ML050900384
| ML050900384 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/15/2005 |
| From: | Hynes C FirstEnergy Nuclear Operating Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| Download: ML050900384 (74) | |
Text
Appendix D Scenario Outline Form ES-D-1 E-3.A, Isolate Ruptured SG
.O, Initiate CIA Train A Service Water Pump Trips. (Backup pump must be manually started.)
(C) ALL I Loss of 4KV Bus 2AE. 2-1 EDG Fails to Auto Start.
(M) ALL I MFW Pump A Degradatiomrip. Reactor Trip.
2-1 EDG Failure (C) PO MDAFW Train B Pump Auto Start Failure TDAFW Pump Auto Start Failure (M) ALL 1 SG B SGTR (when AFW is initiated).
(C) PO 1 CIA Fails To Automatically Actuate (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 3 The crew will assume the shift at approximately 25% power with instructions to raise power to 100%.
After initiation of the power increase, the running service water pump will trip. The backup pump will not start automatically and must be started manually by the RO.
When Technical Specifications have been addressed, 4KV Emergency Bus "ZAE" will be de-energized and the crew must manually start EDG 2-1 and reinitiate charging flow.
The Unit Supervisor will refer to Technical Specifications.
When the plant is stable, the running feedwater pump will trip requiring a reactor trip.
The 2-1 EDG will fail de-energizing 4KV Bus WAE". The Train ' B MDAFW pump and the TDARN pump will fail to automatically start requiring manual start by the operator.
When transition is made to ES-0.1 and AFW pumps have been started, a SGTR will develop requiring SI initiation. CIA valves will not automatically close requiring manual closure by the PO while performing Attachment A-0.11, Verification of Automatic Actions.
The scenario is terminated when the ruptured SG is isolated in E-3 and the crew has commenced an RCS cooldown.
EOP Flow Path: E-0, ES-0.1, E-0, E-3
RTL# A5.670.M 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: License Operator Traini ng/Licensed Requalif ication Training SUBDIVISION: Simulator SCENARIO TITLEINO.: 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 2LOT5 Scenario No. 3 Revision No. Date IN STRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hours PREPARED BY:
Date REVIEWED BY:
Date APPROVED FOR I M PLEMENTATION:
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 DATVTIME 00s TECHNICAL SPECIFICATION(S) 2RCS*PCV455D Yesterday 1500 3.4.11.a SHIFT TURNOVER INFORMATION
- 1. AOP-1/2.75.2 is in effect. River water level is 671 feet and stable.
- 2. Train 6is protected train.
- 3. Raise power to 100% after a trip due to loss of all circulating water.
SCENARIO SUPPORT MATERIAL REQUIRED 20M-52.4.A, Increasing Power From 5% Reactor Power And Turbine On Turning Gear To Full Load Operation Reactivity Plan for 12%/Hr. Power Ascension Protected Train 6 Wall Plaque
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
EVENT #1 Raise Power US directs power increase to 100% 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 2CHSFCV114A, 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 Settinu = 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 3of 21
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I 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. ZCHS'FCV114B opens OR open IF mode selector was in Manual.
- b. Verify correct flowrate on 2CHS-FR113.
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
INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE [ OBJECTIVE 1 EXPECTED STUDENT RESPONSE EVENT ##2 Train A$W Pump Trips. Backup 2sws*P21A trips, 2sWs*P216 fails to Pump Manually Started auto start.
When directed, insert the following RO recognizes loss of 2SWSP21 A command: Annunciators: and reports to US.
IMF PMP-SWSOOG (0 0 ) 1 [A1-4H], Service Water System Trouble
[A1-4f7, Service Water Pump Auto RO recognizes and reports StarVAuto Stop 2SWE*P21A failure to auto start.
2SWE*P21A running. RO manually starts 2SWPP21A.
US refers to AOP-2.30.1, Service Water/Normal Intake Structure Loss.
US directs local operator to rack 2SWS-P21C onto 2AE bus.
US refers to TS 3.7.4.1.
BVPS 2 NRC Scenario 3 5 of 21
INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 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 U nde rvoltage
[A8-G4], Diesel Gen Auto Start US enters AOP 2.36.2, Loss Of 4KV Emergency Bus
[A8-2A], 4160V 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.
2CHSP21A not running. RO stops charging pump that auto started on the EDG sequencer.
2RHS*P21A not running. Crew may elect to stop LHSI 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
[ INSTRUCTIONAL GUIDELINES ] PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #4 Loss of Feedwater 2FWS*P21A trips.
When directed, insert the following Crew identifies loss of main feedwater command: Annunciators: pump and SG feed flow.
IMF PMP-CFW004 (0 0) 1 [A6-8A], Reactor Trip 8 Low Tavg or SVMain Feedwater Valve Closed
[A6-1OA], SG Feed Pump 21 NB 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
INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 EVENTS #5,6, & 7 SG 21B SGTR, 2-1 EDG Failure, MDAFW Train 6Pump 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:
[A5601 lit. [A5-60] 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 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 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 Tnva trending to 547F. Check RCS temperature stable at or trending to 547F.
PO maintains RCS temperature:
All MSIV's open. . Check at least 1 MSlV open Condenser available. . Check condenser available Steam header setpoint above existing steam header pressure.
. Set steam header setpoint slightly 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
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I 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 AFW flowrate to the SGs by manually starting an AFW pump.
. Verifies AFW flow to each SG.
. 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
[ INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE [ EXPECTED STUDENT RESPONSE 1 All control rods inserted. RO verifies all control rods fully inserted.
When the crew reaches ES-0.1, Step 6, insert the following:
IMF RCS04B (0 0) 500 SG 21B 500 gpm SGTR.
PRZR level and pressure dropping RO maintains crew informed of PRZR rapidly. pressure and level.
Crew returns to E-0. US directs RO to actuate SI and returns to E-0.
Reactor tripped. RO reverifies reactor trip.
Turbine tripped. PO reverifies turbine trip.
Main generator tripped. PO reverifies generator trip.
2DF bus energized. PO reverifies power to AC emergency busses.
No. 2 EDG running. PO verifies 2-2 EDG is running.
BVPS 2 NRC Scenario 3 11 of21
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE^
SI actuated. RO manually actuates SI both trains.
RO/PO sound Standby alarm and announce Unit 2 reactor trip and SI.
2HVSFN204NB running PO checks leak collection filtered exhaust fan is running.
2CHS*P23B running. RO/PO verifies two charging pumps are running.
HHSl flow indicated. RO checks HHSl flow is indicated.
LHSl pumps running. RO/PO check LHSl pumps are both running.
PO verifies AFW status.
AFW throttle valves full open. AFW throttle valves full open AFW flow >340gpm. Total AFW flow > 340 gpm.
BVPS - 2 NRC Scenario 3 12 of 21
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 NOTE: CRITICAL TASK #2 is PO performs Attachment A-0.11, performed as part of Attachment Verification of Automatic Actions.
A-0.11 actions. (Steps listed at end of scenario guide.)
TAVG stable. RO check RCS TAvastable at or trending to 547QF.
Recirc spray pumps not running. RO checks recirc spray pumps are running.
PORV's closed. RO checks PRZR PORV's, 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 MOV's.
Block MOV's open (except previously closed 2RCS*MOV537).
D/P between RCS pressure and highest RO checks if RCP's should be SG pressure < 185 psid. stopped.
BVPS 2 NRC Scenario 3 13 of 21
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 No SG pressures dropping in an Crew checks if any SG's are faulted uncontrolled manner.
SG 216 level rising in an uncontrolled PO checks if SG tubes are intact.
manner.
Secondary radiation high.
Crew enters E-3. US makes transition to E-3 and informs crew.
CREVS not actuated, nor required. PO checks if CREVS is actuated.
2RMC*RQ201 202 not in high alarm.
CIB has not occurred.
D/P between RCS pressure and highest RO checks if RCP's should be SG pressure < 185 psid. stopped.
SG 21 B ruptured. Crew identifies ruptured SG.
Unexpected rise in NR level.
US directs RadCon to initiate steamline su weys .
BVPS 2 NRC Scenario 3 14 of 21
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 CRITICAL TASK #3:
Crew isolates feed flow into and 2SVS*PCVlOlB in manual and closed. RO places SG 21B ADV in manual and steam flow from the ruptured SG closes.
before a transition to ECA-3.1 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+28is 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*AOVlOOBl and 101I31 closed. PO verifies SG 21 B SG blowdown isolation valves are closed.
2SDS*AOVlll B1 and 111B2 closed. PO verifies SG 218 stearnline drain valves are closed.
BVPS 2 NRC Scenario 3 15 of 21
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 2SDS*AOV129A closed RO/PO verifies RHR piping drain valve is closed.
2MSS*AOVlOl B and 1028 closed. PO verifies SG 21B MSlV and bypass valves are closed.
SG 21 B level > 12%. PO checks SG 21 B level.
EOP pre-emptive action. 2FWEHCVl OOC,D closed. (May have PO closes SG 21B ANV throttle been previously performed.) valves.
Main feedwater isolated. PO checks FWl - previously verified.
SG 21 B pressure > 240 psig. PO checks SG 21B 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
[ INSTRUCTlONAL GUlDELtNES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSEI)
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.
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
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I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPC 2 1 OBJECTIVE I EXPECTED STUDENT RESP0N.C 7 ATTACHMENT A-0.1 1, Verification Of Automatic Actions Diesel generators - BOTH RUNNING Ensure reheat steam isolation:
- a. Verify 2MSS-MOViOOA, 8 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.
. 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 19 of 21
I INS I , ,JCTIONAL GUIDELINES I PLANT STATUS OR RESt , JSE 1 OBJECTIVE I EXPECTED STUDENT RESPC -7 Establish domestic water system cooling to station air compressors:
- a. Open 2CCS-AOVl18
- b. Check station air compressors -
ONE RUNNING.
Check CCP Pumps - AT LEAST ONE RUNNING.
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
. 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 TR A I N) .
BVPS 2 NRC Scenario 3 20 of 21
,dCTIONAL GUIDELINES I PLANT STATUS OR RE5 ,\ISE I OBJECTIVE I EXPECTED STUDENT RESPC a
- 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: 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 SM/US.
BVPS 2 NRC Scenario 3 21 of 21
Appendix D Scenario Outline Form ES-D-1 Facility: BVPS-2 Examiners: Candidates: CRS RO I 1 I I PO Initial Conditions: MOL, 48% power.
2CHS*P21C, HHSI Pump 00s.
2RCS*PCV455D leakage. 2RCS*MOV-537, Block Valve closed with power maintained.
Flood warnings due to heavy rains.
Maintenance investigating 2SWSP21A, Service Water Pump abnormal vibration/ noise.
Turnover: Reduce power to take the unit off-line due to circulating water intake clogging.
Critical Tasks: E-0.1, Start Train B HHSI E
=
S Event Malf. No.
No.
1 Event Description Reduce Power 2 MSS005A SG Level Transmitter Fails High 3 DSGO1B Train 6(2-2) EDG Failure 4 LDS007A (C) RO, Letdown Pressure Control Valve Fails Closed In Auto us 5 cFw1OB SG A FRV Controller Fails Closed In Auto 6 RCS02A (C) RO, RCS Leak us (TS) us RCS02A (M) ALL SBLOCA PPL07A Train A HHSVCharging Pump Auto Start Failure PPLO7B AFW Start Failure (Auto SI Failure Train B)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 2 The crew will assume the shift at 48% power with directions to reduce power to take the unit off-line due to circulating water intake clogging.
As power is being reduced, a SG "B" level transmitter will fail high requiring the Unit Supervisor to refer to Technical Specifications.
When the Unit Supervisor has reviewed Technical Specifications, a fuel oil leak on the 2-2Emergency Diesel Generator will occur making it inoperable. This failure provides the Unit Supervisor with an additional Technical Specification referral and sets up required actions post-trip.
When Technical Specifications have been addressed, the letdown pressure control valve will fail closed requiring the RO to take manual control to restore letdown flow.
When letdown is restored, SG " A main feedwater control valve will fail closed in automatic requiring the PO to take manual control to stabilize SG level.
When SG level is stabilized, an RCS leak will develop. When the Unit Supervisor refers to Technical Specifications, the leak will degrade into a SBLOCA requiring a reactor trip and safety injection actuation by the crew.
The Train "A" HHSVCharging Pump will fail to automatically start and must be started manually. RCP's must be tripped when criteria is met due to the LOCA. Train "B" AFW Pump must be started manually by the operator.
The scenario may be terminated upon entry to ES-1.2, Post LOCA Cooldown And Depressurization, or when RCS cooldown is initiated.
EOP Flow path: E-0, E-I, ES-1.2
RTL# A5.670.W 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 SCENAR IO T ITLUN0.: 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 2LOT5 Scenario No. 4 1 ~
Revision No. f Date Revision No. I Date 1 12-7-04 I
INSTR UCT IONAL SETTING: SimuI ato r APPROXIMATE DURATION: 1.5 Hours PREPARED BY:
Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date BVPS-2 NRC Scenario 4 Page 1 of 23
INITIAL CONDITIONS:
. IC-146; PW = NRC2; 48% power, RCS Boron 2CHS*P21C 00s.
ppm.
.. 2RCS*PCV455D 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 STlCKERS VOND MARKINGS EQUIPMENT STATUS 1 DATWIMEOOS I TECHNICAL SPECIFICATION(S) 12RCSPCV456 I Yesterday 1500 1 3.4.1 1.a I
SHIFT TURNOVER INFORMATION
- 1. AOP-1275.2 is in effect. River water level is 671 feet and stable.
- 2. 2SWS*P21A, Service Wafer Pump is operable, but investigation of noisehibration is ongoing.
- 3. Train 6is protected train.
- 4. Reduce power to take the unit off-line due to circulating water intake clogging.
SCENARIO SUPPORT MATERIAL REQUIRED 20M-52.4.BI Load Following, Step IV.B.5 Reactivity Plan for 12% per hour power reduction Protected Train 6Wall Plaque
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I 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.B, 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
- 2GFof 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 I PLANT STATUS OR RESPONSE 1 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.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 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 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1
- 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 InleVOutlet a. lnservice 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-FR113.
BVPS 2 NRC Scenario 2 5 of 21
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I When directed, insert the following command:
An nunciator:
IMF XMT-MSSOOSA (0 0 ) 100 [A6-D10], 21 B SG HI LEVEL PO refers to ARP.
NOTE: No system response US refers to 20M-24.4.F 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
[ 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 DSGOl 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
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
EVENT #4 Letdown Pressure Control Valve 2RCS*PCV145 fails closed resulting in a Faits Ctosed In Auto loss of normal letdown.
When directed, insert the following RO notes indications and alarms.
command:
Annunciator:
IMF XMT-LDS007A (0 0 ) 0 [A2-3FJ,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 2 C HS PCV145.
BVPS 2 NRC Scenario 2 8 of 21
INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE EVENT #5 SG 21A MFRV Controller Fails In 2FWSFCV478, Main Feed Reg Valve Auto controller fails closed.
When directed, insert the following command:
IMF CNH-CFWIOB (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 21A feed flow oscillation.
SG 21A MFRV position and feed flow PO takes manual control of SG 21 A 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
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
EVENT #6:
RCS Leak 25 gpm RCS leak in CTMT.
When directed, insert the following Crew responds to indications and command: alarms.
IMF RCSO2A (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-RQ1100, 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
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE ]
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-51.1.
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
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I EVENTS #7 & 8:
RCS Leak degrades into SBLOCA; RCS leak rises to 700 gpm Train 6HHSl 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 A5-6D1Turbine 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 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I 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 A not 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 HHSI 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
lNSJRUCJJONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 LHSl pumps are running. RO/PO checks both LHSl pumps are running .
A MDAFW and TDAFW pumps PO verifies AFW status.
running. BMDAFW pump not running.
B MDAFW pump running PO manually starts 2FWE*P23B.
AFW flow > 340 gpm. PO performs Attachment A-0.11 I Verification of Automatic Actions.
(Steps listed to end of scenario guide.)
TAVG stable. RO check RCS TAvostable at or trending to 547QF.
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 normat.
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
[ INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I 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 rapidly.
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 (or due to ClB) and prior to exiting Procedure E-1.
BVPS 2 NRC Scenario 2 15 of 21
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[ INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I Check Aux. Bldy. and Safeguards radiation consistent with pre-event values.
Obtain samples.
Start additional plant equipment to assist in recovery.
1 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
[ INS7 ,JCTIONAL GUIDELINES I PLANT STATUS OR RESF , &E I OBJECTIVE 1 EXPECTED STUDENT RESPO. 2 ATTACHMENT A-0.11, 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-MOW 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.
. Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS.
- b. Verify steamline isolation:
YELLOW SLl marks - LIT BVPS 2 NRC Scenario 2 19 of 21
1 .
INS I JCTIONAL GUIDELINES I I PLANT STATUS OR RESt .4SE I OBJECTIVE 1 EXPECTED STUDENT RESPC -1 Establish domestic water system cooling to station air compressors:
- a. Open 2CCS-AOVll8.
- 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 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 TRAlN).
BVPS 2 NRC Scenario 2 20 of 21
I INS ,dCTIONAL GUIDELINES I PLANT STATUS OR RESt ,JSE I OBJECTIVE I EXPECTED STUDENT RESPC
- 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 FWl 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 of21
Appendix D Scenario Outline Form ES-D-1 Facility: BVPS-2 I Scenario NO.: 1 1 I OpTest No.: I NRC Examiners: Candidates: CRS RO I I I Initial Conditions: BOL, 100% Power 2CHSP21C, HHSl Pump 00s.
2RCSPCV455D leakage. 2RCS*MOV-537, Block Valve closed with power maintained.
Flood warnings from heavy rains.
Maintenance investigating 2SWS*P21A, Service Water Pump abnormal vibrationhoise.
Turnover: Initiate power reduction to 75% for waterbox cleaning.
Critical Tasks: FR-S.1 .C, Initiate RCS bration andor insert RCCA's LA, Isolate F JRed SG Event P-Type' Event Description 1 (R) RO Power Reduction for Waterbox Cleaning (N) PO, US 2 EHCOG (C) ALL Turbine Control Valve failure (Load Rejection)
CRFOlA (TS)us Control Rods Fail in Auto 3 RCS031A (I)RO, US Pressurizer Pressure Transmitter Fails High (TS)us ~~
4 MSS047A (I)PO, us SG Pressure Transmitter Fails Low (TS)us ~~
5 EHCO7 (M) ALL Turbine Trip - Steam Dump Failure. Reactor Trip required.
xc2 10790 6 PPLOlA (C) RO, US Auto and Manual Reactor Trip Failure PPLOlB ~
7 MSS02A (C) PO, us One SG Atmosphere Dump Valve Fails Partially Open (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario Event Description NRC Scenario 1 The crew will assume the shift at 100% power with instructions to reduce load to 75% for waterbox cleaning.
A turbine load rejection will occur due to a turbine valve position limiter failure requiring the crew to stabilize the plant by matching Tave and Tref, and resetting condenser steam dump valves.
After Technical Specifications have been addressed and the plant is stable, Pressurizer Pressure Channel PT-445 will fail high slowly requiring the RO to take manual control of Pressurizer heaters, spray valves, and PORVs. The Unit Supervisor will then address Technical Specifications.
When RCS pressure is stable, SG Pressure Transmitter PT-476 will fail low causing the steam flow signal to its associated SG main feedwater control valve to fail low. The PO will take manual control of the affected valve to prevent RPS actuation on SG low-low level.
When SG level is under control and Technical Specifications have been addressed, a turbine trip will occur with a steam dump failure requiring a reactor trip.
Upon reactor trip, the reactor trip breakers will not open automatically or manually. The RO must insert control rods and initiate emergency boration. The Unit Supervisor will direct crew response in accordance with the ATW S Functional Recovery procedure.
A faulted SG develops due to a stuck open SG atmospheric dump valve requiring transition to E-2 to isolate the faulted SG. The scenario is terminated upon completion of E-2, or upon transition to ES-1 .l.
EOP Flow Path: E-0, FR-S.1, E-0, E-2
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: Simu1ator SCENARIO TITLE/NO.: 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 2LOT5 Scenario No. 1
- Revision No. 1 Date t Revision NO. 1 I
Date 1 I 12-7-04 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hours PREPARED BY:
Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date BVPS 2 NRC Scenario 1 Page 1 of 26
INITIAL CONDITIONS: IC-181 PW = NRC1; 100% Power, RCS Boron ppm 8
2CHS*P21C, HHSVCharging Pump 00s for repair.
8 2RCS*PCV455D leakage. 2RCS*MOV537, Block Valve closed with power maintained.
Flood warnings from heavy rains.
8 Maintenance investigating 2SWS*P21A, Service Water Pump vibrationhoise.
1 ADDITIONAL LINEUP CHANGES I STICKERS VOND MARKINGS I
I EQUIPMENT STATUS DATElTIME 00s TEC HNICA L S PECIFICAT10 N( S )
2RCS*PCV455D Yesterday 1500 3.4.11.a SHIFT TURNOVER INFORMATION
- 1. 2SWS*P21A, Service Water Pump is operable, but abnormal vibrationhoise 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.Bl Load Following Reactivity Plan for 12%/Hr Power Reduction Protected Train B Wall Plaque
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #1 Reduce power to 75% 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 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%/hr. 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 1 3 of 26
[ INSTRUCTIONAL GUIDELINES [ PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1
- 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 [2CHSFCV113A] as follows:
Pot Setting = Boric Acid Flow 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 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I 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*FCVl13Bl 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-FRll3.
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 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE ] 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 Operations.
BVPS 2 NRC Scenario 1 6 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
EVENT #2 Turbine Control Valve Failure (Load Rejection) Annunciators:
IMF EHCO6 (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 INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I 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 2".
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
I 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
I I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 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
[A4-1D], Pressurizer Control Pressure US refers to 20M-6.4.IFI Attachment 2.
HighlLow
[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 4550 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
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 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
[A6-9Fl1Loop A Feedwater Flow >
Steam Flow
[A6-9GIl Loop A Steamline Pressure Low SG 21A Channel 3 2MSSPT476 fails low.
SG 21 A channel 3 steam flow drops (density Compensation input).
SG 27A feed flow, NR level drops. PO notes problem with SG 21 A level control, takes manual control of 2FWSFCV478 and informs US.
2FWS*FCV478 modulates closed in automatic.
Loop 1 steamline pressure feed flow >
steam flow alarms.
BVPS 2 NRC Scenario 1 11 of26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 NOTE: Level deviation is SG 21 A level deviation. Crew determines that steam pressure dependent on time of channel 2MSSPT476 failed low.
establishing normal MFRV control to restore SG level.
US refers to 20M-24.4.IF, Attachment 4.
US 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
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE ] EXPECTED STUDENT RESPONSE 1 IMF BST-PCSO29 (0 0) 0 2LS/476C (BS-2) High-High FWI.
IRF LOA-PCS003 (0 0) 0 Protection Rack C3 Door closed.
IRF LOA-PCS004 (0 0) 1 Protection Rack C4 Door Open.
IMF BST-PCSO77 (0 0) 0 2PS/476A (BS-1) Low Pressure SI and SLI.
IMF BST-PCS068 (0 0) 0 2PS/476B (BS-2) High Pressure Rate s LI 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
[ INSTRUCTIONAL GUIDELINES [ PLANT STATUS OR RESPONSE I 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 66-A reactor trip pushbutton to attempt reactor trip.
Crew enters FR-S.1. Control rods remain withdrawn. US enters FR-S.1 and announces entry to crew.
Turbine trips. PO presses both turbine trip pushbuttons.
BVPS - 2 NRC Scenario 1 14 of 26
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 PO/RO verifies TWFis 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.
2CHSP21A and 6 running. . Verifies at least 1 charging pump running SI not actuated. Verifies SI not actuated 2CHSMOV350 open. Opens 2CHSMOV350 Boric acid transfer pump running in Starts boric acid transfer pump fast speed.
Boration flow > 30 gpm. . Verifies emergency boration flow >
30 gpm Charging flow > 40 gpm. . Adjusts [2CHSFCV122] to establish charging flow > 40 gpm PZR pressure is < 2330 psig. Checks PZA pressure less than 2330 Psig BVPS - 2 NRC Scenario 1 15 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I 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
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Power range indicates < 5%. 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 open.
. Annunciator A5-6D, Turbine Trip Due 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
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
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.
[2H V SFN204A/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 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I 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.)
TAVGlowering.
RO check RCS TAVG stable 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
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE [ OBJECTIVE 1 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 216and 21C pressures PO checks for any non-faulted SG.
stable.
BVPS 2 NRC Scenario 1 20 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
SG 21 A pressure dropping PO identifies 21A SG as faulted.
uncontrollably.
All green FWI marks are lit. PO verifies FWI green marks previously verified.
PO closes AFW throttle valve on SG 2 1A.
Residual heat release valve closed. RO checks RHR valve closed.
US/RO direct operator to locally close 2svs*27.
Operator dispatched to locally close 2MSS15.
CRITICAL TASK #2:
Isolate feed flow into and steam SG 21 A ADV not closed. RO attempts to close SG 21A ADV.
flow out of faulted SG.
Operator is dispatched to locally close 2SVS*23, SG A ADV isolation valve.
BVPS 2 NRC Scenario 1 21 of26
INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE ]
2BDGAOVlOOAl closed. Verify SG B/D isolation valve from SG 21A is closed.
Check PPDWST level > 85 inches.
No SGTR is indicated. Crew checks if SG tubes are intact.
SI Termination Criteria is met. Crew checks if SI flow should be reduced.
Crew transitions to ES-1.l. US transitions to ES-1.1, SI Termination.
Scenario may be terminated upon transition to ES-1.l.
BVPS - 2 NRC Scenario 1 22 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 ATTACHMENT A-0.1 1, Verification Of Auto matic 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.
. 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 INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1
- 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 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
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I 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.
- 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.
BVPS 2 NRC Scenario 1 25 of 26
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