ML030230139
| ML030230139 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/16/2002 |
| From: | Hynes C FirstEnergy Nuclear Operating Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-412/03-302 50-412/03-302 | |
| Download: ML030230139 (62) | |
Text
RTL# A5.670.AA 1/2-ADM-1357.F11 Page 1 of I Revision 1 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
SUBDIVISION:
SCENARIO TITLE/NO.:
COMPUTER CODE FOR L.P.:
2LOT4 NRC Exam BVPS Unit 2 Simulator NRC Scenario #1 N/A INSTRUCTIONAL SETTING:
APPROXIMATE DURATION:
PREPARED BY:
REVIEWED BY:
General Physics Corp.
8/01/2002 Date 12-
-01.
Date (2
APPROVED FOR IMPLEMENTATION:
Date 1
10/25/02 2
12/4/02 Simulator 1.5 Hours i
Appendix D Scenario Outline Form ES-D-1 Facility:
FENOC BVPS Unit 2 Scenario No. I Op Test No.:
2002-02 Examiners:
Candidates:
Demonstrate the ability to safely operate the plant during normal and upset conditions in accordance with plant procedures.
Initial IC 128: 100% power, Equ. Conditions, BOL, CB "D" at 225 steps, RCS Conditions:
boron at 1576 ppm.
Turnover:
2FWE*P23A is OOS & will not be returned. Perform a normal power reduction to remove 2FWS-P21A, Main Feed Pump from service.
Critical Tasks:
FR-S.1.C, Insert RCCAs E-1.C, Stop RCPs Event Malf. No.
Event Event Description No.
Type*
I I
N (US)
Normal power reduction.
N (PO)
R (RO) 2 CNH CFW12 C (PO) 21B SG MFRV sticks in position during power reduction.
C (US)
(Manual operation available).
3 BKR HIVO1 C (PO)
Loss of 4160V bus 2AE.
C (US) 4 BKR HIVI I C (PO) 2-1 EDG output breaker fails to close; manual closure C (US) available.
Pressurizer Pressure Master Controller fails high.
I (US) 6 IOR XB 1I035C M (ALL)
PORV fails open; PORV block valve leaks after being RCS10A closed leading to reactor trip.
7 PPLO1A C (RO)
ATWS PPLO IB C (US) 8 BKRHIV13 C (PO)
EDG No. 2 output breaker fails to close automatically I
I C (US)
(manual closure successful).
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor BVPS-2 NRC Sim #1 Rev 2.doc 2 of 17
Appendix D Scenario Outline Form ES-D-1 After taking the shift, the crew will lower power in preparation for removing a main feed pump from service.
After lowering power, the 21B SG Main Feedwater Regulating Valve (MFRV) sticks in position as the power reduction continues, resulting in a slowly rising SG level, requiring manual control of the MFRV.
When SG level is stable with the MFRV in manual, a loss of 4160 Volt Emergency Bus 2AE results in loss of the running charging pump (2CHS*P21A). The 2-1 EDG will automatically start but its output breaker fails to automatically close and must be manually closed. Due to the loss of 2CHS*P21A, the crew may start 2CHS*P21B while evaluating the manual closure of 2-1 EDG output breaker 2E10. When the 2-1 EDG breaker is closed, crew will secure one charging pump.
After recovering, the Pressurizer Master Pressure Controller fails high, and a PORV opens.
Pressurizer heaters turnoff, spray valves open, and RCS pressure decreases. Manual control of Pressurizer heaters and spray valves is available; however, the PORV will remain stuck open and Pressurizer pressure will lower until the reactor automatically trips, or the Unit Supervisor directs a manual reactor trip. When the crew attempts to close the PORV block valve, the block valve will shut, but will leak. The PORV will remain open and the block valve will leak for the duration of the scenario.
After the reactor is tripped, an ATWS occurs. Also following the reactor trip, System Station Service Transformer 2B trips, and the 2-2 EDG output breaker 2F 10 fails to close automatically but can be closed manually, restoring power to 4KV Emergency Bus 2DF.
Expected procedure flow path is E FR-S. 1-E E-1.
BVPS-2 NRC Sim #1 Rev 2.doc 3 of 17
Program
Title:
2LOT4 NRC Examination (2002-02) 1/2-ADM-1357, Rev. 1 Attachment D Initial Conditions REV.
2 INITIAL CONDITIONS:
IC 12 8 PW = NRCI1 100%, BOL EQU XE, CBD = 225, RCS boron = 1576 ppm ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS 2FWE*P23A PTL 2FWE*P23A YCT N/A EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S) 2FWE*P23A 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago TS 3.7.1.2, Action b SHIFT TURNOVER INFORMATION
- 1.
100%, BOL, EQU XE, 1576 ppm, CB "D" at 225 steps.
- 2.
Reduce power to remove 2FWS-P21A from service due to bearing high vibration.
- 3.
Severe weather is expected.
- 4.
2FWE*P23A is OOS for motor replacement. Motor is removed and the pump will not be returned this shift.
SCENARIO SUPPORT MATERIAL REQUIRED
- 1.
Power reduction reactivity plan.
- 2.
20M-52.4.B, Load Following, Step IV.B. 1.
4 of 17 BVPS-2 NRC Scenario 1
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE EVENT #1 Following the Reactivity Plan, Crew lowers reactor power toward 60%.
Lower reactor power - 5%.
Turbine load and reactor power reduction at 12%/hr or less.
US directs load decrease. Crew initiates a turbine load decrease.
PO initiates turbine load decrease.
RO initiates RCS boration as necessary to maintain Tavg - Tref.
EVENT #2 Actuate when Crew reaches first hold in power reduction.
IMF CNH-CFW12 (0 0) 1 NOTE: Level deviation dependent on time of establishing normal MFRV control to restore 21B SG level.
21B SG FWRV sticks in position. SG feed flow and Nký level rises.
Alarm received:
[A6-ElO], SG 21B Level Deviation From Setpoint PO notes problem with 21B SG level control, valve and takes manual control of 2FWS*FCV488, inform US.
Crew refers to ARP's.
US directs PO to restore 21 B SG level to program value.
US notifies I&C of 2FWS*FCV488 problem.
BVPS-2 NRC Scenario 1 5 of 17
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE F EXPECTED STUDENT RESPONSE EVENT #3 2DF bus remains energized. 2AE bus is deenergized. 2-1 EDG output breaker fails to automatically shut.
Loss of 4KV Emergency Bus 2AE Alarms received:
[A8-C2], 4160V Emer Bus 2AE Undervoltage
[A8-A2], 4160V Emer Bus 2AE ACB 2A10/2E7 Auto Trip 2CHS*P21B running.
PO determines 2AE bus deenergized.
Crew responds per ARPs.
US/PO determine at least one AC emergency bus energized.
RO determines that no charging pumps are operating.
US directs RO to start 2CHS*P21B.
RO closes 2CHS-FCV122 & 2CHS HCV186 then starts 2CHS*P21B.
PO recognizes failure ofACB-2E10 to auto shut and informs US.
Crew responds per AOP-2.36.2.
BVPS-2 NRC Scenario 1 IMF BKR-HIVOI (0 0) 0 IMF BKR-HIV11 (0 0) 2 (preload) 6 of 17
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE
-OBJECTIVE I EXPECTED STUDENT RESPONSE NOTE: Crew should respond expeditiously to reenergize bus 2AE and verify service water supply to 2-1 EDG.
2CHS*P21A, Charging Pump, 2CCP*P21A, CCP Pump and 2SWE*P21A, Service Water Pump all deenergized.
EDG No. 1 output breaker shut. 4KV bus 2AE re-energized.
Loads sequence onto 2-1 EDG.
2 charging pumps operating.
Crew discretion as to which charging pump is secured.
2CHS*P21A or B secured.
US directs PO to shut ACB-2E 10, 2-1 EDG output breaker, and reenergize bus 2AE.
PO manually shuts ACB-2E 10, 2-1 EDG output breaker and re-energizes bus 2AE.
RO ensures CCP flow to all RCP thermal barriers.
RO reports charging pump status.
US directs RO to secure 1 charging pump.
RO secures 1 charging pump.
US refers to T.S. 3.0.5 and 3.8.1.1 IF requested insert:
IRF DSGO05 (0 0) 1 Reset of 2-1 EDG oil pump shunt trip.
Not procedurally required, but good operating practice.
BVPS-2 NRC Scenario 1 7 of 17
1/2-ADM-1357, Rev. 1 Attachment D I
INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE EVENT #4 IMF CNH-PCS1OA (0 0) 100
[2RCS*PK444A], Pressurizer Master Pressure Controller output fails high.
[2RCS*PCV455C], PORV open, PRZR control heaters turn off, spray valves open, RCS pressure decreases rapidly.
Alarms received:
[A4-A1], Pressurizer Power/Safety Relief Valve Trouble
[A4-D 1], Pressurizer Control Pressure High/Low
[A4-E1], Pressurizer Control Pressure Deviation High/Low
[A4-F1], Pressurizer PORV Open Permissive
[A4-H3], Pressurizer Relief Tank Trouble RO notes indications and alarms, informs US.
US refers to ARP's.
RO notes failure of Pressurizer Master Pressure Controller and informs US.
BVPS-2 NRC Scenario 1 8 of 17
1/2-ADM-1357, Rev. 1 Attachment D I
INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
Manual control of PRZR Master Pressure Controller fails to close PORV, fails to control heaters, and fails to control spray valves.
Spray valves close. PRZR heaters energized.
PORV remains open.
RCS pressure continues to decrease due to PORV failure. Charging flow increases.
PORV Block Valve closed.
RCS pressure continues to lower due to leaking PORV Block Valve.
US directs RO to place PRZR Master Pressure Controller in manual, close spray valves and PORV and take manual control of PRZR heaters.
Crew recognizes entry into T.S. 3.2.5 (DNB) for reduced RCS pressure.
RO uses individual component controls to shut spray valves and take manual control of PRZR heaters, and attempts to close PORV.
Crew identifies PORV remains open.
US directs closing of PORV block valve. RO closes valve.
US contacts I&C to investigate failure.
At Examiners discretion:
IMF RCS1OA (0 0) 0.5 PORV Block Valve Leakage BVPS-2 NRC Scenario 1 EVENT 5 (partial)
IOR XBlIO35C (0 0) 0 (preload)
PORV Block Valve leaks after closing.
EVENT 5 9 of 17
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE -FEXPECTED STUDENT RESPONSE RAMP SMLRCS10(1) 0.05 1.0 180 (block valve leakage increases)
IMF PPL01A (0 0) 1 (preload)
IMF PPLO1B (0 0) 1 (preload)
RCS pressure continue to decrease due to stuck open PORV and leaking block valve. Charging flow remains high.
RCS pressure dropping. Charging flow rising.
Manual reactor trip or automatic Pressurizer pressure low reactor trip.
RO monitors RCS, identifies that RCS pressure is continuing to decrease.
US directs RO to turn on all PRZR heaters (if not previously done).
US directs a manual reactor trip.
RO places reactor trip switch to trip.
Crew identifies that the reactor failed to trip.
ATWS - Reactor fails to trip automatically or when manual trip is attempted.
Steps 1 - 5 of FR-S.1 are Immediate Actions.
Operators commence Immediate Actions for E-0 and FR-S. 1.
US refers to E-0 and makes transition to FR-S.1.
SNA requested to monitor CSF status trees.
BVPS-2 NRC Scenario 1 10 of 17
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE CT#1 - FR-S.1.C:
Crew inserts negative reactivity into the core by inserting RCCA's before completing the immediate action steps of FR-S.1.
After directed to locally open RTB's, insert:
IMF PPL02A (10 120)
IMF PPL02B (10 130)
IRF LOA-CRFOO7 (10 150)
IRF LOA CRF008 (10 160)
TRG! 10 Report RTB's manually opened &
MG sets secured.
FR-S.1 Immediate Actions complete.
Rods inserting.
RO uses auto or manual rod control to insert rods.
CT#1 S/U Crew sounds standby alarm and announces Unit 2 reactor trip failure.
Crew dispatches an operator to locally open the RTB's.
Reactor tripped (time delay).
MG sets secured (time delay).
Turbine manually tripped.
Throttle, governor, reheat stop, and interceptor valves all closed.
Steam dump bypass interlock selector switches in OFF.
MSR steam supply block valves closed.
Reheat controller reset.
PO manually trips turbine.
PO verifies turbine trip.
PO places Condenser Steam Dump Selector Switches in "OFF".
PO ensures reheat steam isolation and depresses reheat controller RESET pushbutton.
BVPS-2 NRC Scenario 1 11 of 17
1/2-ADM-1357, Rev. 1 Attachment D I
INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE NOTE: The following actions will not occur until AFTER the reactor trip breakers are opened, therefore, may occur later in the scenario.
IMF SWD02C (2 45) (preload)
IMF BKR-HIV13 (0 0) 2 (preload) 2B SSST trips 45 seconds after reactor trip.
2-1 EDG output breaker fails to auto close.
2C, 2D & 2DF buses deenergized.
2F10 closed, 2DF energized, loads sequencing on EDG.
2FWE*P23A on clearance.
2FWE*P23B running.
TDAFW pump steam supply valves open.
AFW throttle valves full open.
PO reports loss of 2B SSST and 2-1 EDG output breaker auto closure failure.
US directs PO to close 2F10 breaker and verify loads sequence on EDG.
PO closes 2F10 and reports loads sequencing.
PO verifies AFW status.
BVPS-2 NRC Scenario 1 12 of 17
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE F EXPECTED STUDENT RESPONSE
]
HHSI/Charging pumps running.
2CHS*MOV350 open.
Boric acid transfer pump running.
Emergency boration flow > 30 gpm.
Charging flow path aligned through 2CHS*FCV122 with > 40 gpm flow.
PRZR pressure < 2335 psig.
[A5-4G], Pressurizer Low Pressure Reactor Trip Safety Injection lit.
SG levels < 12% NR.
2CHS*FCV1 13B closed.
2CHS*FCV1 14A closed.
2CHS*FCV1 14B closed.
Uncontrolled cooldown not in progress.
Core exit temperatures less than 1200'F.
RO initiates emergency boration of RCS.
RO checks PRZR pressure less than 2335 psig.
Crew checks SI signal status, performs first ten steps of E-0 when time permits.
PO checks SG levels, verifies AFW flow is greater than 700 gpm. PO controls feed flow to maintain 12 (31%
adverse) - 50% SG NR level.
RO verifies dilution paths isolated.
RO monitors RCS for uncontrolled cooldown.
US transitions to Step 16 of FR-S. 1.
Crew verifies core exit temperatures.
BVPS-2 NRC Scenario 1 13 of 17
1/2-ADM-1357, Rev. 1 Attachment D I
iiNS.) i I*'*A.J.
I I*.JlIl '..UILJr-LII"JIr-L S.
I
,,,,,.,/,",,*C M
'JD, JEL7IIVr EXPECTED STUDENT RESPONSE PR NI's less than 5%.
IR NI's negative SUR.
Crew enters E-0.
RO verifies reactor subcritical.
US makes transition from FR-S.1 back to E-O. Directs crew to perform E-O Immediate Actions.
Reactor locally tripped.
Rods bottom lights lit.
Flux decreasing.
Previously requested.
Throttle or governor valves closed, reheat stops or interceptor valves closed.
MSR steam supply block valves closed.
Reheat controller reset pushbutton depressed.
Main generator output breakers open.
Main generator volts ZERO.
Exciter circuit breaker open.
2AE and 2DF busses energized.
RO verifies reactor trip.
RO sounds standby alarm and announces Unit 2 safety injection.
PO verifies turbine trip.
PO ensures reheat steam isolation.
PO verifies generator trip.
PO verifies power to AC emergency busses.
BVPS-2 NRC Scenario 1 14 of 17 Steps 1 - 7 of E-0 are Immediate Actions.
Previously completed.
[
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1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
E-0 Immediate Actions complete.
[A5-4G], Pressurizer Low Pressure Reactor Trip Safety Injection lit.
SI actuation status light, A12-1D lit.
Both trains of SI manually initiated.
Automatic actions of A-0. 11 are SAT with the following exceptions:
2FWE*P23A OOS at turnover.
Leak collection filtered exhaust fan status SAT.
RCS temperature trending to 547°F.
Recirc spray pumps not running.
PRZR pressure < 2310 psig.
[2RCS*PCV455C], PORV failed open.
Crew checks if SI is actuated/ required.
US directs RO to manually initiate SI (both trains).
US direct operators to verify automatic actions by performing Attachment A-0. 11, when time permits.
Operator assigned to perform Attachment A-0. 11 reports status of Attachment to US and any actions taken when completed.
Crew verifies Leak collection filtered exhaust fan status.
RO reports Tavg status, US directs crew to control steam/feed flow as necessary to achieve desired status.
RO checks recirc spray pump status.
RO checks PRZR isolated. PRT conditions normal.
BVPS-2 NRC Scenario 1 15 of 17
1/2-ADM-1357, Rev. 1 Attachment D I
INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE PORV block valve shut but leaking.
Crew enters E-1.
Radiation not in alarm status and CIB has not occurred.
CT#2 - E-1.C:
Crew trips all RCP's when RCS to highest SG D/P criteria is exceeded and SI flow verified prior to exiting procedure E-1.
RCP's secured.
RO verifies PORV Block Valve shut for open PORV.
US enters E-1 and announces entry to Crew.
PO checks Control Room habitability.
RO checks if RCP's should be stopped.
CT#2 S/U Recirc spray pumps not operating.
Both CNMT hydrogen analyzers operating.
No SG's faulted.
AFW flow > 340 gpm.
Power available to block valves.
PORV open. [2RCS*MOV535], PORV Block Valve shut but leaking.
RO reports Recirc Spray pmp status.
RO reports H2 analyzer status.
PO checks if SG's are faulted.
PO checks intact SG levels and control levels.
RO checks PRZR PORV and block valves.
RO verifies PORV block valve shut.
BVPS-2 NRC Scenario 1 16 of 17
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1
No SG levels rising in an uncontrolled manner.
Subcooling < 43°F.
Adequate secondary heat sink.
RCS pressure NOT stable or rising.
PO checks is SG tubes are intact.
Crew checks if SI flow can be terminated.
Crew determines SI flow CANNOT be terminated.
Terminate the scenario when the crew determines that SI flow cannot be terminated.
EPP classification is a Site Area Emergency based EPP/I-lb, Tab 2.3, Failure of Rx Protection.
BVPS-2 NRC Scenario 1 17 of 17
RTL# A5.670.AA 1/2-ADM-1357.F1 I Page 1 of I Revision 1 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
SUBDIVISION:
SCENARIO TITLE/NO.:
COMPUTER CODE FOR L.P.:
INSTRUCTIONAL SETTING:
APPROXIMATE DURATION:
PREPARED BY:
REVIEWED BY:
2LOT4 NRC Exam BVPS Unit 2 Simulator NRC Scenario #2 N/A Simulator 1.5 Hours General Physics Corp.
A17 0
APPROVED FOR IMPLEMENTATION:
Date
-Revision No.'
D )ate 1
11/18/02 2
12/4/02
'-Revision No.
'.Date 8/01/2002 Date D2a-t- 0.
Date
Appendix D Scenario Outline Form ES-D-1 Facility:
Examiners:
Objectives:
Initial Conditions:
Turnover:
Critical Task FENOC BVPS Unit 2 Scenario No. 2 Op Test No.:
20U0-U0 Candidates:
CRS RO PO Demonstrate the ability to safely operate the plant during normal and upset conditions in accordance with plant procedures.
IC 127: 9% pwr, BOL, EQU XE, RCS boron = 2080 ppm, CB "D" = 116 steps.
Continue plant startup.
s:
E-0.I, Manually Start HHSI Pump E-3.A, Isolate Ruptured SG E-3.B, Cooldown RCS Event Malf. No.
Event Event Description No.
Type*
I 1
R (RO)
Continue plant startup.
N (PO)
N (US) 2 NIS07B C (US)
Intermediate Range instrument power fuse blows.
3 XMT I (PO) 2MSS*PT-464 fails low causing condenser steam dumps MSS044A I (US) to close.
4 CNI MSS03B C (PO)
SG 21B atmospheric dump valve fails open.
C (US) 5 RCP06B C (RO) 21B RCP high vibration with rising seal leakoff flow.
RCP01B C (US) 6 RCS04B M (ALL) 21 B SG Tube Rupture 7
Running HHSI pump trips.
PPL07A C (US)
Standby HHSI pump fails to auto start (manual start available).
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor BVPS-2 NRC Sim #2 Rev 2.doc 2 of 18 1
Appendix D Scenario Outline Form ES-D-1 After taking the shift, the crew will continue the startup. Intermediate Range Channel N-36 power fuse blows after reactor power is > 10%. The RO verifies which instrument channel has failed, and the Unit Supervisor directs actions per the AOP and refers to Technical Specifications.
2MSS*PT-464 then fails low causing the condenser steam dumps to close. Tavg rises causing automatic opening of the SG atmospheric steam dump valves. Operator action is required to place the condenser steam dump controller in manual and reopen the valves.
21B SG atmospheric steam dump valve then fails open requiring the crew to place the valve controller in manual and stabilize plant conditions.
After plant conditions have stabilized, 21B RCP high vibration condition develops and continues to worsen. The crew will eventually trip the reactor and take the pump out of service.
Following the reactor trip, a SGTR occurs on 21B SG. Additionally, the running HHSI/Charging pump trips and the standby HHSI/Charging pump fails to auto start, but can be manually started.
Expected procedure flow path is E0 -
E3.
BVPS-2 NRC Sim #2 Rev 2.doc 3 of 18
Program
Title:
2LOT4 NRC Examination (2002-02) 1/2-ADM-1357, Rev. 1 Attachment D Initial Conditions REV 2
INITIAL CONDITIONS:
IC 127 PW = NRC2 9%, BOL, EQU XE, CBD = 116, RCS boron = 2080 ppm.
ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATIONLS)
SHIFT TURNOVER INFORMATION
- 1.
Plant is at 9% power, BOL, EQU XE, CB "D" at 116 steps, RCS boron = 2080 ppm.
- 2.
Continue the plant startup to 100% JAW 20M-52.4.A, Step 3.
- 3.
Severe weather is expected.
SCENARIO SUPPORT MATERIAL REQUIRED
- 1.
2.
Plant startup reactivity plan.
20M-52.4.A, Increasing Power From 5% Reactor Power And Turbine On Turning Gear To Full Load Operation, Step.3.
BVPS-2 NRC Scenario 2 4 of 18
1/2-ADM-1357, Rev. 1 Attachment D I
I r,r-.r,.rIr.
rN-ri ir.rk Ir nI-C.nrsKIerr I
P1 ANT STATH(S OP RESUPNl1-EVENT #1 Reactor at 9% power.
Status lights on Panel 308 actuate at 10%.
[A12-2B], NIS IR Trip Blocked is ON.
[A12-2C], Power Range Low Setpoint Trip Blocked is ON.
[A12-1H], NOT P-7 is OFF.
Crew commences power increase in accordance with reactivity plan.
RO commences raising reactor power to between 10 and 20%.
RO verifies P-10 bistables actuate as required as power increases to > 10%.
RO blocks the IR Trip and Rod Stop and verifies annunciator ON.
RO blocks Power Range low overpower trip and verifies annunciator ON.
RO verifies that annunciator NOT P-7 is OFF.
RO selects highest power ranges on N-45.
BVPS-2 NRC Scenario 2 I IMTI ICTIflKI (I IIflII IN1I
Reactor Power Increase Continue reactor startup.
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1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE I
EVENT #2 After Crew has raised reactor power to greater than 10% and IR trips have been blocked:
IMF NIS07B (0 0) 0 NI-36 Instrument power fuse fails.
Meters for NI-36 indicate zero and blown fuse indication exists on drawer.
Alarms received:
[A4-4G], NIS Detector/Compensator Loss of Voltage RO acknowledges annunciators and identifies N-36 as the failed channel.
RO reports diagnosis to US.
US refers to AOP-2.2. 1B, Intermediate Range Channel Malfunction. Verifies Unit is in Mode 1 and goes to Step 4.
Crew verifies power still greater than 10% and intermediate range trip is still blocked.
Crew places level trip switch on failed channel to BYPASS.
Crew places a caution tag on source range indication.
BVPS-2 NRC Scenario 2 6 of 18
1/2-ADM-1357, Rev. 1 Attachment D I IMTPI ICTIflNI (I linPi INFS SPLANITATI U UP Kb-IUNZ-d I
jJA..IIVIZ I ELJ I LJLJLIN I
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I After the startup continues:
IMF XMT-MSS044A (0 0) 0 2MSS*PT464 fails low.
Condenser steam dump valves close.
Condenser steam dump demand indicates zero.
2MSS-PI464A indicates zero.
PO determines condenser steam dumps are closed and informs US/RO.
PO identifies failure of 2MSS*PT464 and informs US.
Tavg rising.
Atmospheric dump valves open automatically.
BVPS-2 NRC Scenario 2 I
r-Ar-LF__.g Ir' OIU F_.*I r0
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I jl~r'L, I IVI" Crew places a caution tag on level trip switch of failed channel.
US references Technical Specification 3.3.1.1.
US directs the Crew to continue with unit startup.
RO withdraws rods as directed.
RO/PO maintain reactor power, Tavg, and SG level in preparation for unit synchronization.
EVENT #3 7 of 18
1/2-ADM-1357, Rev. 1 Attachment D I INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE EXPECTED STUDENT RESPONSE Alarms received:
[A6-7A], Steamline Pressure High Condenser steam dumps reopened.
EVENT #4 IMF CNH-MSS03B (3 0) 100 (preload) 21B SG Atmospheric Dump Valve fails open.
SG level deviation alarms may actuate.
US directs RO to take manual control of steam dumps.
RO opens condenser steam dumps in manual.
US contacts I&C to investigate.
PO identifies failed open atmospheric dump valve and informs US.
US directs PO to take manual control of open ADV, and close it.
RO places controller for 21B SG ADV in manual and closes ADV.
US requests I&C assistance.
US may refer to LR 6.1 for inoperable atmospheric dump valve.
BVPS-2 NRC Scenario 2 8 of 18
1/2-ADM-1357, Rev. 1 Attachment D I INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
EVENT #5 21B RCP seal leakoff rising as indicated on 2CHS-FR154A.
[A2-5C], Reactor Coolant Pump Vibration Alert/Danger.
21B RCP vibration rises to >16 mils.
Shaft vibration > 15 mils and rising at >
1.0 mils/hr.
EVENT #6 IMF RCS04B (2 0) 500 (preload) 21B SGTR when the reactor is tripped.
Steps 1 - 7 of E-0 are Immediate Actions.
[A5-6D], Turbine Trip Due To Reactor Trip lit.
Rod bottom lights lit.
Neutron flux dropping.
RO acknowledges RCP vibration alarm, informs US, refers to [A2-5C]
ARP. Crew trends RCP vibration.
US enters AOP-2.6.8.
US continues in AOP 2.6.8 to address vibration problem.
When it is determined that RCP vibration is > 15 mils rising at >1 mil/hr., the US should direct a reactor trip and the stopping of21B RCP after E-0 Immediate Actions are completed.
RO manually trips reactor.
RO informs US of a reactor trip.
RO/PO commence IMA's of E-0, US references E-0 to verify IMA's.
RO verifies reactor trip.
BVPS-2 NRC Scenario 2 Insert the following:
IMF RCP01B (0 0) 1 300 IMF RCP06B (0 0) 15 IMF RCP06B (0 0) 21 1800 9 of 18
1/2-ADM-1357, Rev. 1 Attachment D I
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I V D E C 'Tr-I ' Q T I IIlZ N IT hDI:
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.i RO sounds standby alarm, announces Unit 2 reactor trip.
Throttle or governor valves closed.
Reheat stops or interceptors closed.
MSR steam supply block valves closed.
Reheat controller reset pushbutton depressed.
Output breakers open.
Main generator volts ZERO.
Exciter ACB open.
2AE and 2DF busses energized.
PO verifies turbine trip.
PO ensures reheat steam isolation.
PO verifies generator trip.
PO verifies power to AC emergency busses.
NOTE: SI may not have actuated at this time however, RCS conditions are degrading due to 21B SGTR. If crew transitions to ES 0.1 at this time, they will be required to manually actuate SI and return here. This drill assumes SI is actuated at this time and the crew continues with E-O.
BVPS-2 NRC Scenario 2 INSTRUCT 10 of 18 11 I T III.
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1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE SI actuated on low PZR pressure.
Immediate Actions of E-0 complete.
21 B RCP secured.
Automatic actions of A-0.11 are SAT with the following exceptions:
2CHS*P21A failed to auto start on SI, manual start is successful.
2CHS*P21B tripped on SI and cannot be manually restarted.
RO reports SI status, manually actuates SI.
US directs RO to secure 21B RCP due to high vibration/seal leakoff trouble.
US direct operators to verify automatic actions by performing Attachment A 0.11 when time permits.
Operator assigned to perform Attachment A-0. 11 reports status of attachment to US and any actions taken when completed.
CT#1 - E-0.I:
Crew establishes flow from at least one high head ECCS pump before transition out of E-0.
2CHS*P21A manually started.
Leak collection filtered exhaust fan status SAT.
PO manually starts 21A HHSI pump &
reports actions/status to US.
Crew verifies leak collection filtered exhaust fan status.
BVPS-2 NRC Scenario 2 CT#1 - S/U 11 of 18
1/2-ADM-1357, Rev. 1 Attachment D I INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE RCS temperature trending to 5477F.
Recirc spray pumps not running.
PORVs closed (not leaking).
Spray valves closed.
Safeties closed (PSMS data).
PRT conditions normal.
PORV/block valve alignment SAT.
21B RCP previously secured.
21A & 21C RCPs running.
CCP flow normal.
No SG pressure dropping in an uncontrolled manner.
21B SG level rising in an uncontrolled manner. Secondary rad monitors not consistent with pre-event levels.
Crew transitions to E-3.
RO reports Tavg status, US directs crew to control steam/feed flow as necessary to achieve desired status.
RO checks recirc spray pump status.
RO checks PRZR isolated.
RO checks if RCPs should be stopped.
PO checks if any SGs are faulted.
US directs operator to check if SG tubes are intact.
US makes transition to E-3 and informs crew.
US directs SNA to monitor status trees.
BVPS-2 NRC Scenario 2 12 of 18
1/2-ADM-1357, Rev. 1 Attachment D I INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE CT#2 - E-3.A:
Crew isolates feed flow into and steam flow from the ruptured SG and directs operator to close isolations valve(s) operated from outside of the control room before a transition to ECA-3.1 occurs.
IRF LOA-MSSO1O (0 0) 0 IRF LOA-AFW026 (0 0) 0 Control room habitability system not required.
21B RCP previously secured.
21A & 21C RCPs running.
CCP flow normal.
21B SG level rising in an uncontrolled manner. Secondary rad levels higher than normal.
Adjust ruptured SG atmospheric steam dump controller setpoint to 100% and verify 2SVS*PCV1O1B closed.
2SVS*HCV104 - closed.
2SVS*28 - closed.
2MSS*16 - closed.
2BDG*AOV100B1 - closed.
2SDS*AOV111B1 - closed.
2SDS*AOV129A - closed.
2MSS*AOV101B, 102B - closed.
PO verifies control room habitability.
RO/PO check if RCPs should be stopped.
Crew identifies ruptured SG.
Crew isolates flow from ruptured SG.
CT#2 S/U BVPS-2 NRC Scenario 2 13 of 18
1/2-ADM-1357, Rev. 1 Attachment D SINSTRIUCTION GUIDELINES Notify crew that 2MSS* 16 is closed. Also report 2SVS*28 closed when requested.
I PLANT STATUS OR RESPONSE Verify closed 21B SG steam supply to TDAFW pump, 2MSS* 16 and 2SVS*28.
21B SG narrow range level greater than 12% (31% adverse).
2FWE*HCV100C & D closed.
Main feedwater isolation valve 2FWS*HYV157B closed.
Main feed reg valve 2FWS*FCV488 closed.
Main feed bypass valve 2FWS*FCV489 closed.
Ruptured SG pressure > 240 psig.
I
....
I
,..--------------I I OBJECTIVE I EXPI-T;I.D I UUlN I tIt.'UNlr_
I PO checks ruptured SG level.
PO isolates feed flow to 21B SG.
PO verifies ruptured SG pressure > 240 psig.
BVPS-2 NRC Scenario 2 14 of 18 INSTRUCTI N GUIDELINES I
PLANT STATUS OR RESPONSE
1/2-ADM-1357, Rev. 1 Attachment D I INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE EXPECTED STUDENT RESPONSE CT#3 - E-3.B:
Crew establishes/maintains an RCS temperature so that transition from E-3 does not occur because the RCS temperature is in either of the following conditions: Too high to maintain minimum required subcooling for subsequent RCS depressurization, OR below the RCS temperature that causes a red or orange path challenge to Subcriticality or Integrity CSF.
Based on ruptured SG pressure.
1000 - 1084 = 505°F (480°F).
900 - 999 = 492-F (467-F).
US determines target temperature for cooldown.
Steam dump is available, greater than 1 00°F per hour cooldown.
Condenser steam dumps closed in manual due to previous failure, 21A &
21C atmospheric dump valve controllers in auto with pot setting corresponding to current intact SG pressure.
RO blocks low steamline pressure SI when PRZR pressure is less than 1950 psig.
PO dumps steam at maximum rate.
SNA monitors thermocouples.
PO stops cooldown when core exit TCs < target temperature.
CT#3 S/U BVPS-2 NRC Scenario 2 15 of 18
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE
-OBJECTIVE I EXPECTED STUDENT RESPONSE Intact SG levels > 12% (31% adverse).
Power to PORVs & block valves SAT.
PORVs closed, not leaking.
PORV/block alignment SAT.
Auto SI blocked [A12-1C] lit.
SI signal [A12-1D] NOT lit.
Both trains of CIA reset.
CIB not actuated.
Station air available.
Instrument air established to CNMT.
2IAC-MOV131 - open.
2IAC-MOV130 - open.
Instrument air header pressure > 85 psig.
RCS pressure > 225 psig (250 psig adverse).
LHSI pumps stopped, in auto.
Ruptured SG pressure stable.
PO controls intact SG feed flow as required (340 gpm min) to achieve/maintain levels between 12%
(3 1%) and 50%.
RO verifies PORV/block valve conditions as expected.
RO resets CIA and CIB (both trains).
PO verifies/reports status of station air system.
Crew establishes instrument air to CNMT.
RO stops LHSI pumps and places them in auto.
PO verifies ruptured SG pressure stable.
BVPS-2 NRC Scenario 2 16 of 18
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE T EXPECTED STUDENT RESPONSE CT#4 - E-3.C:
Crew depressurizes RCS to meet SI termination criteria before water release from the ruptured SG safety or atmospheric relief valve.
Subcooling > 61'F (79°F adverse).
PRZR level < 75% (6 1%).
RCS subcooling > 41'F (59°F).
21A & 21C RCPs running.
Spray valves available. Both spray valves open.
IF AVAILABLE, 1 PORV will be used to assist depressurization.
Depressurization Termination:
PRZR level >75% (6 1%)
OR RCS subcooling < value listed on Attachment A-5.1 OR RCS pressure < ruptured SG pressure AND PRZR level > 17% (38%).
Crew verifies subcooling SAT.
RO depressurizes RCS to minimize break flow and refill PRZR.
RO closes spray valves and PORV, if used.
CT#4 S/U BVPS-2 NRC Scenario 2 17 of 18
1/2-ADM-1357, Rev. 1 Attachment D I INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Terminate scenario upon completion of RCS depressurization.
EPP classification is an ALERT based on EPP/I-lb, Tab 1.2, RCS Barrier.
BVPS-2 NRC Scenario 2 18 of 18
RTL# A5.670.AA 1/2-ADM-1357.F11 Page 1 of 1 Revision 1 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
SUBDIVISION:
SCENARIO TITLE/NO.:
COMPUTER CODE FOR L.P.:
2LOT4 NRC Exam BVPS Unit 2 Simulator NRC Scenario #3 N/A INSTRUCTIONAL SETTING:
APPROXIMATE DURATION:
PREPARED BY:
REVIEWED BY:
General Phvsics Corn.
APPROVED FOR IMPLEMENTATION:
Rkevision No.
-Date 1
11/18/02 2
12/4/02 Revision No-.
Date Simulator 1.5 Hours 8/01/2002 Date Date Date
Appendix D Scenario Outline Form ES-D-1 Facility:
FENOC BVPS Unit 2 Scenario No.: 3 Op Test No.:
2002-02 Examiners:
Candidates:
Demonstrate the ability to safely operate the plant during normal and upset conditions in accordance with plant procedures.
Initial IC 126: 100% power, BOL, EQU XE, CB "D" = 225 steps, RCS boron Conditions:
1576 ppm.
Turnover:
2FWE*P23B OOS, 2FWE*P22 is aligned to the "B" header.
Critical Tasks:
E-O.A, Manually Trip Reactor ECA-O.O.B, Establish Feedwater Flow To At Least 1 SG Event Malf. No.
Event Event Description No.
Type*I I
R (RO)
Normal power reduction N (PO)
N (US) 2 CNI-PCS09B I (RO)
Pressurizer master level controller fails high.
I (US) 3 XMT-I (PO)
Selected feedwater flow transmitter fails high.
CFW055A I (US) 4 EHC06 C (All)
Main turbine valve position limiter failure causes load rejection.
5 HIVOID M (All)
Loss of 4KV bus 2D (condensate pump and feed pump trip).
6 FLX CFW07 Pipe rupture in condensate header 7
PPLOIA C (RO)
Automatic reactor trip fails (manual trip available).
PPLO1B C (US) 8 LOA AFWOO I C (PO)
Turbine driven AFW pump (2FWE*P22) fails to start.
LOA AFWO13 C (US)
DSGOIB C (PO)
EDG 2-2 trips during loading after powering 4KV bus C (US) 2DF.
9 BKR HIVOI C (US)
Loss of 4160V bus 2AE after entering ES-0.1.
LOA DSGOI C (PO)
EDG 2-1 fails to auto start (manual start available in ECA-0.0).
10 PPL07A C (US) 2FWE*P23A fails to auto start on EDG sequencer, C (PO)
(manual start available).
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor BVPS-2 NRC Sim #3 Rev. 2.doc 2 of 15
Appendix D Scenario Outline Form ES-D-1 After the crew has lowered reactor power, the Pressurizer Master Level Controller fails high.
Charging flow will increase causing actual Pressurizer level to rise. The crew must take manual control of Pressurizer level, halt the transient and restore level to program.
As Pressurizer level is being returned to normal, the 21C SG feedwater flow transmitter fails high requiring manual control of the SG main feedwater regulating valve to stabilize SG level.
The US refers to Technical Specifications and directs actions for the failed channel.
Once conditions stabilize, a main turbine valve position limiter failure causes a load rejection and the crew must stabilize the plant in accordance with the load rejection abnormal operating procedure.
When plant conditions have stabilized, a loss of 4KV Bus 2D results in a condensate pump and a main feed pump trip resulting in a reactor trip condition; however, automatic reactor trip will fail requiring the crew to manually trip the reactor.
Concurrently, a pipe rupture in the condensate header causes a loss of suction to the remaining main feed pump. Additionally, the turbine driven AFW pump fails to start and will remain unavailable.
The loss of 4KV Bus 2D also de-energizes 4KV bus 2DF. The 2-2 EDG will start, but trips after briefly powering the 2DF bus. After the crew enters ES-0.1, a loss of 4KV bus 2AE occurs and the 2-1 EDG fails to automatically start when the 2AE bus is de-energized. The 2-1 EDG; however, can be manually started in ECA-0.0 allowing the 2AE bus to be reenergized and the recovery of the only available motor driven AFW pump (2FWE*P23A).
Expected procedure flow path is EO -- ES-0.1 -- ECA-0.0 -- ES-0.1 BVPS-2 NRC Sim #3 Rev. 2.doc 3 of 15
Program
Title:
2LOT4 NRC Examination (2002-02) 1/2-ADM-1357, Rev. 1 Attachment D Initial Conditions REV 2
INITIAL CONDITIONS:
IC 126 PW = NRC3 100%, EQU XE, BOL, CB "D" 225 steps, RCS boron = 1576 ppm.
ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS 2FWE*P23B PTL 2FWE*P23B YCT Fig 20M 24-3: 2FWE*36 closed 2FWE* 102 open EOUIPMENT STATUS ATE/TIME 0 TECHNICAL SPECIFICATION(S) 2FWE*P23B OOS 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago TS 3.7.1.2, Action b SHIFT TURNOVER INFORMATION
- 1.
100% power, EQU XE, BOL, CB "D" 225 steps, RCS boron = 1576 ppm.
- 2.
Reduce power to remove 2FWS*P21B from service due to bearing high vibration.
- 3.
Severe weather is expected.
- 4.
2FWE*P23B is OOS for motor replacement and will not be returned this shift. 2FWE*P22 is aligned to the "B" header.
SCENARIO SUPPORT MATERIAL REQUIRED
- 1.
2.
Power reduction reactivity plan.
20M-52.4.B, Load Following BVPS-2 NRC Scenario 3 4 of 15
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE EVENT 1 Lower power - 5%.
EVENT 2 At Examiner's direction insert:
IMF CNH-PCS09B (0 0) 100 Turbine load and reactor power lowering at 12%/hr or less.
Pressurizer Master Level Controller fails high.
Charging pump flow increases.
Alarms expected:
[A2-E3], Charging Flowpath Trouble
[A2-D4], Reactor Coolant Pump Seal Trouble US assumes control and directs Operators to lower reactor power to 60%.
Crew reviews/agrees with reactivity plan. US approves for use. Crew begins power reduction in accordance with the reactivity plan.
PO initiates turbine load reduction.
RO initiates RCS boration as necessary to maintain Tavg-Tref.
RO notes indications and alarms, informs US.
BVPS-2 NRC Scenario 3 5 of 15
1/2-ADM-1357, Rev. 1 Attachment D
_________________________________________I I ORIF(TIVL I
EXPtUILUIUUtiNI Or'JINQL INSTRUCTION GUIDELINES I
PLANT STATUS OR F
L..%.JI Sn'Jb-I PRZR level controller 2CHS*FCV122 in manual.
Alarms clear.
US directs RO to place PRZR level controller or charging pump discharge control valve in manual.
RO takes manual control of PRZR level.
US requests I&C to investigate Pressurizer level controller failure.
EVENT 3 21 C SG Feed Flow Transmitter fails high.
IMF XMT-CFW055A (0 0) 5 Level deviation annunciator is dependent on operator action to manually control the 21C MFRV.
[2FWS*FT496], 21C SG Feed Flow Transmitter fails high.
[2FWS*FCV498], 21C SG MFRV modulates shut lowering SG level.
Alarms expected:
[A6-F11 ], Loop C Feedwater Flow >
Steam Flow
[A6-D 11], SG 21C Level Deviation From Setpoint PO acknowledges alarms, diagnoses problem, informs US.
2FWS*FCV498 in manual.
US directs PO to take manual control of 2FWS*FCV498 and restore SG level to normal.
BVPS-2 NRC Scenario 3 EXPEUAtU,'.)1UUr-1-41 mr-or Not-I I )Q.
C.IE 6 of 15
1/2-ADM-1357, Rev. I Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE Crew refers to applicable ARPs, and 20M-24.4.IF, Attachment 2.
US directs PO to transfer 2FWS*FR498 to alternate channel.
US refers to T.S. 3.3.1 for actions for inoperable SG level channel.
US contacts I&C to take actions per 20M-24.4.IF and to investigate failed feed flow transmitter.
EVENT #4 Load rejection to 50% limiter position (approx. 600 MW). RCS temperature rises. SG level deviation alarms.
Condenser steam dumps open. Load rejection 15% - 50% status light A12-4A (C-7A actuated).
Crew recognizes load rejection.
US directs operators to stabilize the plant and refers to AOP-2.35.2.
RO checks auto rod insertion, or drives rods and/or borates to match Tavg vs.
Tref.
Crew sounds standby alarm and announces Unit 2 load rejection.
Crew checks operation of EHC System.
BVPS-2 NRC Scenario 3 IMF EHC06 (0 0) 50 7 of 15
1/2-ADM-1357, Rev. 1 Attachment D
.-
I
IT-I r'-rir' cri Ir%NI DI AMT QTATI I- (M.' I--4-'(
)NSd-I IJM.II,I IVt
I IArEA
I ELJ Q I '..JLJLIN T RESPONSE VPL failed low, vibration and load satisfactory for condition. EHC control transfers from partial to full arc mode.
Generator load > 270 MW Vacuum > 24.5 inches Hg.
Generator output breakers closed.
Generator volts, amps, and power factor satisfactory.
Crew may perform actions to recover GV control from the valve position limiter per 20M-26.4.X.
Load rejection bistables reset.
Crew checks if governor valves have closed in sequence, checks turbine vibration recorders, and EHC control is transferring to full arc mode.
Crew monitors for subsequent load reductions > 90 MWE.
Crew checks if turbine should be tripped, verifies load is greater than 270 MW.
PO verifies if the main generator is on line.
RO checks Tavg - Tref within 5'F.
PO resets steam dump controller, if necessary.
Crew notifies System Operator of load loss and reason (if determined).
US directs I&C to investigate problem with valve position limiter.
8 of 15 BVPS-2 NRC Scenario 3 I Ivr-r-ru I
INS I RUC I I N OUIUMLINE0 I
r-L-/-%l 14 EAF ~l M 0-IU-ACI*
1
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1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE
-FOBJECTIVE EXPECTED STUDENT RESPONSE Load rejection > 15%.
2CNM-AOV100 closed.
Supervisory limits normal.
US directs chemistry to sample as required for load rejection > 15%.
Crew checks 2CNM-AOV 100 closed.
PO monitors all turbine supervisory limits.
Crew recognizes entry into T.S. 3.2.5 for DNB parameters.
Continue with scenario when Tavg Tref mismatch is within 3°F OR when directed by Examiner.
EVENT 5 IMF HIV1D (0 0)
Loss of 4KV Bus D.
Crew identifies loss of 4KV Bus D, 2FWS-P21B, 2CNM-P21C and 2CNM-P21A.
IMF FLX-CFW07 (1 0) 20000 IMF PPLO1A (0 0) 0 (preload)
IMF PPL01B (0 0) 0 (preload)
TDAFW pump trips during startup IMF AFW03A (0 0) 5440 (preload)
Pipe rupture in condensate header.
Reactor fails to auto trip.
RO notes that a reactor trip has not occurred.
BVPS-2 NRC Scenario 3 9 of 15
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE US refers to E-0 to verify immediate actions while RO and PO commence immediate actions.
US directs RO to manually trip reactor.
CT#1 - E-O.A:
Crew manually trips reactor from the Control Room before performing the mitigation strategy of FR-S.1.
Steps 1 - 7 of E-0 are Immediate Actions.
RO manually trips reactor.
CT#1 S/U RO/PO commence IMAs of E-0, US references E-0 to verify IMAs.
[A5-6D], Turbine Trip Due To Reactor Trip lit.
Rod bottom lights lit.
Neutron flux dropping.
RO verifies reactor trip.
RO sounds standby alarm, announces Unit 2 reactor trip.
Throttle or governor valves closed.
Reheat stops or interceptors closed.
PO verifies turbine trip.
BVPS-2 NRC Scenario 3 10 of 15
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE IMF DSG01B (1 40) (preload)
MSR steam supply block valves closed.
Reheat controller reset pushbutton depressed.
Output breakers open.
Main generator volts ZERO.
Exciter ACB open.
2AE energized.
2DF de-energized, 2-2 EDG tripped during loading and will not be recovered.
No SI annunciator.
PO ensures reheat steam isolation.
PO verifies generator trip.
PO verifies power to AC emergency busses, reports loss of 2DF bus and 2-2 EDG.
Crew checks if SI is actuated/required.
SI actuation status light not lit.
E-0 Immediate Actions complete.
Transition to ES-O. 1.
SI is not required.
Crew dispatch operators to investigate loss of 2-2 EDG and 2FWE*P22.
US makes transition to ES-0.1 and informs the Control Room.
SNA directed to monitor CSF status trees.
No SI annunciator.
Crew checks SI not actuated.
BVPS-2 NRC Scenario 3 11 of 15
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE EXPECTED STUDENT RESPONSE WHEN APPROPRIATE, report as Turbine Building Operator that there is a large condensate header rupture just down stream of pump's discharge.
NOTE: After report from field, crew may opt to secure remaining condensate pumps.
Maintain RCS temperature.
Steam dumps in steam pressure mode, RCS Tavg > 547°F and rising. Monitor RCS temperature.
Crew checks/monitors T-avg.
PO places steam dumps in steam pressure mode.
RO reports that Tavg is stable.
EVENT6 When steam dump control mode selector switch is placed in Steam Pressure position:
IMF BKR-HIV01 (2 0) 0 (preload)
IRF LOA-DSGO01 (5 0) 0 (preload)
IMF PPL07A (2 1) 5 (preload)
Crew enters ECA-0.0.
Loss of 4KV Bus 2AE bus. 2-1 EDG fails to auto start.
PO identifies loss of 4KV Bus 2AE and reports loss to US.
US determines no ESF busses are energized.
2FWE*P23A fails to auto start on EDG sequencer, manual start successful.
US makes transition to ECA-0.0 and informs the Control Room.
BVPS-2 NRC Scenario 3 12 of 15
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE When requested to check why 2-2 EDG tripped, report that the Local Alarm No. 5 (overspeed trip) is actuated and there is physical damage to the EDG.
[A8-5E], 2-2 EDG Local Panel Trouble alarm.
SNA monitors CSF status trees for information only.
Annunciator A5-6D lit.
Neutron flux dropping.
SLI manually actuated.
MSIVs and bypass valves closed.
Exciter and output breakers open.
PORVs closed.
Letdown isolated.
RCPs stopped.
RO reverifies reactor trip.
RO sounds standby alarm and announces Unit 2 loss of power.
SM requested to reevaluate EPP.
PO ensures steamlines isolated.
PO verifies generator trip.
RO verifies RCS isolated, stops running RCPs.
13 of 15 BVPS-2 NRC Scenario 3
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE "WHEN APPROPRIATE report that 2FWE*P22 has physical damage to the trip and throttle valve, and will not be returned.
Transition to ES-0.1 NOTE: Crew may start 2FWE*P23A when 2AE bus is re energized before transition to ES 0.1.
AFW flow not indicated due to loss of all AFW pumps.
SR & IR channels aligned to 2NME NR45.
2-1 EDG starts manually and sequences loads WITH EXCEPTION OF 2FWE*P23A.
2AE emergency bus energized.
2FWE*P23A failed to auto start on 2-1 EDG sequencer.
PO reports AFW system status, operators previously dispatched to investigate loss of 2FWE*P22.
US dispatches operator to perform Attachments A-1.12 and A-1.11 to restore AFW flow.
RO verifies source range &
intermediate NIs displayed on 2NME NR45.
PO tries to start 2-1 EDG and reports it started and is sequencing loads.
US directs return to ES-0.1, Step 5, (step in effect), based on reports of power restored to one 4KV emergency bus.
PO reports no AFW pumps operating.
US directs PO to manually start 2FWE*P23A and commence feeding SGs.
14 of 15 BVPS-2 NRC Scenario 3
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR I OBJECTIVE EXPECTED STUDENT RESPONSE I CT#2 - ECA-O.O.B:
Crew establishes the minimum required AFW flow rate to the SGs before SG dryout occurs.
Terminate scenario when AFW flow is verified following transition to ES-0.1.
EPP classification is an ALERT based on EPP/I-lb, Tab 3.1, Loss of AC Power.
AFW flow restored to > 340 gpm.
PO starts 2FWE*P23A and restores feed flow to all SGs.
CT#2 S/U AFW flow > 340 gpm.
15 of 15 BVPS-2 NRC Scenario 3 N-S..........
I i
RTL# A5.670.AA 1/2-ADM-1357.F 11 Page 1 of 1 Revision I SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
SUBDIVISION:
SCENARIO TITLE/NO.:
COMPUTER CODE FOR L.P.:
~Ressiow'N6O7.
-,-ate 1
10/25/02 2
12/4/02 INSTRUCTIONAL SETTING:
APPROXIMATE DURATION:
PREPARED BY:
REVIEWED BY:
2LOT4 NRC Exam BVPS Unit 2 Simulator NRC Scenario #4 N/A Simulator 1.5 Hours General Physics Corp.
8/01/2002 Date 12-5-01 Date APPROVED FOR IMPLEMENTATION:
Date
Appendix D Scenario Outline Form ES-D-1 Facility:
FENOC BVPS Unit 2 Scenario No. 4 Op Test No.:
2002-02 Examiners:
Candidates:
Demonstrate the ability to safely operate the plant during normal and upset conditions in accordance with plant procedures.
Initial Conditions:
IC 125: 80% power, BOL, Equ. Conditions, CB "D" = 172 steps, RCS boron at 1615 ppm.
Turnover:
2FWE*P23B OOS. Perform a normal power reduction to remove 21A Main Feed Pump from service.
Critical Tasks:
E-O.H, Start LHSI Pump E-0.O, Manually Initiate CIB Event Malf. No.
Event Event Description No.
Type*
I 1
N (US)
Normal power reduction N (PO)
R (RO) 2 PMP FW4 C (All) 2FWS*P21A trips at approximately 77% power.
PMP CFW008 2FWS*P24 trips 3 minutes after being started.
Running CCP pump trips.
PPL07B C (US)
Manually start standby CCP pump.
4 FLX CCP34 C (RO)
CCP supply leak to 2RCS*P21B (10 minute ramp to 450 C (US) gpm leads to reactor trip).
5 RCS03B M (All)
Large break LOCA 6
PPL07A C (PO)
Both low head SI pumps fail to auto start (manual start PPL07B C (US) available).
7 BST-PCS048 C (RO)
Auto CIB failure (manual available)
BST-PCS049 C (US)
BST-PCS052 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor BVPS-2 NRC Sim #4 Rev. 2.doc 2 of 12
Appendix D Scenario Outline Form ES-D-1 The crew will lower power in preparation for removing a main feed pump from service. When power has been lowered to approximately 77%, the pump will trip and the startup feed pump will also subsequently trip requiring the crew to rapidly reduce power to less than 60% to avoid a reactor trip.
When plant conditions have begun to stabilize, the running component cooling pump trips requiring operator action to manually start the standby component cooling pump.
After starting the standby pump, a leak develops on the supply line to 21B RCP. The leak will ramp to 450 gpm over ten minutes requiring operator action to locate and isolate the leak. The Unit Supervisor should eventually direct a manual reactor trip.
Inmmediately following the reactor trip, a large break LOCA occurs. After completing E-0 immediate actions, all RCPs should be manually tripped due to the loss of component cooling.
Following the LOCA, Containment Isolation Phase "B" (CIB) will fail to actuate automatically requiring operator action to manually initiate CIB. Also both low head SI pumps fail to start automatically, but can be manually started by the crew.
Expected procedure flow path is EO -- El.
BVPS-2 NRC Sim #4 Rev. 2.doc 3 of 12
Program
Title:
2LOT4 NRC Examination (2002-02) 1/2-ADM-1357, Rev. 1 Attachment D Initial Conditions REV 2
INITIAL CONDITIONS:
IC 125 PW = NRC4 80%, BOL, EQU XE, CBD = 172, RCS boron = 1615 ppm ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS 2FWE*P23B PTL 2FWE*P23B YCT Fig 20M 24-3: 2FWE*36 closed 2FWE* 102 open "EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S) 2FWE*P23B OOS 24 Hours ago TS 3.7.1.2, Action b SHIFT TURNOVER INFORMATION
- 1.
- 2.
- 3.
4.
80%, BOL, EQU XE, 1615 ppm, CB "D" at 172 steps.
Reduce power to remove 2FWS*P21A from service due to high bearing high vibration.
Severe weather is expected.
2FWE*P23B is OOS for motor replacement and will not be returned this shift. 2FWE*P22 is aligned to the "B" header.
SCENARIO SUPPORT MATERIAL REQUIRED
- 1.
2.
Power reduction reactivity plan.
20M-52.4.B, Load Following, Step IV.B. 1.
BVPS-2 NRC Sim #4 Rev. 2.doc 4 of 12
1/2-ADM-1357, Rev. 1 Attachment D PLANT STATUS OR RESPONSE I OBJECTIVE EXPECTED STUDENT RESPONSE EVENT #1 Lower reactor power to 75%.
EVENT #2 After power is lowered to 77%:
IMF PMP-CFW004 (1 0) 1 (preload)
IMF PMP-CFW008 (2 180) 1 (preload)
Turbine load and reactor power reduction at 12%/Hr or less.
2FWS-P21A trips.
Following the Reactivity Plan, Crew lowers reactor power.
US directs load decrease. Initiates Turbine load reduction.
PO initiates turbine load decrease.
RO initiates RCS boration as necessary to maintain Tavg-Tref.
PO recognizes feed pump trip and informs US.
2FWS-P24 trips 3 minutes after startup.
Alarms received:
[A6-A1O0], SG Feed Pump 21 A/B Auto Stop US refers to AOP-2.24.1, Loss of Main Feedwater.
US verifies reactor power < 90%.
Refers to ARPs as time permits.
5 of 12 BVPS-2 NRC Sim #4 Rev. 2.doc
1/2-ADM-1357, Rev. 1 Attachment D PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE 2FWS-P24 started.
2FWS-P24 trips 3 minutes after starting.
Turbine load reduction at 5%/minute.
At Examiner's discretion, proceed with next event.
US directs starting 2FWS-P24.
PO starts 2FWS-P24 and dispatches operator to locally check pump.
PO reports trip of 2FWS-P24 after starting.
US refers to AOP-2.5 1.1 and directs load decrease to < 60% at 5% per minute.
PO decreases turbine load at 5% per minute.
RO performs RCS boration to maintain Tavg-Tref.
EVENT #3 (following are preloaded)
IMF PMP-CCPOO1 (0 0) 1 IMF PMP-CCP002 (0 0) 1 TRGSET 3 'XB4IO09T =--1' TRG 3 'DMF PMP-CCP002' Running CCP Pump trips. Standby CCP Pump manually started.
Alarms Received:
[A6-G1], Pri Comp Cooling Pump Auto Start/Auto Stop
[A6-H 1], Pri Comp Cooling Water System Trouble PO manually starts standby CCP Pump.
BVPS-2 NRC Sim #4 Rev. 2.doc 6 of 12
1/2-ADM-1357, Rev. 1 Attachment D I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
EVENT #4 IMF FLX-CCP34 (3 0) 450 600 (preload)
CCP leak when standby pump started.
Decreasing CCP Surge Tank level on 2CCP*LI1 0OB.
Increasing containment sump levels.
Increasing 21 RCP motor and bearing temperatures.
1 CCP pump operating.
Level control in manual with maximum makeup.
Determine CCP header leak inside containment.
US refers to AOP-2.15.1, Loss of Primary Component Cooling Water.
RO/PO Check CCP system status.
RO/PO place surge tank level control valve in manual and adjust control signal to maximize makeup to surge tank.
NOTE: Due to the rapidly degrading CCP system, it is expected that the crew will conservatively trip the reactor (based on surge tank level) and secure RCPs.
Non-essential loads isolated.
Crew monitors RCP motor bearing upper and lower temperatures for RCPs.
Crew attempts to locate the leak.
BVPS-2 NRC Sim #4 Rev. 2.doc 7 of 12
1/2-ADM-1357, Rev. 1 Attachment D PLANT STATUS OR RESPONSE I OBJECTIVE F EXPECTED STUDENT RESPONSE Surge tank continues to decrease.
Cavitation of CCP pumps possible.
Leakage excessive.
Crew - If any RCP temperatures are approaching limits OR operating CCP pumps discharge pressure and current indicates cavitation, or if leakage is determined to be excessive:
Manually trip the reactor, perform IMAs and trip all RCPs.
EVENT #5 (preloaded)
IMF PPL07A (0 0) 4 IMF PPL07B (0 0) 4 IMF RCS03B (4 0)
IMF BST-PCS048 (0 0) 2 IMF BST-PCS049 (0 0) 2 IMF BST-PCS052 (0 0) 2 Steps 1 - 7 of E-0 are Immediate Actions.
2SIS*P21A auto start failure 2SIS*P21B auto start failure DBA LOCA on reactor trip Auto CIB failure Auto CIB failure Auto CIB failure Rod bottom lights lit. Neutron flux dropping.
First Out: [A5-6D], TURBINE TRIP DUE TO REACTOR TRIP US directs manual reactor trip.
RO manually trips reactor.
RO verifies reactor trip.
RO sounds standby alarm, announces Unit 2 reactor trip.
Throttle or governor valves closed, reheat stops or interceptors closed.
PO verifies turbine trip.
BVPS-2 NRC Sim #4 Rev. 2.doc 8 of 12
1/2-ADM-1357, Rev. 1 Attachment D PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE MSR steam supply block valves closed.
Reheat controller reset pushbutton depressed.
Main generator output breakers open.
Main gen. volts ZERO.
Exciter circuit breaker opens.
2AE and 2DF busses energized.
E-0 Immediate Actions completed.
SI actuated.
Manual reactor trip resulted in a DBA LOCA on RCS Loop B.
RCS pressure, PRZR level off scale low.
CNMT parameters degrade rapidly.
PO ensures reheat steam isolation.
PO verifies generator trip.
PO verifies power to at least one AC emergency bus.
RO checks if SI is actuated, manually actuates SI pushbuttons.
US directs manual trip of all RCPs.
US direct operators to verify automatic actions by performing Attachment A 0.11, when time permits.
BVPS-2 NRC Sim #4 Rev. 2.doc 9 of 12
1/2-ADM-1357, Rev. 1 Attachment D I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE -
CT#1 - E-0.H:
Crew manually starts at least one low head ECCS pump before transition out of E-0.
CT#2 - E-O.E:
Crew manually actuates at least the minimum required complement of containment cooling equipment before an Extreme (red path) challenge develops to the Containment CSF.
Automatic actions of A-0. 11 are SAT with the following exceptions:
2FWE*P23B OOS at turnover.
Both LHSI pumps failed to auto start and were manually started.
CIB failed to auto actuate and was manually actuated.
LHSI pumps manually started.
CIB/Spray manually actuated.
Leak collection filtered exhaust fan status SAT.
Plant rapidly cooled down due to DBA LOCA.
Operator assigned to perform Attachment A-0. 11 reports status of attachment to US/crew and any actions taken when completed.
PO manually starts both LHSI pumps during performance of Attachment A 0.11 and reports actions to US when complete.
CT#1 S/U PO manually actuates CmB & CNMT Spray during performance of Attachment A-0. 11 and reports actions to US when complete.
CT#2 S/U Crew verifies leak collection filtered exhaust fan status.
RO reports RCS cold leg temperature and cooldown caused by LOCA.
BVPS-2 NRC Sim #4 Rev. 2.doc 10 of 12
I BVPS-2 NRC Sim #4 Rev. 2.doc Transition to E-1.
11 of 12 1/2-ADM-1357, Rev. 1 Attachment D PLANT STATUS OR RESPONSE I
Recirc spray pumps will start after CIB and appropriate time delay.
RCS Pressure at CNMT pressure due to DBA LOCA.
PRZR PORVs, safeties, spray valves closed.
PORVs/block valves alignment SAT.
RCPs previously secured.
SGs not faulted.
SG tubes intact.
CNMT parameters not consistent with pre-event, indicate large LOCA in progress.
CTB actuated.
RCP's previously secured.
Recirc spray pumps operating.
OBJECTIVE I EXPECTED STUDENT RESPONSE RO checks recirc spray pump status.
RO checks PRZR isolated. PRT conditions normal.
RO verifies PORV alignment SAT.
Crew determines no faulted SGs.
Crew determines no SGTR event in progress.
US enters E-1 and announces entry to crew.
PO checks Control Room habitability systems actuated.
RO reports recirc spray pump status.
1/2-ADM-1357, Rev. 1 Attachment D PLANT STATUS OR RESPONSE I OBJECTIVE -EXPECTED STUDENT RESPONSE Both CNMT hydrogen analyzers operating.
No SG's faulted.
AFW flow > 340 gpm.
Power available to block valves.
PORV/block valve alignment SAT.
No SG levels rising in an uncontrolled manner.
Subcooling < 43°F.
Adequate secondary heat sink.
RCS pressure NOT stable or rising.
RO reports H2 analyzer status.
PO checks if SG's are faulted.
PO checks intact SG levels and control levels.
RO checks PORV and block valves alignment.
PO checks is SG tubes are intact.
Crew checks is SI flow can be terminated.
Crew determines SI flow CANNOT be terminated.
Terminate the scenario when the crew determines that SI flow cannot be terminated.
US evaluates EPP and declares an ALERT due to Loss of RCS Barrier (TAB 1.2).
BVPS-2 NRC Sim #4 Rev. 2.doc 12 of 12