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: 2LOT4 NRC Exam SUBDIVISION: BVPS Unit 2 Simulator SCENARIO TITLE/NO.: NRC Scenario #1 COMPUTER CODE FOR L.P.: N/A 1 10/25/02 2 12/4/02 i
INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hours PREPARED BY: General Physics Corp. 8/01/2002 Date REVIEWED BY: 12- -01.
(2 Date APPROVED FOR IMPLEMENTATION:
Date
Appendix D Scenario Outline Form ES-D-1 Facility: FENOC BVPS Unit 2 Scenario No. I Op Test No.: 2002-02 Examiners: Candidates: CRS RO PO Objectives: 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.
5 CNH PCS 1OA I (RO) 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-0 - FR-S. 1- E-0 - E-1.
BVPS-2 NRC Sim #1 Rev 2.doc 3 of 17
1/2-ADM-1357, Rev. 1 Attachment D Initial Conditions REV. 2 Program
Title:
2LOT4 NRC Examination (2002-02)
INITIAL CONDITIONS: IC 12 8 PW = NRCI1 100%, BOL EQU XE, CBD = 225, RCS boron = 1576 ppm STICKERS VOND MARKINGS ADDITIONAL LINEUP CHANGES 2FWE*P23A YCT N/A 2FWE*P23A PTL EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S) 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 2FWE*P23A 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.
this shift.
- 4. 2FWE*P23A is OOS for motor replacement. Motor is removed and the pump will not be returned SCENARIO SUPPORT MATERIAL REQUIRED
- 1. Power reduction reactivity plan.
- 2. 20M-52.4.B, Load Following, Step IV.B. 1.
BVPS-2 NRC Scenario 1 4 of 17
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 US directs load decrease. Crew at 12%/hr or less. 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 21B SG FWRV sticks in position. SG feed flow and Nký level rises.
NOTE: Level deviation dependent Alarm received: PO notes problem with 21B SG level on time of establishing normal [A6-ElO], SG 21B Level Deviation From control, valve and takes manual control MFRV control to restore 21B SG Setpoint of 2FWS*FCV488, inform US.
level.
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 IMF BKR-HIVOI (0 0) 0 2DF bus remains energized. 2AE bus is IMF BKR-HIV11 (0 0) 2 deenergized. 2-1 EDG output breaker (preload) fails to automatically shut.
Loss of 4KV Emergency Bus 2AE PO determines 2AE bus deenergized.
Crew responds per ARPs.
Alarms received:
[A8-C2], 4160V Emer Bus 2AE Undervoltage
[A8-A2], 4160V Emer Bus 2AE ACB 2A10/2E7 Auto Trip 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.
2CHS*P21B running. 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 6 of 17
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE -OBJECTIVEI EXPECTED STUDENT RESPONSE NOTE: Crew should respond 2CHS*P21A, Charging Pump, US directs PO to shut ACB-2E 10, 2-1 expeditiously to reenergize bus 2CCP*P21A, CCP Pump and EDG output breaker, and reenergize 2AE and verify service water 2SWE*P21A, Service Water Pump all bus 2AE.
supply to 2-1 EDG. deenergized.
EDG No. 1 output breaker shut. 4KV PO manually shuts ACB-2E 10, 2-1 bus 2AE re-energized. EDG output breaker and re-energizes bus 2AE.
Loads sequence onto 2-1 EDG. RO ensures CCP flow to all RCP thermal barriers.
2 charging pumps operating. RO reports charging pump status.
Crew discretion as to which US directs RO to secure 1 charging charging pump is secured. pump.
2CHS*P21A or B secured. 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.
RO notes indications and alarms, Alarms received: informs US.
[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 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 US directs RO to place PRZR Master Controller fails to close PORV, fails to Pressure Controller in manual, close control heaters, and fails to control spray spray valves and PORV and take valves. manual control of PRZR heaters.
Crew recognizes entry into T.S. 3.2.5 (DNB) for reduced RCS pressure.
Spray valves close. PRZR heaters RO uses individual component controls EVENT 5 (partial) energized. to shut spray valves and take manual control of PRZR heaters, and attempts IOR XBlIO35C (0 0) 0 (preload) PORV remains open. to close PORV.
RCS pressure continues to decrease due to PORV failure. Charging flow increases.
PORV Block Valve leaks after PORV Block Valve closed. Crew identifies PORV remains open.
closing.
RCS pressure continues to lower due to US directs closing of PORV block leaking PORV Block Valve. valve. RO closes valve.
US contacts I&C to investigate failure.
EVENT 5 At Examiners discretion:
IMF RCS1OA (0 0) 0.5 PORV Block Valve Leakage BVPS-2 NRC Scenario 1 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 RCS pressure continue to decrease due to RO monitors RCS, identifies that RCS 180 stuck open PORV and leaking block pressure is continuing to decrease.
(block valve leakage increases) valve. Charging flow remains high.
US directs RO to turn on all PRZR heaters (if not previously done).
RCS pressure dropping. Charging flow US directs a manual reactor trip.
rising.
IMF PPL01A (0 0) 1 (preload) Manual reactor trip or automatic RO places reactor trip switch to trip.
IMF PPLO1B (0 0) 1 (preload) Pressurizer pressure low reactor 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 Operators commence Immediate Actions. 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: Rods inserting. RO uses auto or manual rod control to Crew inserts negative reactivity insert rods.
into the core by inserting RCCA's CT#1 S/U before completing the immediate action steps of FR-S.1.
Crew sounds standby alarm and announces Unit 2 reactor trip failure.
After directed to locally open Crew dispatches an operator to locally RTB's, insert: open the RTB's.
IMF PPL02A (10 120)
IMF PPL02B (10 130) Reactor tripped (time delay).
IRF LOA-CRFOO7 (10 150) MG sets secured (time delay).
IRF LOA CRF008 (10 160)
TRG! 10 Report RTB's manually opened & SM requested to evaluate EPP.
MG sets secured.
Turbine manually tripped. PO manually trips turbine.
Throttle, governor, reheat stop, and PO verifies turbine trip.
interceptor valves all closed.
Steam dump bypass interlock selector PO places Condenser Steam Dump switches in OFF. Selector Switches in "OFF".
FR-S.1 Immediate Actions MSR steam supply block valves closed. PO ensures reheat steam isolation and complete. Reheat controller reset. 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) 2B SSST trips 45 seconds after reactor trip.
IMF BKR-HIV13 (0 0) 2 2-1 EDG output breaker fails to auto (preload) close.
2C, 2D & 2DF buses deenergized. 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.
2F10 closed, 2DF energized, loads PO closes 2F10 and reports loads sequencing on EDG. sequencing.
2FWE*P23A on clearance. PO verifies AFW status.
2FWE*P23B running.
TDAFW pump steam supply valves open.
AFW throttle valves full open.
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. RO initiates emergency boration of 2CHS*MOV350 open. RCS.
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. RO checks PRZR pressure less than 2335 psig.
[A5-4G], Pressurizer Low Pressure Crew checks SI signal status, performs Reactor Trip Safety Injection lit. first ten steps of E-0 when time permits.
SG levels < 12% NR. 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.
2CHS*FCV1 13B closed. RO verifies dilution paths isolated.
2CHS*FCV1 14A closed.
2CHS*FCV1 14B closed.
Uncontrolled cooldown not in progress. RO monitors RCS for uncontrolled cooldown.
US transitions to Step 16 of FR-S. 1.
Core exit temperatures less than 1200'F. 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 [ t"* D I E/*'T'I\ IE I r S. . ......... . ...... . ,,,,,.,/,",,*C I M 'JD, JEL7IIVr EXPECTED STUDENT RESPONSE PR NI's less than 5%. RO verifies reactor subcritical.
IR NI's negative SUR.
Crew enters E-0.
US makes transition from FR-S.1 back to E-O. Directs crew to perform E-O Immediate Actions.
Steps 1 - 7 of E-0 are Immediate Reactor locally tripped. RO verifies reactor trip.
Actions. Rods bottom lights lit.
Flux decreasing.
Previously completed.
RO sounds standby alarm and announces Unit 2 safety injection.
Previously requested.
Throttle or governor valves closed, reheat PO verifies turbine trip.
stops or interceptor valves closed.
MSR steam supply block valves closed. PO ensures reheat steam isolation.
Reheat controller reset pushbutton depressed.
Main generator output breakers open. PO verifies generator trip.
Main generator volts ZERO.
Exciter circuit breaker open.
2AE and 2DF busses energized. PO verifies power to AC emergency busses.
BVPS-2 NRC Scenario 1 14 of 17
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
[A5-4G], Pressurizer Low Pressure Crew checks if SI is actuated/ required.
Reactor Trip Safety Injection lit.
SI actuation status light, A12-1D lit.
E-0 Immediate Actions complete. Both trains of SI manually initiated. 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.
Automatic actions of A-0. 11 are SAT Operator assigned to perform with the following exceptions: Attachment A-0. 11 reports status of Attachment to US and any actions 2FWE*P23A OOS at turnover. taken when completed.
Leak collection filtered exhaust fan status Crew verifies Leak collection filtered SAT. exhaust fan status.
RCS temperature trending to 547°F. RO reports Tavg status, US directs crew to control steam/feed flow as necessary to achieve desired status.
Recirc spray pumps not running. RO checks recirc spray pump status.
PRZR pressure < 2310 psig. RO checks PRZR isolated. PRT conditions normal.
[2RCS*PCV455C], PORV failed open.
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. RO verifies PORV Block Valve shut for open PORV.
Crew enters E-1. US enters E-1 and announces entry to Crew.
Radiation not in alarm status and CIB has PO checks Control Room habitability.
not occurred.
CT#2 - E-1.C: RCP's secured. RO checks if RCP's should be stopped.
Crew trips all RCP's when RCS to highest SG D/P criteria is CT#2 S/U exceeded and SI flow verified prior to exiting procedure E-1.
Recirc spray pumps not operating. RO reports Recirc Spray pmp status.
Both CNMT hydrogen analyzers RO reports H2 analyzer status.
operating.
No SG's faulted. PO checks if SG's are faulted.
AFW flow > 340 gpm. PO checks intact SG levels and control levels.
Power available to block valves. RO checks PRZR PORV and block valves.
PORV open. [2RCS*MOV535], PORV RO verifies PORV block valve shut.
Block Valve shut but leaking.
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 PO checks is SG tubes are intact.
manner.
Subcooling < 43°F. Crew checks if SI flow can be terminated.
Adequate secondary heat sink. Crew determines SI flow CANNOT be terminated.
RCS pressure NOT stable or rising.
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: 2LOT4 NRC Exam SUBDIVISION: BVPS Unit 2 Simulator SCENARIO TITLE/NO.: NRC Scenario #2 COMPUTER CODE FOR L.P.: N/A
-Revision No.' D)ate '-Revision No. '.Date 1 11/18/02 2 12/4/02 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hours PREPARED BY: General Physics Corp. 8/01/2002 Date REVIEWED BY:
A17 D2a-t-0.
0 Date APPROVED FOR IMPLEMENTATION:
Date
Appendix D Scenario Outline Form ES-D-1 Facility: 1FENOC BVPS Unit 2 Scenario No. 2 Op Test No.: 20U0-U0 Examiners: Candidates: CRS RO PO Objectives: Demonstrate the ability to safely operate the plant during normal and upset conditions in accordance with plant procedures.
Initial IC 127: 9% pwr, BOL, EQU XE, RCS boron = 2080 ppm, CB "D" = 116 Conditions: steps.
Turnover: Continue plant startup.
Critical Task 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
PMP CHS002 C (RO) 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
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
1/2-ADM-1357, Rev. 1 Attachment D Program
Title:
2LOT4 NRC Examination (2002-02) 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
- 2. Continue the plant startup to 100% JAW 20M-52.4.A, Step 3.
- 3. Severe weather is expected.
SCENARIO SUPPORT MATERIAL REQUIRED
- 1. Plant startup reactivity plan.
- 2. 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
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EVENT #1 Reactor Power Increase Crew commences power increase in accordance with reactivity plan.
Continue reactor startup. Reactor at 9% power.
RO commences raising reactor power to between 10 and 20%.
Status lights on Panel 308 actuate at RO verifies P-10 bistables actuate as 10%. required as power increases to > 10%.
[A12-2B], NIS IR Trip Blocked is ON. RO blocks the IR Trip and Rod Stop and verifies annunciator ON.
[A12-2C], Power Range Low Setpoint RO blocks Power Range low Trip Blocked is ON. overpower trip and verifies annunciator ON.
RO verifies that annunciator NOT P-7
[A12-1H], NOT P-7 is OFF.
is OFF.
RO selects highest power ranges on N-45.
BVPS-2 NRC Scenario 2 5 of 18
1/2-ADM-1357, Rev. 1 Attachment D PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE I INSTRUCTION GUIDELINES EVENT #2 After Crew has raised reactor power to greater than 10% and IR trips have been blocked:
IMF NIS07B (0 0) 0 Meters for NI-36 indicate zero and blown RO acknowledges annunciators and fuse indication exists on drawer. identifies N-36 as the failed channel.
NI-36 Instrument power fuse fails.
Alarms received:
[A4-4G], NIS Detector/Compensator RO reports diagnosis to US.
Loss of Voltage RO refers to ARPs.
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 I jJA..IIVIZ I ELJ I LJLJLIN I [XL-*)I '-'-"-- I I IMTPI ICTIflNI (I linPi INFS SPLANITATI U UP Kb-IUNZ-d jl~r'L, I IVI" I r-Ar-LF__.g Ir' OIU 1 ~L F_.*I r0 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 After the startup continues: 2MSS*PT464 fails low. PO determines condenser steam dumps are closed and informs US/RO.
Condenser steam dump valves close. PO identifies failure of 2MSS*PT464 IMF XMT-MSS044A (0 0) 0 and informs US.
Condenser steam dump demand indicates zero.
2MSS-PI464A indicates zero.
Tavg rising.
Atmospheric dump valves open automatically.
BVPS-2 NRC Scenario 2 7 of 18
1/2-ADM-1357, Rev. 1 Attachment D I INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE EXPECTED STUDENT RESPONSE US directs RO to take manual control Alarms received: of steam dumps.
[A6-7A], Steamline Pressure High Condenser steam dumps reopened. RO opens condenser steam dumps in manual.
US contacts I&C to investigate.
EVENT #4 21B SG Atmospheric Dump Valve fails PO identifies failed open atmospheric IMF CNH-MSS03B (3 0) 100 dump valve and informs US.
(preload) open.
SG level deviation alarms may actuate. 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 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
I INSTRUCTION GUIDELINES EVENT #5 RO acknowledges RCP vibration Insert the following:
alarm, informs US, refers to [A2-5C]
21B RCP seal leakoff rising as indicated ARP. Crew trends RCP vibration.
IMF RCP01B (0 0) 1 300 on 2CHS-FR154A.
[A2-5C], Reactor Coolant Pump US enters AOP-2.6.8.
IMF RCP06B (0 0) 15 Vibration Alert/Danger.
21B RCP vibration rises to >16 mils. US continues in AOP 2.6.8 to address IMF RCP06B (0 0) 21 1800 vibration problem.
Shaft vibration > 15 mils and rising at > When it is determined that RCP 1.0 mils/hr. 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.
EVENT #6 RO informs US of a reactor trip.
IMF RCS04B (2 0) 500 (preload) 21B SGTR when the reactor is tripped.
RO/PO commence IMA's of E-0, US Steps 1 - 7 of E-0 are Immediate references E-0 to verify IMA's.
Actions.
[A5-6D], Turbine Trip Due To Reactor RO verifies reactor trip.
Trip lit.
Rod bottom lights lit.
Neutron flux dropping.
BVPS-2 NRC Scenario 2 9 of 18
1/2-ADM-1357, Rev. 1 Attachment D
. . . . . . .-. .. . .. . . ,- ,,-- I tm ,r' - T I\ / I V D E C 'Tr-I ' Q T I IIlZ N IT ( hDI: IK NZID f'%l IIr'lf-'l IKIr"l* 11 I T O( - III. " H HI-"i JNJ.'Nl-- I UIJJI-L, I Ivr-INSTRUCT-It"%l*l IMIAN U.juI r-LIINIEO r '-, i .i -. *,. , -.-....... .. . .
RO sounds standby alarm, announces Unit 2 reactor trip.
Throttle or governor valves closed. PO verifies turbine trip.
Reheat stops or interceptors closed.
PO ensures reheat steam isolation.
MSR steam supply block valves closed.
Reheat controller reset pushbutton depressed.
PO verifies generator trip.
Output breakers open.
Main generator volts ZERO.
Exciter ACB open.
PO verifies power to AC emergency 2AE and 2DF busses energized.
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 10 of 18
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. RO reports SI status, manually actuates SI.
US directs RO to secure 21B RCP due Immediate Actions of E-0 to high vibration/seal leakoff trouble.
complete.
21 B RCP secured. RO secures 21B RCP.
US direct operators to verify automatic actions by performing Attachment A 0.11 when time permits.
Automatic actions of A-0.11 are SAT Operator assigned to perform with the following exceptions: Attachment A-0. 11 reports status of attachment to US and any actions taken when completed.
2CHS*P21A failed to auto start on SI, manual start is successful.
2CHS*P21B tripped on SI and cannot be manually restarted.
2CHS*P21A manually started. PO manually starts 21A HHSI pump &
CT#1 - E-0.I: reports actions/status to US.
Crew establishes flow from at least one high head ECCS pump CT#1 - S/U before transition out of E-0.
Leak collection filtered exhaust fan status Crew verifies leak collection filtered SAT. exhaust fan status.
BVPS-2 NRC Scenario 2 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. RO reports Tavg status, US directs crew to control steam/feed flow as necessary to achieve desired status.
Recirc spray pumps not running. RO checks recirc spray pump status.
PORVs closed (not leaking). RO checks PRZR isolated.
Spray valves closed.
Safeties closed (PSMS data).
PRT conditions normal.
PORV/block valve alignment SAT.
21B RCP previously secured. RO checks if RCPs should be stopped.
21A & 21C RCPs running.
CCP flow normal.
No SG pressure dropping in an PO checks if any SGs are faulted.
uncontrolled manner.
21B SG level rising in an uncontrolled US directs operator to check if SG manner. Secondary rad monitors not tubes are intact.
consistent with pre-event levels.
Crew transitions to E-3. 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 Control room habitability system not PO verifies control room habitability.
required.
21B RCP previously secured. RO/PO check if RCPs should be 21A & 21C RCPs running. stopped.
CCP flow normal.
CT#2 - E-3.A: 21B SG level rising in an uncontrolled Crew identifies ruptured SG.
Crew isolates feed flow into and manner. Secondary rad levels higher steam flow from the ruptured SG than normal.
and directs operator to close isolations valve(s) operated from outside of the control room before a transition to ECA-3.1 occurs.
Adjust ruptured SG atmospheric steam Crew isolates flow from ruptured SG.
IRF LOA-MSSO1O (0 0) 0 dump controller setpoint to 100% and IRF LOA-AFW026 (0 0) 0 verify 2SVS*PCV1O1B closed. CT#2 S/U 2SVS*HCV104 - closed.
2SVS*28 - closed.
2MSS*16 - closed.
2BDG*AOV100B1 - closed.
2SDS*AOV111B1 - closed.
2SDS*AOV129A - closed.
2MSS*AOV101B, 102B - closed.
BVPS-2 NRC Scenario 2 13 of 18
1/2-ADM-1357, Rev. 1 Attachment D I .... I ... ,..--------------I SINSTRIUCTION GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPI-T;I.D I UUlN I tIt.'UNlr_ I INSTRUCTI N GUIDELINES I PLANT STATUS OR RESPONSE Notify crew that 2MSS* 16 is Verify closed 21B SG steam supply to closed. Also report 2SVS*28 TDAFW pump, 2MSS* 16 and 2SVS*28.
closed when requested.
21B SG narrow range level greater than PO checks ruptured SG level.
12% (31% adverse).
2FWE*HCV100C & D closed. PO isolates feed flow to 21B SG.
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. PO verifies ruptured SG pressure > 240 psig.
BVPS-2 NRC Scenario 2 14 of 18
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: Based on ruptured SG pressure. US determines target temperature for Crew establishes/maintains an 1000 - 1084 = 505°F (480°F). cooldown.
RCS temperature so that 900 - 999 = 492-F (467-F).
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.
RO blocks low steamline pressure SI when PRZR pressure is less than 1950 psig.
Steam dump is available, greater than PO dumps steam at maximum rate.
100°F per hour cooldown.
SNA monitors thermocouples.
Condenser steam dumps closed in PO stops cooldown when core exit manual due to previous failure, 21A & TCs < target temperature.
21C atmospheric dump valve controllers CT#3 S/U in auto with pot setting corresponding to current intact SG pressure.
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). PO controls intact SG feed flow as required (340 gpm min) to achieve/maintain levels between 12%
(31%) and 50%.
Power to PORVs & block valves SAT. RO verifies PORV/block valve PORVs closed, not leaking. conditions as expected.
PORV/block alignment SAT.
Auto SI blocked [A12-1C] lit. RO resets SI (both trains).
SI signal [A12-1D] NOT lit.
Both trains of CIA reset. RO resets CIA and CIB (both trains).
CIB not actuated.
Station air available. PO verifies/reports status of station air system.
Instrument air established to CNMT. Crew establishes instrument air to 2IAC-MOV131 - open. CNMT.
2IAC-MOV130 - open.
Instrument air header pressure > 85 psig.
RCS pressure > 225 psig (250 psig RO stops LHSI pumps and places them adverse). in auto.
LHSI pumps stopped, in auto.
Ruptured SG pressure stable. 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 Subcooling > 61'F (79°F adverse). Crew verifies subcooling SAT.
PRZR level < 75% (6 1%). RO depressurizes RCS to minimize CT#4 - E-3.C: break flow and refill PRZR.
Crew depressurizes RCS to meet RCS subcooling > 41'F (59°F).
SI termination criteria before 21A & 21C RCPs running.
water release from the ruptured Spray valves available. Both spray SG safety or atmospheric relief valves open.
valve. IF AVAILABLE, 1 PORV will be used to assist depressurization.
Depressurization Termination: RO closes spray valves and PORV, if PRZR level >75% (6 1%) used.
OR RCS subcooling < value listed on CT#4 S/U Attachment A-5.1 OR RCS pressure < ruptured SG pressure AND PRZR level > 17% (38%).
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: 2LOT4 NRC Exam SUBDIVISION: BVPS Unit 2 Simulator SCENARIO TITLE/NO.: NRC Scenario #3 COMPUTER CODE FOR L.P.: N/A Rkevision No. -Date Revision No-. Date 1 11/18/02 2 12/4/02 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hours PREPARED BY: General Phvsics Corn. 8/01/2002 Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date
Appendix D Scenario Outline Form ES-D-1 Facility: FENOC BVPS Unit 2 Scenario No.: 3 Op Test No.: 2002-02 Examiners: Candidates: CRS RO PO Objectives: 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
1/2-ADM-1357, Rev. 1 Attachment D Program
Title:
2LOT4 NRC Examination (2002-02) 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
- 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. Power reduction reactivity plan.
- 2. 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 US assumes control and directs Operators to lower reactor power to 60%.
EVENT 1 Turbine load and reactor power lowering Crew reviews/agrees with reactivity Lower power - 5%.
at 12%/hr or less. 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.
EVENT 2 At Examiner's direction insert:
IMF CNH-PCS09B (0 0) 100 Pressurizer Master Level Controller fails high.
Charging pump flow increases.
Alarms expected:
[A2-E3], Charging Flowpath Trouble RO notes indications and alarms,
[A2-D4], Reactor Coolant Pump Seal informs US.
Trouble BVPS-2 NRC Scenario 3 5 of 15
1/2-ADM-1357, Rev. 1 Attachment D
_________________________________________I II ORIF(TIVL I EXPtUILUIUUtiNI Or'JINQL Sn'Jb-L..%.JI I )Q. C.IE INSTRUCTION GUIDELINES I PLANT STATUS OR F EXPEUAtU,'.)1UUr-1-41 mr-or Not- I US directs RO to place PRZR level controller or charging pump discharge control valve in manual.
RO takes manual control of PRZR PRZR level controller 2CHS*FCV122 in level.
manual.
US requests I&C to investigate Alarms clear. Pressurizer level controller failure.
EVENT 3 21 C SG Feed Flow Transmitter fails high.
[2FWS*FT496], 21C SG Feed Flow PO acknowledges alarms, diagnoses IMF XMT-CFW055A (0 0) 5 problem, informs US.
Transmitter fails high.
Level deviation annunciator is [2FWS*FCV498], 21C SG MFRV dependent on operator action to modulates shut lowering SG level.
manually control the 21C MFRV.
Alarms expected:
[A6-F11 ], Loop C Feedwater Flow >
Steam Flow
[A6-D 11], SG 21C Level Deviation From Setpoint 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 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 Crew recognizes load rejection.
IMF EHC06 (0 0) 50 (approx. 600 MW). RCS temperature rises. SG level deviation alarms.
US directs operators to stabilize the Condenser steam dumps open. Load rejection 15% - 50% status light A12-4A plant and refers to AOP-2.35.2.
(C-7A actuated).
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 7 of 15
1/2-ADM-1357, Rev. 1 Attachment D II I ELJ cri IArEA r'-rir' Ir%NI T RESPONSE II
... .- IT- Q I '..JLJLIN
)NSd- IJM.II,I IVt DI 1AMT I-
-1 QTATI "ol II/3* (M.' I--4-'(
l#l-:l[
MMTATI .I- I t Jl"l. I P"I.. I I V I* I EAF ~l M 0-IU-ACI*
I INS I RUC I I N OUIUMLINE0 I r- L-/-%l 14 I Ivr- r-ru VPL failed low, vibration and load Crew checks if governor valves have closed in sequence, checks turbine satisfactory for condition. EHC control vibration recorders, and EHC control is transfers from partial to full arc mode.
transferring to full arc mode.
Crew monitors for subsequent load reductions > 90 MWE.
Crew checks if turbine should be Generator load > 270 MW tripped, verifies load is greater than 270 Vacuum > 24.5 inches Hg.
MW.
PO verifies if the main generator is on Generator output breakers closed.
line.
Generator volts, amps, and power factor satisfactory.
RO checks Tavg - Tref within 5'F.
PO resets steam dump controller, if Crew may perform actions to Load rejection bistables reset.
necessary.
recover GV control from the valve position limiter per 20M-26.4.X. Crew notifies System Operator of load loss and reason (if determined).
US directs I&C to investigate problem with valve position limiter.
BVPS-2 NRC Scenario 3 8 of 15
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE -FOBJECTIVE EXPECTED STUDENT RESPONSE Load rejection > 15%. US directs chemistry to sample as required for load rejection > 15%.
2CNM-AOV100 closed. Crew checks 2CNM-AOV 100 closed.
Supervisory limits normal. 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 Pipe rupture in condensate header.
Reactor fails to auto trip. RO notes that a reactor trip has not IMF PPLO1A (0 0) 0 (preload) occurred.
IMF PPL01B (0 0) 0 (preload)
TDAFW pump trips during startup IMF AFW03A (0 0) 5440 (preload)
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.
Reactor trip. RO manually trips reactor.
CT#1 - E-O.A:
Crew manually trips reactor CT#1 S/U from the Control Room before performing the mitigation strategy of FR-S.1.
Steps 1 - 7 of E-0 are Immediate RO/PO commence IMAs of E-0, US references E-0 to verify IMAs.
Actions.
[A5-6D], Turbine Trip Due To Reactor RO verifies reactor trip.
Trip lit.
Rod bottom lights lit.
Neutron flux dropping.
RO sounds standby alarm, announces Unit 2 reactor trip.
Throttle or governor valves closed. PO verifies turbine trip.
Reheat stops or interceptors closed.
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 MSR steam supply block valves closed. PO ensures reheat steam isolation.
Reheat controller reset pushbutton depressed.
Output breakers open. PO verifies generator trip.
Main generator volts ZERO.
Exciter ACB open.
IMF DSG01B (1 40) (preload) 2AE energized. PO verifies power to AC emergency 2DF de-energized, 2-2 EDG tripped busses, reports loss of 2DF bus and 2-2 during loading and will not be recovered. EDG.
No SI annunciator. Crew checks if SI is actuated/required.
SI actuation status light not lit.
E-0 Immediate Actions complete. Crew dispatch operators to investigate loss of 2-2 EDG and 2FWE*P22.
Transition to ES-O. 1. SI is not required. 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 Maintain RCS temperature. Crew checks/monitors T-avg.
as Turbine Building Operator that there is a large condensate header rupture just down stream of pump's discharge.
NOTE: After report from field, Steam dumps in steam pressure mode, PO places steam dumps in steam crew may opt to secure remaining RCS Tavg > 547°F and rising. Monitor pressure mode.
condensate pumps. RCS temperature.
RO reports that Tavg is stable.
EVENT6 When steam dump control mode Loss of 4KV Bus 2AE bus. 2-1 EDG PO identifies loss of 4KV Bus 2AE and selector switch is placed in Steam fails to auto start. reports loss to US.
Pressure position:
IMF BKR-HIV01 (2 0) 0 US determines no ESF busses are (preload) energized.
IRF LOA-DSGO01 (5 0) 0 (preload)
IMF PPL07A (2 1) 5 (preload) 2FWE*P23A fails to auto start on EDG sequencer, manual start successful.
Crew enters ECA-0.0. 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 PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE INSTRUCTION GUIDELINES
[A8-5E], 2-2 EDG Local Panel Trouble SNA monitors CSF status trees for When requested to check why 2-2 information only.
alarm.
EDG tripped, report that the Local Alarm No. 5 (overspeed trip) is actuated and there is physical damage to the EDG.
Annunciator A5-6D lit. RO reverifies reactor trip.
Neutron flux dropping.
RO sounds standby alarm and announces Unit 2 loss of power.
SM requested to reevaluate EPP.
PO ensures steamlines isolated.
SLI manually actuated.
MSIVs and bypass valves closed.
PO verifies generator trip.
Exciter and output breakers open.
RO verifies RCS isolated, stops PORVs closed. running RCPs.
Letdown isolated.
RCPs stopped.
BVPS-2 NRC Scenario 3 13 of 15
1/2-ADM-1357, Rev. 1 Attachment D INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE AFW flow not indicated due to loss of all PO reports AFW system status, "WHENAPPROPRIATE report operators previously dispatched to that 2FWE*P22 has physical AFW pumps.
investigate loss of 2FWE*P22.
damage to the trip and throttle valve, and will not be returned. US dispatches operator to perform Attachments A-1.12 and A-1.11 to restore AFW flow.
RO verifies source range &
SR & IR channels aligned to 2NME intermediate NIs displayed on 2NME NR45.
NR45.
PO tries to start 2-1 EDG and reports it 2-1 EDG starts manually and sequences started and is sequencing loads.
loads WITH EXCEPTION OF 2FWE*P23A.
US directs return to ES-0.1, Step 5, 2AE emergency bus energized.
Transition to ES-0.1 (step in effect), based on reports of power restored to one 4KV emergency bus.
PO reports no AFW pumps operating.
NOTE: Crew may start 2FWE*P23A failed to auto start on 2-1 2FWE*P23A when 2AE bus is re EDG sequencer.
energized before transition to ES 0.1.
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 OBJECTIVE EXPECTED STUDENT RESPONSE I INSTRUCTION GUIDELINES PLANT STATUS OR IS..........
N- -- -
I i AFW flow restored to > 340 gpm. PO starts 2FWE*P23A and restores CT#2 - ECA-O.O.B: feed flow to all SGs.
Crew establishes the minimum required AFW flow rate to the CT#2 S/U SGs before SG dryout occurs.
Terminate scenario when AFW AFW flow > 340 gpm.
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.
15 of 15 BVPS-2 NRC Scenario 3
RTL# A5.670.AA 1/2-ADM-1357.F 11 Page 1 of 1 Revision I SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: 2LOT4 NRC Exam SUBDIVISION: BVPS Unit 2 Simulator SCENARIO TITLE/NO.: NRC Scenario #4 COMPUTER CODE FOR L.P.: N/A
~Ressiow'N6O7. -,-ate :
1 10/25/02 2 12/4/02 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hours PREPARED BY: General Physics Corp. 8/01/2002 Date REVIEWED BY: 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: CRS RO PO Objectives: 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.
3 PMP CCPO1 C (RO) 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.
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1/2-ADM-1357, Rev. 1 Attachment D Initial Conditions REV 2 Program
Title:
2LOT4 NRC Examination (2002-02)
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 "EQUIPMENTSTATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S) 2FWE*P23B OOS 24 Hours ago TS 3.7.1.2, Action b SHIFT TURNOVER INFORMATION
- 1. 80%, BOL, EQU XE, 1615 ppm, CB "D" at 172 steps.
- 2. Reduce power to remove 2FWS*P21A from service due to high 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. Power reduction reactivity plan.
- 2. 20M-52.4.B, Load Following, Step IV.B. 1.
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1/2-ADM-1357, Rev. 1 Attachment D PLANT STATUS OR RESPONSE I OBJECTIVE EXPECTED STUDENT RESPONSE EVENT #1 Turbine load and reactor power reduction Following the Reactivity Plan, Crew Lower reactor power to 75%. lowers reactor power.
at 12%/Hr or less.
US directs load decrease. Initiates Turbine load reduction.
PO initiates turbine load decrease.
RO initiates RCS boration as necessary to maintain Tavg-Tref.
EVENT #2 PO recognizes feed pump trip and After power is lowered to 77%: 2FWS-P21A trips. informs US.
IMF PMP-CFW004 (1 0) 1 (preload) 2FWS-P24 trips 3 minutes after startup.
IMF PMP-CFW008 (2 180) 1 (preload) US refers to AOP-2.24.1, Loss of Main Feedwater.
US verifies reactor power < 90%.
Alarms received: Refers to ARPs as time permits.
[A6-A1O0], SG Feed Pump 21 A/B Auto Stop 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. US directs starting 2FWS-P24.
PO starts 2FWS-P24 and dispatches operator to locally check pump.
PO reports trip of 2FWS-P24 after 2FWS-P24 trips 3 minutes after starting. starting.
Turbine load reduction at 5%/minute. 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.
At Examiner's discretion, proceed RO performs RCS boration to maintain with next event. Tavg-Tref.
EVENT #3 (following are preloaded)
IMF PMP-CCPOO1 (0 0) 1 Running CCP Pump trips. Standby CCP PO manually starts standby CCP Pump.
IMF PMP-CCP002 (0 0) 1 Pump manually started.
TRGSET 3 'XB4IO09T =--1' TRG 3 'DMF PMP-CCP002' Alarms Received:
[A6-G1], Pri Comp Cooling Pump Auto Start/Auto Stop
[A6-H 1], Pri Comp Cooling Water System Trouble 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 CCP leak when standby pump started.
IMF FLX-CCP34 (3 0) 450 600 Decreasing CCP Surge Tank level on Determine CCP header leak inside (preload) 2CCP*LI1 0OB. containment.
Increasing containment sump levels. US refers to AOP-2.15.1, Loss of Primary Component Cooling Water.
Increasing 21 RCP motor and bearing temperatures.
1 CCP pump operating. RO/PO Check CCP system status.
Level control in manual with maximum RO/PO place surge tank level control makeup. 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.
Crew monitors RCP motor bearing upper and lower temperatures for RCPs.
Non-essential loads isolated. Crew attempts to locate the leak.
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1/2-ADM-1357, Rev. 1 Attachment D PLANT STATUS OR RESPONSE I OBJECTIVE F EXPECTED STUDENT RESPONSE Surge tank continues to decrease. Crew - If any RCP temperatures are approaching limits OR operating CCP Cavitation of CCP pumps possible. pumps discharge pressure and current indicates cavitation, or if leakage is Leakage excessive. determined to be excessive:
Manually trip the reactor, perform IMAs and trip all RCPs.
EVENT #5 (preloaded)
IMF PPL07A (0 0) 4 2SIS*P21A auto start failure US directs manual reactor trip.
IMF PPL07B (0 0) 4 2SIS*P21B auto start failure IMF RCS03B (4 0) DBA LOCA on reactor trip IMF BST-PCS048 (0 0) 2 Auto CIB failure IMF BST-PCS049 (0 0) 2 Auto CIB failure IMF BST-PCS052 (0 0) 2 Auto CIB failure RO manually trips reactor.
Steps 1 - 7 of E-0 are Immediate Rod bottom lights lit. Neutron flux RO verifies reactor trip.
Actions. dropping.
First Out: [A5-6D], TURBINE TRIP DUE TO REACTOR TRIP RO sounds standby alarm, announces Unit 2 reactor trip.
Throttle or governor valves closed, reheat PO verifies turbine trip.
stops or interceptors closed.
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1/2-ADM-1357, Rev. 1 Attachment D PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE MSR steam supply block valves closed. PO ensures reheat steam isolation.
Reheat controller reset pushbutton depressed.
Main generator output breakers open. PO verifies generator trip.
Main gen. volts ZERO.
Exciter circuit breaker opens.
2AE and 2DF busses energized. PO verifies power to at least one AC emergency bus.
E-0 Immediate Actions completed. SI actuated. RO checks if SI is actuated, manually actuates SI pushbuttons.
Manual reactor trip resulted in a DBA US directs manual trip of all RCPs.
RCS pressure, PRZR level off scale low. RO trips all RCPs.
CNMT parameters degrade rapidly.
US direct operators to verify automatic actions by performing Attachment A 0.11, when time permits.
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1/2-ADM-1357, Rev. 1 Attachment D I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE -
Automatic actions of A-0. 11 are SAT Operator assigned to perform with the following exceptions: Attachment A-0. 11 reports status of attachment to US/crew and any actions 2FWE*P23B OOS at turnover. taken when completed.
Both LHSI pumps failed to auto start and were manually started.
CIB failed to auto actuate and was manually actuated.
CT#1 - E-0.H: LHSI pumps manually started. PO manually starts both LHSI pumps Crew manually starts at least one during performance of Attachment A low head ECCS pump before 0.11 and reports actions to US when transition out of E-0. complete.
CT#1 S/U CT#2 - E-O.E: CIB/Spray manually actuated. PO manually actuates CmB & CNMT Crew manually actuates at least Spray during performance of the minimum required Attachment A-0. 11 and reports actions complement of containment to US when complete.
cooling equipment before an CT#2 S/U Extreme (red path) challenge develops to the Containment CSF.
Leak collection filtered exhaust fan status Crew verifies leak collection filtered SAT. exhaust fan status.
Plant rapidly cooled down due to DBA RO reports RCS cold leg temperature LOCA. and cooldown caused by LOCA.
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1/2-ADM-1357, Rev. 1 Attachment D I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Recirc spray pumps will start after CIB RO checks recirc spray pump status.
and appropriate time delay.
RCS Pressure at CNMT pressure due to DBA LOCA.
PRZR PORVs, safeties, spray valves RO checks PRZR isolated. PRT closed. conditions normal.
PORVs/block valves alignment SAT. RO verifies PORV alignment SAT.
RCPs previously secured. RO reports RCP status.
SGs not faulted. Crew determines no faulted SGs.
SG tubes intact. Crew determines no SGTR event in progress.
Transition to E-1. CNMT parameters not consistent with US enters E-1 and announces entry pre-event, indicate large LOCA in to crew.
progress.
CTB actuated. PO checks Control Room habitability systems actuated.
RCP's previously secured. RO reports RCP status.
Recirc spray pumps operating. RO reports recirc spray pump status.
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1/2-ADM-1357, Rev. 1 Attachment D PLANT STATUS OR RESPONSE I OBJECTIVE -EXPECTED STUDENT RESPONSE Both CNMT hydrogen analyzers RO reports H2 analyzer status.
operating.
No SG's faulted. PO checks if SG's are faulted.
AFW flow > 340 gpm. PO checks intact SG levels and control levels.
Power available to block valves. RO checks PORV and block valves PORV/block valve alignment SAT. alignment.
No SG levels rising in an uncontrolled PO checks is SG tubes are intact.
manner.
Subcooling < 43°F. Crew checks is SI flow can be terminated.
Adequate secondary heat sink. Crew determines SI flow CANNOT be terminated.
RCS pressure NOT stable or rising.
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).
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