ML051030217

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Draft - Section C Operating (Folder 2)
ML051030217
Person / Time
Site: Beaver Valley
Issue date: 12/27/2004
From: Hynes C
FirstEnergy Nuclear Operating Co
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
Download: ML051030217 (91)
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Text

RTL# A 5 . 6 7 0 . M 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: License Operator TrainingILicensed Requalification Training SUBDIVISION: Si mu1ator SCENARIO TITLWNO.: 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 2LOT5 Scenario No. 2 I

I Revision No.

1 I

I Date 12-7-04 II Revision No. Date INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hours PREPARED BY:

Date REVIEWED BY:

Date APPROVED FOR IMPLEMENTATION:

Date BVPS-2 NRC Scenario 2 Page 1 of 21

INITIAL CONDITIONS: IC-159; PW = NRC4; 75/0Power, RCS boron at ______. ppm.

a 2RCSPCV455D leakage. 2RCS*MOV537, Block Valve closed with power maintained a River water level has receded. Flood watch cancelled on last shift.

rn 2SWS*P21A, Service Water Pump 00s.

I Turbine control selected to IMP In.

I ADDITIONAL LINEUP CHANGES I STICKERS I VOND MARKINGS I

EQUIPMENT STATUS DATEJTIME 0 0 s TECHNICAL SPECIFICATION(S) 1 2RCS*PCV455D I

I I

Yesterday 1500 I I

3.4.11.a I I

SHIFT TURNOVER INFORMATION

1. Continue raising power to 100% at 12/% per hour.
2. Protected Train is Train B.

SCENARIO SUPPORT MATERIAL REQUIRED 20M-52.4.BI Load Following Reactivity Plan for 12%/Hr Power Ascension Protected Train BWall Plaque

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 EVENT #1 Raise Power US directs power increase to 100% per 20M-52.4.B, Step IV.A.5.

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

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

PO initiates turbine load increase.

a. Set the desired turbine load on the EHC SETTER.
b. Set the LOAD RATE thumbwheel to the desire rate (5 percentlminute maximum).

Turbine load and reactor power c. Depress the GO pushbutton on the increasing at 12%/hr. Turbine EH Control station.

RO initiates RCS dilution as necessary to maintain TAvCj - TRHper 20M-7.4.L, Step 1V.A.

Obtain the RCS boron concentration.

BVPS 2 - NRC Scenario 4 3 of 23

I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Place the boric acid blender control switch in the Stop position.

Set 2CHS*FCV114A, Primary Grade Water to Boric Acid Blender to the desired flowrate as determined on Figure 7-47 in 20M-7.

Set 2CHS*FCV114A as follows:

Desil-edFlowRate Pot Setting =

16gpm Set the total makeup from blender flow totalizer to the total volume in gallons of makeup water to be added using one of the following:

a. 20M-7, Figure 7-46, Boron Dilution
b. WAG Tables
c. Current reactivity plan
d. Reactor Engineering approved computer based methods Ensure 2CHS-FQIS113, Boric Acid Flow To Blender Totalizer is set to zero.

BVPS 2 NRC Scenario 4 4 of 23

i I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Place the makeup mode selector switch in the Dilute OR Manual position.

To initiate a dilution, place the boric acid makeup control switch to the Start position.

Verify the following:

a. 2CHS*FCV114B opens OR open if mode selector switch was in Manual.
b. Verify correct flowrate on 2CHS-FRI 13.

Operate pressurizer heaters to automatically initiate spray as required to equalize boron concentration between coolant loops and pressurizer to within 50 ppm.

When the dilution is complete, Place the makeup control systems in automatic in accordance with 20M-7.4.J, Blender Automatic Makeup Operations.

BVPS 2 NRC Scenario 4 5 of 23

i 1 INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #2:

B MFW Pump Trip; Load 2FWS-P21 B trips Crew responds to indications and Reduction alarms.

When directed, insert the following Annunciators:

command: [A6-1OA], SG 21 A(21 B) Feed Pump Trip IMF PMP CFWOOS (0 0) 1 [A6-9E], SG 21A level Deviation From PO determines that 21B Main Feed Setpoint Pump tripped.

[A6-1OE], SG 218 Level Deviation From Setpoint

[A6-11El1 SG 21C Level Deviation From US refers to AOP-2.24.1, Loss Of Main Setpoint Feedwater.

[A6-8BIIStm Gen Feed Pump 21N B Recirc Valve Trouble PO verifies condensate pumps, heater drain pumps, and separator drain receiver drain pumps running.

Only 2FWS-P21A running. RO determines reactor power is >

65%.

If requested, SM should direct a US directs load reduction to 65%

load reduction at rate of 5%/minute. power at 5% per minute in accordance with AOP-2.51.l.

Crew alerts plant personnel of emergency shutdown.

PORVs 455C and 456 are available. Verify PORVs available.

BVPS 2 - NRC Scenario 4 6 of 23

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

Crew initiates a plant shutdown.

PO sets turbine load setter at 5O/6 per minute.

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

RO initiates emergency borating by performing 20M-7.4.Q Emergency Boration.

Turbine load decreasing. PO depresses the reference control GO pushbutton.

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

PRZR heaters energized. RO places all PRZR heaters to On.

Maintain valve position limit at 5%

above existing turbine load during the load reduction.

BVPS 2 NRC Scenario 4 7 of 23

[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #3 Dropped Control Rod Rod K-6 drops due to stationary gripper failure.

Insert malfunction following load Crew responds to indications and reduction, after crew has control of alarms.

SG level and TAvais within 2F of TREF. Annunciators:

IMF CRF03-K6 (0 0 ) 0 [A4-5H], NIS Power Range High/Low SP Flux Deviation Auto Defeat

[A4-4F], NIS Power Range Comparator US refers to AOP-2.1.8, Rod Deviat ion Inoperability.

[A4-9F], Rod at Bottom

[A4-8G], Rod Position Deviation RO checks only 1 rod dropped.

Rod K-6 dropped. US confirms 1 control rod dropped RO places control bank selector switch in Manual.

RCS TAV(; > 541 F and stable. Crew checks RCS T A V G > 541 F, within

+/- 4F of Tref and stable.

US determines power operation may continue if within 1 hour:

. Rod declared inoperable

. Verify shutdown margin requirements of TS 3.1.1.1

. Power reduce to less than 75%

BVPS 2 - NRC Scenario 4 8 of 23

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

. High Neutron Flux Setpoint reduced to less than 85% within 4

. hours Verify shutdown margin once per

. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Request RE perform lncore Flux Map As Manager, Operations direct that US requests guidance from Manager, conditions remain stable while Operations on whether to withdraw determining cause of rod problem. misaligned rod.

Continue with scenario when US may refer to Technical Technical Specifications have Specification 3.1.3.1 Action c.3.

been addressed.

BVPS 2 - NRC Scenario 4 9 of 23

I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 EVENT #4 Pressurizer Master Pressure 2RCS-PK444A fails in Auto, Manual Control Output Fails High control available.

When directed, insert the following Crew responds to indications and command: Annunciators: alarms.

IMF CNH-PCS1OB (-1 0) 100 [A4-1D], Pressurizer Control Pressure High/Low

[A4-1E], Pressurizer Control Press RO takes manual control of PRZR Deviation High/Low Master Pressure Controller

[A4-1 F], Pressurizer PORV Open Permissive Spray valves open. RO reduces output of controller to close PORV and spray valves.

PORV 45% opens.

PRZR heaters energized.

US refers to TS 3.2.1.

BVPS 2 NRC Scenario 4 10 of 23

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE EXPECTED STUDENT RESPONSE 7 EVENT #5 Feed Flow Transmitter Fails High 2FWSFT476, SG 21 A Channel 4 fails high slowly.

When directed, insert the following Crew responds to indications and command: ala rrns.

Annunciators:

IMF XMT-CFW051A (0 0) 5 [A6-9F], Loop A Feedwater Flow >

Steam Flow

[A6-9H], Loop A Steam Flow > US refers to 20M-24.4.IFI Attachment Feedwater Flow 2.

2FWS*FCV478 slowly closes. PO takes manual control of SG 21 A Feed Reg Valve and adjusts SG level, as required.

PO verifies SG 21A feedwater flow signal selector in the FT477 position.

When directed, insert the following:

IOR XC11083F (0 0 ) 0 2FWS-FR478 selected to FT474 US directs placing SG 21A steam flow position. signal selector in the FT474 position.

US declares SG 21A NR LT476 channel inoperable.

BVPS 2 NRC Scenario 4 11 of 23

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I 2FWSFCV478 in Auto. PO returns SG 21 A Feed Reg Valve to Auto when SG level is stable within normal range.

When directed to trip bistables, US directs tripping bistables.

insert the following:

IRF LOA-PCS003 (0 0) 1 Protection Rack C3 door open.

IMF BST-PCS038 (0 0 ) 0 2LS/476A (BS-I) SG LO LO level tripped.

IMF BST-PCSO29 (0 0 ) 0 2LS/476C (BS-1) SG HI HI level tripped IRF LOA-PCS003 (0 0 ) 0 Protection Rack C3 door closed US contacts I&C to investigate failure of 2FW S*FT476.

BVPS 2 NRC Scenario 4 12 of 23

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

EVENTS #6 SG 21 A Feedwater Regulating 2FWS'FCV478 fails closed. Manual Valve Fails Closed control unsuccessful. Reactor Trip required.

When directed, insert the following PO takes manual control of SG 21A command: Feed Reg Valve.

IMF CNH-CFW1OA (0 0) 0 120 US determines FRV failure is not recoverable.

Crew enters E-O. US directs RO to manually trip reactor and enters E-0.

RO verifies reactor trip:

[A5-6D] lit. [A5-6D] lit.

Power range < 5%. Power range indication < 5".

Neutron flux dropping. . Neutron flux dropping.

Throttle or governor valves closed. PO verifies turbine trip Main generator output breakers open. PO verifies generator trip.

Exciter breaker open.

BVPS 2 NRC Scenario 4 13 of 23

1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I 2AE bus de-energized, 2DF bus PO verifies power to AC emergency energized by offsite power. busses.

SI not actuated and not required. RO checks if SI is actuated.

Crew enters ES-0.1. US directs transition to ES-0.1.

US directs STA to begin monitoring CSF status trees.

BVPS 2 NRC Scenario 4 14 of 23

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I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I EVENTS #7 Main Steam Line Break With MSlV Steam break downstream of SG 21 B Failure MSIV.

When directed, insert the following Crew sounds Standby alarm and command: announces Unit 1 reactor trip.

IMF MSS03 (0 0 ) 1E7 Preloaded command for MSlV RCS temperature dropping. RO checks RCS temperature stable at failure. or trending to 547F.

CRITICAL TASK #1: Steam dump valves closed. . Stops dumping steam Close MSIVs prior to an Orange condition on the Integrity CSF 2MSS-MOV1OOA, B closed. . Verify reheat steam isolation status tree.

SG blowdown valves closed. . Verify SG blowdown isolated.

AFW flow throttled to < 340 gpm. . Throttle total feed flow > 340 gpm.

SG 21 B MSlV closed. PO recognizes continuing cooldown and initiates SLI.

SI actuated. US directs SI initiation or SI actuates.

Crew re-enters E-0. US re-enters E-0 and announces entry to crew.

BVPS 2 - NRC Scenario 4 15 of 23

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

Reactor tripped. RO reverifies reactor trip.

Turbine tripped. PO reverifies turbine trip.

Main generator tripped. PO reverifies generator trip 2AE and 2DF busses energized PO reverifies power to AC emergency busses.

SI actuated. RO manually actuates both SI trains.

RO/PO sound Standby alarm and announce Unit 2 reactor trip and SI.

2HVS*FN204NB running. PO checks leak collection filtered exhaust fan running.

2CHSPZl A and 21 B running. RO verifies two Charging/HHSI pumps are running.

HHSl flow indicated. RO verifies HHSl flow indicated.

BVPS 2 - NRC Scenario 4 16 of 23

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

LHSl pumps running. RO/PO check both LHSl pumps are running.

PO verifies AFW status:

2FWEiP23B running. . Manually starts 2FWE*P23B AFW throttle valves full open. . AFW throttle valves full open AFW flow >340 gpm. . Total AFW flow > 340 gpm.

PO performs Attachment A-0.1 1 Verification of Automatic Actions.

(Steps listed at end of scenario guideline.)

TAVG stabilizing after MSlV closure. RO check RCS TAVG stable at or trending to 547*F.

Recirc spray pumps off. RO checks recirc spray pumps are running.

PORVs closed. RO verifies PRZR is isolated.

Spray valves at zero demand Safety valves closed.

BVPS 2 NRC Scenario 4 17 of 23

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I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I One HHSl pump running. RO stops one HHSl pump.

RCS pressure is rising. RO checks RCS pressure stable or rising.

CRITICAL TASK #2:

Stop ECCS prior to water relief 2SIS*MOV867A, B, C, D closed RO closes high head SI cold leg through Pressurizer PORVs. injection valves.

2CCS-AOV118 open. PO establishes domestic water system cooling to station air compressors.

Station air compressors running PO checks station air compressors are running.

21AC-MOV130 and 131 open. PO establishes instrument air to CNMT.

Instrument air header pressure > 85 PO checks instrument air header psig. pressure > 85 psig.

2CHS+FCVl22closed. RO establishes normal charging flow.

2CHS*MOV310 open.

2CHS*MOV289 open.

BVPS 2 NRC Scenario 4 19 of 23

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[ INS!! e ,dCTIONAL GUIDELINES I PLANT STATUS OR RES .dSE I OBJECTIVE l _l_ - I EXPECTEDS-fEEm 2 ATTACHMENT A-0.1 1, Verification Of Automatic Actions Diesel generators - BOTH RUNNING Ensure reheat steam isolation:

a. Verify 2MSS-MOV1OOA, B closed.
b. Reset reheater controller Check If main steamline isolation required.
a. Check if any of the following exists:

. CNMT pressure - GREATER THAN 3 PSIG.

OR

. SG steam pressure - LESS THAN 500 PSIG.

OR

. Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS.

b. Verify steamline isolation:

. YELLOW SLI marks - LIT BVPS 2 NRC Scenario 4 21 of 23

rA INSThdCTIONAL GUIDELINES I PLANT STATUS OR RESF.( ;E I OBJECTIVE I EXPECTED STUDENT RESPT

- -J Establish domestic water system cooling to station air compressors:

a. Open 2CCS-AOVI 18
b. Check station air compressors -

ONE RUNNING.

Check CCP Pumps - AT LEAST ONE RUNNING.

Align neutron flux monitoring for shutdown:

a. Transfer 2NME-NR45 Nuclear Recorder to operable source and intermediate range displays.

NOTE: The RSS pumps will not Check CIB and CNMT spray status.

start until 10.5 minutes after the CIB signal is initiated.

Containment pressure - HAS REMAINED LESS THAN 8 PSIG.

Verify service water system in service:

a. Service Water Pumps - TWO RUNNING (ONE PUMP PER TRAIN).

BVPS 2 NRC Scenario 4 22 of 23

_- I _-

OBJECTIVE J EXPECTEDSTUEEWKC~ 2 7

b. Service water header pressure -

GREATER THAN 55 PSIG.

c. SWS Pumps seal water pressure -

NOT LOW.

Verify both CNMT hydrogen analyzers

- RUNNING.

a. Verify CNMT hydrogen analyzer 2HCS*SOVl OOA, B1, CNMT Sample amber light - LIT.

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 SM/US.

BVPS 2 NRC Scenario 4 23 of 23

RTL# A5.670.AA 1/2-ADM- 1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: License Operator Training/Licensed Requalification Training SUBDIVISION: Simulator SCENARIO TITLWNO.: 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 2LOT5 Scenario No. 1 Revision No. Date 1 Revision No. 1 Date -1 12-7-04 I

1 INSTR UCT 10NAL SETTING : Si muIat or APPROXIMATE DURATION: 1.5 Hours PREPARED BY:

Date REVIEWED BY:

Date APPROVED FOR IMPLE MENTATION:

Date BVPS - 2 NRC Scenario 1 Page 1 of 26

i INITIAL CONDITIONS: . IC-181, P w = NRC1; 100% Power, RCS Boron ppm 2CHS*P21C, HHSKharginy Pump 00s for repair.

. 2RCS*PCV455D leakage. 2RCS*MOV537, Block Valve closed with power maintained

. Flood warnings from heavy rains.

Maintenance investigating 2SWS*P21A, Service Water Pump vibration/noise.

I ADDITIONAL LINEUP CHANGES I STICKERS I VOND MARKINGS I

I EQUIPMENT STATUS 1 DATUTIMEOOS I TECHNICA L S PECIFICAT10N( S )

I I 2RCS*PCV455D I Yesterday 1500 I 3.4.11.a I

SHIFT TURNOVER INFORMATION

1. 2SWS*P21A, Service Water Pump is operable, but abnormal vibratiodnoise is under investigation.
2. AOP-1/2.75.2 is in effect. River water level is currently 671 feet and stable.
3. Train B is the protected train.
4. Initiate a power reduction to 75% to remove a condenser waterbox from service for cleaning.

SCENARIO SUPPORT MATERIAL REQUIRED 20M-52.4.B, Load Following Reactivity Plan for 120;o/Hr Power Reduction Protected Train B Wall Plaque

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STlJDENT RESPONSE 1 EVENT #1 Reduce power to 759; at 12% per US directs load reduction in hour accordance with Reactivity Plan PO initiates load reduction per 20M-52.4.B, Step IV.B.2.

At the rate specified by the SM/US, reduce load as follows:

a. Set the desired turbine load on the EHC SETTER.
b. Set the LOAD RATE thumbwheel to the desired rate (5 percent/

minute maximum).

Turbine load and reactor power c. Depress the GO pushbutton on the decreasing at 12%/hr. Turbine EH Control Station.

d. As load is reduced, perform the following:
1) Maintain Median Selected TAVG within 2eF of Tref.
2) Maintain indicated axial flux difference within Target Band of COLR and Curve Book AFD Limits Curve.
3) Maintain control rods above their insertion limits as defined in the COLR Fig. 1.

BVPS 2 NRC Scenario 1 3 of 26

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

4) As the turbine load reduces, Maintain the valve position limiter at 5 percent above turbine load to prevent load excursions.

RO initiates RCS boration as necessary to maintain Tavg - Tref per 20M-7.4.K, Step 1V.A and reactivity plan.

Place the Boric Acid Makeup Blender Control switch in the Stop position.

Set [2CHS*FCV113A], Boric Acid To Boric Acid Blender, to the flow rate determined on Figure 7-48 in 20M-7.

a. Set [2CHS*FCV113A] as follows:

Pot Setting = Boric Acid Flow 4 GlPm Set 2CHS-FQISll3, Boric Acid To Blender Flow Totalizer to the total volume in gallons of boric acid to be added using one of the following:

a. 20M-7, Figure 7-45, Boron Add ition
b. WAG Tables
c. Current reactivity plan BVPS 2 NRC Scenario 1 4 of 26

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

d. Reactor Engineering approved computer based method Ensure total makeup from blender flow totalizer is zero.

Place the makeup mode selector switch in the Borate OR Manual position.

To initiate boration, place the boric acid makeup control switch to Start position.

An nunciator: Verify the following:

[A2-2E], Boric Acid Blender Inlet/Outlet a. Inservice boric acid transfer pump Deviation from SP starts.

b. 2CHS*FCV113B, Boric Acid Blender Disch to Chg Pumps, Opens OR Open it IF Mode Selector was in manual.
c. Boric acid flow is indicated on 2CHS-FRl13.

Operate pressurizer heaters to automatically initiate spray as required to equalize boron concentration between coolant loops and pressurizer to within 50 ppm.

BVPS 2 NRC Scenario 1 5 of 26

i 1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 When the boration is complete, flush the boration lines for at least 10 seconds with a boric acid concentration equal to the last chemical analysis of RCS boron concentration in accordance with 20M-7.4.N, Blender Manual Makeup Operations.

Place the makeup control system in automatic in accordance with 20M-7.4.J, Blender Automatic Makeup Ope rations.

BVPS 2 NRC Scenario 1 6 of 26

i 1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #2 Turbine Control Valve Failure (Load Rejection) Annunciators:

IMF EHCOG (0 0 ) 65 [A4-3C], Tavg Deviation from Tref Crew acknowledge alarms, notifies US and investigates.

[A4-1D], Pressurizer Control Pressure High/Low

[A4-2F], Pressure Relief Block Crew informs US of the loss of electrical load.

Tavg increasing.

RCS pressure increasing.

MW decreasing. US refers to AOP-2.35.2.

Steam dump valves opening.

Control rods inserting. RO places control rods in AUTO.

Crew sounds standby alarm and announces Unit 2 load rejection.

EHC system normal except for valve PO verifies normal EHC operation.

position limiter.

BVPS 2 NRC Scenario 1 7 of 26

i I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE [ OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Valve position limiter failure, vibration Crew checks if governor valves have and load satisfactory for condition. closed in sequence, checks turbine vibration recorders.

PO identifies VPL failure.

[A4-6D], Delta Flux Outside Target Band RO may initiate boration.

Crew monitors for subsequent load reductions > 90 Mwe.

Generator load > 270 MW and vacuum Crew checks if turbine should be is greater than 27 inches HG. tripped, verifies load is greater than 270 MW and if vacuum is adequate.

Generator output breakers closed. PO verifies if the main generator is on Generator volts, amps, and power factor line.

satisfactory.

Tavg lowering to Tref value. RO checks Tavg-Tref within 2gF Crew may perform actions to US directs I&C to investigate problem recover GV control from the valve with governor valve.

position limiter per 20M-26.4.X.

US checks for load reduction of > 15%

and informs Chemistry, if necessary.

BVPS 2 NRC Scenario 1 8 of 26

1 INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 SM direction, if requested by US, 2CNM-AOV100 closed Crew checks 2CNM-AOV100 closed not to lower turbine load.

Supervisory limits-normal. PO monitors all turbine supervisory limits. Refers to 20M-25.4.ABD.

Continue with scenario when Crew should review Tech. Specs 3.2.5, limiter problem is identified and 3.1.3.6 for compliance.

Tavg-Tref are matched, or at Examiners discretion.

US will review T.S. 3.4.8 for RCS sampling requirements if power changed by >15%.

BVPS 2 NRC Scenario 1 9 of 26

1 INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #3 Pressurizer Pressure Transmitter RO notes alarm, informs US. Crew PT-445 Fails High Slowly refers to ARPs, if necessary.

Insert the following:

IMF XMT-RCS031A (0 0 ) 2500 120 Annunciators:

[A4-1D], Pressurizer Control Pressure US refers to 20M-6.4.IF, Attachment 2.

High/Low

[A4-1F], Pressurizer PORV Open permissive

[A4-2E], Pressurizer Control Press High RO closes PORVs 456 and 455D.

PORV Actuation

[A4-A1], Pressurizer Power/Safety Relief Trouble PORV 455D and 456 open. RO closes PORVs.

US refers to Technical Specifications.

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

T.S. 3.4.11.a may be referenced, but PORV remains operable in manual, capable of being cycled.

BVPS - 2 NRC Scenario 1 10 of 26

1 INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I EVENT #4 SG Pressure Transmitter PT-476 Fails Low Annunciators:

IMF XMT-MSS047A (-1 0) 0 30 [A6-9C], Loop A Steamline High Rate of Crew responds per ARPs.

Pressure Change

[A6-9F], Loop A Feedwater Flow >

Steam Flow

[A6-9G], Loop A Steamline Pressure Low SG 21AChannel 3 2MSS*PT476 fails low.

SG 21 A channel 3 steam flow drops (density compensation input).

SG 21Afeed flow, NR level drops. PO notes problem with SG 21A level control, takes manual control of 2FWS*FCV478 and informs US.

2FWSFCV478 modulates closed in automatic.

Loop 1 steamline pressure feed flow >

steam flow alarms.

BVPS - 2 NRC Scenario 1 11 of 26

1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I NOTE: Level deviation is SG 21 A level deviation. Crew determines that steam pressure dependent on time of channel 2MSS*PT476 failed low.

establishing normal MFRV control to restore SG level.

US refers to 20M-24.4.IF, Attachment 4.

U S directs PO to restore SG 21A level to program level.

IOR XC11083F Channel 3 steam flow locally selected. US directs selecting redundant channel for 21 A SG steam flow signal (FT-477).

NR level = 44%. US directs PO to return feedwater control to AUTO when SG level is within normal range.

US refers to T.S. 3.3.2.1 and identifies 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> requirement to place channel in the tripped condition.

Action to trip bistables:

IRF LOA-PCS003 (0 0) 1 Protection Rack C3 Door open. US directs crew to trip associated bistables per 20M-24.4.IF, Attachment 4 Table 1.

IMF BST-PCS038 (0 0) 0 2LS/476A (BS-1) Low-Low Trip.

BVPS 2 NRC Scenario 1 12 of 26

{ i I 1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I IMF BST-PCS029 (0 0) 0 2LS/476C (6s-2)High-High FWI.

IRF LOA-PCSOOS (0 0) 0 Protection Rack C3 Door closed.

IRF LOA-PCS004 (0 0) 1 Protection Rack C4 Door Open.

IMF BST-PCS077 (0 0) 0 2PS/476A (6s-1)Low Pressure SI and SLI.

IMF BST-PCSO68 (0 0) 0 2PS/476B (6s-2) High Pressure Rate SLI IRF LOA-PCS004 (0 0) 0 Protection Rack C4 Door closed.

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

Insert PRIOR to next event:

Condenser Steam Dumps Failure IOR XC210790 (0 0) 1 When bistables have been tripped and malfunction is inserted, continue with next event.

BVPS - 2 NRC Scenario 1 13 of 26

i I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #5,6, & 7 Turbine Trip - Steam Dump failure Reactor Trip required; Auto and manual Reactor Trip Failure; A SG ADV fails partially open When directed, insert the following:

IMF EHC07 (0 0 ) Turbine trips. US directs a manual reactor trip.

RCS pressure and Tavg rising.

ATWS - reactor fails to trip RO places reactor trip switch to Trip.

automatically or when Manual trip is attempted.

Crew identifies that the reactor failed to trip.

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

Crew enters FR-S.l. Control rods remain withdrawn. US enters FR-S.l and announces entry to crew.

Turbine trips. PO presses both turbine trip pushbuttons.

BVPS 2 NRC Scenario 1 14 of 26

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 PO/RO verifies THtl is decreasing.

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

RO drives rods in manual after automatic rod motion stops.

CRITICAL TASK #1: All AFW pumps running. PO verifies AFW status Insert control rods or initiate RCS RO initiates emergency boration of the Boration. RCS.

2CHS*P21A and 6 running. Verifies at least 1 charging pump running SI not actuated. Verifies SI not actuated 2CHS*MOV350 open. . Opens 2CHS*MOV350 Boric acid transfer pump running in fast speed.

. Starts boric acid transfer pump Boration flow > 30 gpm. . Verifies emergency boration flow >

30 gpm Charging flow > 40 gpm. Adjusts [2CHS*FCV122] to establish charging flow > 40 gpm PZR pressure is < 2330 psig. . Checks PZR pressure less than 2330 Psig BVPS 2 NRC Scenario 1 15 of 26

1 INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 US dispatches Operator to locally trip the reactor.

RO/PO alert plant personnel by sounding the standby alarm and announcing ATWS.

PO verifies turbine tripped:

All throttle and governor valves closed.

. All throttle or all governor valves are closed

[2MSS-MOVl OOA, B] closed. All reheat stop or interceptor valves are closed

. Reset reheater controller When directed to locally trip the reactor, insert:

TRG! 30 RTB A open.

RTB B open (30 sec delay).

Control rods drop.

Power decreases. US determines that SI has not actuated.

RO verifies reactor is subcritical:

BVPS 2 NRC Scenario 1 16 of 26

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 Power range indicates i5% Power range channels are less than 5%.

Intermediate range SUR negative. Intermediate range rate indicates a negative startup rate.

RO continues boration, as necessary Crew returns to E-0. US enters E-0 and announces entry to crew.

RO verifies reactor tripped:

Reactor trip and bypass breakers Annunciator A5-6D, Turbine Trip Due open. To Reactor Trip lit Power range indicates < 5%. Power range indication less than 5%.

Nuclear flux decreasing. Neutron flux is dropping Throttle and governor valves PO verifies turbine trip.

closed.

US identifies need to evaluate EPP.

BVPS 2 NRC Scenario 1 17 of 26

i I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Main generator output breakers PO verifies generator trip and exciter circuit breakers open.

2AE and 2DF busses energized. PO verifies power to AC emergency busses.

SI actuated. RO verifies SI actuated and manually actuates SI.

Crew sounds Standby Alarm and announces Unit 2 reactor trip and safety injection.

[2HVS*FN204A/B] running. PO checks leak collection filtered exhaust fan running.

HHSl pumps running with flow RO/PO verify SI system status.

indicated. LHSl pumps running.

MDAFW and TDAFW pumps PO verifies AFW status.

running.

BVPS 2 NRC Scenario 1 18 of 26

i 1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I AFW flow > 340 gpm. PO performs Attachment A-0.1 1, Verification of Automatic Actions. (Steps attached to end of scenario guide.)

TAvc;lowering.

RO check RCS TAVGstable at or trending to 547QF.

SG A ADV stuck open. Verify reheat steam isolation

. Reduce total AFW flow to minimize cooldown

. PO initiates main steam line isolation.

Recirc spray pumps off. RO checks recirc spray pumps running.

PORVs closed. RO checks PRZR isolated.

Spray valves at zero demand.

Safety valves closed.

PRT conditions normal. PRT conditions normal.

RCS to SG DP >185 psid. RO checks if RCPs should be stopped.

BVPS - 2 NRC Scenario 1 19 of 26

1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I SG A faulted and depressurizing Crew checks if any SGs are faulted.

in an uncontrolled manner.

Crew transitions to E-2. US exits E-0, enters E-2 and informs crew.

US directs STA to monitor CSF status trees.

Control Room dampers shut. PO initiates CREVS and verifies system Timers running, control room activated.

pressurizing.

PO commences Attachment A-2.4.

When requested as U1 Operator, PO verifies CREVS actuated in U1 by report CREVS actuation. requesting U1 CREVS status.

All yellow SLI marks lit. Crew verifies steam line isolation.

SG 21 6 and 21C pressures PO checks for any non-faulted SG stable.

BVPS 2 NRC Scenario 1 20 of 26

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

ATTACHMENT A-0.1 1, Verification Of Automatic Actions Diesel generators - BOTH RUNNING.

Ensure reheat steam isolation:

a. Verify 2MSS-MOVI OOA, B closed.
b. Reset reheater controller.

Check If main steamline isolation required.

a. Check if any of the following exists:

. CNMT pressure - GREATER THAN 3 PSIG.

OR

. SG steam pressure - LESS THAN 500 PSIG.

OR

. Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS.

BVPS 2 NRC Scenario 1 23 of 26

I i

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

b. Verify steamline isolation:

. YELLOW SLI marks - LIT Establish domestic water system cooling to station air compressors:

a. Open 2CCS-AOV118.
b. Check station air compressors -

ONE RUNNING.

Check CCP Pumps - AT LEAST ONE RUNNING.

Align neutron flux monitoring for shutdown:

a. Transfer 2NME-NR45 Nuclear Recorder to operable source and intermediate range displays.

NOTE: The RSS pumps will not Check CIB and CNMT spray status.

start until 10.5 minutes after the CIB signal is initiated.

Containment pressure - HAS REMAINED LESS THAN 8 PSIG.

BVPS 2 NRC Scenario 1 24 of 26

[ INSTRUCTIONAL GUIDELINES [ PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Verify service water system in service:

a. Service Water Pumps - TWO RUNNING (ONE PUMP PER TRAIN).
b. Service water header pressure -

GREATER THAN 55 PSIG.

e. SWS Pumps seal water pressure -

NOT LOW.

Verify both CNMT hydrogen analyzers

- RUNNING.

a. Verify CNMT hydrogen analyzer 2HCS*SOV1OOA, B1, CNMT Sample amber light - LIT.

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.

BVPS 2 NRC Scenario 1 25 of 26

cu I

RTL# A5.670.M 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: License Operator Training/Licensed Requalification Training SUBDIVISION: Simu1at or SCENARIO TITLUNO.: 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 2LOT5 Scenario No. 4 1 Revision No. 1 Date Revision No. I Date I 1 I 12-7-04 I INSTR UCTlONAL SETTl NG: SimuIat or APPROXIMATE DURATION: 1.5 Hours PREPARED BY:

Date REVIEWED BY:

Date APPROVED FOR IM PLEMENTAT ION:

Date BVPS-2 NRC Scenario 4 Page 1 of 23

i INITIAL CONDITIONS: . IC-146; PW = NRCZ; 48% power, RCS Boron PPm.

2CHS*P21c 00s.

.. 2RCSPCV455D leakage. 2RCS*MOV537, Block Valve closed with power maintained.

. Flood warnings due to heavy rains.

Maintenance is investigating abnormal noisehibration on 2SWS*P21A, Service Water Pump.

. Turbine Control selected to First Stage In.

ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS I EQUIPMENT STATUS 1 DATUTIMEOOS I T ECHNICA L S PECIFICAT10 N(S)

I I 2RCS*PCV455D I Yesterday 1500 1 3.4.11.a I

SHIFT TURNOVER INFORMATION

1. AOP-1/2.75.2 is in effect. River water level is 671 feet and stable.
2. 2SWS*P21A, Service Water Pump is operable, but investigation of noisehibration is ongoing.
3. Train Bis protected train.
4. Reduce power to take the unit off-line due to circulating water intake clogging.

SCENARIO SUPPORT MATERIAL REQUIRED 20M-52.4.6, Load Following, Step IV.B.5 Reactivity Plan for 12% per hour power reduction Protected Train B Wall Plaque

i I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #1 Reduce Power US directs load reduction in accordance with Reactivity Plan.

PO initiates load reduction per 20M-52.4.8, Step IV.B.2.

At the rate specified by the SWUS, reduce load as follows:

a. Set the desired turbine load on the EHC SETTER.
b. Set the LOAD RATE thumbwheel to the desired rate (5 percent/

minute maximum).

Turbine load and reactor power c. Depress the GO pushbutton on the decreasing at 12% per hour. Turbine EH Control Station.

d. As load is reduced, perform the following:
1) Maintain Median Selected TAVG within
  • 2QFof Tref.
2) Maintain indicated axial flux difference within Target Band of COLR and Curve Book AFD Limits Curve.
3) Maintain control rods above their insertion limits as defined in the COLR Fig. 1.

BVPS 2 - NRC Scenario 2 3 of 21

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

4) As the turbine load reduces, Maintain the valve position limiter at 5 percent above turbine load to prevent load excursions.

RO initiates RCS boration as necessary to maintain Tavg - Tref per 20M-7.4.KI Step 1V.A and reactivity plan.

Place the Boric Acid Makeup Blender Control switch in the Stop position.

Set 2CHS*FCV113A, Boric Acid To Boric Acid Blender to the flow rate determined on Figure 7-48 in 20M-7

a. Set [2CHS*FCV113A] as follows:

Pot Setting = Boric Acid Flow 4 gpm Set [2CHS-FQIS113], Boric Acid To Blender Flow Totalizer to the total volume in gallons of boric acid to be added using one of the following:

a. 20M-7, Figure 7-45, Boron Addition
b. WAG Tables BVPS 2 - NRC Scenario 2 4 of 21

I t

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

c. Current reactivity plan
d. Reactor Engineering approved computer based method Ensure total makeup from blender flow totalizer is zero.

Place the makeup mode selector switch in the Borate OR Manual position.

To initiate boration, place the boric acid makeup control switch to Start position.

Annunciator: Verify the following:

[A2-2E], Boric Acid Blender InleffOutlet a. Inservice Boric Acid Transfer Pump Deviation from SP starts.

b. 2CHSFCVI 138, Boric Acid Blender Disch to Chg Pumps, Opens OR Open it IF Mode Selector was in manual.
c. Boric acid flow is indicated on 2CHS-FR113.

BVPS 2 NRC Scenario 2 5 of 21

i 4

I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #2 SG B Level Transmitter Fails High SG 21 B 2FWS*LT484 fails low.

When directed, insert the following command:

Annunciator:

IMF XMT-MSS005A (0 0) 100 [A6-D10], 21 B SG HI LEVEL PO refers to ARP.

NOTE: No system response US refers to 20M-24.4.IF occurs on failure of a single channel due to median signal select feature.

2MSP-24.04-1 lists required US refers to Technical Specifications bistables and locations. TS 3.3.1.1 item 14 and TS 3.3.2.1, item 5.a, 7.a.

BVPS 2 NRC Scenario 2 6 of 21

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE EVENT #3 2-2 EDG Failure 2-2 EDG Start Failure When directed, insert the following command: Annunciator:

IMF DSGO1 6 (0 0) [A8-5E], Diesel Gen 2-2 Local Panel PO refers to ARP.

Trouble Crew dispatches Outside Operator to investigate local alarm.

Outside Operator reports local US refers to Technical Specification TS alarm is for EDG start failure. 3.8.1.1. Action b.

BVPS 2 - NRC Scenario 2 7 of 21

1 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I EVENT #4 Letdown Pressure Control Valve 2RCS*PCV145 fails closed resulting in a Fails Closed In Auto loss of normal letdown.

When directed, insert the following RO notes indications and alarms command:

Annunciator:

IMF XMT-LDS007A (0 0 ) 0 [A2-3F], Letdown Flowpath Trouble RO notifies US. Refers to ARP.

Letdown backpressure rising. US may refer to AOP-2.7.1 or AOP-2.6.7.

Letdown flow lowering.

RO reports 2CHS-FI150 indicates zero flow.

Crew minimizes any power changes in progress.

Letdown flow at 105 gpm. RO controls 2RCS*PCV145 to restore letdown flow.

US contacts I&C to investigate failure of 2CHS*PCV145.

BVPS 2 NRC Scenario 2 8 of 21

! i I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #5 SG 21A MFRV Controller Fails In 2FWS*FCV478, Main Feed Reg Valve Auto controller fails closed.

When directed, insert the following command:

Annunciators:

IMF CNH-CFWlOB (0 0) 0 300 [A6-9H], Loop A Steam Flow > PO recognizes feed flow problem and Feedwater Flow informs US.

[A6-9E], SG21A Level Deviation from Setpoint US directs PO to take manual control of SG 21A MFRV and attempt to stabilize feed flow and level.

SG 21 A feed flow oscillation.

SG 21A MFRV position and feed flow PO takes manual control of SG 21A stabilize in manual control. MFRV to raise feed flow.

US directs I&C to investigate problem with SG 21 A MFRV automatic control.

BVPS 2 NRC Scenario 2 9 of 21

INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #6:

RCS Leak 25 gpm RCS leak in CTMT.

When directed, insert the following Crew responds to indications and command: alarms.

Annunciators:

IMF RCS02A (0 0 ) 25 [A4-A5], Radiation Monitoring System US refers to AOP 2.6.7, Excessive Trouble Primary Plant Leakage.

[A2-E3], Charging Flowpath Trouble RO checks if PRZR level can be maintained.

[A2-D4], Reactor Coolant Pump Seal RO controls charging flow as Trouble necessary to maintain PRZR level.

[A2-B2], Unidentified Leakage System US requests SM to evaluate EPP.

Trouble

[A2-B3], Unidentified Leakage Flow Greater than 60 Gallons RO checks if VCT level can be maintained by normal makeup.

2SSR-RQI100, SG B/D Monitor normal PO checks secondary plant radiation trends normal.

2ARC-RQ100, Condenser Air Ejector normal.

PRT pressure, level, and temperature RO checks PRT conditions consistent normal. with pre-event values.

BVPS 2 NRC Scenario 2 10 of 21

! i I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Slight rise in containment temperature RO checks containment temperature may not be noticeable. normal.

Aux. Bldg. radiation normal. PO checks Aux. Bldg. radiation levels normal.

PRZR level remains stable. RO isolates charging and letdown to check for CVCS leakage.

NOTE: If contacted by US, SM RO restores charging and letdown.

may direct an emergency shutdown per 20M-51 .l.

US refers to T.S. 3.4.6.2.

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

BVPS 2 - NRC Scenario 2 11 of 21

1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENTS #7 818:

RCS Leak degrades into SBLOCA; RCS leak rises to 700 gpm.

Train B HHSl Auto Start Failure; Train A ESF Components Manually Started When directed, insert the following RCS pressure and Pressurizer level US orders reactor trip and entry to E-0.

command: rapidly lowering.

IMF RCSOPA (0 0 ) 700 300 RO verifies reactor tripped:

Crew enters E-O. Reactor trip and bypass breakers open. . Annunciator A5-6D, Turbine Trip Due To Reactor Trip Lit.

Power range < 5%. . Power range indication < 5%

Neutron flux dropping. . Neutron flux is dropping.

Throttle and governor valves closed. PO verifies turbine trip.

Main generator output breakers and PO verifies generator trip.

exciter circuit breakers open.

Only 2AE bus energized. 2-2 EDG not PO verifies power to AC emergency running, busses.

BVPS 2 - NRC Scenario 2 12 of 21

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

Crew manually actuates at least SI actuated RO verifies SI actuated and manually one train of SIS actuated actuates SI.

safeguards before transition to any ORP.

SI Train Anot actuated. RO determines SI Train A failed to actuate automatically.

SI actuated both trains. RO manually actuates both SI trains.

Crew sounds Standby Alarm, announces Unit 2 Reactor Trip and Safety Injection.

2HVS*FN204NB running. PO checks leak collection filtered exhaust fan running.

2CHS*P21A and 2CHS*P21B are NOT RO verifies HHSl pumps are running.

running.

Manually starts 2CHS*P21A.

2CHS*P21B does not start.

BIT flow indicated RO checks high head SI to BIT flow indicated.

BVPS 2 NRC Scenario 2 13 of 21

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 LHSl pumps are running. RO/PO checks both LHSl pumps are running.

AMDAFW and TDAFW pumps PO verifies AFW status.

running. B MDAFW pump not running.

6 MDAFW pump running. PO manually starts 2FWE*P23B.

AFW flow > 340 gpm. PO performs Attachment A-0.1 1, Verification of Automatic Actions.

(Steps listed to end of scenario guide.)

TAVG stable RO check RCS TAvastable at or trending to 547.

Recirc spray pumps off. RO checks recirc spray pumps running.

PORVs closed.

Spray valves at zero demand. RO checks PRZR isolated.

Safety valves closed.

PRT conditions normal. RO checks PRT conditions are normal.

RCS to SG DP < 185 psid within 10-15 RO checks if RCPs should be minutes of reactor trip. stopped.

BVPS 2 NRC Scenario 2 14 of 21

I I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Crew checks if any SGs are faulted.

No SG levels rising in an uncontrolled PO checks if SG tubes are intact.

manner.

RCS pressure and PRZR level US determines RCS is not intact.

decreasing rapidIy .

Crew transitions to E-1. US makes transition to E-1, Step 1 US directs STA to monitor CSF status trees.

CREVS not actuated or required. PO checks if CREVS actuated.

D/P between RCS pressure and highest RO checks if RCPs should be SG pressure < 185 psid. stopped.

CRITICAL TASK #2:

Crew trips all RCPs when RCS All RCPs stopped. (May have been RO stops all RCPs if not stopped to highest SG D/P criteria is previously stopped.) previously.

exceeded (ordue to CIB) and prior to exiting Procedure E-1.

BVPS 2 NRC Scenario 2 15 of 21

[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE [ OBJECTIVE I EXPECTED STUDENT RESPONSE Recirc spray not actuated. RO/PO checks recirc spray system status.

No SG pressures dropping in an PO checks if any SGs are faulted.

uncontrolled manner.

AFW flow > 340 gpm. PO maintains AFW flow > 340 gpm until NR SG level is 12%.

No SG levels rising in an uncontrolled PO checks if SG tubes are intact.

manner.

PORVs closed. RO checks PZR PORVs, safety and spray valves.

Safety valves closed.

Power available to PORV MOVs.

PORV MOVs open and PORVs in auto.

Spray valves at zero demand.

RCS pressure dropping. RO checks RCS pressure stable or dropping.

BVPS 2 NRC Scenario 2 16 of 21

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

Check Aux. Bldy. and Safeguards radiation consistent with pre-event values.

Obtain samples.

Start additional plant equipment to assist in recovery.

RCS pressure > 225 psig. Check if RCS cooldown and depressurization required.

Crew transitions to ES-1.2. US transition to ES-1.2, Post LOCA Cooldown And Depressurization.

Scenario may be terminated upon transition to ES-1.2 BVPS 2 NRC Scenario 2 18 of 21

r-I INS-I &JCTIONALGUIDELINES I _ JSE I 1 OBJECTIVE

___ I EXPECTEDTUDENT RESP~,

ATTACHMENT A-0.1 1, Verification Of Automatic Actions 2-1 EDG is running. 2-2 EDG did NOT Diesel generators - BOTH RUNNING start.

Ensure reheat steam isolation:

a. Verify 2MSS-MOVl OOA, B closed
b. Reset reheater controller.

Check If main steamline isolation required.

a. Check if any of the following exists:

CNMT pressure - GREATER THAN 3 PSIG.

OR SG steam pressure - LESS THAN 500 PSIG.

OR Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS.

b. Verify steamline isolation:

YELLOW SLI marks - LIT BVPS 2 NRC Scenario 2 19 of 21

I

[ INS I J ~ O N A LGUIDELINES I I I PLANT STATUS OR RES JSE I OBJECTIVE

_____- I EXPECTED STUDENT RESPC!

____- -TJ Estab1ish domestic wate r system cooling to station air compressors:

a. Open 2CCS-AOV118.
b. Check station air compressors -

ONE RUNNING.

Check CCP Pumps - AT LEAST ONE RUNNING.

Align neutron flux monitoring for shutdown:

a. Transfer 2NME-NR45 Nuclear Recorder to operable source and intermediate range displays.

NOTE: The RSS pumps will not Check CIB and CNMT spray status.

start until 10.5 minutes after the CIB signal is initiated.

. Containment pressure - HAS REMAINED LESS THAN 8 PSIG.

Verify service water system in service:

a. Service Water Pumps - TWO RUNNING (ONE PUMP PER TRAIN).

BVPS 2 NRC Scenario 2 20 of 21

I -___

I INS t . ,dCTIONAL GUIDELINES I PLANT STATUS OR RESt .JSE T OBJECTIVE 1-_-EXPECTED STUDENT R E S P ~

b. Service water header pressure -

GREATER THAN 55 PSIG.

c. SWS Pumps seal water pressure -

NOT LOW.

Verify both CNMT hydrogen analyzers

- RUNNING.

a. Verify CNMT hydrogen analyzer 2HCS*SOVl OOA, 61, CNMT Sample amber light - LIT.

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 SM/US.

BVPS 2 NRC Scenario 2 21 of 21

RTL# A5.670.M 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: License Operator Training/Licensed Requalification Training SUBDIVISION: Simulator SCENARIO TITLE/NO.: 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 2LOT5 Scenario No. 3 1 Revision No. 1 Date 1 Revision No. I Date I 1 I 12-9-04 I I I INSTRUCTIONAL SETTING: Simulator

'X APPROXIMATE DURATION: 1.5 Hours PREPARED BY:

Date REVIEWED BY:

Date APPROVED FOR IMPLEMENTATION:

Date BVPS-2 NRC Scenario 3 Page 1 of 21

INITIAL CONDITIONS: . IC-160; PW = NRC3; 25% Power, RCS Boron . ppm.

. 2RCS*PCV455D leakage. 2RCS+MOV537,Block Valve closed with power maintained Flood watch remains in effect.

ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS EQUIPMENT STATUS DATVTIMEOOS I TECHNICAL SPECIFICATION(S) I Yesterday 1500 I 3.4.11 .a I SHIFT TURNOVER INFORMATION

1. AOP-112.752 is in effect. River water level is 671 feet and stable.
2. Train B is protected train.
3. Raise power to 100% after a trip due to loss of all circulating water.

SCENARIO SUPPORT MATERIAL REQUIRED 20M-52.4.AI Increasing Power From 5% Reactor Power And Turbine On Turning Gear To Full Load Operation Reactivity Plan for 12%/Hr. Power Ascension Protected Train B Wall Plaque

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

EVENT #1 Raise Power US directs power increase to 100°/o per 20M-52.4.A, Step IV.131.

Conversion Economics requests RO initiates dilution per 1OM-7.4.N, raising power to 100% at 12%/hr Step 1V.A.

Place the boric acid blender control switch in the Stop position.

Set 2CHS*FCV114A, Primary Grade Water to Boric Acid Blender to the desired flow rate as determined on Figure 7-47 in 20M-7.

Set 2CHS-FCV114A as follows:

Pot Setting = Desired Flow Rate Set the total makeup from blender flow totalizer to the total volume in gallons of makeup water to be added using one of the following:

a. 20M-7, figure 7-46, Boron Dilution
b. WAG Tables
c. Current reactivity plan
d. Reactor Engineering approved computer based methods BVPS 2 NRC Scenario 3 3 of 21

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[ INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 Ensure 2CHS-FQISI 13, Boric Acid Flow To Blender totalizer is set to zero.

Place the makeup mode selector switch in the Dilute OR Manual position.

To initiate dilution, place the boric acid makeup control switch to the Start position.

Verify the following:

a. 2CHS*FCV114B opens OR open IF mode selector was in Manual.
b. Verify correct flowrate on 2CHS-FRll3.

When the dilution is complete, Place the makeup control systems in automatic in accordance with 20M-7.4.J, Blender Automatic Makeup Operations.

Turbine load and reactor power PO initiates turbine load increase to increasing at 12%/hr. 35% power.

BVPS 2 NRC Scenario 3 4 of 21

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OK RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #2 Train ASW Pump Trips, Backup 2SWS*P21A trips, 2SWS*P218 fails t0 Pump Manually Started auto start.

When directed, insert the following RO recognizes loss of 2SWS*P21A command: Annunciators: and reports to US.

IMF PMP-SWSOOG (0 0) 1 [A1-4H], Service Water System Trouble

[A1-4q,Service Water Pump Auto RO recognizes and reports StatVAuto Stop 2SWE*P21A failure to auto start.

2SWE*P21A running. RO manually starts 2SWE*P21A.

US refers to AOP-2.30.1, Service WatedNormal Intake Structure Loss.

US directs local operator to rack 2SWS-P21 C onto 2AE bus.

US refers to TS 3.7.4.1.

BVPS 2 NRC Scenario 3 5 of 21

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #3 Loss of 4KV Bus 2AE bus de-energized, 2-1 EDG fails to auto start.

When directed, insert the following Crew responds to indications and command: Annunciators: alarms.

IMF BKR-HIVO1 (0 0) 0 [A8-C2], 4160V Emerg Bus 2AE Unde rvolt age

[A8-G4], Diesel Gen Auto Start US enters AOP 2.36.2, Loss Of 4KV Emergency Bus

[A8-2A], 41 60V Emerg Bus 2AE ACB 2A10/2E7 Auto Trip RO starts standby charging pump.

If previously racked onto 2AE Bus. 2SWS-P21C auto starts. PO starts 2-1 EDG 2CHS*P21A not running. RO stops charging pump that auto started on the EDG sequencer.

2RHS*P21A not running. Crew may elect to stop LHSl pump.

2SWE*P21A running PO manually restarts 2SWE*P21A.

US refers to TS 3.8.1.1 Action c.

BVPS - 2 NRC Scenario 3 6 of 21

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I EVENT #4 Loss of Feedwater 2FWS*P21A trips When directed, insert the following Crew identifies loss of main feedwater command: pump and SG feed flow.

Annunciators:

IMF PMP-CFW004 (00)1 [A6-8A], Reactor Trip & Low Tavg or SVMain Feedwater Valve Closed

[A6-1OA], SG Feed Pump 21NB Auto stop If the crew attempts to start the startup feed pump, it trips immediately.

SG levels dropping. US directs RO to trip reactor and enters E-0.

Crew enters E-O.

BVPS 2 NRC Scenario 3 7 of 21

t I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 EXPECTED STUDENT RESPONSE I OBJECTIVE I EVENTS #5,6, & 7 SG 218 SGTR, 2-1 EDG Failure, MDAFW Train B Pump Fails To Auto Start; CIA Fails To Auto Actuate Pre-loaded Commands RO manually trips reactor.

Crew continues with E-0.

RO verifies reactor trip:

[A5-6D] lit. . [A5-6D] lit.

Power range < 5%. . Power range indication < 5%.

Neutron flux dropping . Neutron flux dropping.

Throttle or governor valves closed. PO verifies turbine trip Main generator output breakers open. PO verifies generator trip.

Exciter breaker open.

2AE bus de-energized, 2DF bus PO verifies power to AC emergency energized by offsite power. busses.

. PO recognizes and reports trip of 2-1 EDG.

BVPS 2 NRC Scenario 3 8 of 21

i I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I SI not actuated and not required. RO checks if SI is actuated Crew enters ES-0.1. US directs transition to ES-0.1.

US directs STA to begin monitoring CSF status trees.

Crew sounds Standby alarm and announces Unit 2 reactor trip.

RCS TAVGtrending to 547F Check RCS temperature stable at or trending to 547F.

PO maintains RCS temperature:

All MSIVs open. . Check at least 1 MSlV open Condenser available. . Check condenser available Steam header setpoint above existing Set steam header setpoint slightly steam header pressure. above existing steam header pressure Steam dump controller in Manual . Place steam dump controller in Manual Demand at zero. . Verify demand is zero BVPS 2 NRC Scenario 3 9 of 21

INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I STM PRESS Mode. Place steam dumps in STM PRESS Mode Controller in Auto. Place steam dump controller in AUTO Adjust controller setpoint to as necessary to maintain RCS temperature PO checks feedwater status.

No MFPs running. . Stop all but 1 Main Feed Pump

. Checks any SG low-low level reactor trip annunciators lit.

CRITICAL TASK #1:

Crew establishes the minimum 2FWE*P23B running. . Starts at least 1 AFW pump.

required A R N flowrate to the SGsby manually starting an AFW pump.

. Verifies AFW flow to each SG.

m Dispatches an operator to inspect feedwater piping in the Service Bldg. And verify feedwater piping is intact.

MFRVs closed. Verifies main feedwater regulating valves are closed.

AFW flow > 340 gpm. . Checks total feed flow to SGs >

340 gpm.

BVPS - 2 NRC Scenario 3 10 of 21

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1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I NOTE: CRITICAL TASK #2 is PO performs Attachment A-0.11, performed as part of Attachment Verification of Automatic Actions.

A-0.1 1 actions. (Steps listed at end of scenario guide.)

TAvastable. RO check RCS TAVGstable at or trending to 547yF.

Recirc spray pumps not running. RO checks recirc spray pumps are running.

PORVs closed. RO checks PRZR PORVs, safety and spray valves.

Spray valves at zero demand.

Safety valves closed PRT conditions normal. RO checks PRT conditions are normal.

Power available to PORV MOVs.

Block MOVs open (except previously closed 2RCS*MOV537).

D/P between RCS pressure and highest RO checks if RCPs should be SG pressure < 185 psid. stopped.

BVPS 2 NRC Scenario 3 13 of 21

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i 1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 CRITICAL TASK #3:

Crew isolates feed flow into and 2SVS*PCV101B in manual and closed. RO places SG 21 B ADV in manual and steam flow from the ruptured SG closes.

before a transition to ECA9.1 occurs.

2SVS*HCV104 closed. RO verifies residual heat release valve is closed.

Crew dispatches an operator to close RHR isolation valve.

After 5 minutes, report as Operator that 2SVS*28 is closed.

2FWE*P23B running. PO verifies at least one MD AFW pump is running.

Crew dispatches an operator to close TD AFW pump steam supply valve.

After 5 minutes, report as Operator that 2MSS*16 closed.

2BDG*AOV10061 and 101B1 closed. PO verifies SG 21 B SG blowdown isolation valves are closed.

2SDS*AOVlllBl and 1 11B2 closed. PO verifies SG 21 B steamline drain valves are closed.

BVPS 2 NRC Scenario 3 15 of 21

I i

I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I 2SDS*AOV129A closed. RO/PO verifies RHR piping drain valve is closed.

2MSS*AOVlOlB and 102B closed PO verifies SG 21 8 MSlV and bypass valves are closed.

SG 218 level > 12%. PO checks SG 21 B level.

EOP pre-emptive action 2FWE*HCVl OOC, D closed. (May have PO closes SG 21 B AFW throttle been previously performed.) valves.

Main feedwater isolated. PO checks FWI - previously verified.

SG 21B pressure > 240 psig. PO checks SG 21 6 pressure > 240 psig.

US determines target cooldown temperature based on SG 21 B pressure.

US directs STA to trend cooldown rate.

BVPS - 2 NRC Scenario 3 16 Of 21

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

Condenser steam dumps open. PO verifies condenser available and initiates cooldown at maximum rate, (or uses SG atmospherics).

RCS pressure < 1950 psig. RO blocks steamline SI when RCS pressure reaches 1950 psig.

Total AFW flow >340 gpm or SG level PO checks intact SG levels.

between 27% and 50%.

PORVs closed; MOVs open (except RO checks power to PORVs and block previously closed 2RCS*MOV537). valves.

SI reset. RO resets SI.

CIA and CIB reset. RO resets CIA and CIB.

RCS at target temperature. PO stops RCS cooldown at target temperature.

Station air compressors running. PO verifies station air compressors are running.

BVPS 2 NRC Scenario 3 17 of 21

i I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I 21AC-MOV130 and 131 open PO establishes instrument air to CNMT.

CNMT instrument air header pressure > PO checks CNMT instrument air 85 psig. header pressure > 85 psig.

LHSl pumps previously stopped RO checks if LHSl pumps should be stopped.

SG 21B pressure stable. PO checks SG 21 B pressure stable or rising.

Subcooling > 61 F. RO checks subcooling is satisfactory.

Scenario may be terminated upon crew completion of cooldown to target temperature.

BVPS 2 NRC Scenario 3 18 of 21

~ U C T I O N A GUIDELINES L I - P __- i I OBJECTIVE I EXPECTED STUDENT RESPONf' -7 ATTACHMENT A-0.1 1, Verification Of Auto matic Actions Diesel generators - BOTH RUNNING.

Ensure reheat steam isolation:

a. Verify 2MSS-MOV1OOA, 6 closed.
b. Reset reheater controller.

Check If main steamline isolation required.

a. Check if any of the following exists:

m CNMT pressure - GREATER THAN 3 PSIG.

OR m SG steam pressure - LESS THAN 500 PSIG.

OR rn Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS.

b Verify steamline isolation:

YELLOW SLI marks - LIT.

BVPS 2 NRC Scenario 3

-A I I 23 I N S I JCTIONAL GUIDELINES I I I PLANT

- STATUS OR RES( JSE OBJECTIVE --

EXPECTEDSTUDE-Establish domestic water system cooling to station air compressors:

a. Open 2CCS-AOV118.
b. Check station air compressors -

ONE RUNNING.

Check CCP Pumps - AT LEAST ONE R UNNlNG.

Align neutron flux monitoring for shutdown:

a. Transfer 2NME-NR45 Nuclear Recorder to operable source and intermediate range displays.

Check CIB and CNMT spray status.

NOTE: The RSS pumps will not start until 10.5 minutes after the

. Containment pressure - HAS REMAINED LESS THAN 8 PSIG.

CIB signal is initiated.

Verify service water system in service:

a. Service Water Pumps - TWO RUNNING (ONE PUMP PER TRAIN).

BVPS 2 NRC Scenario 3 20 of 21

1 3  ; .dCTIONAL GUIDELINES I PLANTSTATUS OR RE^- ASE I OBJECTIVE I EXPECTED STUDENT -~ RESPL _L]

b. Service water header pressure -

GREATER THAN 55 PSIG.

c. SWS Pumps seal water pressure -

NOT LOW.

Verify both CNMT hydrogen analyzers

- RUNNING.

a. Verify CNMT hydrogen analyzer 2HCSSOVl OOA, B1, CNMT Sample amber light - LIT.

CRITICAL TASK #2: Verify ESF equipment status:

Initiate at least one train of CIA a. Verify SI status by checking all prior to completion of RED SIS marks - LIT.

Attachment A-0.1 1.

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 2 NRC Scenario 3 21 of 21

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