ML051030217
| ML051030217 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley (NPF-073) |
| 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) | |
Text
RTL# A5.670.M Revision No.
1/2-ADM-1357.F11 Page 1 of 1 Revision 0 Date SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
License Operator TrainingILicensed Requalification Training SUBDIVISION:
Si mu1 ator SCENARIO TITLWNO.:
2005 NRC Initial License Exam COMPUTER CODE FOR L.P.:
2LOT5 Scenario No. 2 I Revision No. I Date I
I 1
I 12-7-04 I
INSTRUCTIONAL SETTING:
Simulator APPROXIMATE DURATION:
1.5 Hours PREPARED BY:
REVIEWED BY:
APPROVED FOR I M P LE M E NTAT IO N :
Date Date Date BVPS-2 NRC Scenario 2 Page 1 of 21
INITIAL CONDITIONS:
a a
rn I
EQUIPMENT STATUS IC-159; PW = NRC4; 75/0 Power, RCS boron at ______.
ppm.
2RCSPCV455D leakage. 2RCS*MOV537, Block Valve closed with power maintained River water level has receded. Flood watch cancelled on last shift.
2SWS*P21 A, Service Water Pump 00s.
Turbine control selected to IMP In.
DATEJTIME 00s TECHNICAL SPECIFICATION(S)
I I
I VOND MARKINGS ADDITIONAL LINEUP CHANGES STICKERS I
1 2RCS*PCV455D I
Yesterday 1500 I
3.4.1 1.a I
I I
I I
SHIFT TURNOVER INFORMATION
- 1.
- 2.
Continue raising power to 100% at 12/% per hour.
Protected Train is Train B.
SCENARIO SUPPORT MATERIAL REQUIRED 20M-52.4.BI Load Following Reactivity Plan for 12%/Hr Power Ascension Protected Train B Wall Plaque
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1
EVENT #1 Raise Power 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 20M-52.4.B, Step IV.A.5.
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 maxi mum).
- c. Depress the GO pushbutton on the Turbine EH Control station.
RO initiates RCS dilution as necessary to maintain TAvCj
- TRH per 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 16gpm Pot Setting =
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:
- 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 Reduction When directed, insert the following command:
IMF PMP CFWOOS (0 0) 1 2FWS-P21 B trips Annunciators:
[A6-1 OA], SG 21 A(21 B) Feed Pump Trip
[A6-9E], SG 21A level Deviation From Setpoint
[A6-1 OE], SG 21 8 Level Deviation From Setpoint
[A6-11 El1 SG 21 C Level Deviation From Setpoint
[A6-8BII Stm Gen Feed Pump 21 N B Recirc Valve Trouble Only 2FWS-P21 A running.
If requested, SM should direct a load reduction at rate of 5%/minute.
PORVs 455C and 456 are available.
Crew responds to indications and alarms.
PO determines that 21 B Main Feed Pump tripped.
US refers to AOP-2.24.1, Loss Of Main Feedwater.
PO verifies condensate pumps, heater drain pumps, and separator drain receiver drain pumps running.
RO determines reactor power is >
65%.
US directs load reduction to 65%
power at 5% per minute in accordance with AOP-2.51.l.
Crew alerts plant personnel of emergency shutdown.
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 Bo rat ion.
Turbine load decreasing.
Control rods in Auto.
PRZR heaters energized.
BVPS 2 - NRC Scenario 4 7 of 23 PO depresses the reference control GO pushbutton.
RO places control rods in AUTO and verifies Tavg is within +/- 5F of Tref.
RO places all PRZR heaters to On.
Maintain valve position limit at 5%
above existing turbine load during the load reduction.
[
INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #3 Dropped Control Rod Insert malfunction following load reduction, after crew has control of SG level and TAva is within 2F of TREF.
IMF CRF03-K6 (0 0) 0 Rod K-6 drops due to stationary gripper failure.
[A4-5H], NIS Power Range High/Low SP Flux Deviation Auto Defeat
[A4-4F], NIS Power Range Comparator Devi at i on
[A4-9F], Rod at Bottom
[A4-8G], Rod Position Deviation Rod K-6 dropped.
RCS TAV(; > 541 F and stable.
Crew responds to indications and alarms.
US refers to AOP-2.1.8, Rod Inoperability.
RO checks only 1 rod dropped.
US confirms 1 control rod dropped RO places control bank selector switch in Manual.
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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 conditions remain stable while determining cause of rod problem.
Continue with scenario when Technical Specifications have been addressed.
BVPS 2 - NRC Scenario 4 9 of 23 US requests guidance from Manager, Operations on whether to withdraw misaligned rod.
US may refer to Technical Specification 3.1.3.1 Action c.3.
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 EVENT #4 Pressurizer Master Pressure Control Output Fails High When directed, insert the following command:
IMF CNH-PCS1 OB (-1 0) 100 2RCS-PK444A fails in Auto, Manual control available.
[A4-1 D], Pressurizer Control Pressure Hig h/Lo w
[A4-1 E], Pressurizer Control Press Deviation High/Low
[A4-1 F], Pressurizer PORV Open Permissive Spray valves open.
PORV 45% opens.
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.
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 When directed, insert the following command:
IMF XMT-CFW051 A (0 0) 5 2FWSFT476, SG 21 A Channel 4 fails high slowly.
[A6-9F], Loop A Feedwater Flow >
Steam Flow
[A6-9H], Loop A Steam Flow >
Feedwater Flow 2FWS*FCV478 slowly closes.
Crew responds to indications and ala rrns.
US refers to 20M-24.4.IFI Attachment
- 2.
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 position.
US directs placing SG 21 A steam flow signal selector in the FT474 position.
US declares SG 21 A 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, insert the following:
IRF LOA-PCS003 (0 0) 1 IMF BST-PCS038 (0 0 ) 0 IMF BST-PCSO29 (0 0) 0 IRF LOA-PCS003 (0 0) 0 BVPS 2 - NRC Scenario 4 US directs tripping bistables.
Protection Rack C3 door open.
2LS/476A (BS-I) SG LO LO level tripped.
2LS/476C (BS-1) SG HI HI level tripped Protection Rack C3 door closed 12 of 23 US contacts I&C to investigate failure of 2FW S* FT476.
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE ]
EVENTS #6 SG 21 A Feedwater Regulating Valve Fails Closed control unsuccessful. Reactor Trip 2FWS'FCV478 fails closed. Manual required.
When directed, insert the following command:
PO takes manual control of SG 21A Feed Reg Valve.
IMF CNH-CFW1 OA (0 0) 0 120 US determines FRV failure is not recoverable.
Crew enters E-O.
BVPS 2 - NRC Scenario 4
[A5-6D] lit.
Power range < 5%.
Neutron flux dropping.
Throttle or governor valves closed.
Main generator output breakers open.
Exciter breaker open.
13 of 23 US directs RO to manually trip reactor and enters E-0.
RO verifies reactor trip:
[A5-6D] lit.
Power range indication < 5".
. Neutron flux dropping.
PO verifies turbine trip PO verifies generator trip.
1 INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
2AE bus de-energized, 2DF bus energized by offsite power.
PO verifies power to AC emergency busses.
SI not actuated and not required.
Crew enters ES-0.1.
BVPS 2 - NRC Scenario 4 14 of 23 US directs transition to ES-0.1.
US directs STA to begin monitoring CSF status trees.
l I
INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I
EVENTS #7 Main Steam Line Break With MSlV Failure When directed, insert the following command:
IMF MSS03 (0 0) 1 E7 Preloaded command for MSlV failure.
CRITICAL TASK #1:
Close MSIVs prior to an Orange condition on the Integrity CSF status tree.
Crew re-enters E-0.
Steam break downstream of SG 21 B MSIV.
RCS temperature dropping.
Steam dump valves closed.
2MSS-MOV1 OOA, B closed.
SG blowdown valves closed.
AFW flow throttled to < 340 gpm.
SG 21 B MSlV closed.
SI actuated.
Crew sounds Standby alarm and announces Unit 1 reactor trip.
RO checks RCS temperature stable at or trending to 547F.
. Stops dumping steam
. Verify reheat steam isolation
. Verify SG blowdown isolated.
. Throttle total feed flow > 340 gpm.
PO recognizes continuing cooldown and initiates SLI.
US directs SI initiation or SI actuates.
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 ]
RO reverifies reactor trip.
Reactor tripped.
Turbine tripped.
PO reverifies turbine trip.
Main generator tripped.
PO reverifies generator trip BVPS 2 - NRC Scenario 4 2AE and 2DF busses energized SI actuated.
2HVS*FN204NB running.
2CHSPZl A and 21 B running.
HHSl flow indicated.
16 of 23 PO reverifies power to AC emergency busses.
RO manually actuates both SI trains.
RO/PO sound Standby alarm and announce Unit 2 reactor trip and SI.
PO checks leak collection filtered exhaust fan running.
RO verifies two Charging/HHSI pumps are running.
RO verifies HHSl flow indicated.
[
INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
BVPS 2 - NRC Scenario 4 LHSl pumps running.
2FWEiP23B running.
AFW throttle valves full open.
AFW flow >340 gpm.
TAVG stabilizing after MSlV closure.
Recirc spray pumps off.
PORVs closed.
Spray valves at zero demand Safety valves closed.
17 of 23 RO/PO check both LHSl pumps are running.
PO verifies AFW status:
. Manually starts 2FWE*P23B
. AFW throttle valves full open
. Total AFW flow > 340 gpm.
PO performs Attachment A-0.1 1 Verification of Automatic Actions.
(Steps listed at end of scenario guideline.)
RO check RCS TAVG stable at or trending to 547*F.
RO checks recirc spray pumps are running.
RO verifies PRZR is isolated.
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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.
CRITICAL TASK #2:
Stop ECCS prior to water relief through Pressurizer PORVs.
2SIS*MOV867A, B, C, D closed BVPS 2 - NRC Scenario 4 2CCS-AOV118 open.
Station air compressors running 21AC-MOV1 30 and 131 open.
Instrument air header pressure > 85 psig.
2CHS+FCVl22 closed.
2CHS*MOV310 open.
2CHS*MOV289 open.
19 of 23 RO checks RCS pressure stable or rising.
RO closes high head SI cold leg injection valves.
PO establishes domestic water system cooling to station air compressors.
PO checks station air compressors are running.
PO establishes instrument air to CNMT.
PO checks instrument air header pressure > 85 psig.
RO establishes normal charging flow.
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INS!!
e,dCTIONAL GUIDELINES I
.dSE I OBJECTIVE l_l_- I E X P E C T E D S - f E E m 2 ATTACHMENT A-0.1 1, Verification Of Automatic Actions Diesel generators - BOTH RUNNING Ensure reheat steam isolation:
- a. Verify 2MSS-MOV1 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.
. SG steam pressure - LESS THAN 500 PSIG.
. Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS.
BVPS 2 - NRC Scenario 4
- b. Verify steamline isolation:
. YELLOW SLI marks - LIT 21 of 23
PLANT STATUS OR RESF.(
- E I OBJECTIVE I EXPECTED STUDENT
- RESPT
-J A
r INSThdCTIONAL GUIDELINES I 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:
NOTE: The RSS pumps will not start until 10.5 minutes after the CIB signal is initiated.
BVPS 2 - NRC Scenario 4 Containment pressure - HAS REMAINED LESS THAN 8 PSIG.
Verify service water system in service:
- a. Service Water Pumps - TWO RUNNING (ONE PUMP PER TRAIN).
22 of 23 Check CIB and CNMT spray status.
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.
Verify ESF equipment status:
- 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 Revision No.
1 1 /2-ADM-1 357. F11 Page 1 of 1 Revision 0 Date 12-7-04 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
SUBDIVISION:
SCENARIO TITLWNO.:
COMPUTER CODE FOR L.P.:
I N STR U CT 10 N AL SETTING :
APPROXIMATE DURATION:
PREPARED BY:
REVIEWED BY:
APPROVED FOR I M P LE MENTATION :
License Operator Training/Licensed Requalification Training Simulator 2005 NRC Initial License Exam 2LOT5 Scenario No. 1 1 Revision No.
1 Date
-1 I Si mu I at or 1.5 Hours Date Date Date BVPS - 2 NRC Scenario 1 Page 1 of 26
i INITIAL CONDITIONS:. IC-1 81, P w = NRC1; 100% Power, RCS Boron ppm 2CHS*P21 C, HHSKharginy Pump 00s for repair.
2RCS*PCV455D leakage. 2RCS*MOV537, Block Valve closed with power maintained Flood warnings from heavy rains.
Maintenance investigating 2SWS*P21 A, Service Water Pump vibration/noise.
I ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS I
I I
I I
EQUIPMENT STATUS 1
DATUTIMEOOS TECHNIC A L S P EC I FIC AT10 N (S)
I I
I 2RCS*PCV455D I
Yesterday 1500 I
3.4.1 1.a SHIFT TURNOVER INFORMATION
- 1.
- 2.
- 3.
- 4.
2SWS*P21 A, Service Water Pump is operable, but abnormal vibratiodnoise is under investigation.
AOP-1/2.75.2 is in effect. River water level is currently 671 feet and stable.
Train B is the protected train.
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 hour Turbine load and reactor power decreasing at 12%/hr.
US directs load reduction in 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).
- c. Depress the GO pushbutton on the 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:
- 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.
BVPS - 2 NRC Scenario 1 An nu nciato r:
[A2-2E], Boric Acid Blender Inlet/Outlet Deviation from SP 5 of 26 Place the makeup mode selector switch in the Borate OR Manual posit ion.
To initiate boration, place the boric acid makeup control switch to Start position.
Verify the following:
- a. Inservice boric acid transfer pump 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.
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)
IMF EHCOG (0 0 ) 65 BVPS - 2 NRC Scenario 1 Annunciators:
[A4-3C], Tavg Deviation from Tref
[A4-1 D], Pressurizer Control Pressure High/Low
[A4-2F], Pressure Relief Block Tavg increasing.
RCS pressure increasing.
MW decreasing.
Steam dump valves opening.
Control rods inserting.
EHC system normal except for valve position limiter.
7 of 26 Crew acknowledge alarms, notifies US and investigates.
Crew informs US of the loss of electrical load.
US refers to AOP-2.35.2.
RO places control rods in AUTO.
Crew sounds standby alarm and announces Unit 2 load rejection.
PO verifies normal EHC operation.
i I
INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE
[ OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Crew may perform actions to recover GV control from the valve position limiter per 20M-26.4.X.
BVPS - 2 NRC Scenario 1 Valve position limiter failure, vibration and load satisfactory for condition.
[A4-6D], Delta Flux Outside Target Band Generator load > 270 MW and vacuum is greater than 27 inches HG.
Generator output breakers closed.
Generator volts, amps, and power factor satisfactory.
Tavg lowering to Tref value.
8 of 26 Crew checks if governor valves have closed in sequence, checks turbine vibration recorders.
PO identifies VPL failure.
RO may initiate boration.
Crew monitors for subsequent load reductions > 90 Mwe.
Crew checks if turbine should be tripped, verifies load is greater than 270 MW and if vacuum is adequate.
PO verifies if the main generator is on line.
RO checks Tavg-Tref within 2gF US directs I&C to investigate problem with governor valve.
US checks for load reduction of > 15%
and informs Chemistry, if necessary.
1 INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 SM direction, if requested by US, not to lower turbine load.
2CNM-AOV100 closed Supervisory limits-normal.
Continue with scenario when limiter problem is identified and Tavg-Tref are matched, or at Examiners discretion.
Crew checks 2CNM-AOV100 closed PO monitors all turbine supervisory limits. Refers to 20M-25.4.ABD.
Crew should review Tech. Specs 3.2.5, 3.1.3.6 for compliance.
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 PT-445 Fails High Slowly Insert the following:
[A4-1 D], Pressurizer Control Pressure Hig h/Low
[A4-1 F], Pressurizer PORV Open permissive
[A4-2E], Pressurizer Control Press High PORV Actuation IMF XMT-RCS031A (0 0) 2500 120
[A4-A1], Pressurizer Power/Safety Relief Trouble PORV 455D and 456 open.
RO notes alarm, informs US. Crew refers to ARPs, if necessary.
US refers to 20M-6.4.IF, Attachment 2.
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 - 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 Pressure Change
[A6-9F], Loop A Feedwater Flow >
Steam Flow
[A6-9G], Loop A Steamline Pressure Low SG 21 A Channel 3 2MSS*PT476 fails low.
SG 21 A channel 3 steam flow drops (density compensation input).
SG 21 A feed flow, NR level drops.
2FWSFCV478 modulates closed in automatic.
Loop 1 steamline pressure feed flow >
steam flow alarms.
Crew responds per ARPs.
PO notes problem with SG 21 A level control, takes manual control of 2FWS*FCV478 and informs US.
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.
dependent on time of establishing normal MFRV control to restore SG level.
IOR XC11083F Action to trip bistables:
IRF LOA-PCS003 (0 0) 1 IMF BST-PCS038 (0 0) 0 Channel 3 steam flow locally selected.
NR level = 44%.
Protection Rack C3 Door open.
2LS/476A (BS-1) Low-Low Trip.
Crew determines that steam pressure channel 2MSS*PT476 failed low.
US refers to 20M-24.4.IF, Attachment
- 4.
U S directs PO to restore SG 21A level to program level.
US directs selecting redundant channel for 21 A SG steam flow signal (FT-477).
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.
US directs crew to trip associated bistables per 20M-24.4.IF, Attachment 4 Table 1.
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 IRF LOA-PCSOOS (0 0) 0 IRF LOA-PCS004 (0 0) 1 IMF BST-PCS077 (0 0) 0 IMF BST-PCSO68 (0 0) 0 IRF LOA-PCS004 (0 0) 0 2LS/476C (6s-2) High-High FWI.
Protection Rack C3 Door closed.
Protection Rack C4 Door Open.
2PS/476A (6s-1) Low Pressure SI and SLI.
2PS/476B (6s-2) High Pressure Rate SLI 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)
RCS pressure and Tavg rising.
ATWS - reactor fails to trip automatically or when Manual trip is attempted.
Crew enters FR-S.l.
Control rods remain withdrawn.
US directs a manual reactor trip.
RO places reactor trip switch to Trip.
Crew identifies that the reactor failed to trip.
RO depresses BB-A reactor trip pushbutton to attempt reactor trip.
US enters FR-S.l and announces entry to crew.
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 CRITICAL TASK #1:
All AFW pumps running.
Insert control rods or initiate RCS Boration.
BVPS - 2 NRC Scenario 1 2CHS*P21 A and 6 running.
SI not actuated.
2CHS*MOV350 open.
Boric acid transfer pump running in fast speed.
Boration flow > 30 gpm.
Charging flow > 40 gpm.
PZR pressure is < 2330 psig.
15 of 26 RO places control rod group selector in AUTO and verifies rods are inserting.
RO drives rods in manual after automatic rod motion stops.
PO verifies AFW status RO initiates emergency boration of the RCS.
Verifies at least 1 charging pump running Verifies SI not actuated
. Opens 2CHS*MOV350
. Starts boric acid transfer pump
. Verifies emergency boration flow >
Adjusts [2CHS*FCV122] to establish charging flow > 40 gpm Checks PZR pressure less than 2330 30 gpm Psig
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.
[2MSS-MOVl OOA, B] closed.
. All throttle or all governor valves are closed All reheat stop or interceptor valves are closed
. Reset reheater controller When directed to locally trip the reactor, insert:
TRG! 30 BVPS - 2 NRC Scenario 1 RTB A open.
RTB B open (30 sec delay).
Control rods drop.
Power decreases.
16 of 26 US determines that SI has not actuated.
RO verifies reactor is subcritical:
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 Crew returns to E-0.
BVPS - 2 NRC Scenario 1 Power range indicates i 5%
Intermediate range SUR negative.
Reactor trip and bypass breakers open.
Power range indicates < 5%.
Nuclear flux decreasing.
Throttle and governor valves closed.
17 of 26 Power range channels are less than 5%.
Intermediate range rate indicates a negative startup rate.
RO continues boration, as necessary US enters E-0 and announces entry to crew.
RO verifies reactor tripped:
Annunciator A5-6D, Turbine Trip Due To Reactor Trip lit Neutron flux is dropping Power range indication less than 5%.
PO verifies turbine trip.
US identifies need to evaluate EPP.
i I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
BVPS - 2 NRC Scenario 1 Main generator output breakers and exciter circuit breakers open.
2AE and 2DF busses energized.
SI actuated.
[2 HVS *FN204A/B] running.
HHSl pumps running with flow indicated. LHSl pumps running.
MDAFW and TDAFW pumps ru n ning.
18 of 26 PO verifies generator trip PO verifies power to AC emergency busses.
RO verifies SI actuated and manually actuates SI.
Crew sounds Standby Alarm and announces Unit 2 reactor trip and safety injection.
PO checks leak collection filtered exhaust fan running.
RO/PO verify SI system status.
PO verifies AFW status.
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 TAVG stable at or trending to 547QF.
BVPS - 2 NRC Scenario 1 SG A ADV stuck open.
Recirc spray pumps off.
PORVs closed.
Spray valves at zero demand.
Safety valves closed.
PRT conditions normal.
19 of 26 Verify reheat steam isolation Reduce total AFW flow to minimize cooldown
. PO initiates main steam line isolation.
RO checks recirc spray pumps running.
RO checks PRZR isolated.
PRT conditions normal.
RO checks if RCPs should be stopped.
1 INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
Crew transitions to E-2.
When requested as U1 Operator, report CREVS actuation.
BVPS - 2 NRC Scenario 1 SG A faulted and depressurizing in an uncontrolled manner.
Control Room dampers shut.
Timers running, control room pressurizing.
All yellow SLI marks lit.
SG 21 6 and 21 C pressures stable.
20 of 26 Crew checks if any SGs are faulted.
US exits E-0, enters E-2 and informs crew.
US directs STA to monitor CSF status trees.
PO initiates CREVS and verifies system activated.
PO com mences Attachment A-2.4.
PO verifies CREVS actuated in U1 by requesting U1 CREVS status.
Crew verifies steam line isolation.
PO checks for any non-faulted SG
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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.
. SG steam pressure - LESS THAN 500 PSIG.
. 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:
NOTE: The RSS pumps will not start until 10.5 minutes after the CIB signal is initiated.
BVPS - 2 NRC Scenario 1 24 of 26 Check CIB and CNMT spray status.
Containment pressure - HAS REMAINED LESS THAN 8 PSIG.
[ 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.
Verify ESF equipment status:
- 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:
Si mu1 at or SCENARIO TITLUNO.:
2005 NRC Initial License Exam COMPUTER CODE FOR L.P.:
2LOT5 Scenario No. 4 1 Revision No. 1 Date I
1 I
12-7-04 I
Revision No. I Date I NSTR UCTl ON AL SETTl NG :
Si mu I at or APPROXIMATE DURATION:
1.5 Hours PREPARED BY:
Date REVIEWED BY:
Date APPROVED FOR I M P LE M E NT AT IO N :
Date BVPS-2 NRC Scenario 4 Page 1 of 23
i ADDITIONAL LINEUP CHANGES STICKERS INITIAL CONDITIONS:. IC-146; PW = NRCZ; 48% power, RCS Boron PPm.
2CHS*P21 c 00s.
2RCSPCV455D leakage. 2RCS*MOV537, Block Valve closed with power maintained.
Flood warnings due to heavy rains.
Maintenance is investigating abnormal noisehibration on 2SWS*P21 A, Service Water Pump.
Turbine Control selected to First Stage In.
VOND MARKINGS EQUIPMENT STATUS 1
DATUTIMEOOS I
I I
T EC H N IC A L S P EC I FIC AT10 N(S)
I Yesterday 1500 1
3.4.1 1.a I
I 2RCS*PCV455D SHIFT TURNOVER INFORMATION
- 1.
AOP-1/2.75.2 is in effect. River water level is 671 feet and stable.
- 2.
2SWS*P21 A, Service Water Pump is operable, but investigation of noisehibration is ongoing.
- 3.
Train B is 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 Turbine load and reactor power decreasing at 12% per hour.
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).
- c. Depress the GO pushbutton on the Turbine EH Control Station.
- d. As load is reduced, perform the following:
- 1) Maintain Median Selected TAVG within
- 2QF 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 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:
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.
BVPS 2 - NRC Scenario 2 Annunciator:
[A2-2E], Boric Acid Blender InleffOutlet Deviation from SP 5 of 21 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.
Verify the following:
- a. Inservice Boric Acid Transfer Pump 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.
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 When directed, insert the following command:
IMF XMT-MSS005A (0 0) 100 NOTE: No system response occurs on failure of a single channel due to median signal select feature.
2MSP-24.04-1 lists required bistables and locations.
SG 21 B 2FWS*LT484 fails low.
Annunciator:
[A6-D10], 21 B SG HI LEVEL PO refers to ARP.
US refers to 20M-24.4.IF US refers to Technical Specifications 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 When directed, insert the following command:
IMF DSGO1 6 (0 0) 2-2 EDG Start Failure Annunciator:
[A8-5E], Diesel Gen 2-2 Local Panel Trouble Outside Operator reports local alarm is for EDG start failure.
PO refers to ARP.
Crew dispatches Outside Operator to investigate local alarm.
US refers to Technical Specification TS 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 Fails Closed In Auto When directed, insert the following command:
2RCS*PCV145 fails closed resulting in a loss of normal letdown.
Annunciator:
RO notes indications and alarms IMF XMT-LDS007A (0 0) 0
[A2-3F], Letdown Flowpath Trouble RO notifies US. Refers to ARP.
Letdown backpressu re rising.
Letdown flow lowering.
Letdown flow at 105 gpm.
US may refer to AOP-2.7.1 or AOP-2.6.7.
RO reports 2CHS-FI150 indicates zero flow.
Crew minimizes any power changes in progress.
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 21 A MFRV Controller Fails In Auto 2FWS*FCV478, Main Feed Reg Valve controller fails closed.
When directed, insert the following command:
IMF CNH-CFWlOB (0 0) 0 300
[A6-9H], Loop A Steam Flow >
Feedwater Flow PO recognizes feed flow problem and informs US.
[A6-9E], SG21 A 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 21 A MFRV position and feed flow stabilize in manual control.
PO takes manual control of SG 21 A 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 command:
IMF RCS02A (0 0) 25
[A4-A5], Radiation Monitoring System Trouble
[A2-E3], Charging Flowpath Trouble
[A2-D4], Reactor Coolant Pump Seal Trouble
[A2-B2], Unidentified Leakage System Trouble Crew responds to indications and alarms.
US refers to AOP 2.6.7, Excessive Primary Plant Leakage.
RO checks if PRZR level can be maintained.
RO controls charging flow as necessary to maintain PRZR level.
US requests SM to evaluate EPP.
[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 2ARC-RQ100, Condenser Air Ejector normal.
PRT pressure, level, and temperature normal.
PO checks secondary plant radiation trends normal.
RO checks PRT conditions consistent 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 may not be noticeable.
normal.
RO checks containment temperature Aux. Bldg. radiation normal.
PRZR level remains stable.
NOTE: If contacted by US, SM may direct an emergency shutdown per 20M-51.l.
PO checks Aux. Bldg. radiation levels normal.
RO isolates charging and letdown to check for CVCS leakage.
RO restores charging and letdown.
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 81 8:
RCS Leak degrades into SBLOCA; Train B HHSl Auto Start Failure; Train A ESF Components Manually Started When directed, insert the following command:
RCS leak rises to 700 gpm.
RCS pressure and Pressurizer level rapidly lowering.
US orders reactor trip and entry to E-0.
IMF RCSOPA (0 0 ) 700 300 RO verifies reactor tripped:
Crew enters E-O.
Reactor trip and bypass breakers open.
Power range < 5%.
Neutron flux dropping.
Throttle and governor valves closed.
Main generator output breakers and exciter circuit breakers open.
Only 2AE bus energized. 2-2 EDG not
- running,
. Annunciator A5-6D, Turbine Trip Due To Reactor Trip Lit.
Power range indication < 5%
.. Neutron flux is dropping.
PO verifies turbine trip.
PO verifies generator trip.
PO verifies power to AC emergency 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 one train of SIS actuated safeguards before transition to any ORP.
SI actuated BVPS 2 - NRC Scenario 2 SI Train A not actuated.
RO verifies SI actuated and manually actuates SI.
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.
2CHS*P21 A and 2CHS*P21 B are NOT running.
BIT flow indicated 13 of 21 PO checks leak collection filtered exhaust fan running.
RO verifies HHSl pumps are running.
Manually starts 2CHS*P21 A.
2CHS*P21 B does not start.
RO checks high head SI to BIT flow indicated.
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 BVPS 2 - NRC Scenario 2 LHSl pumps are running.
A MDAFW and TDAFW pumps running. B MDAFW pump not running.
RO/PO checks both LHSl pumps are running.
PO verifies AFW status.
6 MDAFW pump running.
PO manually starts 2FWE*P23B.
AFW flow > 340 gpm.
TAVG stable Recirc spray pumps off.
PORVs closed.
Spray valves at zero demand.
Safety valves closed.
PRT conditions normal.
RCS to SG DP < 185 psid within 10-1 5 minutes of reactor trip.
14 of 21 PO performs Attachment A-0.1 1, Verification of Automatic Actions.
(Steps listed to end of scenario guide.)
RO check RCS TAva stable at or trending to 547.
RO checks recirc spray pumps running.
RO checks PRZR isolated.
RO checks PRT conditions are normal.
RO checks if RCPs should be stopped.
I I
INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Crew checks if any SGs are faulted.
Crew transitions to E-1.
CRITICAL TASK #2:
No SG levels rising in an uncontrolled manner.
RCS pressure and PRZR level decreasing rapid I y.
CREVS not actuated or required.
D/P between RCS pressure and highest SG pressure < 185 psid.
Crew trips all RCPs when RCS to highest SG D/P criteria is exceeded (or due to CIB) and prior to exiting Procedure E-1.
All RCPs stopped. (May have been previously stopped.)
PO checks if SG tubes are intact.
US determines RCS is not intact.
US makes transition to E-1, Step 1 US directs STA to monitor CSF status trees.
PO checks if CREVS actuated.
RO checks if RCPs should be stopped.
RO stops all RCPs if not stopped previously.
BVPS 2 - NRC Scenario 2 15 of 21
[
INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE
[ OBJECTIVE I EXPECTED STUDENT RESPONSE BVPS 2 - NRC Scenario 2 Recirc spray not actuated.
No SG pressures dropping in an uncontrolled manner.
AFW flow > 340 gpm.
No SG levels rising in an uncontrolled manner.
PORVs closed.
Safety valves closed.
PORV MOVs open and PORVs in auto.
Spray valves at zero demand.
RO/PO checks recirc spray system status.
PO checks if any SGs are faulted.
PO maintains AFW flow > 340 gpm until NR SG level is 12%.
PO checks if SG tubes are intact.
RO checks PZR PORVs, safety and spray valves.
RCS pressure dropping.
RO checks RCS pressure stable or dropping.
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.
Crew transitions to ES-1.2.
Scenario may be terminated upon transition to ES-1.2 BVPS 2 - NRC Scenario 2 RCS pressure > 225 psig.
US transition to ES-1.2, Post LOCA Cooldown And Depressurization.
18 of 21 Check if RCS cooldown and depressurization required.
-I r INS-I
&JCTIONAL GUIDELINES I
_I JSE 1 OBJECTIVE I
EXPECTEDTUDENT R E S P ~,
ATTACHMENT A-0.1 1, Verification Of Automatic Actions 2-1 EDG is running. 2-2 EDG did NOT start.
Diesel generators - BOTH RUNNING 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 I OBJECTIVE I EXPECTED STUDENT RESPC!
TJ
[
INS I I I J ~ O N A L GUIDELINES I PLANT STATUS OR RES JSE Est ab1 ish 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:
NOTE: The RSS pumps will not start until 10.5 minutes after the CIB signal is initiated.
BVPS 2 - NRC Scenario 2 20 of 21 Check CIB and CNMT spray status.
. Containment pressure - HAS REMAINED LESS THAN 8 PSIG.
Verify service water system in service:
- a. Service Water Pumps - TWO RUNNING (ONE PUMP PER TRAIN).
I I
t INS.,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.
Verify ESF equipment status:
- 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
'X 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
I 1
I 12-9-04 I
Revision No. I Date I
INSTRUCTIONAL SETTING:
APPROXIMATE DURATION:
PREPARED BY:
REVIEWED BY:
APPROVED FOR IMPLEMENTATION: I Simulator 1.5 Hours Date Date Date BVPS-2 NRC Scenario 3 Page 1 of 21
ADDITIONAL LINEUP CHANGES INITIAL CONDITIONS:. IC-1 60; PW = NRC3; 25% Power, RCS Boron
. ppm.
2RCS*PCV455D leakage. 2RCS+MOV537, Block Valve closed with power maintained Flood watch remains in effect.
STICKERS VOND MARKINGS EQUIPMENT STATUS DATVTIMEOOS I
I TECHNICAL SPECIFICATION(S)
I Yesterday 1500 I
3.4.1 1.a 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 Conversion Economics requests raising power to 100% at 12%/hr US directs power increase to 100°/o per 20M-52.4.A, Step IV.131.
RO initiates dilution per 1 OM-7.4.N, 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:
- b. WAG Tables
- c. Current reactivity plan
- d. Reactor Engineering approved computer based methods BVPS - 2 NRC Scenario 3 3 of 21
i
[
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.
BVPS - 2 NRC Scenario 3 Turbine load and reactor power increasing at 12%/hr.
4 of 21 PO initiates turbine load increase to 35% power.
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OK RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #2 Train A SW Pump Trips, Backup Pump Manually Started auto start.
2SWS*P21 A trips, 2SWS*P218 fails t0 When directed, insert the following command:
IMF PMP-SWSOOG (0 0) 1
[A1 -4H], Service Water System Trouble
[A1 -4q, Service Water Pump Auto StatVAuto Stop 2SWE*P21A running.
RO recognizes loss of 2SWS*P21 A and reports to US.
RO recognizes and reports 2SWE*P21 A failure to auto start.
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 When directed, insert the following command:
IMF BKR-HIVO1 (0 0) 0
[A8-C2], 4160V Emerg Bus 2AE U nd e rvol t ag e
[A8-G4], Diesel Gen Auto Start 2AE bus de-energized, 2-1 EDG fails to auto start.
Crew responds to indications and alarms.
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.
2CHS*P21A not running.
2RHS*P21 A not running.
2SWE*P21A running PO starts 2-1 EDG RO stops charging pump that auto started on the EDG sequencer.
Crew may elect to stop LHSl pump.
PO manually restarts 2SWE*P21 A.
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 When directed, insert the following command:
IMF PMP-CFW004 (0 0) 1 If the crew attempts to start the startup feed pump, it trips immediately.
Crew enters E-O.
2FWS*P21A trips Annunciators:
[A6-8A], Reactor Trip & Low Tavg or SVMain Feedwater Valve Closed
[A6-1 OA], SG Feed Pump 21 NB Auto stop SG levels dropping.
Crew identifies loss of main feedwater pump and SG feed flow.
US directs RO to trip reactor and enters E-0.
BVPS - 2 NRC Scenario 3 7 of 21
t I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1
EXPECTED STUDENT RESPONSE 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 Crew continues with E-0.
BVPS - 2 NRC Scenario 3
[A5-6D] lit.
Power range < 5%.
Neutron flux dropping Throttle or governor valves closed.
Main generator output breakers open.
Exciter breaker open.
2AE bus de-energized, 2DF bus energized by offsite power.
8 of 21 RO manually trips reactor.
RO verifies reactor trip:
. [A5-6D] lit.
.. Neutron flux dropping.
Power range indication < 5%.
PO verifies turbine trip PO verifies generator trip.
PO verifies power to AC emergency busses.
. PO recognizes and reports trip of 2-1 EDG.
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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.
BVPS - 2 NRC Scenario 3 RCS TAVG trending to 547F All MSIVs open.
Condenser available.
Steam header setpoint above existing steam header pressure.
Steam dump controller in Manual Demand at zero.
9 of 21 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.
Check RCS temperature stable at or trending to 547F.
PO 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
INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I
No MFPs running.
CRITICAL TASK #1:
STM PRESS Mode.
Controller in Auto.
Crew establishes the minimum required ARN flowrate to the SGs by manually starting an AFW pump.
2FWE*P23B running.
MFRVs closed.
AFW flow > 340 gpm.
Place steam dumps in STM PRESS Mode Place steam dump controller in AUTO Adjust controller setpoint to as necessary to maintain RCS temperature PO checks feedwater status.
Stop all but 1 Main Feed Pump Checks any SG low-low level reactor trip annunciators lit.
. Starts at least 1 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.
Verifies main feedwater regulating valves are closed.
. 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 performed as part of Attachment A-0.1 1 actions.
BVPS - 2 NRC Scenario 3 TAva stable.
Recirc spray pumps not running.
PORVs closed.
Spray valves at zero demand.
Safety valves closed PRT conditions normal.
Block MOVs open (except previously closed 2RCS*MOV537).
D/P between RCS pressure and highest SG pressure < 185 psid.
13 of 21 PO performs Attachment A-0.11, Verification of Automatic Actions.
(Steps listed at end of scenario guide.)
RO check RCS TAVG stable at or trending to 547yF.
RO checks recirc spray pumps are running.
RO checks PRZR PORVs, safety and spray valves.
RO checks PRT conditions are normal.
RO checks if RCPs should be stopped.
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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 steam flow from the ruptured SG before a transition to ECA9.1 occurs.
2SVS*PCV101 B in manual and closed.
2SVS*HCV104 closed.
RO places SG 21 B ADV in manual and closes.
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 101 B1 closed.
2SDS*AOVlllBl and 1 11 B2 closed.
PO verifies SG 21 B SG blowdown isolation valves are closed.
PO verifies SG 21 B steamline drain valves are closed.
BVPS - 2 NRC Scenario 3 15 of 21
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I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
EOP pre-emptive action 2SDS*AOV129A closed.
2MSS*AOVlOl B and 102B closed SG 218 level > 12%.
2FWE*HCVl OOC, D closed. (May have been previously performed.)
Main feedwater isolated.
SG 21 B pressure > 240 psig.
RO/PO verifies RHR piping drain valve is closed.
PO verifies SG 21 8 MSlV and bypass valves are closed.
PO checks SG 21 B level.
PO closes SG 21 B AFW throttle valves.
PO checks FWI - previously verified.
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.
RCS pressure < 1950 psig.
Total AFW flow >340 gpm or SG level between 27% and 50%.
PORVs closed; MOVs open (except previously closed 2RCS*MOV537).
SI reset.
CIA and CIB reset.
RCS at target temperature.
Station air compressors running.
PO verifies condenser available and initiates cooldown at maximum rate, (or uses SG atmospherics).
RO blocks steamline SI when RCS pressure reaches 1950 psig.
PO checks intact SG levels.
RO checks power to PORVs and block valves.
RO resets CIA and CIB.
PO stops RCS cooldown at target temperature.
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 Scenario may be terminated upon crew completion of cooldown to target temperature.
BVPS - 2 NRC Scenario 3 21AC-MOV130 and 131 open CNMT instrument air header pressure >
85 psig.
LHSl pumps previously stopped SG 21 B pressure stable.
Subcooling > 61 F.
18 of 21 PO establishes instrument air to CNMT.
PO checks CNMT instrument air header pressure > 85 psig.
RO checks if LHSl pumps should be stopped.
PO checks SG 21 B pressure stable or rising.
RO checks subcooling is satisfactory.
~ U C T I O N A L GUIDELINES 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-MOV1 OOA, 6 closed.
- b. Reset reheater controller.
Check If main steamline isolation required.
- a.
m m
rn b
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.
Verify steamline isolation:
YELLOW SLI marks - LIT.
BVPS - 2 NRC Scenario 3
JSE I
OBJECTIVE I EXPECTEDSTUDE-23
-A I N S I I I JCTIONAL GUIDELINES I 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 UNNl NG.
Align neutron flux monitoring for shutdown:
Check CIB and CNMT spray status.
NOTE: The RSS pumps will not 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 3 20 of 21
I OBJECTIVE I EXPECTED STUDENT RESPL _L]
13;.dCTIONAL GUIDELINES I PLANTSTATUS OR RE^ - ASE
-~
- b. Service water header pressure -
GREATER THAN 55 PSIG.
- c. SWS Pumps seal water pressure -
NOT LOW.
Verify both CNMT hydrogen analyzers
- RUNNING.
CRITICAL TASK #2:
Initiate at least one train of CIA prior to completion of Attachment A-0.1 1.
Verify ESF equipment status:
- 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