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 MDAFW Train B Pump Auto Start Failure TDAFW Pump Auto Start Failure (C) PO (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
- 1 -
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 Revision No.
1/2-ADM-1357.F11 Page 1 of 1 Revision 0 Date SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
SUBDIVISION:
SCENARIO TITLEINO.:
COMPUTER CODE FOR L.P.:
License Operat or Trai ni ng/Licen sed Requ alif icati on Training Simulator 2005 NRC Initial License Exam 2LOT5 Scenario No. 3 I N STRUCTION AL SETTING:
Simulator APPROXIMATE DURATION:
1.5 Hours PREPARED BY:
REVIEWED BY:
APPROVED FOR I M P LE ME NTAT ION :
Date Date Date BVPS-2 NRC Scenario 3 Page 1 of 21
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.
ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS EQUIPMENT STATUS DATVTIME 00s TECHNICAL SPECIFICATION(S)
SHIFT TURNOVER INFORMATION
- 1.
AOP-1/2.75.2 is in effect. River water level is 671 feet and stable.
- 2.
Train 6 is protected train.
- 3.
Raise power to 100% after a trip due to loss of all circulating water.
2RCS*PCV455D 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 Yesterday 1500 3.4.1 1.a
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% 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 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.
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.
INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE
[ OBJECTIVE 1 EXPECTED STUDENT RESPONSE EVENT ##2 Train A
$W Pump Trips. Backup Pump Manually Started auto start.
When directed, insert the following command:
IMF PMP-SWSOOG (0 0) 1 2sws*P21 A trips, 2sWs*P216 fails to Annunciators:
[A1 -4H], Service Water System Trouble
[A1 -4f7, Service Water Pump Auto StarVAuto Stop 2SWE*P21 A running.
RO recognizes loss of 2SWSP21 A and reports to US.
RO recognizes and reports 2SWE*P21 A failure to auto start.
RO manually starts 2SWPP21A.
US refers to AOP-2.30.1, Service Water/Normal 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
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 command:
IMF BKR-HIVO1 (0 0) 0
[A8-C2], 4160V Emerg Bus 2AE U n de rvol t age
[A8-G4], Diesel Gen Auto Start
[A8-2A], 41 60V Emerg Bus 2AE ACB 2A10/2E7 Auto Trip If previously racked onto 2AE Bus.
2SWS-P21C auto starts.
2CHSP21A not running.
2RHS*P21A not running.
2SWE*P21 A running.
Crew responds to indications and alarms.
US enters AOP 2.36.2, Loss Of 4KV Emergency Bus RO starts standby charging pump.
PO starts 2-1 EDG.
RO stops charging pump that auto started on the EDG sequencer.
Crew may elect to stop LHSI pump.
PO manually restarts 2SWE*P21A.
BVPS - 2 NRC Scenario 3 6 of 21 US refers to TS 3.8.1.1 Action c.
[
INSTRUCTIONAL GUIDELINES ]
PLANT STATUS OR RESPONSE I OBJECTIVE I 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.
[A6-8A], Reactor Trip 8 Low Tavg or SVMain Feedwater Valve Closed
[A6-1OA], 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
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 6 Pump Fails To Auto Start; CIA Fails To Auto Actuate Pre-loaded Commands Crew continues with E-0.
[A5601 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.
RO manually trips reactor.
RO verifies reactor trip:
[A5-60] lit.
Power range indication < 5%
.. Neutron flux dropping.
PO verifies turbine trip.
PO verifies generator trip.
PO verifies power to AC emergency 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.
BVPS - 2 NRC Scenario 3 RCS Tnva trending to 547F.
All MSIV's 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
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
STM PRESS Mode.
Controller in Auto.
No MFPs running.
CRITICAL TASK #1:
Crew establishes the minimum required AFW flowrate to the SGs by manually starting an AFW pump.
2FWE*P23B running.
MFRVs closed.
AFW flow > 340 gpm.
BVPS - 2 NRC Scenario 3 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.
. 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.
10 of 21
[ INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE 1 OBJECTIVE [
EXPECTED STUDENT RESPONSE 1 When the crew reaches ES-0.1, Step 6, insert the following:
IMF RCS04B (0 0) 500 Crew returns to E-0.
BVPS - 2 NRC Scenario 3 All control rods inserted.
PRZR level and pressure dropping rapidly.
Reactor tripped.
Turbine tripped.
Main generator tripped.
2DF bus energized.
No. 2 EDG running.
11 of21 RO verifies all control rods fully inserted.
RO maintains crew informed of PRZR pressure and level.
US directs RO to actuate SI and returns to E-0.
RO reverifies reactor trip.
PO reverifies turbine trip.
PO reverifies generator trip.
PO reverifies power to AC emergency busses.
PO verifies 2-2 EDG is running.
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE^
BVPS - 2 NRC Scenario 3 SI actuated.
2HVSFN204NB running 2CHS*P23B running.
HHSl flow indicated.
LHSl pumps running.
AFW throttle valves full open.
AFW flow >340 gpm.
12 of 21 RO manually actuates SI both trains.
RO/PO sound Standby alarm and announce Unit 2 reactor trip and SI.
PO checks leak collection filtered exhaust fan is running.
RO/PO verifies two charging pumps are running.
RO checks HHSl flow is indicated.
RO/PO check LHSl pumps are both running.
PO verifies AFW status.
AFW throttle valves full open Total AFW flow > 340 gpm.
[
INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 NOTE: CRITICAL TASK #2 is performed as part of Attachment A-0.11 actions.
BVPS - 2 NRC Scenario 3 TAVG stable.
Recirc spray pumps not running.
PORV's closed.
Spray valves at zero demand.
Safety valves closed.
PRT conditions normal.
Power available to PORV MOV's.
Block MOV's 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 TAva stable at or trending to 547QF.
RO checks recirc spray pumps are running.
RO checks PRZR PORV's, safety and spray valves.
RO checks PRT conditions are normal.
RO checks if RCP's should be stopped.
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Crew enters E-3.
BVPS - 2 NRC Scenario 3 No SG pressures dropping in an uncontrolled manner.
SG 216 level rising in an uncontrolled manner.
Secondary radiation high.
CREVS not actuated, nor required.
2RMC*RQ201 202 not in high alarm.
CIB has not occurred.
D/P between RCS pressure and highest SG pressure < 185 psid.
SG 21 B ruptured.
Unexpected rise in NR level.
14 of 21 Crew checks if any SG's are faulted PO checks if SG tubes are intact.
US makes transition to E-3 and informs crew.
PO checks if CREVS is actuated.
RO checks if RCP's should be stopped.
Crew identifies ruptured SG.
US directs RadCon to initiate steamline su we ys.
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 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 ECA-3.1 occurs.
2SVS*PCVlOlB 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*AOVlOOBl and 101 I31 closed.
2SDS*AOVlll B1 and 11 1 B2 closed.
PO verifies SG 21 B SG blowdown isolation valves are 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 EOP pre-emptive action.
2SDS*AOV129A closed 2MSS*AOVlOl B and 1028 closed.
SG 21 B level > 12%.
2FWEHCVl 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 B MSlV and bypass valves are closed.
PO checks SG 21 B level.
PO closes SG 21 B ANV throttle valves.
PO checks FWl - previously verified.
PO checks SG 21 B 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 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
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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 CIB signal is initiated.
BVPS - 2 NRC Scenario 3 20 of 21
. Containment pressure - HAS REMAINED LESS THAN 8 PSIG.
Verify service water system in service:
- a. Service Water Pumps - TWO RUNNING (ONE PUMP PER T R A I N ).
,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:
Initiate at least one train of CIA prior to completion of Attachment A-0.1 1.
BVPS - 2 NRC Scenario 3 21 of 21 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.
Appendix D Scenario Outline Form ES-D-1 Facility:
BVPS-2 Examiners:
Candidates:
Turnover:
Critical Tasks:
Event No.
1 2
3 4
5 6
I 1
I I PO MOL, 48% power.
2CHS*P21 C, HHSI Pump 00s.
2RCS*PCV455D leakage. 2RCS*MOV-537, Block Valve closed with power maintained.
Flood warnings due to heavy rains.
Maintenance investigating 2SWSP21 A, Service Water Pump abnormal vibration/ noise.
Reduce power to take the unit off-line due to circulating water intake clogging.
E-0.1, Start Train B HHSI S
E
=
Malf. No.
Event Description Reduce Power SG Level Transmitter Fails High MSS005A Train 6 (2-2) EDG Failure DSGO1 B Letdown Pressure Control Valve Fails Closed In Auto (C) RO, us LDS007A cFw1 OB SG A FRV Controller Fails Closed In Auto RCS02A (C) RO, us RCS Leak (TS) us (M) ALL RCS02A SBLOCA PPL07A Train A HHSVCharging Pump Auto Start Failure AFW Start Failure (Auto SI Failure Train B)
PPLO7B (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
- 1 -
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 2-2 Emergency 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 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 12-7-04 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
License Operator Training/licensed Requalification Training SUBDIVISION:
Simulator SC EN AR IO T ITLUN 0. :
2005 NRC Initial License Exam COMPUTER CODE FOR L.P.:
2LOT5 Scenario No. 4 1 Revision No. f Date I Revision No. I Date I N STR U CT IO N AL SETTING :
Si mu I at o r APPROXIMATE DURATION:
1.5 Hours PREPARED BY:
REVIEWED BY:
APPROVED FOR IMPLEMENTATION:
Date Date Date BVPS-2 NRC Scenario 4 Page 1 of 23
INITIAL CONDITIONS:. IC-146; PW = NRC2; 48% power, RCS Boron ppm.
. 2CHS*P21 C 00s.
2RCS*PCV455D 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.
ADDITIONAL LINEUP CHANGES STlC KERS VOND MARKINGS EQUIPMENT STATUS 1
DATWIMEOOS I
TECHNICAL SPECIFICATION(S) 12RCSPCV456 I
I Yesterday 1500 1
3.4.1 1.a SHIFT TURNOVER INFORMATION
- 1.
AOP-1275.2 is in effect. River water level is 671 feet and stable.
- 2.
2SWS*P21 A, Service Wafer Pump is operable, but investigation of noisehibration is ongoing.
- 3.
Train 6 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.BI Load Following, Step IV.B.5 Reactivity Plan for 12% per hour power reduction Protected Train 6 Wall Plaque
1 INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I 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.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).
- 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
- 2GF 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 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:
[A2-2E], Boric Acid Blender InleVOutlet Deviation from SP Verify the following:
- a. lnservice 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-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 nu nciato r:
IMF XMT-MSSOOSA (0 0) 100
[A6-D10], 21 B SG HI LEVEL 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.
BVPS 2 - NRC Scenario 2 PO refers to ARP.
US refers to 20M-24.4.F US refers to Technical Specifications TS 3.3.1.1 item 14 and TS 3.3.2.1, item 5.a, 7.a.
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)
Outside Operator reports local alarm is for EDG start failure.
BVPS 2 - NRC Scenario 2
[A8-5E], Diesel Gen 2-2 Local Panel Trouble 7 of 21 PO refers to ARP Crew dispatches Outside Operator to investigate local alarm.
US refers to Technical Specification TS 3.8.1.1, Action b.
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
EVENT #4 Letdown Pressure Control Valve Faits Ctosed 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
[A2-3FJ, Letdown Flowpath Trouble RO notifies US. Refers to ARP.
Letdown backpressure 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 2 C HS PCV 1 45.
BVPS 2 - NRC Scenario 2 8 of 21
INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE EVENT #5 SG 21 A MFRV Controller Fails In Auto controller fails closed.
2FWSFCV478, Main Feed Reg Valve When directed, insert the following command:
IMF CNH-CFWIOB (0 0) 0 300
[A6-9H], Loop A Steam Flow >
Feedwater Flow PO recognizes feed flow problem and 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 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
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 command:
IMF RCSO2A (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-RQ1100, 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
[
INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE ]
NOTE: If contacted by US, SM may direct an emergency shutdown per 20M-51.1.
Slight rise in containment temperature may not be noticeable.
Aux. Bldg. radiation normal.
PRZR level remains stable.
RO checks containment temperature normal.
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
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I EVENTS #7 & 8:
RCS Leak degrades into SBLOCA; Train 6 HHSl Auto Start Failure; Train A ESF Components Manually Started When directed, insert the following command:
IMF RCSOPA (0 0 ) 700 300 Crew enters E-O.
BVPS 2 - NRC Scenario 2 RCS leak rises to 700 gpm RCS pressure and Pressurizer level rapidly lowering.
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.
12 of 21 US orders reactor trip and entry to E-0.
RO verifies reactor tripped:
. Annunciator A5-6D1 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.
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
CRITICAL TASK #1:
Crew manually actuates at least one train of SIS actuated safeguards before transition to any ORP.
SI actuated.
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.
PO checks leak collection filtered exhaust fan running.
RO verifies HHSI pumps are running.
. Manually starts 2CHS*P21 A.
. 2CHS*P21 B does not start.
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.
A MDAFW and TDAFW pumps running. B MDAFW pump not running.
B MDAFW pump running 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 10-15 minutes of reactor trip.
RO/PO checks both LHSl pumps are running.
PO verifies AFW status.
PO manually starts 2FWE*P23B.
PO performs Attachment A-0.1 1 I
Verification of Automatic Actions.
(Steps listed to end of scenario guide.)
RO check RCS TAvo stable at or trending to 547QF.
RO checks recirc spray pumps running.
RO checks PRZR isolated.
RO checks PRT conditions are normat.
RO checks if RCPs should be stopped.
BVPS 2 - NRC Scenario 2 14 of 21
[
INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
Crew transitions to E-1.
No SG levels rising in an uncontrolled manner.
RCS pressure and PRZR level decreasing rapidly.
CREVS not actuated or required.
D/P between RCS pressure and highest SG pressure < 185 psid.
CRITICAL TASK #2:
Crew trips all RCPs when RCS to highest SG D/P criteria is exceeded (or due to ClB) and prior to exiting Procedure E-1.
All RCPs stopped. (May have been previously stopped.)
BVPS 2 - NRC Scenario 2 15 of 21 Crew checks if any SGs are faulted.
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.
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[
INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I 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.
18 of 21 Check Aux. Bldy. and Safeguards radiation consistent with pre-event values.
Obtain samples.
Start additional plant equipment to assist in recovery.
1 Check if RCS cooldown and depressurization required.
US transition to ES-1.2, Post LOCA Cooldown And Depressurization.
[
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 start.
Diesel generators - BOTH RUNNING 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 I. JCTIONAL GUIDELINES 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 start until 10.5 minutes after the CIB signal is initiated.
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 TRAl N).
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 I
I I
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*P21 A, Service Water Pump abnormal vibrationhoise.
Initiate power reduction to 75% for waterbox cleaning.
FR-S.1.C, Initiate RCS bration andor insert RCCA's LA, Isolate F Event Type' (R) RO P-(N) PO, US (C) ALL (TS) us (I) RO, US (TS) us (I) PO, us (TS) us (M) ALL Facility:
BVPS-2 I Scenario NO.:
1 1 I OpTest No.:
I NRC Examiners:
Candidates:
Turnover:
Critical Tasks:
1 2
EHCOG CRFOl A 3
RCS031 A 4
MSS047A 5
EHCO7 xc2 10790 6
PPLOl A PPLOl B 7
MSS02A (C) RO, US
~
(C) PO, us JRed SG Event Description Power Reduction for Waterbox Cleaning Turbine Control Valve failure (Load Rejection)
Control Rods Fail in Auto Pressurizer Pressure Transmitter Fails High
~~
SG Pressure Transmitter Fails Low
~~
Turbine Trip - Steam Dump Failure. Reactor Trip required.
Auto and Manual Reactor Trip Failure 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
- Revision No. 1 Date 1
I 12-7-04 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
SUBDIVISION:
SCENARIO TITLE/NO.:
COMPUTER CODE FOR L.P.:
INSTRUCTIONAL SETTING:
APPROXIMATE DURATION:
PREPARED BY:
REVIEWED BY:
License Operator Training/Licensed Requalification Training Si mu1 at or 2005 NRC Initial License Exam 2LOT5 Scenario No. 1 t Revision NO. 1 Date I
Simulator 1.5 Hours Date Date APPROVED FOR IMPLEMENTATION:
Date BVPS - 2 NRC Scenario 1 Page 1 of 26
INITIAL CONDITIONS:
8 8
8 I
EQUIPMENT STATUS DATElTIME 00s 2RCS*PCV455D Yesterday 1500 IC-1 81 PW = NRC1; 100% Power, RCS Boron ppm 2CHS*P21 C, HHSVCharging 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 vibrationhoise.
TEC H N IC A L S P EC I FIC AT10 N (S) 3.4.1 1.a STICKERS I
1 ADDITIONAL LINEUP CHANGES VOND MARKINGS I
SHIFT TURNOVER INFORMATION
- 1.
- 2.
- 3.
- 4.
2SWS*P21 A, Service Water Pump is operable, but abnormal vibrationhoise 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.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 hour BVPS - 2 NRC Scenario 1 Turbine load and reactor power decreasing at 12%/hr.
3 of 26 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).
- 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.
[
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.
BVPS - 2 NRC Scenario 1 An nunciator:
[A2-2E], Boric Acid Blender Inlet/Outlet Deviation from SP 5 of 26 Verify the following:
- a. Inservice boric acid transfer pump 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.
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)
IMF EHCO6 (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 INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I
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.
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 2".
US directs I&C to investigate problem with governor valve.
US checks for load reduction of > 15%
and informs Chemistry, if necessary.
I 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 Continue with scenario when limiter problem is identified and Tavg-Tref are matched, or at Examiners discretion.
BVPS - 2 NRC Scenario 1 Supervisory limits-normal.
9 of 26 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%.
I I
INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE 1
EXPECTED STUDENT RESPONSE 1 EVENT #3 Pressurizer Pressure Transmitter PT-445 Fails High Slowly Insert the following:
IMF XMT-RCS031A (0 0) 2500 120 BVPS - 2 NRC Scenario 1 Annunciators:
[A4-1 D], Pressurizer Control Pressure HighlLow
[A4-1 F], Pressurizer PORV Open permissive
[A4-2E], Pressurizer Control Press High PORV Actuation
[A4-A1], Pressurizer Power/Safety Relief Trouble PORV 4550 and 456 open.
10 of 26 RO notes alarm, informs US. Crew refers to ARPs, if necessary.
US refers to 20M-6.4.IFI 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.
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 Pressure Change
[A6-9Fl1 Loop A Feedwater Flow >
Steam Flow
[A6-9GIl Loop A Steamline Pressure Low SG 21 A Channel 3 2MSSPT476 fails low.
SG 21 A channel 3 steam flow drops (density Compensation input).
SG 27 A feed flow, NR level drops.
2FWS*FCV478 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 2FWSFCV478 and informs US.
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.
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 BVPS - 2 NRC Scenario 1 Channel 3 steam flow locally selected.
NR level = 44%.
Protection Rack C3 Door open.
2LS/476A (BS-1) Low-Low Trip.
12 of 26 Crew determines that steam pressure channel 2MSSPT476 failed low.
US refers to 20M-24.4.IF, Attachment
- 4.
US 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.
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE ]
EXPECTED STUDENT RESPONSE 1 IMF BST-PCSO29 (0 0) 0 IRF LOA-PCS003 (0 0) 0 IRF LOA-PCS004 (0 0) 1 IMF BST-PCSO77 (0 0) 0 IMF BST-PCS068 (0 0) 0 IRF LOA-PCS004 (0 0) 0 2LS/476C (BS-2) High-High FWI.
Protection Rack C3 Door closed.
Protection Rack C4 Door Open.
2PS/476A (BS-1) Low Pressure SI and SLI.
2PS/476B (BS-2) High Pressure Rate s LI 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)
ATWS - reactor fails to trip automatically or when Manual trip is attempted.
Crew enters FR-S.1.
BVPS - 2 NRC Scenario 1 RCS pressure and Tavg rising.
Control rods remain withdrawn.
14 of 26 US directs a manual reactor trip.
RO places reactor trip switch to Trip.
Crew identifies that the reactor failed to trip.
RO depresses 66-A reactor trip pushbutton to attempt reactor trip.
US enters FR-S. 1 and announces entry to crew.
PO presses both turbine trip pushbuttons.
[ INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 CRITICAL TASK #1:
Insert control rods or initiate RCS Bo ration.
Control rods inserting.
All AFW pumps running.
2CHSP21A and 6 running.
SI not actuated.
2CHSMOV350 open.
Boric acid transfer pump running in fast speed.
Boration flow > 30 gpm.
Charging flow > 40 gpm.
PZR pressure is < 2330 psig.
PO/RO verifies TWF is decreasing.
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 2CHSMOV350 Starts boric acid transfer pump
. Verifies emergency boration flow >
. Adjusts [2CHSFCV122] to establish charging flow > 40 gpm Checks PZA pressure less than 2330 30 gpm Psig BVPS - 2 NRC Scenario 1 15 of 26
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I All throttle and governor valves closed.
[2MSS-MOVl OOA, B] closed.
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 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 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 Crew returns to E-0.
BVPS - 2 NRC Scenario 1 Power range indicates < 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
. Power range indication less than 5%.
. Neutron flux is dropping.
PO verifies turbine trip.
US identifies need to evaluate EPP.
[
INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
BVPS - 2 NRC Scenario 1 Main generator output breakers and exciter circuit breakers open.
2AE and 2DF busses energized.
SI actuated.
[2 H V S FN204A/B] running.
HHSl pumps running with flow indicated. LHSl pumps running.
MDAFW and TDAFW pumps running.
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 INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I BVPS - 2 NRC Scenario 1 AFW flow > 340 gpm.
TAVG lowering.
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 PO performs Attachment A-0.1 1, Verification of Automatic Actions. (Steps attached to end of scenario guide.)
RO check RCS TAVG stable at or trending to 547QF.
. 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.
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE
[ OBJECTIVE 1 EXPECTED STUDENT RESPONSE I SG A faulted and depressurizing in an uncontrolled manner.
Crew transitions to E-2.
Control Room dampers shut.
Timers running, control room pressurizing.
When requested as U1 Operator, report CREVS actuation.
All yellow SLI marks lit.
SG 21 6 and 21 C pressures stable.
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 commences 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.
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 uncontrollably.
All green FWI marks are lit.
Residual heat release valve closed.
CRITICAL TASK #2:
Isolate feed flow into and steam flow out of faulted SG.
SG 21 A ADV not closed.
PO identifies 21 A SG as faulted.
PO verifies FWI green marks previously verified.
PO closes AFW throttle valve on SG 2 1 A.
US/RO direct operator to locally close 2svs*27.
Operator dispatched to locally close 2MSS15.
RO attempts to close SG 21 A ADV.
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 ]
Crew transitions to ES-1.l.
2BDGAOVlOOAl closed.
No SGTR is indicated.
SI Termination Criteria is met.
Verify SG B/D isolation valve from SG 21 A is closed.
Check PPDWST level > 85 inches.
Crew checks if SG tubes are intact.
Crew checks if SI flow should be reduced.
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 ma tic 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.
OR BVPS - 2 NRC Scenario 1 Steamline pressure high rate of change - 100 PSIG DROP IN 50 SECONDS.
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 start until 10.5 minutes after the CIB signal is initiated.
Check CIB and CNMT spray status,
. 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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