A faulted.

Main and Bypass Feed Reg Valves closed.

NOTE: Pre-emptive action may have been previously performed.

AFW throttle valves closed. (May have been previously closed.)

When directed to close MS-23, insert the following command:

IRF MSS07 (0 600) 0 (Closes MS-23 on 10 min. delay)

BVPS -1 NRC Scenario 1 PCV-MS-101 A open.

HCV-1 MS-104 closed.

No SG levels rising in an uncontrolled manner.

SI Termination Criteria met.

25 of 29 BOP identifies SG 1 A pressure decreasing in uncontrolled manner.

Crew isolates faulted SG.

9 Check FWI - previously verified.

9 Close AFW throttle valves on faulted SG.

9 Direct locally closing MS-15.

. Attempt to close atmospheric dump valve.

9 Close residual heat release valve.

Crew directs operator to locally close MS-23.

BOP checks PPDWST level > 27.5 feet.

Crew checks if SG tubes are intact.

Crew checks if SI flow can be reduced.

W VI z 0

a VI W

U I-Z W n 3

I-VI W

I-n Y

tl a

W >

F Y m

0 -

Q, N

0 (D

N

.c W

VI z 0

a VI W

U U

0 VI 3

I-VI I-2 f

a v)

W z 1

u 2

3 3

Z L) 3 0 z 2

2 r

0 K

z v) n 2i

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Attachment l-K, Verification of Automatic Actions Diesel Generators - BOTH RUNNING.

Check station instrument air header pressure - GREATER THAN 100 PSIG.

Ensure reheat steam isolation:

a. Verify [MOV-1 MS-1 OOA, B]

CLOSED.

b. Reset reheater controller.

Verify CCR Pumps - TWO RUNNING.

Align Neutron Flux Monitoring For Shutdown:

a. Transfer NR-1 NI-45, Nuclear Recorder to operable source and intermediate range displays.

Verify river water system in service.

a. RPRW Pumps - TWO RUNNING.

BVPS -1 NRC Scenario 1 27 of 29

I INSTRUCTIONAL GUIDELINES 1

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I

b. Check CCR Heat EX RW pressure

- GREATER THAN 20 PSIG.

Check If main steamline isolation required.

a. Check the following:

. CNMT pressure - GREATER THAN 3 PSIG.

OR

. Steamline pressure - LESS THAN 500 PSIG.

OR

. Steamline pressure high rate of change - ANY ANNUNCIATOR LIT.

Annunciator A7-41 Annunciator A7-49 Annunciator A7-57

b. Verify steamline isolation:

. YELLOW SLI marks - LIT.

Check CIB and CNMT spray status:

BVPS -1 NRC Scenario 1 28 of 29

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1

. Containment pressure - HAS REMAINED LESS THAN 8 PSIG.

Verify ESF equipment status:

a. Verify SI status by checking all RED SIS marks - LIT.

b. Verify CIA by checking all ORANGE CIA marks - LIT.

c. Verify FWI by checking all GREEN FWI marks - LIT.

Verify power to both AC emergency busses.

Upon completion, report any discrepancies to SWUS.

BVPS -1 NRC Scenario 1 29 of 29

RTL# A5.670.AA 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:

SUBDIVISION:

SCENARIO TITLWNO.:

COMPUTER CODE FOR L.P.:

License Operator TraininULicensed Requalification Training Simulator 2005 NRC Initial License Exam 1 LOT6 Scenario No. 2 I

2 I

2-8-05 I

INSTRUCTIONAL SETTING:

Simulator APPROXIMATE DURATION:

1.5 Hours PREPARED BY:

REVIEWED BY:

APPROVED FOR IMPLEMENTATION:

Date Date Date BVPS-1 NRC Scenario 2 Page 1 of 26

INITIAL CONDITIONS:...

IC-182; PW = NRC2; 53% power, RCS Boron 1350 ppm, CB D at 163 steps, Rods in Manual.

CH-P-1 C, HHSVCharging Pump 00s.

PCV-1 RC-456, PORV 456 leakage. MOV-1 RC-536, Block Valve closed with power maintained.

Flood warnings due to heavy rains.

Maintenance is investigating abnormal vibration/noise on 1 WR-P-1 A, River Water Pump.

Turbine Control selected to First Stage In, Turbine is off the VPL.

PCV-1 RC-456 Control Switch in Close MOV-1 RC-536 Control Switch in Close EQUIPMENT STATUS ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS I

I I

YCT - Both CH-P-1 C Switches YCT - PCV-1 RC-456 Control Switch YCT - MOV-1 RC-536 Control Switch OM Fig. 7-1, 3E: CH-27, 161 Shut OM Fig. 7-1,5E: CH-21, 148 Shut DATUTIME 00s TECHNICAL SPECIFICATION(S1 PCV-1 RC-456 I

1 CH-P-1 C Yesterday 1500 3.4.1 1.a I

N/A 2 days ago I

SHIFT TURNOVER INFORMATION

1.

2.

1 CH-P-1 C is 00s for pump shaft and coupling replacement and is expected to return within the next 24 - 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

PCV-1 RC-456 seat leakage. MOV-1 RC-536 is closed with power maintained per T.S. 3.4.1 1.a.

1 WR-P1 A is operable, but investigation of abnormal vibration/noise by Maintenance is ongoing.

3.

4.

5.

AOP-1/2.75.2 is in effect. River water level is 671 feet and stable. Cooling Tower Pump House level is being logged on the Outside Operator Tour.

Train B is the Protected Train.

Reduce power to take the unit off-line at 12%/hr. due to circulating water intake clogging.

SCENARIO SUPPORT MATERIAL REQUIRED 1 OM-52.4.B, Load Following Reactivity Plan for 12%/Hr Power Reduction Protected Train 6 Wall Plaque

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #1 Reduce Power Turbine load and reactor power decreasing at 12%/hr.

US directs load reduction in accordance with Reactivity Plan.

PO initiates load reduction per 1 OM-52.4.6, Step 1V.A.

. Set the desired terminal load on the SETTER.

. Set the desired rate on the LOAD RATE thumbwheel (5%/min.

maximum).

As the turbine load reduces, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.

Depress the GO pushbutton.

RO initiates RCS boration as necessary to maintain TAVG - TREF per 1 OM-7.4.L, Step 1V.A and reactivity plan.

BVPS 1-NRC Scenario 2 4 of 26

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Estimate the volume of boric acid to be added to the RCS using any of the following:

a. 1 OM-7.5, Figure 7.7, Boron Addition, AND Table 1, Nomograph Correction Factors

b. WAG tables

c. Reactor Engineer approved computer based methods Estimate the rate of boron concentration change as a function of boric acid flow rate using 1 OM-7.5, Figure 7-8, Boron Addition Rate, AND Table 1 Nomograph Correction Factors.

Place the 1 MU control switch to Stop for greater than 1 second to allow the blender to unarm.

Place 43/MU control switch to Borate.

Set FCV-1 CH-113Al Boric Acid to Blender FCV, to the desired boric acid f lowrate.

BVPS 1-NRC Scenario 2 5 of 26

[

INSTRUCTIONAL GUIDELINES 1

PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I Set Boric Acid Integrator YIC-1 CH-113 for the desired quantity.

a. Reset Boric Acid Integrator YIC-1 CH-113.

Start the Reactor Makeup Control System by placing 1 MU control switch to Start.

Verify boric acid to blender flow on FR-1 CH-113, Boric Acid Flow.

Operate the pressurizer spray as required to limit the difference between boron concentration in the pressurizer and that of the RCS to less than 50 PPm-Verify boration automatically stops when Boric Acid Integrator YIC-1 CH-113 reaches the setpoint.

When boration is complete, perform the following:

a. Place the 1 MU control switch to BVPS 1-NRC Scenario 2 6 of 26

I INSTRUCTIONAL GUIDELINES 1

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]

b.

C.

d.

e.

Stop for greater than 1 second.

Place 43/MU control switch to Auto.

Reset Boric Acid Integrator Adjust makeup controls for the new RCS boron concentration.

Place the 1 MU control switch to Start.

YIC-1 CH-113.

BVPS 1-NRC Scenario 2 7 of 26

I OBJECTIVE I EXPECTED STUDENT RESPONSE I I

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE EVENT #2 SG 1 B Level Transmitter Failure When directed, insert the following command:

IMF FWM16D (0 0) 100 LT-1 Fw-484 (Channel 1 ) fails high.

Annunciator:

[A7-521, Steam Generator 1 B Level High-High Crew responds to indications and alarms.

RO refers to 1 OM-24.4.ABEI Steam Generator 1 B Level High-High.

NOTE: No system response occurs on failure of a single channel due to median signal select feature.

US refers to 1OM-24.4.IFI Instrument Failure Procedure, Attachment 1.

US refers to T.S. 3.3.1.1, Item 14 and T.S. 3.3.2.1, Items 5.a and 7.a.

BVPS 1-NRC Scenario 2 8 of 26

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #3 No. 1 EDG Trouble When directed, insert the following command:

Annunciator:

IMF EPS11 A (0 0)

Outside Operator reports EDG No.

1 control power breaker is open.

[A9-71, Diesel Generator No. 1 Not Available Or Local Panel Trouble Crew responds to indications and alarms.

RO refers to 1 OM-36.4.AEC, Diesel Generator No. 1 Not Available Or Local Panel Trouble.

Crew dispatches Outside Operator to investigate local alarm.

US refers to T.S. 3.8.1.1, Action b.

BVPS 1-NRC Scenario 2 9 of 26

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #4 Letdown Pressure Control Valve Fails Closed In Auto When directed, insert the following command:

IOR X06A087P (0 0) 1.0 Valve is physically functional; problem is in the control circuit.

PCV-1 CH-145 fails closed resulting in a loss of normal letdown.

RO responds to indications and alarms.

Annunciator:

[A3-1071, Non-Regen Heat Exchanger Disch Press High Letdown backpressure rising.

Letdown flow decreasing.

Letdown flow at 105 gpm.

BOP refers to 1 OM-7.4.ABJI Non-Regen Heat Exchanger Disch Press High.

US may refer to AOP-1.7.1, Loss Of Charging Or Letdown.

RO reports 1 CHS-FI150 indicates letdown flow is zero.

Crew minimizes any power changes in progress.

RO manually controls PCV-1 CH-145 to restore letdown flow to previous value.

US contacts I&C to investigate failure Of PCV-CH-145.

BVPS 1-NRC Scenario 2 10 of 26

[

INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #5 SG 1A MFRV Controller Fails In Auto When directed, insert the following command:

IMF FWM15A (0 0) 0 300 Valve is physically functional; problem is in the control circuit.

FCV-1 FW-478, Main Feed Reg Valve fails closed.

Annunciator:

[A7-451, Steam Generator 1 A Level Deviation From Setpoint SG 1 A feed flow lowering.

FCV-1 FW-478 position and feed flow stabilize in Manual.

BOP recognizes feed flow problem, informs US.

US directs BOP to take manual control FCV-1 FW-478 to stabilize SG feed flow and level.

BOP takes manual control of FCV-1 FW-478 to raise feed flow.

US directs I&C to investigate problem with FCV-1 FW-478.

BVPS 1-NRC Scenario 2 11 of 26

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 EVENT #6 RCS Leak When directed, insert the following command:

25 gpm RCS leak in CNMT.

Annunciators:

IMF RCSO2A (0 0) 25

[A4-711, Radiation Monitoring High

[A4-721, Radiation Monitoring High-High

[A1 -351, Ctmt Air Total Pressure Hi/Lo Channel 1

[A1 -431, Ctmt Air Total Pressure Hi/Lo Channel 2 RM-1 RM-204 in alarm.

Crew responds to indications and alarms.

US refers to AOP-1.6.7, Excessive Primary Plant Leakage.

RO checks if PRZR level can be maintained.

RO controls charging flow as necessary to maintain PRZR level.

RM-1 RM-215A, B in alarm.

US requests SM to evaluate EPP.

RO controls charging flow as necessary to maintain PRZR level on program.

RO checks if VCT level can be maintained by normal makeup.

BVPS 1-NRC Scenario 2 12 of 26

1 INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I RM-1 MS-102AI B, C, N-16 Steam Generator Leak Monitors normal.

BOP checks secondary plant radiation trends normal.

RIS-SV1 00, Condenser Air Ejector Vent normal.

RM-BD-101, High Capacity Blowdown monitor normal PRT pressure, level, and temperature normal.

Slight rise in containment temperature, (may not be noticeable).

Aux. Bldg. radiation normal.

TV-1 CH-200AI B and C closed.

LCV-1 CH-460A and B closed.

FCV-1 CH-122 closed.

RCP seal injection flow at 6 gpm per pump.

RO checks PRT conditions consistent with pre-event values.

RO checks containment temperature is normal.

BOP checks Aux. Bldg. radiation levels are normal.

RO isolates charging and letdown.

. Close TV-1 CH-200A, B and C Close LCV-1 CH-460A and B

. Close FCV-1 CH-122

=

Reduce seal injection flow to 6 gpm Per Pump BVPS 1-NRC Scenario 2 13 of 26

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I PRZR level stable.

RO checks PRZR level stable or dropping.

RO restores charging and letdown.

NOTE: If contacted by US, SM may direct an emergency shutdown per AOP-1.51.l.

PRZR level > 14%.

PCV-1 CH-145 in Manual and 75% open.

LCV-1 CH-460A and B open.

TV-1 CH-200A and B open.

PI-1 CH-145 indicates - 300 psig.

PCV-1 CH-145 in Auto.

FCV-1 CH-122 in Auto.

CNMT pressure c 1.5 psig.

When charging and letdown are restored, initiate the next event.

Adjust FCV-1 CH-122 to obtain 30 to 50 gpm Verify PRZR level > 14%

Place PCV-1 CH-145 in Manual and 75% open Open LCV-1 CH-460A and B Open TV-1 CH-200A, B and C Adjust PCV-1 CH-145 until backpressure is - 300 psig Place PCV-1 CH-145 in Auto Place FCV-1 CH-122 in Auto Crew checks CNMT pressure < 1.5 psig and stable.

US may refer to T.S. 3.4.6.2.

BVPS 1-NRC Scenario 2 14 of 26

I INSTRUCTIONAL GUIDELINES 1

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENTS #7 & #8 SBLOCA; Train " B HHSl Pump RCS LOOP " A LOCA - 2000 gpm.

Auto Start Failure; Train "A" ESF Components Must Be Started Manually.

When directed, insert the following command:

Annunciators:

IMF RCS02A (0 0) 2000 300

[A4-41, Pressurizer Control Low Level Deviation Pre-loaded Commands:

[A3-58], Charg Pump Disch Flow High-Low TRGSETl JPPLS1(2)==1 IMF SISOSA (1 0)

RCS pressure and PRZR level dropping rapidly.

IMF INH40 (0 0)

IMF SISlOA (0 0)

Reactor trip and bypass breakers open.

Power range < 5%.

Neutron flux dropping.

Crew enters E-0.

Throttle and governor valves closed.

Crew responds to indications and alarms.

US orders reactor trip and enters E-0.

RO verifies reactor trip:

. Reactor trip and bypass breakers open.

. Power range indication < 5%.

. Neutron flux dropping.

BOP verifies turbine trip.

BVPS 1-NRC Scenario 2 15 of 26

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I CRITICAL TASK #1:

Crew manually actuates at least one train of SIS actuated safeguards before transition to any ORP.

BVPS 1-NRC Scenario 2 Main generator output breakers open.

Exciter circuit breaker open.

1AE and 1 DF busses energized from off site power.

SI Train A not actuated.

SI actuated (both trains).

1 VS-F-4A running.

16 of 26 BOP verifies generator trip.

BOP verifies power to AC emergency busses.

RO determines Train A SI failed to actuate automatically. (If SI was not manually actuated previously).

Manually actuates both SI trains.

Crew sounds Standby alarm and announces Unit 1 reactor trip and safety injection.

BOP checks leak collection exhaust fan running.

US directs starting CTMT hydrogen analyzers.

RO verifies SI status.

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I BVPS 1-NRC Scenario 2 CH-P-1 B running, CH-P-1 A tripped and will not restart.

BIT flow indicated.

SI-P-1 A and 1 B running.

MD and TD AFW pumps running.

All SG AFW throttle valves open.

A M I flow > 355 gpm.

Condenser steam dumps closed.

MOV-1 MS-lOOA, B closed.

Total A M I flow > 355 gpm.

Recirc spray pumps not running.

17 of 26 Manually starts CH-P-1 B BIT flow indicated LHSl pumps both running BOP verifies A W status.

A W pumps running SG AFW throttle valves full open Total A M I flow > 355 gpm BOP performs Attachment 1 -K, Verification Of Automatic Actions (Steps listed at end of scenario guide.)

RO verifies RCS Tavg stable at or trending to 547*F.

. Stop dumping steam.

. Verify reheat steam isolation.

m Reduce total feed flow to minimize cooldown.

RO checks recirc spray pump status.

I I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE

[ OBJECTIVE I EXPECTED STUDENT RESPONSE 1 RO verifies PRZR isolated.

PCV-1 RC-456 closed, but leaking.

Spray valves closed.

Safety relief valves closed.

PRT conditions normal.

All PORV MOVs open (except MOV-1 RC-536 previously closed).

D/P between RCS pressure and highest SG pressure < 200 psid.

All RCPs stopped.

No SG pressures dropping in an uncontrolled manner.

No SG levels rising in an uncontrolled manner.

All secondary radiation levels normal.

PORVs closed Spray valves closed Safety relief valves closed PRT conditions at expected values Power to at least one block valve and at least one open RO checks if RCPs should be stopped.

9 Stops all RCPs BOP checks if any SGs are faulted.

BOP checks if SG tubes are intact.

. SG levels - none rising in an uncontrolled manner

. Secondary radiation consistent with pre-event values.

BVPS 1-NRC Scenario 2 18 of 26

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 Crew checks if RCS is intact.

CNMT parameters not consistent with pre-event values.

Crew enters E-1.

CREVS not actuated or required.

D/P between RCS pressure and highest SG pressure < 200 psid and HHSl flow All RCPs stopped.

CRITICAL TASK #2:

indicated.

Crew trips all RCPs when RCS to highest S/G D/P criteria is exceeded (or due to ClB) and prior to exiting E-1.

Recirc spray not actuated.

. CNMT radiation, pressure and sump level consistent with pre-event values US transitions to E-1, and informs crew.

US directs STA to monitor CSF status trees, if not previously done.

BOP checks if CREVS actuated.

RO checks if RCPs should be stopped.

. Stops all RCPs, if not previously performed RO checks recirc spray system status.

BVPS 1-NRC Scenario 2 19 of 26

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I BVPS 1-NRC Scenario 2 No SG pressures dropping in an uncontrolled manner.

AFW flow > 355 gpm.

Instrument air header pressure > 100 psig.

No SG levels rising in an uncontrolled manner.

All secondary radiation levels normal.

Power available to PORV MOV's.

PORVs closed.

All PORV MOV's open (except MOV-1 RC-536 previously closed).

20 of 26 BOP checks if any SG's are faulted.

BOP maintains AFW flow > 355 gpm until NR SG level is > 13%.

BOP checks instrument air header pressure > 100 psig.

BOP checks if SG tubes are intact.

. SG levels - none rising in an uncontrolled manner Secondary radiation consistent with pre-event values.

RO checks PZR PORVs and block va I ves.

Power to block valves

. PORVs closed

. At least one block valve open

I

[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Crew checks if SI flow should be reduced.

BVPS 1-NRC Scenario 2 Subcooling > 46F.

AFW flow > 355 gpm.

RCS pressure dropping.

CTMT spray pumps not running.

SI reset (both trains).

CIA reset (both trains).

RCS pressure z 300 psig.

Both LHSl pumps stopped and in Auto.

21 of 26

=

RCS subcooling > 46F

. Secondary heat sink available RCS pressure stable or rising US determines SI Termination Criteria is not met.

Crew checks if CTMT spray should be stopped.

RO resets SI.

RO resets CIA.

RO checks if LHSl pumps should be stopped.

=

Stop LHSl pumps and place in Auto

1 INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I BVPS 1-NRC Scenario 2 SG pressure stable or rising. RCS pressure stable or dropping.

EE-EG-1 stopped.

Recirc components available.

Radiation levels normal.

RCS pressure > 300 psig.

22 of 26 Check RCS and SG pressures.

BOP checks if diesel generators should be stopped.

. BOP manually stops No. 1 EDG, if not previously performed Crew verifies cold leg recirculation capability.

Crew checks if Aux. Bldg. and Safeguards radiation consistent with pre-event values.

US requests Chemistry and Health Physics to obtain samples.

Crew requests TSC assistance to start additional plant equipment.

Crew checks if RCS cooldown and depressurization is required.

RCS pressure > 300 psig

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Crew enters ES-1.2.

US transitions to ES-1.2, and informs crew.

Scenario may be terminated upon crew transition to ES-1.2.

BVPS 1-NRC Scenario 2 23 of 26

INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I -K, Verification of Automatic Actions No. 2 EDG is running. No. 1 EDG manually stopped, if running.

Diesel Generators - BOTH RUNNING.

Check station instrument air header pressure - GREATER THAN 100 PSIG.

Ensure reheat steam isolation:

a. Verify [MOV-1 MS-1 OOA, B]

CLOSED.

b. Reset reheater controller.

Verify CCR Pumps - TWO RUNNING.

Align Neutron Flux Monitoring For Shutdown:

a. Transfer NR-1 NI-45, Nuclear Recorder to operable source and intermediate range displays.

Verify River Water System In Service.

BVPS 1-NRC Scenario 2 24 of 26

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I

a. RPRW Pumps - TWO RUNNING.

b. Check CCR Heat EX RW pressure

- GREATER THAN 20 PSIG.

Check If Main Steamline Isolation Required.

a. Check the following:

. CNMT pressure - GREATER THAN 3 PSIG.

OR

. Steamline pressure - LESS THAN 500 PSIG.

OR

. Steamline pressure high rate of change - ANY ANNUNCIATOR LIT.

- Annunciator A7-41

- Annunciator A7-49

- Annunciator A7-57

b. Verify steamline isolation:

. YELLOW SLI marks - LIT.

Check CIB and CNMT Spray Status:

BVPS 1-NRC Scenario 2 25 of 26

[ INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1

. Containment pressure - HAS REMAINED LESS THAN 8 PSIG.

Verify ESF Equipment Status:

a. Verify SI status by checking all RED SIS marks - LIT.

b. Verify CIA by checking all ORANGE CIA marks - LIT.

c. Verify FWI by checking all GREEN FWI marks - LIT.

Verify Power To Both AC Emergency Busses.

Upon completion, report any discrepancies to SWUS.

BVPS 1-NRC Scenario 2 26 of 26

RTL# A5.670.AA 2

1/2-ADM-1357.F11 Page 1 of 1 Revision 0 2-8-05 I

SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:

SUBDIVISION:

SCENARIO TITLUNO.:

COMPUTER CODE FOR L.P.:

License Operator Training/Licensed Training Simulator 2005 NRC Initial License Exam 1 LOT6 Scenario No. 3 Requalif ication INSTRUCTIONAL SETTING:

Simulator APPROXIMATE DURATION:

1.5 Hours PREPARED BY:

REVIEWED BY:

APPROVED FOR IMPLEMENTATION:

Date Date Date BVPS-1 NRC Scenario 3 Page 1 of 28

INITIAL CONDITIONS:....

IC-183; PW = NRC3; 25% Power, RCS boron at 1690 ppm, CB D at 133 steps. Rods in Manual.

PCV-1 RC-456, PORV 456 leakage. MOV-1 RC-536, Block Valve closed with power maintained.

FW-P-1 B, Steam Generator Feed Pump is 00s.

Flood watch remains in effect.

Turbine Control selected to First Stage In, Turbine is off the VPL.

ADDITIONAL LINEUP CHANGES PCV-1 RC-456 Control Switch in Close MOV-1 RC-536 Control Switch in Close FW-P-1 B in P-T-L Swap In-service BAST Tags STICKERS VOND MARKINGS YCT - PCV-1 RC-456 Control Switch YCT - MOV-1 RC-536 Control Switch YCT - FW-P-1 B Control Switch EQUIPMENT STATUS DATWIME 00s 1

TECHNICAL SPECIFICATION(S)

I I

PCV-1 RC-456 FW-P-1 B Yesterday 1500 3.4.1 1.a 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ago NIA SHIFT TURNOVER INFORMATION

1.

PCV-1 RC-456 seat leakage. MOV-1 RC-536 is closed with power maintained per T.S. 3.4.1 1.a.

2.

3.

4.

1 CCT-13 is closed.

5.

6.

7.

FW-P-1 B is 00s to replace motor leads and is expected to return within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

AOP-1/2.75.2 is in effect. River water level is 671 feet and stable. Cooling Tower Pump House level is being logged on the Outside Operator Tour.

FCV-RN-150A and 150B have been restored to normal operation.

FCV-MS-1 OOB and 1 OOD, MSR Purge Valves are open.

Main Feedwater Regulating Valves are controlling SG levels in Auto.

i

[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I

8.

9.

Train 6 is the Protected Train Raise power to 60% at 12%/hr. after an extended outage to repair cooling tower pumps.

SCENARIO SUPPORT MATERIAL REQUIRED 1 OM-52.4.A, Raising Power From 5% To Full Load Operation Reactivity Plan for 12YHr Power Ascension Protected Train B Wall Plaque BVPS - 1 NRC Scenario 3 3 of 28

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #1 Raise Power To 60%

Conversion Economics requests raising power to 60% at 12%/hr.

US directs power increase to 60% per 1 OM-52.4.A, Step IV.F.19.

Crew reviewdagrees with reactivity plan. US approves for use. Crew begins power increase.

RO initiates dilution per 1 OM-7.4.N, Step 1V.A.

Estimate the volume of makeup water to be added to the RCS using any of the following:

a. 1 OM-7.5, Figure 7-9, Boron Dilution, AND Table 7-1,

Nomograph Correction Factors

b. WAG tables

c. Reactor Engineering approved computer based methods BVPS - 1 NRC Scenario 3 4 of 28

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Estimate the rate of boron concentration change as a function of dilution water flow using 1 OM-7.5, Figure 7-1 0, Boron Dilution Rate, AND Table 7-1, Nomograph Correction Factors.

Place the 1 MU switch in Stop for greater than 1 second to allow the blender to unarm.

Place 43/MU control switch to DIL OR ALT DIL as directed by the SWUS.

Set AM-1 CH-114, Blender Total Flow Set Point to the desired flow rate.

Set blender output Integrator YIC-1 CH-168A to the desired quantity.

a. Reset blender output integrator YIC-1 CH-168A.

Log the flow totalizer indication, AND add to it the number of gallons set into the batch integrator.

BVPS - 1 NRC Scenario 3 5 of 28

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Turbine load and reactor power increasing at 12Ydhr.

Start the reactor makeup control system by placing 1 MU control switch to Start.

Operate pressurizer heaters to initiate automatic spray operation as required so that the difference in boron concentration between the RCS and pressurizer is e 50 ppm.

Verify dilution automatically stops when blender output integrator YIC-1 CH-168A reaches the setpoint.

When dilution is complete, perform the following:

a.

b.

C.

d.

e.

Place 1 MU control switch in Stop for greater than 1 second.

Place the 4WMU control switch to AUTO.

Reset blender output integrator Place the 1MU switch to Start.

Adjust makeup controls for the new RCS boron concentration.

YIC-1 CH-168A.

BVPS - 1 NRC Scenario 3 6 of 28

m u) n m

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #2 Train A RW Pump Trips; Backup Pump Manual Start start.

1 WR-P-1 A trips, 1 WR-P-1 B fails to auto When directed, insert the following command:

Annunciators:

IMF AUXlOA (0 0)

[A1 -401, CC WTR HT EXCH River WTR PP Disch Line A Press Low

[Al-481, CC WTR HT EXCH River WTR PP Disch Line 8 Press Low

[A1 -591, Intake Struct River WTR PP Disch Line A Press Low

[A1 -671, Intake Struct River WTR PP Disch Line 6 Press Low BOP recognizes loss of 1 WR-P-1 A and reports to US.

US refers to AOP-1.30.2, River Water, Normal Intake Structure Loss.

RO checks reactor plant river water pump status.

[A1 -821, River Water PP Auto Start-Stop RO recognizes and reports 1 WR-P-1 B did not auto start.

1 WR-P-1 B running.

RO manually starts 1WR-P-1 B.

RO checks PI-1 RW-l13A(B), CCR Heat Exchanger RW Pressure > 20 psig.

BVPS - 1 NRC Scenario 3

r INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I NOTE: Do not rack WR-P-1C onto the AE bus.

BVPS - 1 NRC Scenario 3 US directs local operator to rack 1 W R-P-1 C onto bus.

US refers to T.S. 3.7.4.1.

9 of 28 BOP checks turbine plant river water system status.

I I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #3 Loss of 4KV Bus 1AE When directed, insert the following command:

IMF EPS04E (0 0) 1AE bus de-energized, No. 1 EDG fails to auto start.

Annunciators:

[A8-105],4160V Emerg Bus 1 AE ACB 1 A1 0 Auto Trip

[A8-106],416OV Emerg Bus 1AE ACB 1 E7 Auto Trip

[A8-1091, 41 60V Emerg Bus 1 AE U n d e rvo I tag e

[A9-74],48OV Emerg Trans 1 -BN Undervoltage

[A9-100],125V DC Battery Chgr 1 Failure

[A9-108],125V DC Battery Chgr 3 Failure CCR flow indicated to all RCPs.

RHR not in service.

No red or yellow border annunciators in alarm.

Crew responds to indications and alarms.

US enters AOP-1.36.2, Loss Of 4KV Emergency Bus.

BOP checks at least one AC emergency bus is energized.

RO checks at least one charging pump is running.

Crew sounds Standby alarm and announces loss of 4KV 1AE bus.

RO verifies CCR flow to all RCP thermal barriers.

RO checks RHR in service.

Crew responds to color coded annunciators.

BVPS - 1 NRC Scenario 3 10 of 28

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE ]

BOP starts No. 1 EDG to restore power to 1AE bus.

EE-EG-1 running.

ACB 1 E9 closed.

CH-P-1 A running (auto started).

NOTE: Crew may choose to allow CH-P-1 A to auto start and secure CH-P-1 B, or manually start and stop CH-P-1 A.

1WR-P-SA running.

Depress both emergency stop pushbuttons Place selector switch in Exercise position Start EDG No. 1 Ensure EDG speed at 900 rpm Depress field flash pushbutton Close ACB-1 E9 Crew checks associated RPRW pump is running.

. Starts 1 WR-P-SA US refers to T.S. 3.8.1.1 Action c.

BVPS - 1 NRC Scenario 3 11 of 28

1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 EVENT #4 Loss of Feedwater and EDG No. 1 Failure 2 minutes later.

FW-P-1 A trips followed by trip of EE-EG-1 When directed, insert the following command:

Annunciators:

IMF RNMOlA (0 0)

Crew enters E-0.

[A7-371, Steam Generator Feed Pump Auto Stop

[A7-401, Steam Generator Feed Pump Disch Equalizing Press Low

[A7-291, Reactor Trip & Low Tavg or SI Main Feedwater Valve Closed 1 CN-P-1 A and 1 B running. 1 SD-P-1 A and 1 B running.

Reactor power c 65%.

SG levels dropping.

Crew identifies loss of main feedwater pump and SG feed flow.

US enters AOP-1.24.1, Loss Of Main Feedwater.

BOP verifies condensate and heater drain pumps are running.

RO checks reactor power > 65%.

US directs RO to trip the reactor.

US transitions to E-0, and informs crew.

BVPS - 1 NRC Scenario 3 12 of 28

I INSTRUCTIONAL GUIDELINES 1

PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE ]

EVENTS #5.6.7 SG 16 SGTR; MD AFW Pump 6 Fails To Auto Start; CIA Fails To Auto Actuate SG 1 B 500 gpm SGTR (occurs at Step 7 of ES-0.1)

Pre-loaded Commands Crew continues with E-O.

Reactor trip and bypass breakers open.

Power range < 5%.

Neutron flux dropping.

Throttle or governor valves closed.

Main generator output breakers open.

Exciter breaker open.

1 AE bus de-energized; 1 DF bus energized from offsite power.

RO manually trips reactor.

RO verifies reactor trip:

. Reactor trip and bypass breakers open.

Power range indication c 5%.

.. Neutron flux dropping.

BOP verifies turbine trip.

BOP verifies generator trip.

BOP verifies power to AC emergency busses.

. BOP recognizes and reports trip of No. 1 EDG.

BVPS - 1 NRC Scenario 3 13 of 28

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]

E-0 immediate actions complete. SI not actuated and not required.

RO checks if SI is actuated.

Crew enters ES-0.1.

RCS TAVG trending to 547F.

US transitions to ES-0.1, and informs crew.

US directs STA to begin monitoring CSF status trees.

Crew sounds Standby alarm and announces Unit 1 reactor trip.

Check RCS temperature stable at or trending to 547F.

BOP maintains RCS temperature:

. Check at least 1 MSlV open Check condenser available

. Set steam header setpoint slightly above existing steam header pressure Place steam dump controller in Manual Verify demand is zero BVPS - 1 NRC Scenario 3 14 of 28

I INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE I

. Place steam dumps in STM PRESS Mode

=

Place steam dump controller in AUTO

. Adjust controller setpoint to as necessary to maintain RCS temperature CRITICAL TASK #1:

Instrument air pressure > 100 psig.

RCS TAVG < 554F.

MFRV's closed.

No AFW pumps running.

Crew establishes feedwater flow into at least one SG before RCS bleed and feed is required.

Fw-P-2 and FW-P-38 running.

Bypass FRV's closed.

FW-P-1 A tripped. FW-P-1 B out-of-service.

Total feed flow > 355 gpm.

BOP checks station instrument air header pressure > 100 psig.

BOP checks feedwater status.

. RCS TAVG - Less than 554F.

. Verify Main Feedwater Reg Valves closed

. Check AFW Pumps - any running

. BOP manually starts RN-P-2 and FW-P-3B

. Close Bypass FRV's

. Stop all but one main feed pump

. Verify total feed flow > 355 gpm BVPS - 1 NRC Scenario 3 15 of 28

I INSTRUCTIONAL GUIDELINES 1

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 When the crew reaches ES-0.1, Step 7, insert the following:

IMF RCS03B (0 0) 500 All control rods inserted.

PRZR level dropping.

Charging in service.

Letdown in service.

PRZR level dropping.

SG 1 B 500 gpm SGTR PRZR level and pressure dropping.

Crew reenters E-0.

Reactor tripped.

Turbine tripped.

RO verifies all control rods are fully inserted.

RO checks PRZR level > 14%.

RO checks charging is in service.

RO checks letdown in service.

RO verifies PRZR level trending to 22%.

RO maintains crew informed of PRZR pressure and level trends.

US directs RO to actuate SI and transitions to 4.

RO reverifies reactor trip.

BOP reverifies turbine trip.

BVPS - 1 NRC Scenario 3 16 of 28

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Main generator tripped.

BOP reverifies generator trip.

1 DF bus energized.

No. 2 EDG running.

SI actuated (both trains).

1 VS-F-4A running.

CH-P-1 A (1 B) running.

BOP reverifies power to AC emergency busses.

BOP verifies No. 2 diesel generator is running.

RO manually actuates SI both trains.

Crew sounds Standby alarm and announces Unit 2 reactor trip and SI.

BOP checks leak collection exhaust fan is running.

US directs starting CNMT hydrogen analyzers.

RO verifies SI status.

. At least two charging pumps running BVPS - 1 NRC Scenario 3 17 of 28

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 BIT flow indicated.

SI-P-1 A and 1 B running.

FW-P-2 and FW-P3B running.

AFW throttle valves open.

AFW flow > 355 gpm.

When directed, insert the following commands:

IMF VLV-AFW02 (0 0) 0 60 MOV-1 Fw-151 B closed.

IMF VLV-Am04 (0 0) 0 60 IMF VLV-AFWO6 (0 0) 0 60 MOW1 FW-151 D closed.

MOV-1 Fw-151 F closed.

NOTE: CRITICAL TASK #2 is performed as part of Attachment 1-K actions. (Refer to page 28)

BVPS - 1 NRC Scenario 3 RCS TAVG controlled on steam dumps.

18 of 28

. BIT flow indicated

. LHSl pumps both running BOP verifies AFW status.

. AFW pumps running

. AFW throttle valves full open Total AFW flow > 355 gpm.

US directs operator to locally close A W Train "A" valves.

BOP performs Attachment 1 -K, Verification of Automatic Actions (Steps listed at end of scenario guideline.)

BOP verifies RCS TAVG stable or trending to 54PF.

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Recirc spray pumps not running.

RO checks recirc spray pump status.

Crew enters E-3.

BVPS - 1 NRC Scenario 3 PCV-1 RC-456 closed, but leaking.

Spray valves closed.

Safety relief valves closed.

PRT conditions normal.

All PORV MOVs open (except MOV-1 RC-536 previously closed).

D/P between RCS pressure and highest SG pressure > 200 psid.

No SG pressures dropping in an uncontrolled manner.

SG 1 B level rising in an uncontrolled manner.

19 of 28 RO verifies PRZR isolated.

PORVs closed Spray valves closed Safety relief valves closed PRT conditions at expected values Power to at least one block valve and at least one open RO checks if RCPs should be stopped.

BOP checks if any SGs are faulted.

BOP checks if SG tubes are intact.

US transitions to E-3, and informs crew.

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I CREVS not actuated nor required.

CIB not actuated.

RM-1 RM-218A 6 not in high alarm.

D/P between RCS pressure and highest SG pressure > 200 psid.

SG 1 B ruptured.

Unexpected rise in NR level.

CRITICAL TASK #3:

Crew isolates feed flow into and steam flow from the ruptured SG and directs operator to close isolation valve@) operated from outside the control room before a transition to ECA-3.1 occurs.

PCV-1 MS-101 B in manual and closed.

HCV-1 MS-104 closed.

FW-P-3B running.

BOP checks if CREVS is actuated.

RO checks if RCPs should be stopped.

Crew identifies ruptured SG.

RO places SG 1 B ADV in manual and closes.

RO verifies residual heat release valve is closed.

BOP verifies at least one MD AFW pump is running.

BVPS - 1 NRC Scenario 3 20 of 28

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I MOV-1 MS-105 closed.

BOP closes MOV-1 MS-105.

EOP pre-emptive action.

1 MS-16 closed.

TV-1 MS-111 B closed.

TV-1 MS-101 B closed.

MOV-1 MS-101 B closed.

NRV-1 MS-101 B closed.

SG 1 B level > 13%.

SG 1 B AFW throttle valves closed. (May have been previously performed.)

Crew dispatches an operator to close TD A M I pump steam supply valve.

BOP verifies steam supply from intact SG.

BOP restarts TDAMI pump.

BOP closes SG 1 B pre-nrtrn drain isolation valves.

BOP closes SG 1 B main steam trip, bypass, and non-return valves.

BOP checks ruptured SG level.

Crew isolates feed flow to SG 1 B.

BVPS - 1 NRC Scenario 3 21 of 28

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 BVPS - 1 NRC Scenario 3 Main feedwater isolated.

SG 1 B pressure > 380 psig.

Instrument air header pressure > 100 psig.

Condenser steam dumps open.

RCS pressure < 1950 psig.

Tavg c 541°F.

22 of 28 BOP checks FWI previously verified.

BOP checks SG 1 B pressure > 380 psig.

BOP checks instrument air header pressure > 100 psig.

US determines target cooldown temperature based on ruptured SG pressure.

US directs STA to trend cooldown rate.

BOP verifies condenser available and initiates cooldown at maximum rate, (or uses SG ADVs).

RO blocks steamline SI when RCS pressure reaches 1950 psig.

BOP defeats TAVG interlock during cooldown.

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I Total AFW flow > 355 gpm or SG level between 25% and 50%.

BOP checks intact SG levels.

PORV's closed; MOV's open (except previously closed MOV-1 RC-536).

SI reset (both trains).

CIA and CIB reset (both trains).

RCS at target temperature.

Station IA pressure > 100 psig.

TV-1 IA-400 open.

CNMT IA pressure > 85 psig.

LHSl pumps previously stopped.

RO checks power to PORV's and block va I ves.

RO resets SI.

RO resets CIA and CIB.

BOP stops RCS cooldown a. aget temperature.

BOP checks if CNMT instrument air is available.

. Station IA header pressure > 100 Psig

. TV-1 IA-400 open

. CNMT IA header pressure > 85 Psig RO checks if LHSl pumps should be stopped.

BVPS - 1 NRC Scenario 3 23 of 28

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Core exit TCs below target temperature.

SG 1 B pressure stable.

Subcooling > 66F.

RCPs 1 A and 1 C running.

PRZR spray valves open.

PRZR PORV open.

Crew checks if RCS cooldown should be stopped.

BOP checks SG 1 B pressure stable or rising.

RO checks subcooling is satisfactory.

RO initiates RCS depressurization.

Check RCPs 1 A and 1 C are running.

Fully open PRZR spray valves Open one PORV Check depressurization method is effective Crew depressurizes until any of the following conditions are satisfied:

. PRZR level > 75%, OR

. RCS subcooling < Att. 6-A, OR

. RCS pressure c ruptured SG pressure, AND BVPS - 1 NRC Scenario 3 24 of 28

I INSTRUCTIONAL GUIDELINES 1

PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE ]

CRITICAL TASK #4:

Crew depressurizes RCS to meet RCS depressurization stopped.

SI termination criteria before water release from the SG safety or atmospheric relief valve.

. PRZR level > 18%

RO closes PORV and spray valves.

Scenario may be terminated upon crew completion of RCS depressurization in E-3.

BVPS - 1 NRC Scenario 3 25 of 28

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I -K, Verification of Automatic Actions E E-EG-1 tripped.

4KV 1AE bus de-energized.

Only CC-P-1 B running.

4KV 1 AE bus de-energized.

Only WR-P-1 B running.

BVPS - 1 NRC Scenario 3 26 of 28 Diesel Generators - BOTH RUNNING.

Check station instrument air header pressure - GREATER THAN 100 PSIG.

Ensure reheat steam isolation:

a. Verify [MOV-1 MS-1 OOA, B]

CLOSED.

b. Reset reheater controller.

Verify CCR Pumps - TWO RUNNING.

Align Neutron Flux Monitoring For Shutdown:

a. Transfer NR-1 NI-45, Nuclear Recorder to operable source and intermediate range displays.

Verify river water system in service.

a. RPRW Pumps - TWO RUNNING.

1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I

b. Check CCR Heat EX RW pressure

- GREATER THAN 20 PSIG.

Check If main steamline isolation required.

a. Check the following:

=

CNMT pressure - GREATER THAN 3 PSIG.

OR

. Steamline pressure - LESS THAN 500 PSIG.

OR

. Steamline pressure high rate of change - ANY ANNUNCIATOR LIT.

Annunciator A7-41 Annunciator A7-49 Annunciator A7-57

b. Verify steamline isolation:

YELLOW SLI marks - LIT.

BVPS - 1 NRC Scenario 3 27 of 28

[

INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Check CIB and CNMT spray status:

Containment pressure - HAS REMAINED LESS THAN 8 PSIG.

CRITICAL TASK #2:

Initiate at least one train of CIA prior to completion of attachment 1 -K.

CIA manually actuated.

4KV Bus 1AE de-energized. 1 DF bus energized.

Verify ESF equipment status:

a. Verify SI status by checking all RED SIS marks - LIT.

b. Verify CIA by checking all ORANGE CIA marks - LIT.

c. Verify FWI by checking all GREEN NVI marks - LIT.

Verify power to both AC emergency busses.

Upon completion, report any discrepancies to SWUS.

BVPS - 1 NRC Scenario 3

RTL# A5.670.M 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:

SUBDIVISION:

SCENARIO TITLWNO.:

COMPUTER CODE FOR L.P.:

License Operator TrainindLicensed Requalification Training Simulator 2005 NRC Initial License Exam 1 LOT6 Scenario No. 4 I

2 I

2-1 7-05 I

I I

I

~

I I

1 INSTRUCTIONAL SETTING:

Simulator APPROXIMATE DURATION:

1.5 Hours PREPARED BY:

REVIEWED BY:

APPROVED FOR IMPLEMENTATION:

Date Date Date BVPS-1 NRC Scenario 4 Page 1 of 25

INITIAL CONDITIONS:

rn rn rn IC-184; PW = NRC4; 75% Power, Equil Xe, RCS boron at 1279 ppm, CB D at 190 steps.

PCV-1 RC-456, PORV leakage. MOV-1 RC-536, Block Valve closed with power maintained.

River water level has receded. Flood watch cancelled on last shift.

1WR-P-1 A, River Water Pump 00s.

Turbine control selected to First Stage Out, Turbine is on the VPL.

PCV-1 RC-456 Control Switch in Close MOV-1 RC-536 Control Switch in Close WR-P-1A in P-T-L I

VOND MARKINGS I

1 ADDITIONAL LINEUP CHANGES 1

STICKERS YCT - PCV-1 RC-456 Control Switch YCT - MOV-1 RC-536 Control Switch YCT - WR-P-1 A Control Switch I

I I

DATUTIME 00s 1

TECHNICAL SPEClFICATION(S)

EQUIPMENT STATUS I

3.4.1 1.a I

Yesterday 1500 I

I PCV-1 RC-456 I W R-P-1 A I

2 days ago I

1 N/A SHIFT TURNOVER INFORMATION

1.

2.

3.

4.

PCV-1 RC-456 seat leakage. MOV-1 RC-536 is closed with power maintained per T.S. 3.4.1 1.a.

1 WR-P-1 A is 00s for motor bearing replacement. WR-P-1 C is in standby on the AE bus.

Protected Train is Train 6.

Raise power to 100% at 12/% per hour. Plant was at reduced power for 1 week due to condenser water box outage.

SCENARIO SUPPORT MATERIAL REQUIRED 1 OM-52.4.8, Load Following Reactivity Plan for 12O/dHr Power Ascension Protected Train B Wall Plaque

1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #1 Raise Power To 100%

NOTE: This event is not required to satisfy the qualitative or quantitative requirements of NUREG-1021, but may be performed at Chief Examiners discretion.

Turbine load and reactor power increasing at 12%/hr.

US directs power increase to 100% per 1 OM-52.4.8, Step IV.B.13.

Crew reviewdagrees with reactivity pian. US approves for use. Crew begins power increase.

BOP initiates turbine load increase.

a.

b.

C.

d.

Set the desired terminal load on the SETTER.

Set the desired rate on the LOAD RATE thumbwheel (5Ymin.

maximum).

As the turbine load increases, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.

Depress the GO pushbutton.

RO initiates RCS dilution as necessary to maintain TAVG - TREF per 1 OM-7.4.N, Step 1V.A.

BVPS 1-NRC Scenario 4 3 of 1

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Estimate the volume of makeup water to be added to the RCS using any of the following:

a. 1 OM-7.5, Figure 7-9, Boron Dilution, AND Table 7-1, Nomograph Correction Factors

b. WAG tables

c. Reactor Engineering approved computer based methods Estimate the rate of boron concentration change as a function of dilution water flow using 1 OM-7.5, Figure 7-1 0, Boron Dilution Rate, AND Table 7-1, Nomograph Correction Factors.

Place the 1 MU switch in Stop for greater than 1 second to allow the blender to unarm.

Place 43/MU control switch to DIL OR ALT DIL as directed by the SWUS.

Set AM-1 CH-114, Blender Total Flow Set Point to the desired flow rate.

BVPS 1-NRC Scenario 4 4 of 1

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 Set YIC-1 CH-l68A, Blender Output Integrator to the desired quantity.

a. Reset Blender Output Integrator YIC-1 CH-168A.

Log the flow totalizer indication AND add to it the number of gallons set into the batch integrator.

Start the reactor makeup control system by placing 1 MU control switch to Start.

Operate pressurizer heaters to initiate automatic spray operation as required so that the difference in boron concentration between the RCS and pressurizer is c 50 ppm.

Verify dilution automatically stops when YIC-1 CH-l68A, Blender Output Integrator reaches the setpoint.

When dilution is complete, perform the following:

BVPS 1-NRC Scenario 4 5 of 1

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I

a.

b.

C.

d.

e.

BVPS 1-NRC Scenario 4 6 of 1 Place 1 MU control switch in Stop for greater than 1 second.

Place the 43/MU control switch to Auto.

Reset YIC-1 CH-l68A, Blender Output Integrator.

Place the 1 MU switch to Start.

Adjust makeup controls for the new RCS boron concentration.

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 EVENT #2 MFW Pump iiB Trip; Load Reduction Required FW-P-16 trips.

When directed, insert the following command:

Annunciators:

IMF FWMO1 B (0 0)

[A7-371, Steam Generator Feed Pump Auto Stop

[A7-391, Steam Generator Feed Pump Disch Flow Hi Start 2d Pump

[A7-45], Steam Generator 1 A Level Deviation from Setpoint

[A7-53], Steam Generator 16 Level Deviation from Setpoint

[A7-61], Steam Generator 1 C Level Deviation from Setpoint Only FW-P-1 A running.

If requested, SM should direct a load reduction at rate of 5Ydminute.

PORVs 455C and 4550 are available.

Crew responds to indications and alarms.

BOP determines that 16 Main Feed Pump is tripped.

US enters AOP-1.24.1 Loss of Main Feedwater.

BOP verifies condensate pumps and heater drain pumps running.

RO determines reactor power is >

65%.

US directs load reduction to 65%

power in accordance with AOP-1.51.l.

Crew alerts plant personnel of emergency shutdown.

Verify PORVs available.

BVPS 1-NRC Scenario 4 7 of 1

1 INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Crew initiates a plant shutdown.

BOP sets turbine load setter at 2% (or 5%) per minute at direction of US.

RO determines required boration using the reactivity plan for rapid power reduction.

BVPS 1-NRC Scenario 4 Reactor power decreasing.

Turbine load decreasing.

Governor valves responding normally.

Control rods in Auto.

8of 1 RO initiates RCS normal or emergency boration at direction of US.

BOP depresses the reference control GO pushbutton.

After the governor valves are off the limiter:

. Transfer turbine control to the 1' stage pressure feedback by depressing the 1" stage IN pushbutton.

. Verify 1 stage OUT lamp is OFF and 1 stage IN lamp is ON.

Verify governor valve movement not excessive during load reduction.

RO places control rods in AUTO and verifies Tavg is within +/- 5F of Tref.

e 0

E 0

a, lu a,

1=

U N

U lu v) lu n c

4-a 8

0 U

u F

2 a,

N a,

c a,

a, lu a,

c U

N U

Q c

a 7

c 0

Q) 0 Q

C v)

L 8

v) n m

1 INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #3 Dropped Control Rod K-6 Insert malfunction following load reduction] after crew has control of SG level and TAVG is within 2F of TREF.

IMF CRF04BV (0 0) 1 Rod K-6 drops due to stationary gripper failure.

Crew responds to indications and alarms.

Annunciators:

[A4-59], NIS Power Range Low Setpoint Flux Deviation or Auto Defeat

[A4-67], NIS Power Range High Setpoint Flux Deviation or Auto Defeat

[A4-681, NIS Power Range Comparator

[A4-76], Computer Alarm Rod Deviation/Seq Rod K-6 dropped.

Control rods in manual.

RCS TAVG

> 541 F and stable.

US refers to AOP-1.1.8, Rod Inoperability.

RO checks only 1 rod dropped.

US confirms 1 control rod dropped.

RO places control bank selector switch in Manual, if in Auto.

Crew checks RCS TAVG

> 541 F, within f 4F of Tref and stable.

US determines power operation may continue if within 1 hour:

. Rod declared inoperable

. Verify shutdown margin requirements of T.S. 3.1.1.1 BVPS 1-NRC Scenario 4 10of 1

I INSTRUCTIONAL GUIDELINES 1

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Power reduced to less than 75%

reduced to less than 85% within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

' Verify shutdown margin once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

' Request RE perform lncore Flux

' High Neutron Flux Setpoint Map As Manager, Operations direct that conditions remain stable while determining cause of rod problem.

Continue with scenario when Technical Specifications have been addressed, or at Chief Examiner's discretion.

BVPS 1-NRC Scenario 4 11 of 1 US requests guidance from Manager, Operations on whether to withdraw misaligned rod.

US may refer to T.S. 3.1.3.1, Action c.3.

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #4 Pressurizer Master Pressure Control Output Fails High When directed, insert the following command:

IOR X07A090P (0 0) 0 600 RC-PK-444A fails in Auto, Manual control available.

Annunciators:

[A4-121, Pressurizer Control Low Pressure Deviation

[A4-11], Pressurizer Control Pressure Low

[A4-51, Pressurizer Power Oper. Relief Valve Open PORV 455C and spray valves open.

PORV and spray valves closed.

PRZR heaters energized.

Crew responds to indications and alarms.

RO takes manual control of PRZR Master Pressure Controller.

RO reduces output of controller to close PORV and spray valves.

RO energizes PRZR heaters, as required.

US refers to T.S. 3.2.5.

BVPS 1-NRC Scenario 4 120f 1

1 INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]

EVENT #5 Feed Flow Transmitter Fails High When directed, insert the following command:

FT-1 FW-497, SG 1 C Channel 3 fails high.

Annunciators:

IMF FWM14F (0 0) 5E6

[A7-581, Loop 3 Feedwater Flow Greater Than Steam Flow

[A7-611, Steam Generator 1 C Level Deviation from Setpoint

[A7-631, Steam Generator 1C Level Low

[A7-641, Loop 3 Steam Flow Greater Than Feedwater Flow FCV-1 Fw-498 closes slowly.

FC-1 FW-498 selected to FM-496 position.

FCV-1 FW-498 in Auto.

Crew responds to indications and alarms.

US refers to 10M-24.4.IF, Instrument Failure Procedure, Attachment 2.

BOP takes manual control of FCV-1 Fw-498 and adjusts SG level, as required.

BOP selects redundant feed flow transmitter for control.

BOP returns FCV-1 Nv-498 to Auto when SG level is stable within normal range.

BVPS 1-NRC Scenario 4 130f 1

1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1

When directed to trip bistables, insert the following:

IOR XSO3C23 (0 0) 1 IMF BST-RCSO58 (0 0) 0 IMF BST-RCS059 (0 0) 0 DOR XSO3C23 Protection Rack 18 door open.

BS-498B tripped.

BS-498C tripped.

Protection Rack 18 door closed.

US contacts I&C to direct tripping of bistables.

US contacts I&C to investigate failure of Fr-1FW-497.

BVPS 1-NRC Scenario 4 140f 1

1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #6 SG 1 C Feedwater Regulating Valve FCV-1 W-498 fails closed. Manual Fails Closed control unsuccessful. Reactor Trip required.

When directed, insert the following command:

Annunciator:

BOP takes manual control of SG 1C Feed Reg Valve.

IMF FWM07C (0 0) 0 120

[A7-611, Steam Generator 1 C Level Deviation From Setpoint US determines FRV failure is not recove ra b I e.

Crew enters E-0.

BVPS 1-NRC Scenario 4 Reactor trip and bypass breakers open.

Power range < 5%.

Neutron flux dropping.

Throttle or governor valves closed.

15of 1 US directs RO to manually trip reactor and enters E-0.

RO verifies reactor trip:

. Reactor trip and bypass breakers open.

Power range indication < 5%.

. Neutron flux dropping.

BOP verifies turbine trip.

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Crew enters ES-0.1.

BVPS 1-NRC Scenario 4 Main generator output breakers open.

Exciter circuit breaker open.

1 AE and 1 DF busses energized by offsite power.

SI not actuated and not required.

160f 1 BOP verifies generator trip.

BOP verifies power to AC emergency busses.

RO checks if SI is actuated.

US transitions to ES-0.1, and informs crews US directs STA to begin monitoring CSF status trees.

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTED STUDENT RESPONSE I EVENT #7 Main Steam Line Break With MSlV Failure Steam break downstream of MSlV B.

When directed, insert the following command:

IMF MSS02B (0 0) 1E7 Preloaded command for MSlV failure.

RCS temperature dropping.

CRITICAL TASK #1:

Steam dump valves closed.

Crew manually actuates main steam line isolation before a Sever (orange path) challenge develops to either the Subcriticality or Integrity CSF or before transition to ECA-2.1, whichever occurs first.

MOV-1 MS-1 OOA, B closed.

SG blowdown valves closed.

AFW flow throttled to e 355 gpm.

SG 1 B MSlV open.

SI actuated.

Crew reenters E-0.

BVPS 1-NRC Scenario 4 170f 1 Crew sounds Standby alarm and announces Unit 1 reactor trip.

RO checks RCS temperature stable at or trending to 547F.

9 Stop dumping steam Verii reheat steam isolation Verify SG blowdown isolated.

. Throttle total feed flow > 355 gpm.

Close valves with YELLOW SLI marks US directs SI initiation or SI actuates.

US re-enters E-0, and informs crew.

1 INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Reactor tripped.

Turbine tripped.

Main generator tripped.

1 AE and 1 DF busses energized.

SI actuated (both trains).

1 VS-F-4A running.

RO reverifies reactor trip.

BOP reverifies turbine trip.

BOP reverifies generator trip.

BOP reverifies power to AC emergency busses.

BOP manually actuates both SI trains.

Crew sounds Standby alarm and announce Unit 1 reactor trip and SI.

BOP checks leak collection exhaust fan running.

US directs starting CNMT hydrogen analyzers.

BVPS 1-NRC Scenario 4 180f 1

1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I RO verifies SI status.

. Two charging pumps running CH-P-1 A and CH-P-1 B running.

BIT flow indicated.

. BIT flow indicated SI-P-1A and 1 B running.

LHSl pumps both running BVPS 1-NRC Scenario 4 FW-P-3A, 38 and FW-P-2 running.

All SG AFW throttle valves open.

Total AFW flow > 355 gpm.

TAVG stabilizing after MSlV closure.

Recirc spray pumps not running.

19of 1 BOP verifies AFW status.

AFW pumps running

. AFW throttle valves full open.

. Total AFW flow > 355 gpm BOP performs Attachment 1 -K, Verification of Automatic Actions (Steps listed at end of scenario guideline.)

BOP verifies RCS Tavg stable or trending to 547pF.

RO checks recirc spray pump status.

[ INSTRUCTIONAL GUIDELINES

[

PLANT STATUS OR RESPONSE

[ OBJECTIVE I EXPECTED STUDENT RESPONSE 1 RO checks PRZR isolated.

PCV-1 RC-456 closed, but leaking.

Spray valves closed.

Safety relief valves closed.

PRT conditions normal.

All PORV MOVs open (except MOV-1 RC-536 previously closed).

D/P between RCS pressure and highest SG pressure > 200 psid.

No SG pressures dropping in an uncontrolled manner.

No SG levels rising in an uncontrolled manner.

CNMT radiation, pressure and sump levels at pre-event values.

PORVs closed Spray valves closed Safety relief valves closed PRT conditions at expected values Power to at least one block valve and at least one open RO checks if RCPs should be stopped.

BOP checks if any SGs are faulted.

BOP checks if SG tubes are intact.

RO checks if RCS is intact.

Crew checks if SI flow should be reduced.

BVPS 1-NRC Scenario 4 20 of 1

I INSTRUCTIONAL GUIDELINES 1

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]

Crew enters ES-1.l, if SI Termination criteria is satisfied.

SI reset (both trains).

CIA and CIB reset (both trains).

One HHSI pump running.

RCS pressure rising.

US transitions to ES-1.1, and informs crew.

RO resets SI.

RO resets CIA and CIB.

RO stops one HHSl pump.

RO check RCS pressure stable or rising.

CRITICAL TASK #2:

Crew stops HHSl injection prior to water relief through the Pressurizer PORVs.

MOV-SI-867A and 8678 shut.

MOV-SI-867D and 8670 shut.

FCV-1 CH-122 closed.

MOV-1 CH-310 open.

RO isolates the BIT.

. Close MOV-1 SI-867A, 6 I

. Close MOV-1 SI-867C, D RO establishes normal charging flow.

Close FCV-1 CH-122

. Open MOV-1 CH-310 BVPS 1-NRC Scenario 4 21 of 1

I INSTRUCTIONAL GUIDELINES 1

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I MOV-1 CH-289 open.

FCV-1 CH-122 output adjusted.

Open MOV-1CH-289 Adjust FCV-1 CH-122 to maintain PRZR level RO controls charging flow to maintain PRZR level.

Scenario may be terminated after BIT is isolated and normal charging flow is established.

BVPS 1-NRC Scenario 4 22 of 1

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Attachment l-K, Verification of Automatic Actions Diesel Generators - BOTH RUNNING.

Check station instrument air header pressure - GREATER THAN 100 PSIG.

Ensure reheat steam isolation:

a. Verify [MOV-1 MS-1 OOA, B]

CLOSED.

b. Reset reheater controller.

Verify CCR Pumps - TWO RUNNING.

Align Neutron Flux Monitoring For Shutdown:

a. Transfer NR-1 NI-45, Nuclear Recorder to operable source and intermediate range displays.

Verify river water system in service.

a. RPRW Pumps - TWO RUNNING.

BVPS 1-NRC Scenario 4 230f 1

I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1

b. Check CCR Heat EX RW pressure

- GREATER THAN 20 PSIG.

Check If main steamline isolation required.

a..

m Check the following:

CNMT pressure - GREATER THAN 3 PSIG.

OR Steamline pressure - LESS THAN 500 PSIG.

OR Steamline pressure high rate of change - ANY ANNUNCIATOR LIT.

Annunciator A7-41 Annunciator A7-49 Annunciator A7-57

b. Verify steamline isolation:

. YELLOW SLI marks - LIT.

BVPS 1-NRC Scenario 4 24 of 1

1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE ]

Check CIB and CNMT spray status:

Containment pressure - HAS REMAINED LESS THAN 8 PSIG.

Verify ESF equipment status:

a. V e r i SI status by checking all RED SIS marks - LIT.

b. Verify CIA by checking all ORANGE CIA marks - LIT.

c. Verify Fwl by checking all GREEN FWI marks - LIT.

Verify power to both AC emergency busses.

Upon completion, report any discrepancies to SWUS.

BVPS 1-NRC Scenario 4 25 of 1

ML051240145

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