ML051240145
| ML051240145 | |
| 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: ML051240145 (108) | |
Text
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RTL# A5.670.M 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: License Operator TraininglLicensed Requalification Training SUBDIVISION: Simulator SCENARIO TITLWNO.: 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 1LOT6 Scenario No. 1 2 2-8-05 INSTRUCTIONALSETTING: Simulator APPROXIMATE DURATION: 1.5 Hours PREPARED BY:
Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date BVPS-1 NRC Scenario 1 Page 1 of 29
INITIAL CONDITIONS: . IC-181, PW = NRC1; 100% Power, RCS Boron 1205 ppm, CB D at 227 steps, Rods in Auto.
1CH-P-1C, HHSVCharging Pump 00s.
. PCV-1RC-456, PORV leakage. MOV-1RC-536, Block Valve closed with power maintained.
. Flood warnings from heavy rains.
Maintenance investigating 1RW-P-1A, River Water Pump abnormal vibrationhoise.
I ADDITIONAL LINEUP CHANGES I STICKERS I VOND MARKINGS I
PCV-1RC-456 Control Switch in Close YCT - Both CH-P-1C Switches OM Fig. 7-1, 3E: CH-27, 161 Shut MOV-1RC-536 Control Switch in Close YCT - PCV-1RC-456 Control Switch OM Fig. 7-1, 5E: CH-21, 148 Shut YCT - MOV-1RC-536 Control Switch EQUIPMENT STATUS DATE/TIME 0 0 s I TECHNICAL SPECIFICATION(S)
I I 1CH-P-1C I 2 days ago I N/A I
I PCV-1RC-456 I Yesterday 1500 I 3.4.1 1.a I SHIFT TURNOVER INFORMATION
- 1. 1CH-P-1C is 00s for pump shaft and coupling replacement and is expected to return within the next 24 - 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
- 2. PCV-1RC-456 seat leakage. MOV-1RC-536 is closed with power maintained per T.S. 3.4.1 1.a.
- 4. AOP-1/2.75.2, Acts of Nature - Flood is in effect. River water level is currently 671 feet and stable. Cooling Tower Pump House level is being logged on the Outside Operator Tour.
- 5. Train B is the Protected Train.
- 6. Reduce reactor power to 75% at 12Yhr. to remove a condenser waterbox from service for cleaning.
SCENARIO SUPPORT MATERIAL REQUIRED 1OM-52.4.8, Load Following Reactivity Plan for 12%/hr. Load Reduction Protected Train B Wall Plaque
INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #1 Reduce power to 75% at 12% per US directs load reduction in hour accordance with Reactivity Plan.
BOP initiates load reduction per 1OM-52.4.8, Step 1V.A.
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 Depress the GO pushbutton.
decreasing at 12%/hr.
BVPS -1 NRC Scenario 1 4 of 29
I I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I 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 IST STG OUT lamp is OFF.
- 2. The lST STG IN lamp is ON.
After transfer to the 1ST 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 Depress the GO pushbutton.
lowering at 12% per hour BVPS -1 NRC Scenario 1 5 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I RO initiates RCS boration as necessary to maintain Tavg - Tref per 1OM-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:
- 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 1OM-7.5, Figure 7-8, Boron Addition Rate, AND Table 1, Nomograph Correction Factors.
Place the 1MU control switch to Stop for greater than 1 second to allow the blender to unarm.
BVPS -1 NRC Scenario 1 6 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Place 43/MU control switch to Borate.
Set FCV-1CH-l13A, Boric Acid to Blender FCV to the desired boric acid flowrate.
Set Boric Acid Integrator YIC-1CH-113 for the desired quantity.
- a. Reset Boric Acid Integrator YIC-1CH-113.
Start the Reactor Makeup Control System by placing 1MU control switch to Start.
Verify boric acid to blender flow on FR-1CH-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 7 of 29
[ INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Verify boration automatically stops when Boric Acid Integrator YIC-1CH-113 reaches the setpoint.
When boration is complete, perform the following:
- a. Place the 1MU control switch to Stop for greater than 1 second.
- b. Place 43/MU control switch to Auto.
C. Reset Boric Acid Integrator YIC-1CH-113.
- e. Place the 1MU control switch to Start.
BVPS -1 NRC Scenario 1 8 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #2 Valve Position Limiter Failure; Load rejection occurs and control rods Control Rods Fail In Auto fail in Auto after stepping in.
When directed, insert the following Crew acknowledges alarms, notifies command: Annunciators: US and investigates loss of load.
IMF TUR15 (0 0 ) 60 [A4-461, Tavg Deviation from Tref (Other malfunctions pre-loaded) [A4-1241, Rod Control Bank D Low Low
[A4-121, Pressurizer Control Low Crew informs US of the loss of Pressure Deviation electrical load.
[A4-521, Delta Flux Out of Target Band Control rods stop moving after Control rods stepping in. US refers to AOP-1.35.2, Load 10 seconds (preloaded). Rejection Tavg increasing.
Steam dump valves opening.
RCS pressure increasing.
MW decreasing.
Control rods not inserting. RO verifies control rods in Auto.
Rods in Manual and inserting. . Inserts control rods in Manual Boration flow indicated. RO initiates RCS boration.
BVPS -1 NRC Scenario 1 9 of 29
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Crew sounds Standby alarm and announces Unit 1 load rejection.
US requests SM to evaluate EPP.
EHC system normal except for valve BOP verifies normal EHC operation.
position limiter.
. VPL not consistent with pre-event value 1LO-M-SA running. BOP checks at least one EHC pump is running.
EHC pressure > 1550 psig. BOP checks EHC fluid pressure greater than 1550 psig.
Valve position limiter failure; vibration Crew checks if governor valves have and load satisfactory for condition. closed in sequence, checks turbine vibration recorders.
Generator load stable. Crew monitors for subsequent load reductions > 90 Mwe.
BVPS -1 NRC Scenario 1 10 Of 29
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
Crew checks if reactor or turbine should be tripped.
Generator load > 270 Mwe. Generator load > 270 MWe Vacuum < 5.5 inches HgA. . Vacuum -c 5.5 inches HgA Generator volts, amps, and power factor BOP checks main generator satisfactory. parameters.
Tavg lowering to Tref value. RO checks Tavg-Tref within k 2".
BOP resets steam dump controller:
Steam dump valves closed. Verifies steam dump valves closed Steam dumps reset. Places steam dump control mode selector switch to reset Allows switch to spring return to Tavg position Bistable lights extinguished. Verifies load rejection bistables NOT lit V PL malfunctioning. Crew determines VPL reference setting not at pre-event value.
BVPS -1 NRC Scenario 1 11 of 29
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I FE System and Duquesne Light US notifies Wadsworth (FE) System Controllers acknowledge Control Center and Duquesne Light notification of load rejection. System Control Center of load rejection.
At SM direction, do not lower turbine load.
US directs I&C to investigate problem with VPL.
US checks for load reduction of > 15%
and informs Chemistry, if necessary.
TV-1CN-100 closed. Crew checks TV-1CN-100 closed.
Reactor power > 25%. Crew checks if 1CCT-13 should be opened.
Continue with scenario when US may review T.S. 3.2.1, 3.2.5 and VPL problem is identified and 3.1.3.6 for compliance.
Tavg-Tref are matched, or at Examiners discretion.
US reviews T.S. 3.4.8 for RCS sampling requirements, if power changed by >15°/0.
BVPS -1 NRC Scenario 1 12 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #3 Pressurizer Pressure Transmitter PT-1RC-445 fails high slowly. RO notes alarm and informs US. Crew Fails High refers to ARPs, if necessary.
When directed, insert the following command: Annunciators:
IMF PRS08E (0 0) 2500 120 [A4-51, Pressurizer Power Oper Relief US refers to 1OM-6.4.IFI Instrument Valve Open Failure Procedure, Attachment 2.
[A4-9], Pressurizer Control Press High
[A4-121, Pressurizer Control Press Deviation
[A4-131, Pressurizer Control Press High Pwr Relief Act PCV-1RC-455D closed. RO closes PCV-1RC-455D.
PCV-1RC-456 blocked closed.
US refers to Technical Specifications.
. T.S. 3.2.5 may apply if RCS pressure is below DNB setpoint.
T.S. 3.4.1 1.a may be referenced, but PORV remains operable in manual, capable of being cycled.
BVPS -1 NRC Scenario 1 13 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #4 SG Pressure Transmitter Failure PT-1MS-485 fails low.
When directed, insert the following Crew responds to indications and command: alarms.
IMF MSS16E (0 0 ) 0 [A7-491, Loop 2 Steamline Pressure Low or Press Rate Hi
[A7-50], Loop 2 Feedwater Flow >
Steam Flow
[A7-53], Aux Feed to Stm Gen Valves Not Fully Open Train A SG 16 Channel 3, PT-1MS-485 fails low.
SG 1B Channel 3 steam flow drops (density compensation input).
SG 1B feed flow, NR level drops.
FCV-1FW-488 modulates closed in BOP notes problem with SG 1 6 level automatic. control, takes manual control of FCV-1FW-488 and informs US.
BVPS -1 NRC Scenario 1 14 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 NOTE:. Level deviation is SG 1B level deviation. Crew determines that steam pressure dependent on time of channel PT-1MS-485 failed low.
establishing normal MFRV control to restore SG level.
US refers to 1OM-24.4.IF, Instrument Failure Procedure, Attachment 4.
NR level returning to 44%. US directs BOP to restore SG 1B level to program level.
FM-485 selected. BOP selects redundant SG steam flow signal on FC-1Fw-488.
FCV-1Fw-488 in Auto. US directs BOP to return feedwater control to automatic 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.
US 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 15 of 29
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 US directs crew to trip associated bistables per 1OM-24.4.IF, Attachment 4, Table 1.
US directs I&C to investigate failure of steam pressure channel.
Prior to next event, insert the Condenser Steam Dump Failure following command:
IMF MSS07 (0 0)
When bistables have been directed to be tripped and malfunction is inserted, continue with the next event.
BVPS -1 NRC Scenario 1 16 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENTS #5.6, & 7 Turbine Trip; Condenser Steam Spurious turbine trip leads to ATWS Dump Failure; Auto and Manual event followed by faulted SG due to Reactor Trip Failure; SG ADV Fails stuck open atmospheric dump valve.
Open When directed, insert the following command:
IMF TURO1 (0 0) 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 RO identifies that 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 informs crew.
Turbine tripped. BOP verifies turbine is tripped.
BVPS -1 NRC Scenario 1 17 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Crew verifies TREF is decreasing.
CRITICAL TASK #1:
Crew inserts negative reactivity Control rods inserting. RO places control rod group selector in into the core by inserting RCCAs Auto and verifies rods are inserting.
before transitioning from FR-S.l.
RO drives rods in manual after automatic rod motion stops.
FW-P-3A and 38 running. . Motor-driven pumps running TV-IMS-105A and 1056 open. . Turbine-driven AFW pump steam supply valves open MOV-1FW-l51A, 6, C, D, E, and F A W throttle valves - full open open.
RO initiates emergency boration.
CH-P-1A running. Verify at least one charging pump running SI not actuated. . Check SI actuated MOV-1CH-350 open . Open MOV-1CH-350 ICH-P-2A(B) running in fast speed. . Start in-service Boric Acid Transfer Pump in FAST speed BVPS -1 NRC Scenario 1 18 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Boration flow > 30 gpm. Verify emergency boration flow -
greater than 30 gpm FI-1CH-122A indicates > 75 gpm. . Adjust FCV-1CH-122 to establish charging flow greater than 75 gpm PRZR pressure < 2335 psig. RO checks PRZR pressure < 2335 psig.
Crew sounds Standby alarm and announces Unit 1 ATWS.
When directed to locally trip reactor, insert:
TRG! 3 RTB A open (2 minute delay). Crew dispatches operator to locally trip the reactor.
RTB B open (2 minute delay).
Control rods drop.
Power decreasing.
BOP verifies turbine trip and reheat steam isolation.
MOV-1MS-1OOA, B closed. Verify MOV-1MS-1OOA, B closed All reheat stop and interceptor valves Reset reheater controller closed.
BVPS -1 NRC Scenario 1 19 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 BOP places both steam dump control interlock selector switches in Off.
SI not actuated. US determines SI has not actuated.
US directs performance of first 10 steps of E-0, as time permits.
RO checks reactor is subcritical.
Power range indicates < 5%. . Power range channels < 5%.
Intermediate Range SUR negative. . Intermediate range channels negative startup rate.
RO continues boration, as necessary.
Crew returns to E-0. US transitions to E-0, and informs crew.
US directs STA to monitor CSF Status Trees.
BVPS -1 NRC Scenario 1 20 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I RO verifies reactor trip.
Reactor trip and bypass breakers open. Rx trip and bypass breakers are open Rod bottom lights lit. . Rod bottom lights are lit Rods at bottom. . Rod position indication at zero Neutron flux decreasing. . Neutron flux is dropping Throttle and governor valves closed. BOP verifies turbine trip.
Main generator output breakers open. BOP verifies generator trip.
Exciter circuit breaker open.
1AE and 1DF busses energized. BOP verifies power to AC emergency busses.
E-0 immediate actions complete. SI actuated. RO verifies SI actuated.
NOTE: Pre-emptive action may have been previously performed.
. Depresses manual SI actuation pushbuttons (both trains).
Crew sounds Standby Alarm and announces Unit 1 reactor trip and safety injection.
BVPS -1 NRC Scenario 1 21 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 1VS-F-4A running. BOP verifies leak collection exhaust fan is running.
US directs starting CNMT hydrogen analyzers.
CH-P-1A and CH-P-1B running. . Two charging pumps running BIT flow indicated. BIT flow indicated SI-P-1A and 16 running. . LHSl pumps both running BOP verifies AFW status.
MD and TD ARN pumps running. . AFW pumps running All SG AFW throttle valves open. . SG AFW throttle valves full open A M flow > 355 gpm. . Total ANV flow > 355 gpm BOP performs Attachment 1-K, Verification of Automatic Actions (Steps listed at end of scenario guideline.)
BVPS -1 NRC Scenario 1 22 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 PCV-1MS-101A stuck open. TAVG decreasing. RO check RCS TAVG stable at or trending to SPF.
Condenser steam dumps closed. Stop dumping steam.
MOV-1MS-1OOA, B closed. Verify reheat steam isolation.
Total A M I flow > 355 gpm. Reduce total feed flow to minimize cooldown.
Main steam trip and bypass valves Close main steam trip and bypass closed. valves.
Recirc spray pumps not running. RO checks recirc spray pump status.
RO checks PRZR isolated.
PCV-1RC-456 closed, but leaking. PORVs closed Spray valves closed. Spray valves closed Safety relief valves closed. Safety relief valves closed PRT conditions normal. PRT conditions at expected values All PORV MOVs open (except MOV- Power to at least one block valve 1RC-536 previously closed). and at least one open D/P between RCS and highest SG Crew checks if RCPs should be pressure > 200 psid. stopped.
BVPS -1 NRC Scenario 1 23 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Crew checks if any SGs are faulted.
SG 1A faulted. BOP determines SG 1A pressure decreasing in uncontrolled manner.
Crew enters E-2. US transitions to E-2, and informs crew.
Control Room dampers shut and timers BOP initiates CREVS and verifies running. system actuated.
When requested as Unit 2 Crew requests Unit 1 CREVS status.
Operator, report CREVS actuation.
CRITICAL TASK #2:
Crew isolates the faulted SG and All yellow SLI marks lit. Crew verifies steam line isolation.
directs operator to close isolation valve before transition out of E-2.
Pre-nonreturn valves closed. BOP closes steamline pre-nonreturn drain valves.
SG 1B and 1C pressures stable. BOP checks for any non-faulted SG.
BVPS -1 NRC Scenario 1 24 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 SG 1A faulted. BOP identifies SG 1A pressure decreasing in uncontrolled manner.
Crew isolates faulted SG.
Main and Bypass Feed Reg Valves 9 Check FWI - previously verified.
closed.
NOTE: Pre-emptive action may AFW throttle valves closed. (May have 9 Close AFW throttle valves on have been previously performed. been previously closed.) faulted SG.
Direct locally closing MS-15.
9 PCV-MS-101A open. Attempt to close atmospheric dump valve.
HCV-1MS-104 closed. 9 Close residual heat release valve.
When directed to close MS-23, Crew directs operator to locally close insert the following command: MS-23.
IRF MSS07 (0 600) 0 (Closes MS-23 on 10 min. delay) BOP checks PPDWST level > 27.5 feet.
No SG levels rising in an uncontrolled Crew checks if SG tubes are intact.
manner.
SI Termination Criteria met. Crew checks if SI flow can be reduced.
BVPS -1 NRC Scenario 1 25 of 29
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I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Attachment l-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-1MS-1OOA, B]
CLOSED.
- b. Reset reheater controller.
Verify CCR Pumps - TWO RUNNING.
Align Neutron Flux Monitoring For Shutdown:
- a. Transfer NR-1NI-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 27 of 29
I INSTRUCTIONAL GUIDELINES 1 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.
. Steamline pressure - LESS THAN 500 PSIG.
. 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.
Check CIB and CNMT spray status:
BVPS -1 NRC Scenario 1 28 of 29
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1
. 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 SWUS.
BVPS -1 NRC Scenario 1 29 of 29
RTL# A5.670.AA 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: License Operator TraininULicensedRequalification Training SUBDIVISION: Simulator SCENARIO TITLWNO.: 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 1LOT6 Scenario No. 2 I 2 I 2-8-05 I INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hours PREPARED BY:
Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date BVPS-1 NRC Scenario 2 Page 1 of 26
INITIAL CONDITIONS: .. IC-182; PW = NRC2; 53% power, RCS Boron 1350 ppm, CB D at 163 steps, Rods in Manual.
. CH-P-1C, HHSVCharging Pump 00s.
PCV-1RC-456, PORV 456 leakage. MOV-1RC-536, Block Valve closed with power maintained.
.. Flood warnings due to heavy rains.
Maintenance is investigating abnormal vibration/noise on 1WR-P-1A, River Water Pump.
Turbine Control selected to First Stage In, Turbine is off the VPL.
ADDITIONAL LINEUP CHANGES I STICKERS I VOND MARKINGS I
PCV-1RC-456 Control Switch in Close YCT - Both CH-P-1C Switches OM Fig. 7-1, 3E: CH-27, 161 Shut MOV-1RC-536 Control Switch in Close YCT - PCV-1RC-456 Control Switch OM Fig. 7-1,5E: CH-21, 148 Shut YCT - MOV-1RC-536 Control Switch EQUIPMENT STATUS DATUTIME 0 0 s TECHNICAL SPECIFICATION(S1 1CH-P-1C I 2 days ago I N/A I PCV-1RC-456 Yesterday 1500 3.4.1 1.a SHIFT TURNOVER INFORMATION
- 1. 1CH-P-1C is 00s for pump shaft and coupling replacement and is expected to return within the next 24 - 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
- 2. PCV-1RC-456 seat leakage. MOV-1RC-536 is closed with power maintained per T.S. 3.4.1 1.a.
- 3. AOP-1/2.75.2 is in effect. River water level is 671 feet and stable. Cooling Tower Pump House level is being logged on the Outside Operator Tour.
- 4. Train B is the Protected Train.
- 5. Reduce power to take the unit off-line at 12%/hr. due to circulating water intake clogging.
SCENARIO SUPPORT MATERIAL REQUIRED 1OM-52.4.B, Load Following Reactivity Plan for 12%/Hr Power Reduction Protected Train 6Wall Plaque
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #1 Reduce Power US directs load reduction in accordance with Reactivity Plan.
PO initiates load reduction per 1OM-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.
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 Depress the GO pushbutton.
decreasing at 12%/hr.
RO initiates RCS boration as necessary to maintain TAVG- TREFper 1OM-7.4.L, Step 1V.A and reactivity plan.
BVPS 1- NRC Scenario 2 4 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Estimate the volume of boric acid to be added to the RCS using any of the following:
- 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 1OM-7.5, Figure 7-8, Boron Addition Rate, AND Table 1 Nomograph Correction Factors.
Place the 1MU control switch to Stop for greater than 1 second to allow the blender to unarm.
Place 43/MU control switch to Borate.
Set FCV-1CH-113Al Boric Acid to Blender FCV, to the desired boric acid f lowrate.
BVPS 1- NRC Scenario 2 5 of 26
[ INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I Set Boric Acid Integrator YIC-1CH-113 for the desired quantity.
- a. Reset Boric Acid Integrator YIC-1CH-113.
Start the Reactor Makeup Control System by placing 1MU control switch to Start.
Verify boric acid to blender flow on FR-1CH-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-1CH-113 reaches the setpoint.
When boration is complete, perform the following:
- a. Place the 1MU control switch to BVPS 1- NRC Scenario 2 6 of 26
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
Stop for greater than 1 second.
- b. Place 43/MU control switch to Auto.
C. Reset Boric Acid Integrator YIC-1CH-113.
- e. Place the 1MU control switch to Start.
BVPS 1- NRC Scenario 2 7 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I I EVENT #2 SG 1B Level Transmitter Failure LT-1Fw-484 (Channel 1) fails high.
When directed, insert the following Crew responds to indications and command: Annunciator: alarms.
IMF FWM16D (0 0) 100 [A7-521, Steam Generator 1B Level High-High RO refers to 1OM-24.4.ABEI Steam Generator 1B Level High-High.
NOTE: No system response occurs on failure of a single channel due to median signal select feature.
US refers to 1OM-24.4.IFI Instrument Failure Procedure, Attachment 1.
US refers to T.S. 3.3.1.1, Item 14 and T.S. 3.3.2.1, Items 5.a and 7.a.
BVPS 1- NRC Scenario 2 8 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #3 No. 1 EDG Trouble When directed, insert the following Crew responds to indications and command: Annunciator: alarms.
IMF EPS11A (0 0) [A9-71, Diesel Generator No. 1 Not Available Or Local Panel Trouble RO refers to 1OM-36.4.AEC, Diesel Generator No. 1 Not Available Or Local Panel Trouble.
Crew dispatches Outside Operator to investigate local alarm.
Outside Operator reports EDG No. US refers to T.S. 3.8.1.1, Action b.
1 control power breaker is open.
BVPS 1- NRC Scenario 2 9 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #4 Letdown Pressure Control Valve PCV-1CH-145 fails closed resulting in a Fails Closed In Auto loss of normal letdown.
When directed, insert the following RO responds to indications and command: alarms.
Annunciator:
IOR X06A087P (0 0) 1.0 [A3-1071, Non-Regen Heat Exchanger Disch Press High BOP refers to 1OM-7.4.ABJI Non-Regen Heat Exchanger Disch Press High.
Letdown backpressure rising.
Letdown flow decreasing. US may refer to AOP-1.7.1, Loss Of Charging Or Letdown.
RO reports 1CHS-FI150 indicates letdown flow is zero.
Crew minimizes any power changes in progress.
Letdown flow at 105 gpm. RO manually controls PCV-1CH-145 to restore letdown flow to previous value.
Valve is physically functional; US contacts I&C to investigate failure problem is in the control circuit. Of PCV-CH-145.
BVPS 1- NRC Scenario 2 10 of 26
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #5 SG 1A MFRV Controller Fails In FCV-1FW-478, Main Feed Reg Valve Auto fails closed.
When directed, insert the following BOP recognizes feed flow problem, command: informs US.
Annunciator:
IMF FWM15A (0 0) 0 300 [A7-451, Steam Generator 1A Level Deviation From Setpoint SG 1A feed flow lowering. US directs BOP to take manual control FCV-1FW-478 to stabilize SG feed flow and level.
FCV-1FW-478 position and feed flow BOP takes manual control of stabilize in Manual. FCV-1FW-478 to raise feed flow.
Valve is physically functional; US directs I&C to investigate problem problem is in the control circuit. with FCV-1FW-478.
BVPS 1- NRC Scenario 2 11 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 EVENT #6 RCS Leak 25 gpm RCS leak in CNMT.
When directed, insert the following Crew responds to indications and command: alarms.
IMF RCSO2A (0 0) 25 [A4-711, Radiation Monitoring High
[A4-721, Radiation Monitoring High-High US refers to AOP-1.6.7, Excessive Primary Plant Leakage.
[A1-351, Ctmt Air Total Pressure Hi/Lo Channel 1
[A1-431, Ctmt Air Total Pressure Hi/Lo RO checks if PRZR level can be Channel 2 maintained.
RM-1RM-204 in alarm. RO controls charging flow as necessary to maintain PRZR level.
RM-1RM-215A, B in alarm.
US requests SM to evaluate EPP.
RO controls charging flow as necessary to maintain PRZR level on program.
RO checks if VCT level can be maintained by normal makeup.
BVPS 1- NRC Scenario 2 12 of 26
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I RM-1MS-102AI B, C, N-16 Steam BOP checks secondary plant radiation Generator Leak Monitors normal. trends normal.
RIS-SV100, Condenser Air Ejector Vent normal.
RM-BD-101, High Capacity Blowdown monitor normal PRT pressure, level, and temperature RO checks PRT conditions consistent normal. with pre-event values.
Slight rise in containment temperature, RO checks containment temperature is (may not be noticeable). normal.
Aux. Bldg. radiation normal. BOP checks Aux. Bldg. radiation levels are normal.
RO isolates charging and letdown.
TV-1CH-200AI B and C closed. . Close TV-1CH-200A, B and C LCV-1CH-460A and B closed. Close LCV-1CH-460A and B FCV-1CH-122 closed. . Close FCV-1CH-122 RCP seal injection flow at 6 gpm per = Reduce seal injection flow to 6 gpm pump. Per Pump BVPS 1- NRC Scenario 2 13 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I PRZR level stable. RO checks PRZR level stable or dropping.
RO restores charging and letdown.
Adjust FCV-1CH-122 to obtain 30 to 50 gpm NOTE: If contacted by US, SM PRZR level > 14%. Verify PRZR level > 14%
may direct an emergency shutdown per AOP-1.51 .l.
PCV-1CH-145 in Manual and 75% open. Place PCV-1CH-145 in Manual and 75% open LCV-1CH-460A and B open. Open LCV-1CH-460A and B TV-1CH-200A and B open. Open TV-1CH-200A, B and C PI-1CH-145 indicates 300 psig. Adjust PCV-1CH-145 until backpressure is 300 psig PCV-1CH-145 in Auto. Place PCV-1CH-145 in Auto FCV-1CH-122 in Auto. Place FCV-1CH-122 in Auto CNMT pressure c 1.5 psig. Crew checks CNMT pressure < 1.5 psig and stable.
When charging and letdown are US may refer to T.S. 3.4.6.2.
restored, initiate the next event.
BVPS 1- NRC Scenario 2 14 of 26
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENTS #7 & #8 SBLOCA; Train " B HHSl Pump RCS LOOP" A LOCA - 2000 gpm.
Auto Start Failure; Train "A" ESF Components Must Be Started Manually.
When directed, insert the following Crew responds to indications and command: alarms.
IMF RCS02A (0 0) 2000 300 [A4-41, Pressurizer Control Low Level Deviation Pre-loaded Commands: [A3-58], Charg Pump Disch Flow High-Low TRGSETl JPPLS1(2)==1 IMF SISOSA (1 0) RCS pressure and PRZR level dropping US orders reactor trip and enters E-0.
rapidly.
IMF INH40 (0 0) RO verifies reactor trip:
IMF SISlOA (0 0) Reactor trip and bypass breakers open. . Reactor trip and bypass breakers open.
Power range < 5%. . Power range indication < 5%.
Crew enters E-0. Neutron flux dropping. . Neutron flux dropping.
Throttle and governor valves closed. BOP verifies turbine trip.
BVPS 1- NRC Scenario 2 15 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I Main generator output breakers open. BOP verifies generator trip.
Exciter circuit breaker open.
1AE and 1DF busses energized from BOP verifies power to AC emergency off site power. busses.
CRITICAL TASK #1:
Crew manually actuates at least SI Train A not actuated. RO determines Train A SI failed to one train of SIS actuated actuate automatically. (If SI was not safeguards before transition to manually actuated previously).
any ORP.
SI actuated (both trains). Manually actuates both SI trains.
Crew sounds Standby alarm and announces Unit 1 reactor trip and safety injection.
1VS-F-4A running. BOP checks leak collection exhaust fan running.
US directs starting CTMT hydrogen analyzers.
BVPS 1- NRC Scenario 2 16 of 26
I INSTRUCTIONALGUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I CH-P-1B running, CH-P-1A tripped and Manually starts CH-P-1B will not restart.
BIT flow indicated. BIT flow indicated SI-P-1A and 1B running. LHSl pumps both running BOP verifies A W status.
MD and TD AFW pumps running. A W pumps running All SG AFW throttle valves open. SG AFW throttle valves full open A M I flow > 355 gpm. Total A M I flow > 355 gpm BOP performs Attachment 1-K, Verification Of Automatic Actions (Steps listed at end of scenario guide.)
RO verifies RCS Tavg stable at or trending to 547*F.
Condenser steam dumps closed. . Stop dumping steam.
MOV-1MS-lOOA, B closed. . Verify reheat steam isolation.
Total A M I flow > 355 gpm. m Reduce total feed flow to minimize cooldown.
Recirc spray pumps not running. RO checks recirc spray pump status.
BVPS 1- NRC Scenario 2 17 of 26
I I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE [ OBJECTIVE I EXPECTED STUDENT RESPONSE 1 RO verifies PRZR isolated.
PCV-1RC-456 closed, but leaking. PORVs closed Spray valves closed. Spray valves closed Safety relief valves closed. Safety relief valves closed PRT conditions normal. PRT conditions at expected values All PORV MOVs open (except MOV- Power to at least one block valve 1RC-536 previously closed). and at least one open D/P between RCS pressure and highest RO checks if RCPs should be SG pressure < 200 psid. stopped.
All RCPs stopped. 9 Stops all RCPs No SG pressures dropping in an BOP checks if any SGs are faulted.
uncontrolled manner.
BOP checks if SG tubes are intact.
No SG levels rising in an uncontrolled manner.
. SG levels - none rising in an uncontrolled manner All secondary radiation levels normal. . Secondary radiation consistent with pre-event values.
BVPS 1- NRC Scenario 2 18 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 Crew checks if RCS is intact.
CNMT parameters not consistent with pre-event values.
. CNMT radiation, pressure and sump level consistent with pre-event values Crew enters E-1 . US transitions to E-1, and informs crew.
US directs STA to monitor CSF status trees, if not previously done.
CREVS not actuated or required. BOP checks if CREVS actuated.
D/P between RCS pressure and highest RO checks if RCPs should be SG pressure < 200 psid and HHSl flow stopped.
CRITICAL TASK #2: indicated.
Crew trips all RCPs when RCS to highest S/G D/P criteria is All RCPs stopped. . Stops all RCPs, if not previously performed exceeded (or due to ClB) and prior to exiting E-1.
Recirc spray not actuated. RO checks recirc spray system status.
BVPS 1- NRC Scenario 2 19 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I No SG pressures dropping in an BOP checks if any SG's are faulted.
uncontrolled manner.
AFW flow > 355 gpm. BOP maintains AFW flow > 355 gpm until NR SG level is > 13%.
Instrument air header pressure > 100 BOP checks instrument air header psig. pressure > 100 psig.
BOP checks if SG tubes are intact.
No SG levels rising in an uncontrolled manner.
. SG levels - none rising in an uncontrolled manner All secondary radiation levels normal. Secondary radiation consistent with pre-event values.
RO checks PZR PORVs and block vaIves.
Power available to PORV MOV's. Power to block valves PORVs closed. . PORVs closed All PORV MOV's open (except MOV-1RC-536 previously closed).
. At least one block valve open BVPS 1- NRC Scenario 2 20 of 26
I
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Crew checks if SI flow should be reduced.
Subcooling > 46F. = RCS subcooling > 46F AFW flow > 355 gpm. . Secondary heat sink available RCS pressure dropping. RCS pressure stable or rising US determines SI Termination Criteria is not met.
CTMT spray pumps not running. Crew checks if CTMT spray should be stopped.
SI reset (both trains). RO resets SI.
CIA reset (both trains). RO resets CIA.
RCS pressure z 300 psig. RO checks if LHSl pumps should be stopped.
Both LHSl pumps stopped and in Auto. = Stop LHSl pumps and place in Auto BVPS 1- NRC Scenario 2 21 of 26
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I SG pressure stable or rising. RCS Check RCS and SG pressures.
pressure stable or dropping.
BOP checks if diesel generators should be stopped.
EE-EG-1 stopped. . BOP manually stops No. 1 EDG, if not previously performed Recirc components available. Crew verifies cold leg recirculation capability.
Radiation levels normal. Crew checks if Aux. Bldg. and Safeguards radiation consistent with pre-event values.
US requests Chemistry and Health Physics to obtain samples.
Crew requests TSC assistance to start additional plant equipment.
Crew checks if RCS cooldown and depressurization is required.
RCS pressure > 300 psig. RCS pressure > 300 psig BVPS 1- NRC Scenario 2 22 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Crew enters ES-1.2. US transitions to ES-1.2, and informs crew.
Scenario may be terminated upon crew transition to ES-1.2.
BVPS 1- NRC Scenario 2 23 of 26
INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I -K, Verification of Automatic Actions No. 2 EDG is running. No. 1 EDG Diesel Generators - BOTH RUNNING.
manually stopped, if running.
Check station instrument air header pressure - GREATER THAN 100 PSIG.
Ensure reheat steam isolation:
- a. Verify [MOV-1MS-1OOA, B]
CLOSED.
- b. Reset reheater controller.
Verify CCR Pumps - TWO RUNNING.
Align Neutron Flux Monitoring For Shutdown:
- a. Transfer NR-1NI-45, Nuclear Recorder to operable source and intermediate range displays.
Verify River Water System In Service.
BVPS 1- NRC Scenario 2 24 of 26
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
- 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.
. 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.
Check CIB and CNMT Spray Status:
BVPS 1- NRC Scenario 2 25 of 26
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1
. 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 SWUS.
BVPS 1- NRC Scenario 2 26 of 26
RTL# A5.670.AA 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: License Operator Training/LicensedRequalification Training SUBDIVISION: Simulator SCENARIO TITLUNO.: 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 1LOT6 Scenario No. 3 2 2-8-05 I INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hours PREPARED BY:
Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date BVPS-1 NRC Scenario 3 Page 1 of 28
INITIAL CONDITIONS:
.. IC-183; PW = NRC3; 25% Power, RCS boron at 1690 ppm, CB D at 133 steps. Rods in Manual.
PCV-1RC-456, PORV 456 leakage. MOV-1RC-536, Block Valve closed with power maintained.
.. FW-P-1B, Steam Generator Feed Pump is 00s.
Flood watch remains in effect.
Turbine Control selected to First Stage In, Turbine is off the VPL.
ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS PCV-1RC-456 Control Switch in Close YCT - PCV-1RC-456 Control Switch MOV-1RC-536 Control Switch in Close YCT - MOV-1RC-536 Control Switch FW-P-1B in P-T-L YCT - FW-P-1B Control Switch Swap In-service BAST Tags EQUIPMENT STATUS I DATWIME 0 0 s 1 TECHNICAL SPECIFICATION(S)
I PCV-1RC-456 Yesterday 1500 3.4.1 1.a FW-P-1B 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago NIA SHIFT TURNOVER INFORMATION
- 1. PCV-1RC-456 seat leakage. MOV-1RC-536 is closed with power maintained per T.S. 3.4.1 1.a.
- 2. FW-P-1B is 00s to replace motor leads and is expected to return within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 3. AOP-1/2.75.2 is in effect. River water level is 671 feet and stable. Cooling Tower Pump House level is being logged on the i
Outside Operator Tour.
- 4. 1CCT-13 is closed.
- 5. FCV-RN-150A and 150B have been restored to normal operation.
- 6. FCV-MS-1OOB and 1OOD, MSR Purge Valves are open.
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I
- 8. Train 6 is the Protected Train
- 9. Raise power to 60% at 12%/hr. after an extended outage to repair cooling tower pumps.
SCENARIO SUPPORT MATERIAL REQUIRED 1OM-52.4.A, Raising Power From 5% To Full Load Operation Reactivity Plan for 12YHr Power Ascension Protected Train B Wall Plaque BVPS 1 NRC Scenario 3 3 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #1 Raise Power To 60% US directs power increase to 60% per 1OM-52.4.A, Step IV.F.19.
Conversion Economics requests Crew reviewdagrees with reactivity raising power to 60% at 12%/hr. plan. US approves for use. Crew begins power increase.
RO initiates dilution per 1OM-7.4.N, Step 1V.A.
Estimate the volume of makeup water to be added to the RCS using any of the following:
- b. WAG tables
- c. Reactor Engineering approved computer based methods BVPS 1 NRC Scenario 3 4 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Estimate the rate of boron concentration change as a function of dilution water flow using 1OM-7.5, Figure 7-10, Boron Dilution Rate, AND Table 7-1, Nomograph Correction Factors.
Place the 1MU 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-1CH-114, Blender Total Flow Set Point to the desired flow rate.
Set blender output Integrator YIC-1CH-168A to the desired quantity.
- a. Reset blender output integrator YIC-1CH-168A.
Log the flow totalizer indication, AND add to it the number of gallons set into the batch integrator.
BVPS 1 NRC Scenario 3 5 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Turbine load and reactor power Start the reactor makeup control increasing at 12Ydhr. system by placing 1MU 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 e 50 ppm.
Verify dilution automatically stops when blender output integrator YIC-1CH-168A reaches the setpoint.
When dilution is complete, perform the following:
- a. Place 1MU control switch in Stop for greater than 1 second.
- b. Place the 4WMU control switch to AUTO.
C. Reset blender output integrator YIC-1CH-168A.
- d. Place the 1MU switch to Start.
BVPS 1 NRC Scenario 3 6 of 28
m u) n m
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #2 Train A RW Pump Trips; Backup 1WR-P-1A trips, 1WR-P-1B fails to auto Pump Manual Start start.
When directed, insert the following BOP recognizes loss of 1WR-P-1A and command: Annunciators: reports to US.
IMF AUXlOA (0 0) [A1-401, CC WTR HT EXCH River WTR PP Disch Line A Press Low
[Al-481, CC WTR HT EXCH River WTR US refers to AOP-1.30.2, River Water, PP Disch Line 8 Press Low Normal Intake Structure Loss.
[A1-591,Intake Struct River WTR PP Disch Line A Press Low
[A1-671, Intake Struct River WTR PP RO checks reactor plant river water Disch Line 6Press Low pump status.
[A1-821, River Water PP Auto Start-Stop RO recognizes and reports 1WR-P-1B did not auto start.
1WR-P-1B running. RO manually starts 1WR-P-1B.
RO checks PI-1RW-l13A(B), CCR Heat Exchanger RW Pressure > 20 psig.
BVPS 1 NRC Scenario 3
r INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I NOTE: Do not rack WR-P-1C US directs local operator to rack onto the AE bus. 1W R-P-1C onto bus.
BOP checks turbine plant river water system status.
US refers to T.S. 3.7.4.1.
BVPS 1 NRC Scenario 3 9 of 28
I I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #3 Loss of 4KV Bus 1AE 1AE bus de-energized, No. 1 EDG fails to auto start.
When directed, insert the following Crew responds to indications and command: Annunciators: alarms.
IMF EPS04E (0 0) [A8-105],4160V Emerg Bus 1AE ACB 1A10 Auto Trip
[A8-106],416OV Emerg Bus 1AE ACB US enters AOP-1.36.2, Loss Of 4KV 1E7 Auto Trip Emergency Bus.
[A8-1091, 4160V Emerg Bus 1AE UndervoItage
[A9-74],48OV Emerg Trans 1-BN BOP checks at least one AC Undervoltage emergency bus is energized.
[A9-100],125V DC Battery Chgr 1 Failure
[A9-108],125V DC Battery Chgr 3 RO checks at least one charging pump Failure is running.
Crew sounds Standby alarm and announces loss of 4KV 1AE bus.
CCR flow indicated to all RCPs. RO verifies CCR flow to all RCP thermal barriers.
RHR not in service. RO checks RHR in service.
No red or yellow border annunciators in Crew responds to color coded alarm. annunciators.
BVPS 1 NRC Scenario 3 10 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE ]
BOP starts No. 1 EDG to restore power to 1AE bus.
Depress both emergency stop pushbuttons Place selector switch in Exercise position EE-EG-1 running. Start EDG No. 1 Ensure EDG speed at 900 rpm Depress field flash pushbutton ACB 1E9 closed. Close ACB-1E9 NOTE: Crew may choose to CH-P-1A running (auto started).
allow CH-P-1A to auto start and secure CH-P-1B, or manually start and stop CH-P-1A.
Crew checks associated RPRW pump is running.
1WR-P-SA running. . Starts 1WR-P-SA US refers to T.S. 3.8.1.1 Action c.
BVPS 1 NRC Scenario 3 11 of 28
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 EVENT #4 Loss of Feedwater and EDG No. 1 FW-P-1A trips followed by trip of EE-EG-1 Failure 2 minutes later.
When directed, insert the following Crew identifies loss of main feedwater command: Annunciators: pump and SG feed flow.
IMF RNMOlA (0 0) [A7-371, Steam Generator Feed Pump Auto Stop
[A7-401, Steam Generator Feed Pump US enters AOP-1.24.1, Loss Of Main Disch Equalizing Press Low Feedwater.
[A7-291, Reactor Trip & Low Tavg or SI Main Feedwater Valve Closed 1CN-P-1A and 1B running. 1SD-P-1A BOP verifies condensate and heater and 1B running. drain pumps are running.
Reactor power c 65%. RO checks reactor power > 65%.
SG levels dropping. US directs RO to trip the reactor.
Crew enters E-0. US transitions to E-0, and informs crew.
BVPS 1 NRC Scenario 3 12 of 28
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE ]
EVENTS #5.6.7 SG 16 SGTR; MD AFW Pump 6 SG 1B 500 gpm SGTR (occurs at Step 7 Fails To Auto Start; CIA Fails To of ES-0.1)
Auto Actuate Pre-loaded Commands RO manually trips reactor.
Crew continues with E-O. RO verifies reactor trip:
Reactor trip and bypass breakers open. . Reactor trip and bypass breakers open.
Power range < 5%. . Power range indication c 5%.
Neutron flux dropping. . Neutron flux dropping.
Throttle or governor valves closed. BOP verifies turbine trip.
Main generator output breakers open. BOP verifies generator trip.
Exciter breaker open.
1AE bus de-energized; 1DF bus BOP verifies power to AC emergency energized from offsite power. busses.
. BOP recognizes and reports trip of No. 1 EDG.
BVPS 1 NRC Scenario 3 13 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
E-0immediate actions complete. SI not actuated and not required. RO checks if SI is actuated.
Crew enters ES-0.1. US transitions to ES-0.1, and informs crew.
US directs STA to begin monitoring CSF status trees.
Crew sounds Standby alarm and announces Unit 1 reactor trip.
RCS TAVG trending to 547F. Check RCS temperature stable at or trending to 547F.
BOP 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 14 of 28
I INSTRUCTIONALGUIDELINES PLANT STATUS OR RESPONSE 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 temperature Instrument air pressure > 100 psig. BOP checks station instrument air header pressure > 100 psig.
RCS TAVG< 554F. . RCS TAVG- Less than 554F.
MFRV's closed. . Verify Main Feedwater Reg Valves closed CRITICAL TASK #1: No AFW pumps running. . -
Check AFW Pumps any running Crew establishes feedwater flow into at least one SG before RCS Fw-P-2 and FW-P-38 running. . BOP manually starts RN-P-2 and FW-P-3B bleed and feed is required.
Bypass FRV's closed. . Close Bypass FRV's FW-P-1A tripped. FW-P-1B out-of-service.
. Stop all but one main feed pump Total feed flow > 355 gpm. . Verify total feed flow > 355 gpm BVPS 1 NRC Scenario 3 15 of 28
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 When the crew reaches ES-0.1, All control rods inserted. RO verifies all control rods are fully Step 7, insert the following: inserted.
IMF RCS03B (0 0) 500 PRZR level dropping. RO checks PRZR level > 14%.
Charging in service. RO checks charging is in service.
Letdown in service. RO checks letdown in service.
PRZR level dropping. RO verifies PRZR level trending to 22%.
SG 1B 500 gpm SGTR RO maintains crew informed of PRZR pressure and level trends.
PRZR level and pressure dropping.
Crew reenters E-0. US directs RO to actuate SI and transitions to 4.
Reactor tripped. RO reverifies reactor trip.
Turbine tripped. BOP reverifies turbine trip.
BVPS 1 NRC Scenario 3 16 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Main generator tripped. BOP reverifies generator trip.
1DF bus energized. BOP reverifies power to AC emergency busses.
No. 2 EDG running. BOP verifies No. 2 diesel generator is running.
SI actuated (both trains). RO manually actuates SI both trains.
Crew sounds Standby alarm and announces Unit 2 reactor trip and SI.
1VS-F-4A running. BOP checks leak collection exhaust fan is running.
US directs starting CNMT hydrogen analyzers.
CH-P-1A (1B) running. . At least two charging pumps running BVPS 1 NRC Scenario 3 17 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 BIT flow indicated. . BIT flow indicated SI-P-1A and 1B running. . LHSl pumps both running BOP verifies AFW status.
FW-P-2 and FW-P3B running. . AFW pumps running AFW throttle valves open. . AFW throttle valves full open AFW flow > 355 gpm. Total AFW flow > 355 gpm.
When directed, insert the following commands:
IMF VLV-AFW02 (0 0) 0 60 MOV-1Fw-151B closed. US directs operator to locally close A W Train "A" valves.
IMF VLV-Am04 (0 0) 0 60 MOW1FW-151D closed.
IMF VLV-AFWO6 (0 0) 0 60 MOV-1Fw-151F closed.
NOTE: CRITICAL TASK #2 is BOP performs Attachment 1-K, performed as part of Attachment Verification of Automatic Actions 1-K actions. (Refer to page 28) (Steps listed at end of scenario guideline.)
RCS TAVG controlled on steam dumps. BOP verifies RCS TAVG stable or trending to 54PF.
BVPS 1 NRC Scenario 3 18 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Recirc spray pumps not running. RO checks recirc spray pump status.
RO verifies PRZR isolated.
PCV-1RC-456 closed, but leaking. PORVs closed Spray valves closed. Spray valves closed Safety relief valves closed. Safety relief valves closed PRT conditions normal. PRT conditions at expected values All PORV MOVs open (except MOV- Power to at least one block valve 1RC-536 previously closed). and at least one open D/P between RCS pressure and highest RO checks if RCPs should be SG pressure > 200 psid. stopped.
No SG pressures dropping in an BOP checks if any SGs are faulted.
uncontrolled manner.
SG 1B level rising in an uncontrolled BOP checks if SG tubes are intact.
manner.
Crew enters E-3. US transitions to E-3, and informs crew.
BVPS - 1 NRC Scenario 3 19 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I CREVS not actuated nor required. BOP checks if CREVS is actuated.
CIB not actuated.
RM-1RM-218A 6 not in high alarm.
D/P between RCS pressure and highest RO checks if RCPs should be SG pressure > 200 psid. stopped.
SG 1B ruptured. Crew identifies ruptured SG.
Unexpected rise in NR level.
CRITICAL TASK #3:
Crew isolates feed flow into and PCV-1MS-101B in manual and closed. RO places SG 1B ADV in manual and steam flow from the ruptured SG closes.
and directs operator to close isolation valve@) operated from outside the control room before a transition to ECA-3.1 occurs.
HCV-1MS-104 closed. RO verifies residual heat release valve is closed.
FW-P-3B running. BOP verifies at least one MD AFW pump is running.
BVPS 1 NRC Scenario 3 20 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I MOV-1MS-105 closed. BOP closes MOV-1MS-105.
1MS-16 closed. Crew dispatches an operator to close TD A M I pump steam supply valve.
BOP verifies steam supply from intact SG.
BOP restarts TDAMI pump.
TV-1MS-111B closed. BOP closes SG 1B pre-nrtrn drain isolation valves.
TV-1MS-101B closed. BOP closes SG 1B main steam trip, bypass, and non-return valves.
MOV-1MS-101B closed.
NRV-1MS-101B closed.
SG 1B level > 13%. BOP checks ruptured SG level.
EOP pre-emptive action. SG 1B AFW throttle valves closed. (May Crew isolates feed flow to SG 1B.
have been previously performed.)
BVPS 1 NRC Scenario 3 21 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Main feedwater isolated. BOP checks FWI previously verified.
SG 1B pressure > 380 psig. BOP checks SG 1B pressure > 380 psig.
Instrument air header pressure > 100 BOP checks instrument air header psig. pressure > 100 psig.
US determines target cooldown temperature based on ruptured SG pressure.
US directs STA to trend cooldown rate.
Condenser steam dumps open. BOP verifies condenser available and initiates cooldown at maximum rate, (or uses SG ADVs).
RCS pressure < 1950 psig. RO blocks steamline SI when RCS pressure reaches 1950 psig.
Tavg c 541°F. BOP defeats TAVG interlock during cooldown.
BVPS 1 NRC Scenario 3 22 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I Total AFW flow > 355 gpm or SG level BOP checks intact SG levels.
between 25% and 50%.
PORV's closed; MOV's open (except RO checks power to PORV's and block previously closed MOV-1RC-536). va Ives .
SI reset (both trains). RO resets SI.
CIA and CIB reset (both trains). RO resets CIA and CIB.
RCS at target temperature. BOP stops RCS cooldown a. a g e t temperature.
BOP checks if CNMT instrument air is available.
Station IA pressure > 100 psig. . Station IA header pressure > 100 Psig TV-1IA-400 open. . TV-1IA-400 open CNMT IA pressure > 85 psig. . CNMT IA header pressure > 85 Psig LHSl pumps previously stopped. RO checks if LHSl pumps should be stopped.
BVPS 1 NRC Scenario 3 23 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Core exit TCs below target temperature. Crew checks if RCS cooldown should be stopped.
SG 1B pressure stable. BOP checks SG 1B pressure stable or rising.
Subcooling > 66F. RO checks subcooling is satisfactory.
RO initiates RCS depressurization.
RCPs 1A and 1C running. Check RCPs 1A and 1C are running.
PRZR spray valves open. Fully open PRZR spray valves PRZR PORV open. Open one PORV Check depressurization method is effective Crew depressurizes until any of the following conditions are satisfied:
. PRZR level > 75%, OR
. RCS subcooling < Att. 6-A, OR
. RCS pressure c ruptured SG pressure, AND BVPS 1 NRC Scenario 3 24 of 28
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE ]
. PRZR level > 18%
CRITICAL TASK #4:
Crew depressurizes RCS to meet RCS depressurization stopped. RO closes PORV and spray valves.
SI termination criteria before water release from the SG safety or atmospheric relief valve.
Scenario may be terminated upon crew completion of RCS depressurization in E-3.
BVPS 1 NRC Scenario 3 25 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Attachment 1-K, Verification of Automatic Actions EE-EG-1 tripped. Diesel Generators - BOTH RUNNING.
Check station instrument air header pressure - GREATER THAN 100 PSIG.
Ensure reheat steam isolation:
- a. Verify [MOV-1MS-1OOA, B]
CLOSED.
- b. Reset reheater controller.
4KV 1AE bus de-energized. Only CC-P-1B running. Verify CCR Pumps - TWO RUNNING.
Align Neutron Flux Monitoring For Shutdown:
- a. Transfer NR-1NI-45, Nuclear Recorder to operable source and intermediate range displays.
Verify river water system in service.
4KV 1AE bus de-energized. Only WR-P-1B running. a. RPRW Pumps - TWO RUNNING.
BVPS 1 NRC Scenario 3 26 of 28
1 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.
. Steamline pressure - LESS THAN 500 PSIG.
. 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 27 of 28
[ 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 PSIG.
Verify ESF equipment status:
CRITICAL TASK #2: a. Verify SI status by checking all RED SIS marks - LIT.
Initiate at least one train of CIA CIA manually actuated. b. Verify CIA by checking all prior to completion of ORANGE CIA marks - LIT.
attachment 1-K.
- c. Verify FWI by checking all GREEN NVI marks - LIT.
4KV Bus 1AE de-energized. 1DF bus Verify power to both AC emergency energized. busses.
Upon completion, report any discrepancies to SWUS.
BVPS 1 NRC Scenario 3
RTL# A5.670.M 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: License Operator TrainindLicensed Requalification Training SUBDIVISION: Simulator SCENARIO TITLWNO.: 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 1LOT6 Scenario No. 4 I 2 I 2-17-05 I I I I
~
I I 1 INSTRUCTIONALSETTING: Simulator APPROXIMATE DURATION: 1.5 Hours PREPARED BY:
Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date BVPS-1 NRC Scenario 4 Page 1 of 25
INITIAL CONDITIONS: rn IC-184; PW = NRC4; 75% Power, Equil Xe, RCS boron at 1279 ppm, CB D at 190 steps.
PCV-1RC-456, PORV leakage. MOV-1RC-536, Block Valve closed with power maintained.
rn River water level has receded. Flood watch cancelled on last shift.
rn 1WR-P-1A, River Water Pump 00s.
Turbine control selected to First Stage Out, Turbine is on the VPL.
1 ADDITIONAL LINEUP CHANGES 1 STICKERS I VOND MARKINGS I
PCV-1RC-456 Control Switch in Close YCT - PCV-1RC-456 Control Switch MOV-1RC-536 Control Switch in Close YCT - MOV-1RC-536 Control Switch WR-P-1A in P-T-L YCT - WR-P-1A Control Switch I EQUIPMENT STATUS I DATUTIME 00s 1 TECHNICAL SPEClFICATION(S)
I I PCV-1RC-456 I Yesterday 1500 I 3.4.1 1.a I I W R-P-1A I 2 days ago 1 N/A I SHIFT TURNOVER INFORMATION
- 1. PCV-1RC-456 seat leakage. MOV-1RC-536 is closed with power maintained per T.S. 3.4.1 1.a.
- 2. 1WR-P-1A is 00s for motor bearing replacement. WR-P-1C is in standby on the AE bus.
- 3. Protected Train is Train 6.
- 4. Raise power to 100% at 12/% per hour. Plant was at reduced power for 1 week due to condenser water box outage.
SCENARIO SUPPORT MATERIAL REQUIRED 1OM-52.4.8, Load Following Reactivity Plan for 12O/dHr Power Ascension Protected Train B Wall Plaque
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #1 Raise Power To 100% US directs power increase to 100% per 1OM-52.4.8, Step IV.B.13.
NOTE: This event is not required to satisfy the qualitative or quantitative requirements of NUREG-1021, but may be performed at Chief Examiners discretion.
Crew reviewdagrees with reactivity pian. US approves for use. Crew begins power increase.
BOP initiates turbine load increase.
- a. Set the desired terminal load on the SETTER.
- b. Set the desired rate on the LOAD RATE thumbwheel (5Ymin.
maximum).
C. As the turbine load increases, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.
Turbine load and reactor power d. Depress the GO pushbutton.
increasing at 12%/hr.
RO initiates RCS dilution as necessary to maintain TAVG - TREFper 1OM-7.4.N, Step 1V.A.
BVPS 1- NRC Scenario 4 3 of 1
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:
- 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 1OM-7.5, Figure 7-10, Boron Dilution Rate, AND Table 7-1, Nomograph Correction Factors.
Place the 1MU 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-1CH-114, Blender Total Flow Set Point to the desired flow rate.
BVPS 1- NRC Scenario 4 4 of 1
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 Set YIC-1CH-l68A, Blender Output Integrator to the desired quantity.
- a. Reset Blender Output Integrator YIC-1CH-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 1MU 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 c 50 ppm.
Verify dilution automatically stops when YIC-1CH-l68A, Blender Output Integrator reaches the setpoint.
When dilution is complete, perform the following:
BVPS 1- NRC Scenario 4 5 of 1
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
- a. Place 1MU control switch in Stop for greater than 1 second.
- b. Place the 43/MU control switch to Auto.
C. Reset YIC-1CH-l68A, Blender Output Integrator.
- d. Place the 1MU switch to Start.
BVPS 1- NRC Scenario 4 6 of 1
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 EVENT #2 MFW Pump iiB Trip; Load FW-P-16 trips. Crew responds to indications and Reduction Required alarms.
When directed, insert the following command: Annunciators:
IMF FWMO1B (0 0) [A7-371, Steam Generator Feed Pump BOP determines that 16 Main Feed Auto Stop Pump is tripped.
[A7-391, Steam Generator Feed Pump Disch Flow Hi Start 2d Pump
[A7-45], Steam Generator 1A Level US enters AOP-1.24.1 Loss of Main Deviation from Setpoint Feedwater.
[A7-53], Steam Generator 16 Level Deviation from Setpoint
[A7-61], Steam Generator 1C Level BOP verifies condensate pumps and Deviation from Setpoint heater drain pumps running.
Only FW-P-1A running. RO determines reactor power is >
65%.
If requested, SM should direct a US directs load reduction to 65%
load reduction at rate of power in accordance with AOP-1.51 .l.
5Ydminute.
Crew alerts plant personnel of emergency shutdown.
PORVs 455C and 4550 are available. Verify PORVs available.
BVPS 1- NRC Scenario 4 7 of 1
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Crew initiates a plant shutdown.
BOP sets turbine load setter at 2% (or 5%) per minute at direction of US.
RO determines required boration using the reactivity plan for rapid power reduction.
Reactor power decreasing. RO initiates RCS normal or emergency boration at direction of US.
Turbine load decreasing. BOP 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.
Governor valves responding normally. Verify governor valve movement not excessive during load reduction.
Control rods in Auto. RO places control rods in AUTO and verifies Tavg is within +/- 5F of Tref.
BVPS 1- NRC Scenario 4 8of 1
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1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #3 Dropped Control Rod K-6 Rod K-6 drops due to stationary gripper failure.
Insert malfunction following load Crew responds to indications and reduction] after crew has control of alarms.
SG level and T A V G is within 2F of TREF. Annunciators:
IMF CRF04BV (0 0) 1 [A4-59], NIS Power Range Low Setpoint Flux Deviation or Auto Defeat
[A4-67], NIS Power Range High Setpoint US refers to AOP-1.1.8, Rod Flux Deviation or Auto Defeat Inoperability.
[A4-681, NIS Power Range Comparator
[A4-76], Computer Alarm Rod RO checks only 1 rod dropped.
Deviation/Seq Rod K-6 dropped. US confirms 1 control rod dropped.
Control rods in manual. RO places control bank selector switch in Manual, if in Auto.
RCS TAVG > 541F and stable. Crew checks RCS TAVG > 541F, within f 4F of Tref and stable.
US determines power operation may continue if within 1 hour:
.. Rod declared inoperable Verify shutdown margin requirements of T.S. 3.1.1.1 BVPS 1- NRC Scenario 4 10of 1
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Power reduced to less than 75%
' High Neutron Flux Setpoint reduced to less than 85% within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
' Verify shutdown margin once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
' Request RE perform lncore Flux Map As Manager, Operations direct that US requests guidance from Manager, conditions remain stable while Operations on whether to withdraw determining cause of rod problem. misaligned rod.
Continue with scenario when US may refer to T.S. 3.1.3.1 , Action Technical Specifications have c.3.
been addressed, or at Chief Examiner's discretion.
BVPS 1- NRC Scenario 4 11 of 1
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #4 Pressurizer Master Pressure RC-PK-444A fails in Auto, Manual Control Output Fails High control available.
When directed, insert the following Crew responds to indications and command: Annunciators: alarms.
IOR X07A090P (0 0) 0 600 [A4-121, Pressurizer Control Low Pressure Deviation
[A4-11], Pressurizer Control Pressure RO takes manual control of PRZR Low Master Pressure Controller.
[A4-51, Pressurizer Power Oper. Relief Valve Open PORV 455C and spray valves open. RO reduces output of controller to close PORV and spray valves.
PORV and spray valves closed.
PRZR heaters energized. RO energizes PRZR heaters, as required.
US refers to T.S. 3.2.5.
BVPS 1- NRC Scenario 4 120f 1
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
EVENT #5 Feed Flow Transmitter Fails High FT-1FW-497, SG 1C Channel 3 fails high.
When directed, insert the following Crew responds to indications and command: alarms.
IMF FWM14F (0 0) 5E6 [A7-581, Loop 3 Feedwater Flow Greater Than Steam Flow
[A7-611, Steam Generator 1C Level Deviation from Setpoint
[A7-631, Steam Generator 1C Level Low
[A7-641, Loop 3 Steam Flow Greater US refers to 10M-24.4.IF, Instrument Than Feedwater Flow Failure Procedure, Attachment 2.
FCV-1Fw-498 closes slowly. BOP takes manual control of FCV-1Fw-498 and adjusts SG level, as required.
FC-1FW-498 selected to FM-496 BOP selects redundant feed flow position. transmitter for control.
FCV-1FW-498 in Auto. BOP returns FCV-1Nv-498 to Auto when SG level is stable within normal range.
BVPS 1- NRC Scenario 4 130f 1
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 When directed to trip bistables, insert the following:
IOR XSO3C23 (0 0) 1 Protection Rack 18 door open. US contacts I&C to direct tripping of bistables.
IMF BST-RCSO58 (0 0) 0 BS-498B tripped.
IMF BST-RCS059 (0 0) 0 BS-498C tripped.
DOR XSO3C23 Protection Rack 18 door closed.
US contacts I&Cto investigate failure of Fr-1FW-497.
BVPS 1- NRC Scenario 4 140f 1
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #6 SG 1C Feedwater Regulating Valve FCV-1W-498fails closed. Manual Fails Closed control unsuccessful. Reactor Trip required.
When directed, insert the following BOP takes manual control of SG 1C command: Feed Reg Valve.
Annunciator:
IMF FWM07C (0 0) 0 120 [A7-611, Steam Generator 1C Level Deviation From Setpoint US determines FRV failure is not recoverabIe.
Crew enters E-0. US directs RO to manually trip reactor and enters E-0.
RO verifies reactor trip:
Reactor trip and bypass breakers open. . Reactor trip and bypass breakers open.
Power range < 5%. Power range indication < 5%.
Neutron flux dropping. . Neutron flux dropping.
Throttle or governor valves closed. BOP verifies turbine trip.
BVPS 1- NRC Scenario 4 15of 1
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Main generator output breakers open. BOP verifies generator trip.
Exciter circuit breaker open.
1AE and 1DF busses energized by BOP verifies power to AC emergency offsite power. busses.
SI not actuated and not required. RO checks if SI is actuated.
Crew enters ES-0.1. US transitions to ES-0.1, and informs crews US directs STA to begin monitoring CSF status trees.
BVPS 1- NRC Scenario 4 160f 1
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTED STUDENT RESPONSE I EVENT #7 Main Steam Line Break With MSlV Steam break downstream of MSlV B.
Failure When directed, insert the following Crew sounds Standby alarm and command: announces Unit 1 reactor trip.
IMF MSS02B (0 0) 1E7 Preloaded command for MSlV RCS temperature dropping. RO checks RCS temperature stable at failure. or trending to 547F.
CRITICAL TASK #1: Steam dump valves closed. 9 Stop dumping steam Crew manually actuates main MOV-1MS-1OOA, B closed. V e r i i reheat steam isolation steam line isolation before a Sever (orange path) challenge develops to either the Subcriticality or Integrity CSF or before transition to ECA-2.1, whichever occurs first.
SG blowdown valves closed. Verify SG blowdown isolated.
AFW flow throttled to e 355 gpm. . Throttle total feed flow > 355 gpm.
SG 1B MSlV open. Close valves with YELLOW SLI marks SI actuated. US directs SI initiation or SI actuates.
Crew reenters E-0. US re-enters E-0, and informs crew.
BVPS 1- NRC Scenario 4 170f 1
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Reactor tripped. RO reverifies reactor trip.
Turbine tripped. BOP reverifies turbine trip.
Main generator tripped. BOP reverifies generator trip.
1AE and 1DF busses energized. BOP reverifies power to AC emergency busses.
SI actuated (both trains). BOP manually actuates both SI trains.
Crew sounds Standby alarm and announce Unit 1 reactor trip and SI.
1VS-F-4A running. BOP checks leak collection exhaust fan running.
US directs starting CNMT hydrogen analyzers.
BVPS 1- NRC Scenario 4 180f 1
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I RO verifies SI status.
CH-P-1A and CH-P-1B running. . Two charging pumps running BIT flow indicated. . BIT flow indicated SI-P-1A and 1B running. LHSl pumps both running BOP verifies AFW status.
FW-P-3A, 38 and FW-P-2 running. AFW pumps running All SG AFW throttle valves open. . AFW throttle valves full open.
Total AFW flow > 355 gpm. . Total AFW flow > 355 gpm BOP performs Attachment 1-K, Verification of Automatic Actions (Steps listed at end of scenario guideline.)
TAVG stabilizing after MSlV closure. BOP verifies RCS Tavg stable or trending to 547pF.
Recirc spray pumps not running. RO checks recirc spray pump status.
BVPS 1- NRC Scenario 4 19of 1
[ INSTRUCTIONAL GUIDELINES [ PLANT STATUS OR RESPONSE [ OBJECTIVE I EXPECTED STUDENT RESPONSE 1 RO checks PRZR isolated.
PCV-1RC-456 closed, but leaking. PORVs closed Spray valves closed. Spray valves closed Safety relief valves closed. Safety relief valves closed PRT conditions normal. PRT conditions at expected values All PORV MOVs open (except MOV- Power to at least one block valve 1RC-536 previously closed). and at least one open D/P between RCS pressure and highest RO checks if RCPs should be SG pressure > 200 psid. stopped.
No SG pressures dropping in an BOP checks if any SGs are faulted.
uncontrolled manner.
No SG levels rising in an uncontrolled BOP checks if SG tubes are intact.
manner.
CNMT radiation, pressure and sump RO checks if RCS is intact.
levels at pre-event values.
Crew checks if SI flow should be reduced.
BVPS 1- NRC Scenario 4 20 of 1
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
Crew enters ES-1.l,if SI US transitions to ES-1.1, and informs Termination criteria is satisfied. crew.
SI reset (both trains). RO resets SI.
CIA and CIB reset (both trains). RO resets CIA and CIB.
One HHSI pump running. RO stops one HHSl pump.
RCS pressure rising. RO check RCS pressure stable or rising.
CRITICAL TASK #2: RO isolates the BIT.
Crew stops HHSl injection prior to water relief through the MOV-SI-867A and 8678 shut. . Close MOV-1SI-867A, 6 I
Pressurizer PORVs.
MOV-SI-867D and 8670 shut. . Close MOV-1SI-867C, D RO establishes normal charging flow.
FCV-1CH-122 closed. Close FCV-1CH-122 MOV-1CH-310 open. . Open MOV-1CH-310 BVPS 1- NRC Scenario 4 21 of 1
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I MOV-1CH-289 open. Open MOV-1CH-289 FCV-1CH-122 output adjusted. Adjust FCV-1CH-122 to maintain PRZR level RO controls charging flow to maintain PRZR level.
Scenario may be terminated after BIT is isolated and normal charging flow is established.
BVPS 1- NRC Scenario 4 22 of 1
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Attachment l-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-1MS-1OOA, B]
CLOSED.
- b. Reset reheater controller.
Verify CCR Pumps - TWO RUNNING.
Align Neutron Flux Monitoring For Shutdown:
- a. Transfer NR-1NI-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 4 230f 1
I 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 m 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 4 24 of 1
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE ]
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 Fwl by checking all GREEN FWI marks - LIT.
Verify power to both AC emergency busses.
Upon completion, report any discrepanciesto SWUS.
BVPS 1- NRC Scenario 4 25 of 1