ML051320311
| ML051320311 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/28/2004 |
| From: | Hynes C FirstEnergy Nuclear Operating Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| Download: ML051320311 (100) | |
Text
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RTL# A5.670.AA Revision Na.
1/2-ADM-1357.F11 Page 1 of 1 Revision 0 1
Uate SIMULATOR EVALUATION SCENARIO COVER PAGE 1
PROGRAM TITLE:
1 2-1 0-04 License Operator T rai ni n g/Licensed Requali f i cati on Training SUBDIVISION:
Si mu1 at or SC EN AR IO T ITLWNO. :
COMPUTER CODE FOR L.P.:
2005 NRC Initial License Exam 1 LOT6 Scenario No. 1 I NSTR UCTl ON AL SETTl NG :
Si rnul at or APPROXIMATE DURATION:
1.5 Hours PREPARED BY:
REVIEWED BY:
APPROVED FOR IMPLEMENTATION:
Date Date Date BVPS-1 NRC Scenario 1 Page 1 of 28
INITIAL CXNWITOdS:. IC-1 81, PW = NRC1; 100% Power, RCS Boron PPm.
1 CH-P-1 C, HHSKharging Pump 00s.
PCV-1 RC-456, PORV leakage. MOV-1 RC-536, Block Valve closed with power maintained Flood warnings from heavy rains.
Maintenance investigating 1 RW-P-1 A, River Water Pump abnormal vibration/noise.
EQUIPMENT STATUS STICKERS I
ADDITIONAL LINEUP CHANGES DATWIME 00s TECHNICAL SPECIFICATION(S)
VOND MARKINGS I
I PCV-1 RC-456 1
Yesterday 1500 I
3.4.1 1.a SHIFT TURNOVER INFORMATION
- 1.
- 2.
- 3.
- 4.
1 WR-P-1A is operable, but abnormal pump vibration and noise is under investigation.
AOP-1.75.2, Acts of Nature - Flood is in effect. River water level is currently 671 feet and stable.
Train 6 is the Protected Train.
Reduce reactor power to 75% at 12%/hr. to remove a condenser waterbox from service for cleaning.
SCENARIO SUPPORT MATERIAL REQUIRED 1 OM-52.4.B, Load Following Reactivity Plan for 12Whr. Load Reduction Protected Train B Wall Plaque
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #1 Reduce power to 75% at 12% per hour Turbine load and reactor power decreasing at 12%/hr.
US directs load reduction in accordance with Reactivity Plan.
PO initiates load reduction per 1 OM-52.4.6, Step 1V.A.
Set the desired terminal load on the SETTER.
Set the desired rate on the LOAD RATE thumbwheel (5%/min.
maxim u m).
As the turbine load reduces, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.
Depress the GO pushbutton.
BVPS -1 NRC Scenario 1 3 of 28
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I
After the governor valves are off the limiter, transfer the turbine control to the 1 stage pressure feedback mode by depressing the lST STG IN pushbutton AND verify the following:
- 1. The 1 ST STG OUT lamp is OFF.
- 2. The lST STG IN lamp is ON.
After transfer to the 1 ST stage pressure feedback mode, set the desired terminal load on the SETTER.
Set the desired rate on the LOAD RATE thumbwheel (5%/min.
maximum).
As the turbine load reduces, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.
Turbine Load and Reactor Power lowering at 12% per hour Depress the GO pushbutton.
BVPS -1 NRC Scenario 1 4 of 28
I INSTRUCTIONAL GUIDELINES
]
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 RO initiates RCS boration as necessary to maintain Tavg - Tref per 1 OM-7.4.L, Step 1V.A and reactivity plan.
Estimate the volume of boric acid to be added to the RCS using any of the following:
- a. 1 OM-7.5, Figure 7.7, Boron Addition, AND Table 1, Nomograph Correction Factors
- b. WAG tables
- c. Reactor Engineer approved computer based methods Estimate the rate of boron concentration change as a function of boric acid flow rate using 1 OM-7.5, Figure 7-8, Boron Addition Rate, AND Table 1, Nomograph Correction Factors.
Place the 1 MU control switch to Stop for greater than 1 second to allow the blender to unarm.
BVPS -1 NRC Scenario 1 5 of 28
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I Place 43/MU control switch to Borate.
Set FCV-1 CH-l13A, Boric Acid to Blender FCV to the desired boric acid flowrate.
Set Boric Acid Integrator YIC-1 CH-113 for the desired quantity.
- a. Reset Boric Acid Integrator YIC-1 CH-113.
Start the Reactor Makeup Control System by placing 1 MU control switch to Start.
Verify boric acid to blender flow on FR-1 CH-113, Boric Acid Flow.
Operate the pressurizer spray as required to limit the difference between boron concentration in the pressurizer and that of the RCS to less than 50 PPm.
BVPS -1 NRC Scenario 1 6 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Verify bo ration au tomatical I y stops when Boric Acid Integrator YIC-1 CH-113 reaches the setpoint.
When boration is complete, perform the following:
- a.
- b.
C.
- d.
- e.
Place the 1 MU control switch to Stop for greater than 1 second.
Place 43/MU control switch to Auto.
Reset Boric Acid Integrator Adjust makeup controls for the new RCS boron concentration.
Place the 1 MU control switch to Start.
YIC-1 CH-113.
BVPS -1 NRC Scenario 1 7 of 28
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE ]
EVENT #2 Valve Position Limiter Failure (Load Rejection)
When directed, insert the following command:
IMF TUR15 (0 0) 60
[A4-461, Tavg Deviation from Tref
[A4-1241, Rod Control Bank D Low Low (Possible)
[A4-12], Pressurizer Control Low Pressure Deviation
[A4-521, Delta Flux Out of Target Band Rods stepping in.
Tavg increasing Steam dump valves opening.
Crew acknowledges alarms, notifies US and investigates.
Crew informs US of the loss of electrical load.
US refers to AOP-1.35.2.
RCS pressure increasing.
MW decreasing.
RO places control rods in AUTO.
Control rods inserting. Tavg dropping to Tref.
Crew sounds standby alarm and announces Unit 1 load rejection.
BVPS -1 NRC Scenario 1 8 of 28
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 RO may initiate emergency boration.
EHC system normal except for valve position limiter.
Valve position limiter failure; vibration and load satisfactory for condition.
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 PO verifies normal EHC operation.
Crew checks if governor valves have closed in sequence, checks turbine vibration recorders.
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°F.
PO resets steam dump controller:
BVPS -1 NRC Scenario 1 9 of 28
1 INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
Steam dump valves closed.
. Verifies steam dump valves closed Bistable lights extinguished.
Crew may perform actions to recover GV control from the valve position limiter per 1 OM-26.4.AK.
Steam dumps reset.
Places steam dump control mode to reset Allows switch to spring return to Tave position Verifies load rejection bistables NOT lit PO reduces VPL setting to prevent turbine load from returning to pre-event value.
Reduce valve position limit setting to within 5% above governor control Intermittently reduce valve position limit setting until valve limiter light just comes ON US notifies Wadsworth (FE) System Control Center and Duquesne Light System Control Center.
US directs I&C to investigate problem with governor valve.
BVPS -1 NRC Scenario 1 10 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I Continue with scenario when limiter problem is identified and Tavg-Tref are matched, or at Examiners discretion.
BVPS -1 NRC Scenario 1 TV-1 CN-100 closed.
Supervisory limits-normal.
11 of 28 US checks for load reduction of > 15%
and informs Chemistry, if necessary.
Crew checks TV-1 CN-100 closed.
Monitor turbine supervisory limits.
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 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #3 Pressurizer Pressure Transmitter PT-445 Fails High Slowly When directed, insert the following command:
IMF PRS08E (0 0 ) 2500 120 (Other malfunctions pre-loaded)
[A4-91, Pressurizer Control Press High
[A4-121, Pressurizer Control Press Deviation RO notes alarm and informs US. Crew refers to ARPs, if necessary.
US refers to 10M-6.4.IF, Attachment 2.
[A4-131, Pressurizer Control Press High Pwr Relief Act RO closes PORVs.
PORV 455D and 456 open.
US refers to Technical Specifications
. T.S. 3.2.5 may apply if RCS pressure below DNB setpoint.
T.S. 3.4.1 1.a may be referenced, but PORV remains operable in manual, capable of being cycled.
BVPS -1 NRC Scenario 1 12 of 28
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
EVENT #4 SG Pressure Transmitter PT-485 Fails Low When directed, insert the following command:
IMF MSS16E (0 0) 0 An nu nciators:
[A7-491, Loop 2 Steamline Pressure Low or Press Rate Hi
[A7-50], Loop 2 Feedwater Flow >
Steam Flow
[A7-531, Aux Feed to Stm Gen Valves Not Fully Open Train A SG B Channel 3 MSS*PT485 fails low.
SG B Channel 3 steam flow drops (density compensation input).
SG B feed flow, NR level drops.
1 FWS*FCV488 modulates closed in automatic.
Crew responds to indications and alarms.
PO notes problem with SG 8 level control, takes manual control of 1 FWS*FCV488, informs US.
BVPS -1 NRC Scenario 1 13 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 NOTE: Level deviation is SG B level deviation.
dependent on time of establishing normal MFRV control to restore SG level.
NR level = 44%.
Crew determines that steam pressure channel MSS*PT485 failed low.
US refers to 1 OM-24.4.IF, Attachment
- 4.
US directs PO to restore SG B level to program level.
PO selects redundant channel for B SG steam flow signal (PT-488).
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 Table 3.3-3, items 1.e and 4.d.
U S 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.
BVPS -1 NRC Scenario 1 14 of 28
I I
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1
Actions to trip bistables:
IOR XSO3C23 1 IMF BST-RCS157 (0 0) 0 IMF BST-RCSO56 (0 0) 0 DOR XSO3C23 IOR XSO3C23 1 IMF BST-RCS092 (0 0) 0 IMF BST-RCS102 (0 0) 0 DOR XSO3C23 PRIOR to next event, insert the following command::
IMF MSSO7 (0 0)
When bistables have been tripped and malfunction is inserted, continue with next event.
Protection Channel I l l door 18 open.
BS-488C tripped.
BS-488B tripped.
Protection Channel I l l door 18 closed.
Protection Channel Ill door 35 open.
BS-485A tripped.
BS-485B tripped.
Protection Channel Ill door 35 closed.
US directs crew to trip associated bistables per 1 OM-24.4.IF, Attachment 4 Table 1.
Condenser Steam Dump Failure US directs I&C to investigate failure of steam pressure channel.
BVPS -1 NRC Scenario 1 15 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENTS #5,6, & 7 Turbine Trip - Partial Steam Dump Failure. Reactor Trip required; Auto and Manual Reactor Trip Failure; One SG ADV Fails Partially Open IMF TURO1 (0 0)
IMF MSSl2A (1 0) 100 (Pre-loaded)
RCS pressure and Tavg rising.
Crew determines that the turbine has tripped.
US directs a manual reactor trip.
RO places reactor trip switch to Trip.
ATWS - reactor fails to trip automatically or when manual trip is attempted.
Crew identifies that the reactor failed to trip.
RO depresses BB-A reactor trip pushbutton to attempt reactor trip.
Crew enters FR-S.l.
US transitions to FR-S.l and announces entry to crew.
BVPS -1 NRC Scenario 1 16 of 28
1 INSTRUCTIONAL GUIDELINES
[
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Turbine tripped.
PO verifies turbine is tripped.
PO/RO verifies TREF is decreasing CRITICAL TASK #1:
Insert control rods or initiate RCS boration.
Control rods inserting.
All A W pumps are running.
TV-IMS-l05A, B open.
MOV-1 FW-151 A, B, C, D, E, and F open.
CH-P-1 B started manually.
MOV-1 CH-350 open.
1 CH-P-2A(B) running in fast speed.
RO places control rod group selector in Auto and verifies rods are inserting.
RO drives rods in manual after automatic rod motion stops.
PO verifies AFW status.
RO initiates emergency boration.
Verifies at least one HHSl pump running.
. Opens MOV-1 CH-350, Emergency Boration Valve.
. Starts Inservice Boric Acid Transfer Pump in FAST speed.
BVPS -1 NRC Scenario 1 17 of 28
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I PRZR pressure < 2335 psig.
When directed to locally trip reactor, insert:
Boration flow > 30 gpm.
FCV-1 CH-122 indicates > 75 gpm
. Verifies emergency boration flow is greater than 30 gpm.
. Opens Chg Flow to Regen Hx Inlet Control Valve to establish greater than 75 gpm flow.
RO verifies PRZR pressure < 2335 psig.
US dispatches operator to locally trip the reactor.
TRG! 3 RO/PO alert plant personnel by sounding Standby alarm and announcing ATWS.
R I B A open.
RTB B open (30 sec delay).
Control rods drop.
Power decreasing.
PO verifies turbine tripped:
. All throttle or all governor valves are closed.
. All reheat stop or all Interceptor valves are closed.
BVPS -1 NRC Scenario 1 18 of 28
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
PO places both steam dump control interlock selector switches in Off.
MOV-MS-1 OOA. 1 OOB Shut.
SI actuated.
AFW flow > 630 gpm.
Power range indicates < 5%.
Intermediate Range SUR negative.
PO ensures reheat steam isolation by depressing reheat controller reset pushbutton and checks MOV-MS-1 OOA
& B shut.
US determines that SI has actuated.
When time permits, US directs performance of first 10 steps of E-0.
Crew verifies required AFW flow to the steam generators > 630 gpm.
RO checks reactor is subcritical.
. Power range channels < 5%.
. Intermediate range channels negative startup rate.
RO continues boration, as necessary.
BVPS -1 NRC Scenario 1 19 of 28
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
Crew returns to E-0.
Reactor trip and bypass breakers open Rod bottom lights lit.
Rods at bottom.
Neutron flux decreasing Throttle and governor valves closed.
Main generator output breakers open.
Exciter circuit breakers open.
1 AE and 1 DF busses energized.
E-0 immediate actions complete.
SI actuated.
US transitions to E-0.
RO verifies reactor tripped:
. Rx trip and bypass breakers are open m
Rod bottom lights are lit
. Rod position indication at zero Neutron flux is dropping RO sounds Standby alarm and announces Unit 1 reactor trip.
PO verifies turbine trip.
PO verifies generator trip.
PO verifies power to AC emergency busses.
. Depresses manual SI actuation pushbuttons.
BVPS -1 NRC Scenario 1 20 of 28
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I 1 INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 PO performs Attachment 1 -K, Verification of Automatic Actions (Steps listed at end of scenario guideline.)
Stuck open ADV.
TAVG decreasing.
Condenser steam dumps closed.
MOV-1 MS-1 OOA, B closed.
Total AFW flow > 355 gpm.
Main steam trip and bypass valves closed.
Recirc spray pumps not running.
PORV 456 closed but leaking.
Spray valves at zero demand Safety valves closed Power available to PORV MOV's.
All other PORV MOV's open (except MOV-1 -RC-537 previously closed).
RO check RCS TAVG stable at or trending to 547".
. Stop dumping steam.
. Verify reheat steam isolation.
. Reduce total feed flow to minimize cooldown.
. Close main steam trip and bypass valves.
RO checks recirc spray pump status.
RO checks PRZR isolated.
BVPS -1 NRC Scenario 1 22 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTED STUDENT RESPONSE I PRT conditions normal.
RO verifies PRT conditions are normal D/P between RCS and highest SG pressure > 200 psid.
SG A faulted.
Crew enters E-2.
Control room dampers shut. Timers running; control room pressurizing.
When requested as U2 Operator, report 2HVCkMOD201 A-D closed and 2HVCkMOD204A, B closed.
2HVC8MOD201 A-D closed.
2HVCkMOD204A, B closed.
CRITICAL TASK #2:
Isolate steam flow out of and feed flow into faulted SG.
All yellow SLI marks lit.
Crew checks if RCPs should be stopped.
Crew checks if any SGs are faulted.
PO determines SG A pressure decreasing in uncontrolled manner.
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 verifies CREVS actuated in U2 by requesting U2 CREVS status.
Crew verifies steam line isolation.
BVPS -1 NRC Scenario 1 23 of 28
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE 1 OBJECTIVE EXPECTED STUDENT RESPONSE 1 EOP pre-emptive action.
When directed to close MS-23, insert the following command:
IMF MSS07 (0 0) 0 SG 6 and C pressures stable.
SG A faulted.
Main and Bypass Feed Reg Valves closed.
AFW throttle valves closed. (May have been previously closed.)
PCV-MS-101 A open.
HCV-1 MS-104 closed.
No SG levels rising in an uncontrolled manner.
PO checks for any non-faulted SG.
PO identifies SG A pressure decreasing in uncontrolled manner.
Crew isolates faulted SG.
. Check WI - previously verified.
Close AFW throttle valves on faulted SG.
. Direct locally closing MS-15.
. Attempt to close atmospheric dump valve.
. Close residual heat release valve.
PO directs locally closing MS-23.
PO checks PPDWST level > 27.5 feet.
Crew checks if SG tubes are intact.
BVPS -1 NRC Scenario 1 24 of 28
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
SI Termination Criteria met.
Crew enters ES-1.l.
Crew checks if SI flow can be reduced US transitions to ES-1.1, SI Termination and informs crew.
Scenario may be terminated upon transition to ES-1.l.
BVPS -1 NRC Scenario 1 25 of 28
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I -K, Verification of Auto mat i c Actions Diesel Generators - BOTH RUNNING.
Check station instrument air header pressure - GREATER THAN 100 PSIG.
Ensure reheat steam isolation:
- a. Verify [MOV-1 MS-1 OOA, B]
CLOSED.
- b. Reset reheater controller.
Verify CCR Pumps - TWO RUNNING.
Align Neutron Flux Monitoring For Shutdown:
- a. Transfer NR-1 NI-45, Nuclear Recorder to operable source and intermediate range displays.
Verify river water system in service.
- a. RPRW Pumps - TWO RUNNING.
BVPS -1 NRC Scenario 1 26 of 28
[ INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1
- GREATER THAN 20 PSIG.
Check If main steamline isolation required.
- a. Check the following:
. CNMT pressure - GREATER THAN 3 PSIG.
OR Steamline pressure - LESS THAN 500 PSIG.
. Steamline pressure high rate of change - ANY ANNUNCIATOR LIT.
Annunciator A7-41 An nu nci ato r A7-49 Annunciator A7-57
- b. Verify steamline isolation:
. YELLOW SLI marks - LIT Check CIB and CNMT spray status:
BVPS -1 NRC Scenario 1 27 of 28
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
. Containment pressure - HAS REMAINED LESS THAN 8 PSIG.
Verify ESF equipment status:
- b. Verify CIA by checking all ORANGE CIA marks - LIT
- c. Verify FWI by checking all GREEN FWI marks - LIT.
Verify power to both AC emergency busses.
Upon completion, report any discrepancies to SM/US.
BVPS -1 NRC Scenario 1 28 of 28
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:
COMPUTER CODE FOR L.P.:
I NSTR UCTl ON AL SETTING:
APPROXIMATE DURATION:
License Operator Training/Licensed Requalification Training Simulator 2005 NRC Initial License Exam 1LOT6 Scenario No. 2 Simulator 1.5 Hours PREPARED BY:
Date REVIEWED BY:
APPROVED FOR IMPLEMENTATION:
Date Date BVPS-1 NRC Scenario 2 Page 1 of 24
INITIAL CONDITIONS:......
IC-1 82; PW = NRC2; 53% power, RCS Boron _______.
ppm CH-P-1 C, HHSVCharging Pump 00s.
PCV-1 RC-456, PORV 456 leakage. MOV-1 RC-536, Block Valve closed with power maintained Flood warnings due to heavy rains.
Maintenance is investigating abnormal vibrationhoise on 1 WR-P-1 A, River Water Pump.
Turbine Control selected to First Stage In.
PCV-1 RC-456 I
I I
ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS I
Yesterday 1500 3.4.1 1.a I
EQUIPMENT STATUS I
DATE/TIMEOOS I
TECH N IC A L S P EC I FIC AT10 N (SI I
SHIFT TURNOVER INFORMATION
- 1.
- 2.
- 3.
- 4.
AOP-1.75.2 is in effect. River water level is 671 feet and stable.
1 WR-P1 A is operable, but investigation of abnormal vibrationhoise is ongoing.
Train B is the Protected Train.
Reduce power to take the unit off-line due to circulating water intake clogging.
SCENARIO SUPPORT MATERIAL REQUIRED 1 OM-52.4.B, Load Following Reactivity Plan for 12%/Hr Power Reduction Protected Train B Wall Plaque
r INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #1 Reduce Power Turbine load and reactor power decreasing at 12%/hr.
US directs load reduction in accordance with Reactivity Plan.
PO initiates load reduction per 1 OM-52.4.8, Step 1V.A.
Set the desired terminal load on the SETTER.
. Set the desired rate on the LOAD RATE thumbwheel (5Y0/min.
maximum).
As the turbine load reduces, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.
Depress the GO pushbutton.
After the governor valves are off the limiter, transfer the turbine control to the 1 stage pressure feedback mode by depressing the lST STG IN pushbutton AND verify the following:
- 1. The lST STG OUT lamp is OFF.
BVPS 1-NRC Scenario 2 3 of 24
t i
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
- 2. The lST STG IN lamp is ON After transfer to the 1 ST stage pressure feedback mode, set the desired terminal load on the SETTER.
Set the desired rate on the LOAD RATE thumbwheel (5%/min.
maximum).
As the turbine load reduces, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.
Turbine load and reactor power decreasing at 12%/hr.
Depress the GO pushbutton.
RO initiates RCS boration as necessary to maintain TAVG
- TREF per 1 OM-7.4.L, Step 1V.A and reactivity plan.
Estimate the volume of boric acid to be added to the RCS using any of the following:
BVPS 1-NRC Scenario 2 4 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1
- a. 1 OM-7.5, Figure 7.7, Boron Addition, AND Table 1, Nomograph Correction Factors
- b. WAG tables
- c. Reactor Engineer approved computer based methods Estimate the rate of boron concentration change as a function of boric acid flow rate using 1 OM-7.5, Figure 7-8, Boron Addition Rate, AND Table 1, Nomograph Correction Factors.
Place the 1 MU control switch to Stop for greater than 1 second to allow the blender to unarm.
Place 43/MU control switch to Borate.
Set FCV-1 CH-l13A, Boric Acid to Blender FCV, to the desired boric acid flowrate.
BVPS 1-NRC Scenario 2 5 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Set Boric Acid Integrator YIC-1 CH-113 for the desired quantity.
- a. Reset Boric Acid Integrator YIC-1 CH-113.
Start the Reactor Makeup Control System by placing 1 MU control switch to Start.
Verify boric acid to blender flow on FR-1 CH-113, Boric Acid Flow.
Operate the pressurizer spray as required to limit the difference between boron concentration in the pressurizer and that of the RCS to less than 50 PPm.
Verify boration automatically stops when Boric Acid Integrator YIC-1 CH-113 reaches the setpoint.
BVPS 1-NRC Scenario 2 6 of 24
INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I When boration is complete, perform the following:
BVPS 1-NRC Scenario 2 7 of 24
- a.
- b.
C.
- d.
- e.
Place the 1 MU control switch to Stop for greater than 1 second.
Place 43/MU control switch to Auto.
Reset Boric Acid Integrator Adjust makeup controls for the new RCS boron concentration.
Place the 1 MU control switch to Start.
YIC-1 CH-113.
[ INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #2 SG "B" Level Transmitter Fails High When directed, insert the following corn mand 1 IMF fWM16D (0 0) 100 NOTE: No system response occurs on failure of a single channel due to median signal select feature.
BVPS 1-NRC Scenario 2 Annunciator:
[A7-521, SG Level 16 HI-HI 8 of 24 PO refers to ARP US refers to 10M-24.4.lF.
US refers to Technical Specifications TS 3.3.1.1 item 14 and TS 3.3.2.1, items 5.a, 7.a.
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #3 No. 1 EDG Trouble When directed, insert the following command:
Annunciator:
IMF EPS11 A (0 0)
[A9-71, DG Trouble Outside Operator reports EDG control power breaker open on No.
1 EDG.
PO responds to alarm Crew dispatches Outside Operator to investigate local alarm.
US refers to Technical Specification TS 3.8.1.1, Action b.
BVPS 1-NRC Scenario 2 9 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 EVENT #4 Letdown Pressure Control Valve Fails Closed In Auto When directed, insert the following command:
PCV-1 CH-145 fails closed resulting in a loss of normal letdown.
Annunciator:
RO responds to indications and alarms.
IOR XO6AO87P (0 0) 1.O
[A3-1071, NRHX Disch Press High RO notifies US. Refers to ARP Letdown backpressure rising.
Letdown flow lowering.
Letdown flow at 105 gpm.
US may refer to AOP-1.6.7 or AOP-1.7.1.
RO reports 1 CHS-FI150 indicates zero flow.
Crew minimizes any power changes in progress.
RO takes manual control of PCV-1 CH-145 and restores letdown flow to previous value.
US contacts I&C to investigate failure Of PCV-CH-145.
BVPS 1-NRC Scenario 2 10 of 24
1 INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
EVENT #5 SG A MFRV Controller Fails In Auto controller fails closed.
1 FWS-FCV478, Main Feed Reg Valve When directed, insert the following command Annunciator:
IMF FWM15A (0 0) 0 300
[A7-451, Steam Generator 1 A Level Deviation From Setpoint SG A feed flow lowering.
MFRV position and feed flow stabilize in manual control.
PO recognizes feed flow problem, informs US.
US directs PO to take manual control of SG A MFRV and attempt to stabilize SG feed flow and level.
US directs I&C to investigate problem with SG A automatic MFRV control.
BVPS 1-NRC Scenario 2 11 of24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #6 RCS Leak When directed, insert the following command:
IMF RCS02A (0 0) 25
[A4-711, Radiation Monitor Hi
[A4-721, Radiation Monitor Hi-Hi
[A1 -351, Ctmt Air Total Pressure Hi/Lo Channel 1 Crew responds to indications and alarms.
US refers to AOP-1.6.7, Excessive Primary Plant Leakage.
RO checks if PRZR level can be maintained.
[A1 -431, Ctmt Air Total Pressure Hi/Lo Channel 2 US requests SM to evaluate EPP.
RM-1 RM-204 in alarm.
RM-1 RM-215A, B in alarm.
[RM-1 MS-l02A, B, C], N-16 steam generator leak monitors normal.
[RIS-SV1 001, Condenser Air Ejector Vent normal.
RO controls charging flow as necessary to maintain PRZR level on program.
RO checks if VCT level can be maintained by normal makeup.
PO checks secondary plant radiation trends normal.
BVPS 1-NRC Scenario 2 12 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1
[RM-BD-1 011, High Capacity B/D monitor is normal PRT pressure, level, and temperature normal.
Slight rise in containment temperature may not be noticeable.
Aux. Bldg. radiation is normal.
PRZR level remains stable NOTE: If contacted by US, SM may direct an emergency shutdown per 1 OM-51.1.
RO checks PRT conditions consistent with pre-event values.
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 1-NRC Scenario 2 13 of 24
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENTS #7 & #8 RCS Leak Degrades into SBLOCA; Train 6 HHSKharging Pump Auto Start Failure; Train A ESF Components Must Be Started Manually.
When directed, insert the following command:
IMF RCS02A (0 0) 2000 300
[A4-4], Pressurizer Control Low Level Deviation Pre-loaded Commands:
[A3-58], Charging Pump Discharge Flow High-Low TRGSET1 JPPLSI(IL)==l IMF SISOSA (1 0)
RCS pressure and PRZR level dropping rapidly.
IMF INH40 (0 0)
IMF SISlOA (0 0)
Reactor trip and bypass breakers open.
Crew enters E-O.
Power range < 5%.
Neutron flux dropping.
Throttle and governor valves closed.
US orders reactor trip and enters E-0.
RO verifies reactor trip:
Reactor trip and bypass breakers open.
Power range indication < 5%.
Neutron flux dropping.
PO verifies turbine trip.
BVPS 1-NRC Scenario 2 14 of 24
I I
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
Main generator output breakers open.
Exciter circuit breaker open.
PO verifies generator trip.
Only 1 DF bus energized CRITICAL TASK #1:
Crew manually actuates at least one train of SIS actuated safeguards before transition to any ORP.
SI Train A not actuated.
SI actuated both trains.
1 VS-F-4A Leak Coil Exhaust Fan ru nning.
CH-P-1 B running PO verifies power to AC emergency busses.
RO determines Train A SI failed to actuate automatically.
RO manually actuates both SI trains.
Crew sounds Standby Alarm, announces Unit 2 Reactor Trip and Safety Injection.
PO checks leak collection exhaust fan running.
Start CTMT hydrogen analyzers.
RO verifies HHSl pumps are running.
. Manually starts HHSl Pump B.
BVPS 1-NRC Scenario 2 15 of 24
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 CH-P-1 A not running.
BIT flow indicated.
LHSl pumps are running.
. HHSl Pump A does not start.
RO checks high head SI to BIT flow indicated.
RO/PO checks both LHSl pumps are running.
PO verifies AFW status.
TD AFW pump running.
TV-1 MS-105A open.
[A7-71 not lit.
PO checks TO AFW pump is running.
. TV-1 MS-105A is open.
[A7-71 is not lit.
PO verifies all AFW throttle valves are full open.
PO performs Attachment 1 -K, Verification of Automatic Actions (Steps listed at end of scenario guide.)
BVPS 1-NRC Scenario 2 16 of 24
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INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE No SG levels rising in an uncontrolled manner.
RCS pressure and PRZR level decreasing rapidly.
Crew enters E-1.
CREVS not actuated or required CRITICAL TASK #2:
Crew trips all RCPs when RCS to highest S/G DIP criteria is exceeded (or due to ClB) and prior to exiting E-1.
D/P between RCS pressure and highest SG pressure < 200 psid.
All RCPs stopped. (May have been previously stopped.)
Recirc spray not actuated.
No SG pressures dropping in an uncontrolled manner.
PO checks if SG tubes are intact.
US determines RCS is not intact.
US transitions to E-1 and informs crew.
PO checks if CREVS actuated.
RO checks if RCPs should be stopped.
RO stops all RCPs if not stopped previously.
RO/PO checks recirc spray system status.
PO checks if any SGs are faulted.
BVPS 1-NRC Scenario 2 18 of 24
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i INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I -K, Verification of Auto mat i c Actions No. 2 EDG is running. No. 1 EDG did NOT start.
Diesel Generators - BOTH RUNNING.
. PO may attempt to start No. 1 EDG.
Check station instrument air header pressure - GREATER THAN 100 PSIG.
Ensure reheat steam isolation:
- a. Verify [MOV-1 MS-1 OOA, B]
CLOSED.
- b. Reset reheater controller Verify CCR Pumps - TWO RUNNING.
Align Neutron Flux Monitoring For Shutdown:
- a. Transfer NR-1 NI-45, Nuclear Recorder to operable source and intermediate range displays.
BVPS 1-NRC Scenario 2 22 of 24
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Verify river water system in service.
- a. RPRW Pumps - TWO RUNNING
- GREATER THAN 20 PSIG.
Check If main steamline isolation required.
- a. Check the following:
' CNMT pressure - GREATER THAN 3 PSIG.
. Steamline pressure - LESS THAN 500 PSIG.
OR Steamline pressure high rate of change - ANY ANNUNCIATOR LIT.
Annunciator A7-41 Annunciator A7-49 Annunciator A7-57
- b. Verify steamline isolation:
BVPS 1-NRC Scenario 2 23 of 24
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I
. YELLOW SLI marks - LIT.
Check CIB and CNMT spray status:
. Containment pressure - HAS REMAINED LESS THAN 8 PSIG.
Verify ESF equipment status:
- b. Verify CIA by checking all ORANGE CIA marks - LIT.
- c. Verify FWI by checking all GREEN FWI marks - LIT.
Verify power to both AC emergency busses.
Upon completion, report any discrepancies to SM/US.
BVPS 1-NRC Scenario 2 24 of 24
RTL# A5.670.M 1
1/2-ADM-1357.F11 Page 1 of 1 Revision 0 12-1 0-04 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
License Operator Training/Licensed Requalification Training SUBDIVISION:
Simulator SCENARIO TITLUNO.:
2005 NRC Initial License Exam COMPUTER CODE FOR L.P.:
1 LOT6 Scenario No. 3 Revision No. 1 Date I NSTR UCTl ON AL SETTING :
Si mu1 at or APPROXIMATE DURATION:
1.5 Hours PREPARED BY:
REVIEWED BY:
Date Date APPROVED FOR I M P L E M E NT AT I ON:
Date BVPS-1 NRC Scenario 3 Page 1 of 24
INITIAL CONDITIONS:
IC-1 83; PW = NRC3; 25% Power, RCS boron at ___ ppm.
PCV-1 RC-456, PORV 456 leakage. MOV-1 RC-536, Block Valve closed with power maintained.
Flood watch remains in effect.
Turbine Control selected to First Stage In.
ADDITIONAL LINEUP CHANGES EQUIPMENT STATUS STICKERS VOND MARKINGS DATWIME 00s TECHNICAL SPECIFICATION(S)
I 1 PCV-1 RC-456 1
Yesterday 1500 I
3.4.1 1.a SHIFT TURNOVER INFORMATION
- 1.
- 2.
Train 6 is the Protected Train Raise power to 100% after a trip due to loss of all circulating water.
SCENARIO SUPPORT MATERIAL REQUIRED 1 OM-52.4.A, Raising Power From 5% To Full Load Operation Reactivity Plan for 12%/Hr Power Ascension Protected Train B Wall Plaque
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #1 Raise Power To 100%
Conversion Economics requests raising power to 100% at 12%/hr.
BVPS - 1 NRC Scenario 3 3 of 24 US directs power increase to 100% per 1 OM-52.4.Al Step IV.F.19.
Crew reviews/agrees with reactivity plan. US approves for use. Crew begins power increase.
RO initiates dilution per 1 OM-7.4.Nl Step 1V.A.
Estimate the volume of makeup water to be added to the RCS using any of the following:
- a. 1 OM-7.5, Figure 7-9, Boron Dilution, AND Table 7-1, Nomograph Correction Factors
- b. WAG tables
- c. Reactor Engineering approved computer based methods
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I Estimate the rate of boron concentration change as a function of dilution water flow using 1 OM-7.5, Figure 7-1 0, Boron Dilution Rate, AND Table 7-1, Nomograph Correct ion Factors.
Place the 1 MU switch in Stop for greater than 1 second to allow the blender to unarm.
Place 43/MU control switch to DIL OR ALT DIL as directed by the SWUS.
Set AM-1 CH-114, Blender Total Flow Set Point to the desired flow rate.
Set blender output Integrator YIC-1 CH-168A to the desired quantity.
- a. Reset blender output integrator YIC-1 CH-168A.
Log the flow totalizer indication, AND add to it the number of gallons set into the batch integrator.
BVPS - 1 NRC Scenario 3 4 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Turbine load and reactor power increasing at 12%/hr.
Start the reactor makeup control system by placing 1 MU control switch to Start.
Operate pressurizer heaters to initiate automatic spray operation as required so that the difference in boron concentration between the RCS and pressurizer is < 50 ppm.
Verify dilution automatically stops when blender output integrator YIC-1 CH-168A reaches the setpoint.
When dilution is complete, perform the following:
- a.
- b.
C.
- d.
- e.
Place 1 MU control switch in Stop for greater than 1 second.
Place the 43/MU control switch to AUTO.
Reset blender output integrator Place the 1 MU switch to Start.
Adjust makeup controls for the new RCS boron concentration.
YIC-1 CH-168A.
BVPS - 1 NRC Scenario 3 5 of 24
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1 INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1
EVENT #2 Train A RW Pump Trips. Backup Pump Manually Started start.
1 WR-P-1 A trips, IWR-P-1 B fails to auto When directed, insert the following command:
IMF AUXlOA (0 0)
[A1 -401, CC WTR HT EXCH River WTR PP Disch Line A Press Low
[A1 -481, CC WTR HT EXCH River WTR PP Disch Line B Press Low
[A1 -591, Intake Struct River WTR PP Disch Line A Press Low
[A1 -671, Intake Struct River WTR PP Disch Line B Press Low PO recognizes loss of 1 WR-P-1A and reports to US.
US refers to AOP-1.30.2, River Water, Normal Intake Structure Loss.
RO checks reactor plant river water pump status.
[A1 -821, River Water PP Auto Start-Stop RO recognizes and reports 1 WR-P-1 B did not auto start.
1 WR-P-1 B running RO manually starts 1 -WR-P-1 6.
RO checks PI-1 RW-l13A(B), CCR Heat Exchanger RW Pressure > 20 psig.
BVPS - 1 NRC Scenario 3 7 of 24
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I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #3 Loss of 4KV Bus 1AE When directed, insert the following command:
1AE bus de-energized, No. 1 EDG fails to auto start.
IMF EPS04E (0 0)
[A8-105],4160V Emerg Bus 1 AE ACB 1 A1 0 Auto Trip
[A8-106],4160V Emerg Bus 1 AE ACB 1 E7 Auto Trip
[A8-109],4160V Emerg Bus 1 AE U nde rvoltag e
[A9-741, 480V Emerg Trans 1 -BN U nd e rvol t age
[A9-100], 125V DC Battery Charger 1 Failure
[A9-108], 125V DC Battery Charger 3 Failure If 1 WR-P-1 C, River Water Pump was previously racked onto 1AE Bus, it will auto start when EDG No. 1 is started.
Crew responds to indications and alarms.
US enters AOP-1.36.2, Loss Of 4KV Emergency Bus.
RO starts standby charging pump.
PO starts No. 1 EDG.
US refers to TS 3.8.1.1 Action c BVPS - 1 NRC Scenario 3 9 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1
EVENT #4 Loss of Feedwater When directed, insert the following command:
IMF RNMO1 A (0 0)
FW-P-1 A trips.
[A7-371, Steam Generator Feed Pump Auto Stop
[A7-40], Steam Generator Feed Pump Disch Equalizing Press Low Crew enters E-O.
BVPS - 1 NRC Scenario 3
[A7-291, Reactor Trip & Low Tavg or SI Main Feedwater Valve Closed SG levels dropping.
10 of 24 Crew identifies loss of main feedwater pump and SG feed flow.
US directs RO to trip reactor and enters E-0.
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENTS #5,6,7 SG B SGTR; No. 1 EDG Failure; MDAFW Train E Pump Fails To Auto Start; CIA Fails To Auto Actuate Pre-loaded Commands Crew continues with E-0.
BVPS - 1 NRC Scenario 3 Reactor trip and bypass breakers open.
Power range < 5%.
Neutron flux dropping.
Throttle or governor valves closed.
Main generator output breakers open Exciter breaker open.
1 AE bus de-energized; 1 DF bus energized from offsite power.
11 of 24 RO manually trips reactor RO verifies reactor trip:
. Reactor trip and bypass breakers open.
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 No. 1 EDG.
L INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE ]
SI not actuated and not required.
Crew enters ES-0.1.
RCS TAvG trending to 547F.
US directs transition to ES-0.1.
US directs STA to begin monitoring CSF status trees.
Crew sounds Standby alarm and announces Unit I 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 BVPS - 1 NRC Scenario 3 12 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I
Place steam dumps in STM PRESS Mode Place steam dump controller in AUTO Adjust controller setpoint to as necessary to maintain RCS t em pe rat u re Instrument air pressure > 100 psig.
RCS TAVQ < 554F.
All MFRVs closed.
CRITICAL TASK #1:
Crew establishes the minimum required AFW flowrate to the SGs by manually starting an AFW pump.
No AFW pumps running.
B MD AFW and TD AFW pumps running.
Bypass FRVs closed.
MFPs stopped.
PO checks station instrument air header pressure > 100 psig.
PO checks feedwater status.
RCS TAva - Less than 554F.
8 Verify Main Feedwater Reg Valves
- Closed 8
8 Check AFW Pumps - ANY Running
. PO manually starts FW-P-2 and FW-P-36 8
Close Bypass FRVs 8
Stop all but one Main Feed pump BVPS - 1 NRC Scenario 3 13 of 24
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INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
NOTE: CRITICAL TASK #2 is performed as part of Attachment 1 -K actions.
LHSl pumps running.
AFW flow > 355 gpm.
AFW throttle valves fully open.
RCS TAVG controlled on steam dumps.
Recirc spray pumps not running.
PORVs closed Safety valves closed.
Spray valves at zero demand.
PRT conditions normal.
RO/PO checks both LHSl pumps are running.
PO verifies AFW status.
Total AFW flow > 355 gprn.
. AFW throttle valves are full open.
PO performs Attachment 1 -K, Verification of Automatic Actions (Steps listed at end of scenario guideline.)
PO verifies RCS TAVG stable or trending to 547*F.
RO/PO checks recirc spray pump status.
RO checks PRZR PORVs, safety and spray valves.
RO checks PRT conditions are normal.
BVPS - 1 NRC Scenario 3 16 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE ]
Power available to PORV MOVs Block MOVs open (except previously closed MOV-1 RC-536); PORVs in AUTO.
Crew enters E-3.
D/P between RCS pressure and highest SG pressure < 200 psid.
No SG pressures dropping in an u ncon t rolled manner.
Secondary radiation high.
SG B level rising in an uncontrolled manner.
CREVS not actuated, nor required.
CIB not actuated.
RM-1 RM-218A, B not in high alarm.
RO checks if RCPs should be stopped.
PO checks if any SGs are faulted.
PO checks if SG tubes are intact.
US makes transition to E-3 and informs crew.
PO checks if CREVS is actuated.
BVPS - 1 NRC Scenario 3 17 of 24
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I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1
EOP pre-emptive action.
BVPS - 1 NRC Scenario 3 1 MS-16 closed.
TV-1 MS-1 1 1 B closed.
TV-1 MS-101 B closed.
MOV-1 MS-101 B closed.
NRV-1 MS-1016 closed.
SG B level > 13%.
SG B AFW throttle valves closed. (May have been previously performed.)
Main feedwater isolated.
19 of 24 Crew dispatches an operator to close TD AFW pump steam supply valve.
PO verifies steam supply from intact SG.
PO restarts TDAFW pump.
PO closes SG B pre-nrtrn drain isolation valves.
PO closes SG B main steam trip, bypass, and non-return valves.
PO checks ruptured SG level.
Crew isolates feed flow to SG B.
PO checks FWI - previously verified.
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
SG 6 pressure > 380 psig.
Instrument air header pressure > 100 psig.
Condenser steam dumps open.
RCS pressure < 1950 psig.
Tavg < 541°F Total AFW flow > 340 gpm or SG level between 25% and 50%.
PO checks SG B pressure > 380 psig.
PO checks instrument air header pressure > 100 psig.
US determines target cooldown temperature based on SG B pressure.
US directs STA to trend cooldown rate.
PO verifies condenser available and initiates cooldown at maximum rate, (or uses SG ADVs).
RO blocks steamline SI when RCS pressure reaches 1950 psig.
PO defeats TAVG interlock during cooldown.
PO checks intact SG levels.
BVPS - 1 NRC Scenario 3 20 of 24
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
Scenario may be terminated upon crew completion of cooldown to target temperature.
PORVs closed; MOVs open (except previously closed MOV-1 RC-536).
SI reset.
CIA and CIB reset.
RCS at target temperature.
RO checks power to PORVs and block valves.
RO resets SI RO resets CIA and CIB.
PO stops RCS cooldown at target temperature.
BVPS - 1 NRC Scenario 3 21 of 24
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 -K, Verification of Automatic Actions Diesel Generators - BOTH RUNNING.
Check station instrument air header pressure - GREATER THAN 100 PSIG.
Ensure reheat steam isolation:
- a. Verify [MOV-1 MS-1 OOA, B]
CLOSED.
- b. Reset reheater controller.
Verify CCR Pumps - TWO RUNNING.
Align Neutron Flux Monitoring For Shutdown:
- a. Transfer NR-1 NI-45, Nuclear Recorder to operable source and intermediate range displays.
Verify river water system in service.
- a. RPRW Pumps - TWO RUNNING.
BVPS - 1 NRC Scenario 3 22 of 24
I I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I
- GREATER THAN 20 PSIG.
Check If main steamline isolation required.
- a. Check the following:
. CNMT pressure - GREATER THAN 3 PSIG.
. Steamline pressure - LESS THAN 500 PSIG.
OR Steamline pressure high rate of change - ANY ANNUNCIATOR LIT.
Annunciator A7-41 Annunciator A7-49 Annunciator A7-57
- b. Verify steamline isolation:
. YELLOW SLI marks - LIT.
BVPS - 1 NRC Scenario 3 23 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Check CIB and CNMT spray status:
. Containment pressure - HAS REMAINED LESS THAN 8 PSlG CRITICAL TASK #2:
Initiate at least one train of CIA prior to completion of attachment 1 -K.
BVPS - 1 NRC Scenario 3 24 of 24 Verify ESF equipment status:
- b. Verify CIA by checking all ORANGE CIA marks - LIT
- c. Verify NVI by checking all GREEN FWI marks - LIT.
Verify power to both AC emergency busses.
Upon completion, report any discrepancies to SWUS.
RTL# A5.670.M 1
1/2-ADM-1357.F11 Page 1 of 1 Revision 0 12-1 0-04 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
License Operator Training/Licensed Requalification Training SUBDIVISION:
Si mu lator SCENARIO TITLUNO. :
2005 NRC Initial License Exam COMPUTER CODE FOR L.P.:
1 LOT6 Scenario No. 4 I Revision No. 1 Date I
1 Revision No. I, Date 1
I NSTR UCTl ON AL SETTl NG :
Simu I at or AP P R 0 X I MATE D U RAT ION :
PREPARED BY:
REVIEWED BY:
APPROVED FOR I M P LE M ENTATIO N :
BVPS-1 NRC Scenario 4 1.5 Hours Date Date Date Page 1 of 24
i ADDITIONAL LINEUP CHANGES STICKERS i
VOND MARKINGS INITIAL CONDITIONS:. IC-1 84; PW = NRC4; 75% Power, RCS boron at ppm.
. PCV-1 RC-456, PORV leakage. MOV-1 RC-536, Block Valve closed with power maintained.
River water level has receded. Flood watch cancelled on last shift.
1 WR-P-1 A, River Water Pump 00s.
Turbine control selected to First Stage In.
EQUIPMENT STATUS I
DATEAIME 00s I
TECHNICAL SPECIFICATION(S)
PCV-1 RC-456 I
Yesterday 1500 I
3.4.1 1.a I
I SHIFT TURNOVER INFORMATION
- 1.
Protected Train is Train B.
- 2.
Continue raising power to 100°/~ at 12/70 per hour SCENARIO SUPPORT MATERIAL REQUIRED 1 OM-52.4.BI Load Following Reactivity Plan for 12%/Hr Power Ascension Protected Train B Wall Plaque
I INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
EVENT #1 Raise Power NOTE: This event is not required to satisfy the qualitative or quantitative require men ts of NUREG-1 021 but may be performed at Chief Examiners discretion.
Turbine load and reactor power increasing at 12%/hr.
US directs power increase to 100% per 1 OM-52.4.B, Step IV.B.13.
Crew reviews/agrees with reactivity plan. US approves for use. Crew begins power increase.
PO initiates turbine load increase.
- a.
- b.
C.
- d.
Set the desired terminal load on the SETTER.
Set the desired rate on the LOAD RATE thumbwheel (5%/min.
maximum).
As the turbine load increases, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.
Depress the GO pushbutton.
RO initiates RCS dilution as necessary to maintain TnvG - THEF per 1 OM-7.4.N, Step 1V.A.
BVPS 1-NRC Scenario 4 3 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
Estimate the volume of makeup water to be added to the RCS using any of the following:
- a. 1 OM-7.5, Figure 7-9, Boron Dilution, AND Table 7-1, Nomograph Correction Factors
- b. WAG tables
- c. Reactor Engineering approved computer based methods Estimate the rate of boron concentration change as a function of dilution water flow using 10M-7.5, Figure 7-10, Boron Dilution Rate, AND Table 7-1, Nomograph Correction Factors.
Place the 1 MU switch in Stop for greater than 1 second to allow the blender to unarm.
Place 43/MU control switch to DIL OR ALT DIL as directed by the SM/US.
Set AM-1 CH-114, Blender Total Flow Set Point to the desired flow rate.
BVPS 1-NRC Scenario 4 4 of 24
[ INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I
EXPECTED STUDENT RESPONSE ]
Set YIC-1 CH-l68A, Blender Output Integrator to the desired quantity.
- a. Reset Blender Output Integrator YIC-1 CH-168A.
Log the flow totalizer indication AND add to it the number of gallons set into the batch integrator.
Start the reactor makeup control system by placing 1 MU control switch to Start.
Operate pressurizer heaters to initiate automatic spray operation as required so that the difference in boron concentration between the RCS and pressurizer is < 50 ppm.
Verify dilution automatically stops when YIC-1 CH-l68A, Blender Output Integrator reaches the setpoint.
BVPS 1-NRC Scenario 4 5 of 24
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I When dilution is complete, perform the following:
- a.
- b.
C.
- d.
- e.
Place 1 MU control switch in Stop for greater than 1 second.
Place the 43/MU control switch to Auto.
Reset YIC-1 CH-l68A, Blender Output Integrator.
Place the 1 MU switch to Start.
Adjust makeup controls for the new RCS boron concentration.
BVPS 1-NRC Scenario 4 6 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
EVENT #t2 B MFW Pump Trip; Load Reduction Required FW-P-1 B Trips.
When directed, insert the following command:
IMF FWMO1 B (0 0)
[A7-371, Steam Generator Feed Pump Auto Stop If requested, SM should direct a load reduction at rate of 5%/minute.
[A7-391, Steam Generator Fet Disch Flow Hi Start 2nd Pump
[A7-451, Steam Generator 1 A Deviation from Setpoint
[A7-53], Steam Generator 1 B Deviation from Setpoint 3 Pump
.eve1
.eve1
[A7-611, Steam Generator 1 C Level Deviation from Setpoint Only FW-P-1 A running.
PORVs 455C and 455D are available.
Crew responds to indications and alarms.
PO determines that 6 Main Feed Pump tripped.
US enters AOP-1.24.1, Loss of Main Feedwater.
PO verifies condensate pumps and heater drain pumps running.
RO determines reactor power is >
65%.
US directs load reduction to 65%
power at 5% per minute in accordance with AOP-1.51.l.
Crew alerts plant personnel of emergency shutdown.
Verify PORVs available.
BVPS 1-NRC Scenario 4 7 of 24
[
INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
Crew initiates a plant shutdown.
PO sets turbine load setter at 5"/6 per minute.
RO determines required boration using the reactivity plan for rapid power reduction.
RO initiates emergency borating by performing 1 OM-7.4.S, Emergency Boration.
Turbine load decreasing.
Governor valves responding normally.
PO depresses the reference control GO pushbutton.
After the governor valves are off the limiter:
Transfer turbine control to the 1
stage pressure feedback by depressing the 1 stage IN pushbutton.
Verify 1 stage OUT lamp is OFF and 1" stage IN lamp is ON.
Verify governor valve movement not excessive during load reduction.
BVPS 1-NRC Scenario 4 8 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I BVPS 1-NRC Scenario 4 Control rods in Auto.
All PRZR heaters energized.
9 of 24 RO places control rods in AUTO and verifies Tavg is within +/- 5F of Tref.
RO places all PRZR heaters to On.
PO maintains valve position limit at 5%
above existing turbine load during the load reduction.
1 INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #3 Dropped Control Rod K-6 Insert malfunction following load reduction, after crew has control of SG level and TAVG is within 2F of TREF.
IMF CRF04BV (0 0) 1 BVPS 1-NRC Scenario 4 Rod K-6 drops due to stationary gripper failure.
[A4-591, NIS Power Range Low Setpoint Flux Deviation or Auto Defeat
[A4-67], NIS Power Range High Setpoint Flux Deviation or Auto Defeat
[A4-681, NIS Power Range Comparator
[A4-76], Computer Alarm Rod Deviation/Seq Rod K-6 dropped.
RCS TAVG
> 541 F and stable.
10 of 24 Crew responds to indications and alarms.
US refers to AOP-1.1.8, Rod I nope ra bi I it y.
RO checks only 1 rod dropped.
US confirms 1 control rod dropped.
RO places control bank selector switch in Manual.
Crew checks RCS TAva > 541 F, within
+/- 4F of Tref and stable.
US determines power operation may continue if within 1 hour:
. Rod declared inoperable
. Verify shutdown margin requirements of TS 3.1.1.1
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1
As Manager, Operations direct that conditions remain stable while determining cause of rod problem.
Continue with scenario when Technical Specifications have been addressed.
Power reduced to less than 75%
reduced to less than 85% within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Verify shutdown margin once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Request RE perform lncore Flux Map High Neutron Flux Setpoint US requests guidance from Manager, Operations on whether to withdraw misaligned rod.
US may refer to Technical Specification 3.1.3.1 Action c.3.
BVPS 1-NRC Scenario 4 11 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #4 Pressurizer Master Pressure Control Output Fails High When directed, insert the following command:
IOR X07A090P (0 0) 0 600 RC-PK-444A fails in Auto, Manual control available.
[A4-121, Pressurizer Control Low Pressure Deviation
[A4-11], Pressurizer Control Pressure Low
[A4-5], Pressurizer Power Oper. Relief Valve Open Spray valves open.
PORV 455C opens.
PRZR heaters energized.
Crew responds to indications and alarms.
RO takes manual control of PRZR Master Pressure Controller.
RO reduces output of controller to close PORV and spray valves.
RO energizes PRZR heaters, as required.
US refers to TS 3.2.1 BVPS 1-NRC Scenario 4 12 of 24
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #5 Feed Flow Transmitter Fails High When directed, insert the following command:
IMF FWM14F (0 0) 5E6 FT-1 FW-497, SG C Channel 3 fails high slowly.
[A7-581, Loop 3 Feedwater Flow Greater Than Steam Flow
[A7-611, Steam Generator 1 C Level Deviation from Setpoint
[A7-631, Steam Generator 1 C Level Low
[A7-641, Loop 3 Steam Flow Greater Than Feedwater Flow FCV-1 FW-498 closes slowly.
FC-1 FW-498 selected to FM-496 position.
FCV-1 FW-498 in Auto.
Crew responds to indications and alarms.
US refers to 10M-24.4.IF, Attachment
- 2.
PO takes manual control of SG C Feed Reg Valve and adjusts SG level, as required.
PO selects redundant feed flow transmitter for control.
PO returns SG C Feed Reg Valve to Auto when SG level is stable within normal range.
BVPS 1-NRC Scenario 4 13 of 24
1 INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1
When directed to trip bistables, insert the following:
IOR XSO3C23 (0 0) 1 IMF BST-RCS058 (0 0) 0 IMF BST-RCSO59 (0 0) 0 DOR XSO3C23 Protection Rack 18 door open.
BS-498B tripped.
BS-498C tripped.
Protection Rack 18 door closed.
US contacts I&C to direct tripping of bistables.
US contacts I&C to investigate failure of FT-1 FW-497.
BVPS 1-NRC Scenario 4 14 of 24
i I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I EVENT #6 S G "C" Feed wa t e r Reg u I at i n g Valve Fails Closed FCV-1 FW-498 fails closed. Manual control unsuccessful. Reactor Trip required.
When directed, insert the following command:
PO takes manual control of SG "C" Feed Reg Valve.
IMF RNM07C (0 0) 0 120 US determines FRV failure is not recoverable.
Crew enters E-O.
BVPS 1-NRC Scenario 4 Reactor trip and bypass breakers open.
Power range.: 5%.
Neutron flux dropping.
Throttle or governor valves closed.
Main generator output breakers open 15 of 24 US directs RO to manually trip reactor and enters E-0.
RO verifies reactor trip:
. Reactor trip and bypass breakers open.
. Power range indication < 5%.
. Neutron flux dropping.
PO verifies turbine trip.
PO verifies generator trip.
[
INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Exciter circuit breaker open.
Crew enters ES-0.1.
BVPS 1-NRC Scenario 4 1 AE and 1 DF busses energized by offsite power.
SI not actuated and not required 16 of 24 PO verifies power to AC emergency busses.
US directs transition to ES-0.1 US directs STA to begin monitoring CSF status trees.
[ INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #7 Main Steam Line Break With MSlV Failure When directed, insert the following command:
IMF MSS02B (0 0) 1 E7 Preloaded command for MSlV failure.
CRITICAL TASK #1:
Close MSIVs prior to an Orange condition on the Integrity CSF status tree.
Crew re-enters E-0.
Steam break downstream of MSlV B.
Crew sounds Standby alarm and announces Unit 1 reactor trip.
RCS temperature dropping.
Steam dump valves closed.
MOV-1 MS-1 OOA, B closed.
SG blowdown valves closed.
AFW flow throttled to < 355 gpm.
SG B MSlV open.
SI actuated.
Reactor tripped.
RO checks RCS temperature stable at or trending to 547F.
. Stop dumping steam
. Verify reheat steam isolation Verify SG blowdown isolated
. Throttle total feed flow > 355 gpm.
. Close valves with YELLOW SLI marks US directs SI initiation or SI actuates.
US re-enters E-0 and announces entry to crew.
RO reverifies reactor trip.
BVPS 1-NRC Scenario 4 17 of 24
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I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 LHSl pumps running All red SIS lights lit.
RO/PO check both LHSl pumps are running.
RO/PO checks all valves indicating lights with RED marks are LIT.
MD AFW and TD AFW pumps running.
PO reverifies AFW status.
All SG AFW throttle valves open.
TAVG stabilizing after MSlV closure.
Recirc spray pumps not running.
PORVs closed.
PO verifies SG AFW throttle valves are full open.
PO performs Attachment 1 -K, Verification of Automatic Actions (Steps listed at end of scenario guideline.)
PO verifies RCS Tavg stable or trending to 547QF.
RO/PO checks recirc spray pump status.
RO checks PZR PORVs, safety and spray valves.
BVPS 1-NRC Scenario 4 19 of 24
1 INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Safety valves closed.
Spray valves at zero demand.
PORV MOVs open (except previously closed MOV-1 RC-536).
Crew enters ES-1.l, if SI Termination criteria is satisfied.
BVPS 1-NRC Scenario 4 D/P between RCS pressure and highest SG pressure < 200 psid.
No SG pressures dropping in an uncontrolled manner.
No SG levels rising in an uncontrolled manner.
CNMT radiation, pressure and sump levels at pre-event values.
20 of 24 RO checks if RCPs should be stopped.
PO checks if any SGs are faulted.
PO checks if SG tubes are intact.
Crew checks if SI flow should be reduced.
US transitions to ES-1.1 and informs crew.
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[ INSTRUCTIONAL GUIDELINES 1
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I -K, Verification of Automatic Act ions Diesel Generators - BOTH RUNNING.
Check station instrument air header pressure - GREATER THAN 100 PSIG.
Ensure reheat steam isolation:
- a. Verify [MOV-1 MS-1 OOA, B]
CLOSED.
- b. Reset reheater controller.
Verify CCR Pumps - TWO RUNNING.
Align Neutron Flux Monitoring For Shutdown:
- a. Transfer NR-1 NI-45, Nuclear Recorder to operable source and intermediate range displays.
Verify river water system in service.
- a. RPRW Pumps - W O RUNNING BVPS 1-NRC Scenario 4 22 of 24
[ INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
- GREATER THAN 20 PSIG.
Check If main steamline isolation required.
- a. Check the following:
. CNMT pressure - GREATER THAN 3 PSIG.
OR Steamline pressure - LESS THAN 500 PSIG.
. Steamline pressure high rate of change - ANY ANNUNCIATOR LIT.
Annunciator A7-41 Annunciator A7-49 BVPS 1-NRC Scenario 4 Annunciator A7-57
- b. Verify steamline isolation:
YELLOW SLI marks - LIT.
23 of 24
I INSTRUCTIONAL GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 Check CIB and CNMT spray status:
. Containment pressure - HAS REMAINED LESS THAN 8 PSIG.
Verify ESF equipment status:
- b. Verify CIA by checking all ORANGE CIA marks - LIT
- c. Verify FWI by checking all GREEN FWI marks - LIT.
Verify power to both AC emergency busses.
Upon completion, report any discrepancies to SM/US.
BVPS 1-NRC Scenario 4 24 of 24