ML11143A148
| ML11143A148 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/25/2011 |
| From: | Mcneil D Operations Branch III |
| To: | Florida Power & Light Energy Point Beach |
| References | |
| Download: ML11143A148 (79) | |
Text
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
Appendix D Scenario Outline Form ES-D-1 Facility: ___Point Beach_____ Scenario No.: __1_____ Op-Test No.: 2011301 Examiners: D. McNeil Operators:
R. Walton D. Reeser Initial Conditions: _100% reactor power per OP-2A, Normal Power Operation_____
Turnover: G01 Emergency Diesel Generator is Out of Service in day 3 of a planned 5 day maintenance outage. G02 Emergency Diesel Generator is aligned to 1A05 and 2A05 in accordance with OI-35A, Standby Emergency Power Alignment. P-38A, MDAFW Pump is Out of Service in day 1 of a planned 2 day outage for seal replacement. The plant is under a severe weather watch for the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. AOP-13C, Severe Weather Conditions is in effect. IT 07G, Service Water Valves (Quarterly) is scheduled to be performed immediately after shift turnover.
Event Malf. Event Event No. No. Type* Description N-BOP 1 Conduct IT-07G SW Valve Stroke Time Test N-SRO C-RO 2 C Charging Pump Failure C-SRO I-BOP I-SRO 3 S/G B Level Transmitter ILT-471 Fails High TS-SRO I-RO I-SRO 4 Pressurize Pressure Channel PT-431 Fails High TS-SRO C-BOP C-SRO 5 B Steam Generator Tube Leak TS-SRO R-RO 6 N-SRO Conduct Rx Plant Shutdown N-BOP 7 M-ALL B Steam Generator Tube Rupture 8 C-BOP B Stuck Open Atmospheric Steam Dump Valve
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SITE: POINT BEACH SEG # PBN LOI NRC 005E SEG TITLE: 2011 ILT NRC EXAM SCENARIO #1 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING #: PBN LOI TPD COURSE: N/A #: N/A TOTAL TIME: 2.0 HOURS Page 2 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
Guide Requirements Malfunctions:
Before EOP Entry:
- 1. 1P-2C Charging Pump failure
- 2. 1LT-471 B S/G Level Transmitter fails high
- 1. B Steam Generator Atmospheric fails open Abnormal Events:
- 1. Steam Generator Tube Leak Major Transients:
- 1. B Steam Generator Tube Rupture Critical Tasks:
- 1. E-2 A: Isolate the faulted steam generator before transition out of EOP-2.
- 2. E-3 A: Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs.
Page 3 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO OVERVIEW:
INITIAL CONDITIONS:
- 1. This scenario can be run from the following Standard (Specific) IC sets:
- IC-95, created from IC-02
- 2. The following equipment is OOS:
- Red dot on G01 alarm windows C02 D 2-5 and 2-6.
- Red dot on P-38A OOS alarm windows C01A 2-8 and 2-10.
SEQUENCE OF EVENTS:
Event 1: Conduct IT-07G Service Water Valves (Quarterly)
- Crew conducts testing on SW-2890 per IST request for increased frequency testing per IT-07G.
Event 2: C Charging Pump fails
- RO starts B Charging Pump and restores PZR Level
- SRO addresses Technical Requirements Manual for failure.
Event 3: B SG Level Transmitter LT-471 fails high
- SRO Addresses Technical Specifications Event 4: Pressurizer Pressure channel PT-431 fails high
- RO identifies malfunction, takes manual control and restores pressure
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
- SRO addresses Technical Specifications Event 5: B Steam Generator Tube Leak
- Crew recognizes tube leak
- SRO enters AOP-3 Steam Generator Tube Leak
- SRO addresses Technical Specifications Event 6: Rapid Power Reduction Unit 1
- SRO enters AOP-17A to reduce power on the unit due to SGTL Event 7: Steam Generator Tube Rupture
- Crew recognizes SGTR and trips the unit
- SRO enters EOP network Event 8: B Steam Generator Atmospheric fails open
- Crew recognizes failed valve and isolates locally Page 5 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
NOTE: Table may be modified as needed to include all scenario time-line items SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS INITIAL CONDITIONS:
Standard IC-95 from IC-02 Unit 1
- Mode: 1
- Burnup: 10,000 MWD/MTU
- Power: 100%
- Boron: 774 ppm (MOL)
- Temperature: NOT
- Pressure: NOP
- Xenon: Equilibrium
- Rods: Bank D @ 220 steps
- Generator: 530 Mwe Unit 2
- Mode: 1
- Burnup: 500 MWD/MTU
- Power: 100%
- Boron: 1280 ppm (BOL)
- Temperature: NOT
- Pressure: NOP
- Xenon: Equilibrium
- Rods: Bank D @ 220 steps
- Generator: 530 Mwe Page 6 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS SIMULATOR SET UP (perform set up per the
Simulator Setup Checklist, including entering
- Protected equipment tags for P-38B, 1P-29, G02, action items per the Simulator Input Summary.) G03, G04 EDGs
- Red dot on alarm windows C02 D 2-5, 2-6 and C01A 2-8 and 2-10.
Simulator Pre-brief:
COMPLETE TURNOVER: Provide students with a copy of IT-07G, Service Water Review applicable current Unit Status Valves (Quarterly) that has been prepared for SW-Review relevant At-Power Risk status 2890 stroke test. Also provide a TS and TS Bases for Review current LCOs not met and Action reference.
Requirements Verify crew performs walk down of control boards and reviews turnover checklists.
Page 7 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 1: Conduct IT-07G SW Valve Stroke Test Crew Crew briefs evolution prior to coming into simulator.
BOP Verifies at least one SW pump operating in South and North headers Communications: TH AO will be contacted to locally SRO/BOP Enters TSAC 3.7.8.C and logs completion of RA verify valve position. Report OPEN or CLOSED to match what the board operator sees.
Strokes SW-2890 and records data.
BOP Review data recorded by BOP and exit TSAC as SRO required per IT-07G.
Communications: If asked, cue that the 4th licensed operator will make the required log entry End of evolution: Proceed to next event at Lead Examiner discretion.
Page 8 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 2: C Charging Pump Fails SRO When C charging pump trips, enter AOP-1D, CVCS Malfunction.
Checks RCS Leak not in progress Continuous action RO (CA)
Communication: When sent out to investigate Charging pump and associated breaker, inform control room Addresses Foldout page and notes.
breaker is tripped on overcurrent and motor is hot to the touch. Determines Chg Pump trip and goes to Step 3.
Check any charging pump running - A should be Communication: If sent to check charging pump relief, running.
wait 2 minutes and report charging reliefs on Unit 1 are NOT lifting Check Charging Flow Stable - Should answer yes.
Check Charging Pump relief not lifted - no indication of lifting relief. May dispatch AO.
Communication: If sent to check a charging pump prior to start and after start report conditions ready for start Check VCT Level - Should be > 17%
and conditions normal after start. Check Charging System response: Should start B Charging Pump and adjust lab seals using CV-142.
SRO May place C charging pump in pullout.
Communication: If requested, OS2 will follow up with OI-35C, 480v Electrical Load Conservation due to 1P-2A Requests DCS Notification.
and 1P-2B Charging Pumps running.
Refers to TRM for Charging Pump requirements (TRM requirements are met with two pumps operable).
End of evolution: Proceed to next event at Lead Examiner discretion.
Page 9 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 3: B S/G Level Transmitter LT-471 fails BOP Identifies the failed instrument by channel indicating high high, S/G level alarms, actual level lowering on the unaffected channels or the feedwater regulating valve going shut.
SRO If the crew is slow to take manual control of the Implements AOP-2B, Feedwater System Malfunction feedwater regulating valve and thus initiates a RO Maintain Reactor Power<100%
manual or auto reactor trip, immediately insert the BOP SGTR. Check Feedwater Regulating Valve response normal.
- No, so take RNO actions and then enter AOP-24 Identify failed instrument.
NOTE: IF asked for guidance, the Shift Manager will Check if failed instrument is controlling, the BOP state OS2 will prepare the required paperwork should determine LT-471 is controlling channel.
per 0-SOP-IC-001 YELLOW to remove LT-471 Establish manual control as desired. BOP takes from service. Prompt OS1 to complete additional actions while OS2 prepares the paperwork.
manual control of B Feedwater Regulating Valve.
Return affected parameters to normal.
NOTE: IF asked for guidance, the Shift Technical Advisor will provide the following logic diagrams Determine if failed instrument affects RTO (LT-471 as referenced in 0-SOP-IC-001-YELLOW page doesnt)
- 18. Sheets #172, #176, and #182. SRO Page 10 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 3 (cont): B S/G Level Transmitter LT-471 SRO 0-SOP-IC-002, Technical Specifications LCO -
fails high Instrument Cross Reference, used to determine applicable Technical Specification requirements.
Which are:
Table 3.3.1-1 item 13 S/G level low-low (TSAC NOTE: IF asked for guidance, the Shift Technical 3.3.1.A&D)
Advisor will provide 0-SOP-IC-002 in its entirety.
Table 3.3.2-1 item 5b S/G level high (TSAC 3.3.2.A&D)
Table 3.3.2-1 item 6b S/G level low-low (TSAC 3.3.2.A&D)
All 3.3.1 & 3.3.2 table items are one hour actions Table 3.3.3-1 item 16 is met, requires only 2 channels End of evolution: Proceed to next event at Lead to be Operable Examiner discretion. The intent is to not have the crew perform the actions to remove the channel from service.
Page 11 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 4: Pressurizer Pressure PT-431 Fails High RO Recognizes PT-431 failing high causing spray valves to open lowering RCS pressure.
If the crew is slow to take manual control of the SRO spray valves and thus initiates a manual or auto Enters AOP 24 for instrument malfunction.
RO reactor trip, immediately insert the SGTR. Identify failed instrument.
Check if failed instrument is controlling, the RO should NOTE: IF asked for guidance, the Shift Manager will determine PT-431 is controlling.
state OS2 will prepare the required paperwork Establish manual control as desired. RO takes manual per 0-SOP-IC-001 BLUE to remove PT-431 from control of HC-431 and controls Pressurizer pressure service. Prompt OS1 to complete additional actions while OS2 prepares the paperwork.
manually.
SRO/BOP Return affected parameters to normal.
NOTE: IF asked for guidance, the Shift Technical Advisor will provide the following logic diagrams Determine if failed instrument affects RTO, which PT-as referenced in 0-SOP-IC-001-BLUE page 24. 431 does not (alternate channels).
Sheets #169, #175, #177, #178, #180 and #181. If RCS pressure gets <2205 PSIG, then LCO 3.4.1 is not met.
Communication: IF OS1 determines the need to enter AOP-21 PPCS Malfunction, The Shift Manager should inform OS1 that OS2 will review AOP-21 and take any necessary actions.
Page 12 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Address the low pressure condition with the ARBs.
Event 4 (cont): Pressurizer Pressure PT-431 RO/BOP Fails High Controlling channel can be changed over per ARB 1C04 1C 1-2 step 6.6.
PORVs and spray controller to manual prior to defeating PT-431 Blue NOTE: IF asked for guidance, the Shift Technical Advisor will provide 0-SOP-IC-002 in its entirety. SRO Return affected parameters to Automatic Address Technical Specifications for PT-431 using 0-SOP-IC-002.
Table 3.3.1-1 item 5 OverTemp Delta T Table 3.3.1-1 item 7a PZR Pressure-Low Table 3.3.1-1 item 7b PZR Pressure-High Table 3.3.2-1 item 1d SI-PZR Pressure-Low Table 3.3.2-1 item 3c CI-Safety Injection (No Action)
Table 3.3.2-1 item 4d-2 SLI-Coincident with SI (No End of evolution: Proceed to next event at Lead Action)
Examiner discretion. The intent is to not have the Table 3.3.2-1 item 4e-2 SLI-Coincident with SI (No crew perform the actions to remove the channel Action) from service.
Table 3.3.2-1 item 5c FI-Safety Injection (No Action)
Table 3.3.2-1 item 6c AFW-Safety Injection (No Action)
Table 3.3.2-1 item 8 SI Block-PZR Pressure Table 3.3.3-1 item 5 RCS Pressure (NR) (No Action)
Table 3.3.5-1 item 2 CREFS Cont. Isolation (No Action)
Page 13 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 5: B Steam Generator Tube Leak RO Announces Unit 1 B Steam Line Radiation High Alarm.
BOP Refers to ARB 1C20 C 2-2 for above alarm and RMSARB for 1RE-232 and addresses RMS server.
SRO Enters AOP-3, Steam Generator Tube Leak.
Addresses Fold Out Page.
RO (CA STEP) Check SI Not Required.
PZR level w/in 10% of Program.
Communication: If surveys are requested for the Subcooling > 30°F.
steam lines, RP can report after 5 minutes that B steam (CA STEP) Check Rx Trip Not Required.
line is slightly above background and A steam line is Rx Critical.
background Chg aligned to VCT.
(CA STEP) Check PZR Level - Stable or trending to program.
Controls charging to maintain level.
Page 14 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 5 (cont): B Steam Generator Tube Leak RO Check PZR Pressure - Stable or trending to program Check Rx Makeup control - proper concentration, armed and in auto.
SRO Notify DCS, Chem and communicate E-plan need to SM.
RO/BOP Identify Leaking SG - uses High Main Steam Line Communications: SM will be asked to notify DCS and implement E-Plan alarm to identify B SG as leaking.
RO Determine Leak Rate - RO should be able to determine leak rate using charging/letdown balance.
Otherwise, SRO requests performance of CAMP 014 SRO from chemistry or OI-55 to determine rate.
Communications: If asked, the SM can let OS1 know Addresses note regarding TS leakage requirement he will take care of limited plant evacuation using EPIP and recognizes violation of TS 3.4.13.
6.1.
Checks RX shutdown required - leakage clearly exceeds 75 GPD and requires a shutdown.
Addresses caution regarding time clock and RMS alarm.
(CA STEP) Determines action based on step 10 of AOP-3.
Leak is > 75GPD and has risen more than 30 GPD over the last hour. Power to be reduced to <50%
in one hour and in MODE 3 in following 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Enters AOP-17A, Rapid Power Reduction.
Page 15 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 6: Rapid Power Reduction Unit 1 SRO Determines desired power level and ramp rate and announces to CR - SRO determines that unit must be
<50% within one hour of receipt of High Radiation Alarm and that the unit is at 100% power.
SRO also determines that the unit needs to be taken off line and could direct BOP to set the endpoint at 0%
on the turbine.
Requests SM to notify PSS.
RO Checks Rod control in Auto.
Selects Rate Reduction method, likely Operator Auto BOP - Impulse IN per the note prior to step 4.
(CA STEP) Commences boration, should refer to NOTE: If excessive ramp rate is selected, crew will RO ROD 1.3 for power reduction boration and rod bank have difficulty maintaining VCT level and may requirements manually trip due to Charging Pump swap over to RWST. (CA STEP) Check PZR Pressure - Stable or trending to program (CA STEP) Check PZR Level - Stable at or trending to program Page 16 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 6 (cont): Rapid Power Reduction Unit 1 BOP (CA STEP) Check SG levels - controlling in Auto RO (CA STEP) Maintain Tavg - Checks Tavg within limits Communication: When requested, TH AO start 1P-99A BOP Check MFW Seal Water Pumps Running - Contacts and B SGFP Seal Water Pumps U1 Turbine Operator to Start 1P-99A and B.
SRO Determines endpoint is MODE 3.
BOP May transfer auxiliary loads.
Per Lead Evaluator, the SGTL malfunction will increase from 0.4 to 7 ramped in over 120 seconds.
The B Steam Generator Atmospheric Dump valve will fail open on reactor trip.
End of evolution: Proceed to next event at Lead Examiner discretion.
Page 17 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7 and 8: B Steam Generator Tube Crew Recognizes increased leak rate and uses fold out Rupture with Atmospheric Dump page/continuous action guidance from AOP-3 to trip Valve failed open the reactor.
RO Inserts Manual Trip to trip the reactor.
RO inserts manual SI and CI also and carries out Immediate Actions of EOP-0.
Verify Reactor Trip - RTBs open, bottom lights all lit, IRPIs on bottom, Flux lowering.
Verify Turbine Trip - Turbine Stop Valves both shut:
Turbine Stop Valves Two Closed Alarm OR Turbine Valves Bistable both lit.
Page 18 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7 and 8: B Steam Generator Tube RO Verify Safeguards Buses - At least one 4160 and one Rupture with Atmospheric Dump 480 V Bus energized.
Valve failed open (contd) Checks voltage on buses and breaker configuration Check if SI is Actuated SI and RHR pumps both running.
RO/SRO Verifies Immediate Action steps.
NOTE: When the crew directs local actions to isolate the B S/G Atmospheric Dump Crew Valve, allow three minutes for AO transit BOP/SRO Addresses Fold Out Page.
and 2 minutes to close the valve. Do not BOP notes the stuck open Atmospheric Dump close the isolation valve until after the crew Valve on the B S/G and isolates feed flow to B has transitioned to EOP-2. If crew starts to S/G per Foldout Page for faulted S/G (while push the AO to hurry up inform them the maintaining at least 200 gpm total AFW flow).
valve is very difficult to operate and you are working on closing it. o P-38B PCV is taken to manual and shut and/or discharge valve to B SG is taken to Manual and Shut. If 1P-29, TDAFW Pump is running, it may be stopped or isolation valve to B SG shut.
Page 19 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7 and 8: B Steam Generator Tube BOP o If the B S/G Atmospheric Dump Valve has not Rupture with Atmospheric Dump been noted, then the crew might maintain AFW Valve failed open (contd) flow to the ruptured B S/G per the Fold Out Page for ruptured S/G as needed in order to get level above 29%.
Performs Attachment A. All conditions normal except for P-38A MDAFW Pump is OOS.
Verifies Secondary Heat Sink - >29% in at least one SG. Adjusts AFW flow to A SG as desired to maintain level.
RO Verify RCP Seal Cooling - Lab seals on both RCPs should be >20.
(CA STEP) Verify RCS Temp Control - RNO actions taken for the uncontrolled cooldown. Ensure not BOP dumping steam.
Lower AFW to A S/G (but ensure at least 200 gpm).
Ensure MSIVs are shut.
Check Normal spray valves both shut.
Check Aux spray valve shut.
Check if RCPs should remain running (they should)
Page 20 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7 and 8: B Steam Generator Tube SRO Direct STA to monitor CSFSTs.
Rupture with Atmospheric Dump Valve failed open (contd) BOP (CA STEP) Verify Containment Sump Recirc not required - RWST level should still be over 90%.
BOP Check if Secondary System is intact - B SG pressures should be noted as lowering uncontrollably.
SRO Transition to EOP-2 Review notes and foldout page information. Crew SRO/RO should determine that the A S/G is available for cooldown.
BOP Check RCS temperature. The RNO directs stop If not previously accomplished, the crew may have dumping steam and control AFW flow.
the B S/G Atmospheric Dump Valve isolated Crew Isolate MSIVs. (will have isolated previously) locally here. If not, then step 7 explicitly checks the valve shut. Determines that 1MS-236, MSIV bypass valve is shut under admin control.
Once isolated, the crew should complete the Check if any S/G NOT faulted. (A is intact).
actions of EOP-2 and transition to EOP-3, although an acceptable alternative is to use EOP-0.0 Rediagnosis to transition to EOP-3.
Page 21 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7 and 8: B Steam Generator Tube Crew Identify faulted S/G. Crew determines B S/G is faulted Rupture with Atmospheric Dump BOP Reset LOFWTT - depresses LOFWTT reset Valve failed open (contd) pushbutton and alarm reset buttons to clear LOFWTT alarm.
BOP Isolate Feedwater to faulted S/G.
CRITICAL TASK: Ensure B FWRV and Bypass Valves are shut E A: Isolate the faulted SG before transition P-38B AFW Pump is stopped and taken to pullout out of EOP-2.
SRO 1AF-4000 TAFP discharge to B S/G and AF-4021 B MDAFP discharge to B S/G taken to manual and shut.
BOP (Unit 2 will be in TSAC 3.7.5.d when placing P-The intent is that the crew has taken actions to 38B in pullout [2 MDAFW Pumps OOS].)
isolate feed to the B S/G prior to shutting the Isolate flow from S/G.
Atmospheric Dump Valve isolation valve. They will then have to decide whether to re-establish feeding Ensure 1MS-2015, B ADV shut - is failed open.
in EOP-3 if level is not >29% by then. Shuts 1MS-2019, TDAFW supply if still open.
Shuts 1MS-5959 and 2045 SGBD isolations if open.
Dispatches AO to shut 1MS-237 and 238 locally, should remind AO that the SG is ruptured and rad levels may be elevated.
Page 22 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7 and 8: B Steam Generator Tube BOP Check CST level.
Rupture with Atmospheric Dump RO Check RMS normal Valve failed open (contd)
BOP/ B SG has indications of a rupture (high radiation, SRO rising level after the atmospheric dump valve is isolated).
Crew Addresses Cautions and notes regarding identification and isolation of ruptured SG, Chem Sampling and Fold Out Page.
Reviews Fold Out Page - None of the items on the Fold Out Page should require action at this time.
RO (CA STEP) Check if RCPs should remain running -
RCPs should remain running.
BOP/RO Identify Ruptured SG - identifies B as ruptured.
Page 23 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7 and 8: B Steam Generator Tube RO/BOP Shut MSIV on ruptured SG - 1MS-2017 is already Rupture with Atmospheric Dump shut.
Valve failed open (contd) BOP Reset Loss of FW Turbine Trip - previously done Minimize Steam Dump from Ruptured SG:
1HC-478 in auto at 1050 Communication: When the PAB AO is contacted, insert 1MS-2015, B ADV shut - is failed open Trigger 14 to shut 1MS-237 and report both valves shut, Shuts 1MS-2019, TDAFW supply - previously shut 1MS-238 is not modeled on Simulator.
1MS-236, MSIV bypass valve - previously addressed BOP Isolate flow from ruptured SG:
1MS-5959 and 2045 SGBD previously addressed.
CRITICAL TASK E3-A: 1MS-237 and 238 isolation valves previously Isolate feedwater flow into, and steam flow from the addressed ruptured SG before a transition to ECA-3.1 occurs.
BOP (CA STEP) Check if Feed Flow to Ruptured SG should be stopped - level in B SG may be >29%,
SRO thus BOP will secure P-38B MDAFW pump (in pullout) and shut AF-4021 and 1AF-4000 to secure feed from MDAFWP and TDAFWP. Should recognize impact on Unit 2 and inform U2 operator of action. (TSAC 3.7.5.D).
Page 24 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7 and 8: B Steam Generator Tube Crew Verify Ruptured SG not needed for cooldown - checks Rupture with Atmospheric Dump A SG available for cooldown and B MSIV shut.
Valve failed open (contd)
Check ruptured SG pressure >430 psig - should be BOP above 430 psig in B SG.
Determine Target Core Exit Temp:
RO/SRO RO reports pressure in ruptured SG, which will vary depending on timing of isolating the Atmospheric Dump Valve. SRO determines target temperature.
Addresses notes prior to step 11 concerning cooldown rate and RCP trip criteria.
Crew Cooldown RCS to Target Temperature BOP Lock in SI Signal - manually actuates SI and CI and trips SI bistables in racks behind control boards. Then SI is reset.
BOP A MSIV is shut, open 1MS-2016 A ADV fully in manual.
RO Check PORVs and Block Valves - PORVs should be shut and block valves open with power.
Check PZR safety valves - Shut.
Page 25 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS BOP (CA STEP) Stabilize intact SG level - direction to Event 7 and 8: B Steam Generator Tube Rupture with Atmospheric Dump maintain SG level 29-65% during cooldown.
Valve failed open (contd)
SRO Addresses caution regarding loss of offsite power.
Reset SI, CI and 1B-03 and 1B-04 Lockouts -
BOP performs resets on rear of C01 panel.
Check 4160 Safeguards buses both energized from offsite - verifies buses energized from 1X04.
Reestablish IA to Containment:
-Starts second IA compressor on C01 Rear.
-Checks IA pressure - should be 100 PSIG.
-Opens IA-3047, listening for click of IA relay and sets timer for reminder to do the same for IA-3048.
RO (CA STEP) Check if RHR pumps should be stopped -
Once action has been taken to start the checks RCS pressure >425 psig and stops both RHR cooldown, the scenario can be terminated at pumps and monitors RCS pressure.
Lead Evaluators discretion.
Page 26 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EOP 0 Attachment A BOP Verify feedwater isolation.
Verify containment isolation.
Verify AFW actuation. Since P-38B is OOS, will ensure that the TDAFWP is running.
Check SI pumps running.
Check RHR pumps running.
Unit 2 will enter TSAC 3.7.8.F when SW-2907 and 2908 are opened. Check only 1 CCW pump running.
Verify Service Water System alignment. BOP should contact the PAB to check 2 local valves.
Verify containment accident cooling.
Check CR ventilation in accident mode.
Communication: When contacted the PAB AO should Check if main steam lines can remain open.
report that SW-LW-61 and 62 radwaste SW isolation valves are both shut. Verify proper SI valve alignment.
Page 27 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS BOP EOP 0 Attachment A (contd) (CA STEP) Verify containment spray not required.
Verify SI flow.
(CA STEP) Check CSR ventilation operating.
(CA STEP) Check AFW Area ventilation operating.
(CA STEP) Check Computer Room ventilation operating.
(CA STEP) Check CWPH temperature.
Communication: When contacted, wait 2 minutes and have the AO report CWPH temperature at 65 F and stable.
When the conditions are stabilized or at discretion of Crew:
lead instructor/evaluator
- No debrief or critique due to this being an End the scenario by placing the simulator in freeze evaluated scenario.
Inform Examinees they are to remain at their stations and cannot discuss the scenario. They are to wait for any follow up questions the examiners may have.
Page 28 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) 1.0 PLANT CONDITIONS:
UNIT 1 UNIT 2 Time in core life 10,000 500 (MWD/MTU):
Reactor power (%): 100% 100%
Boron concentration 774 ppm 1280 ppm (ppm):
Rod height (CBD @): CBD @ 220 CBD @ 220 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:
TSAC Description Reason TSAC 3.7.5.C Restore motor driven AFW pump system P-38A, MDAFP, is Out of S to OPERABLE status within 7 days. of a planned 2 day outage replacement.
3.0 EQUIPMENT OUT OF SERVICE:
- P-38A, MDAFP, is Out of Service in day 1 of a planned 2 day outage for seal replacement.
4.0 PLANNED EVOLUTIONS:
- IT 07G Service Water Valves (Quarterly) will be performed at the start of the shift in order to stroke SW-2890, North SW Hdr Xconn Valve to provide data for increased frequency testing per the IST Engineer. Stroke testing of the other valves (SW-2870 / SW-2869 / SW-2891) and seat flushing is not required. An AO is standing by locally at the valves.
5.0 TURNOVER INFORMATION:
- Safety Monitor is Green.
- G02 EDG is aligned to 1A05 and 2A05 4160 Safeguards busses accordance with OI-35A, Standby Emergency Power Alignment.
Page 29 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
- The plant is under severe weather watch for the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. AOP-13C, Severe Weather Conditions, is in effect.
- Clock time is real time and you have the normal shift complement.
- IT 07G Service Water Valves (Quarterly) has been prepared for partial use with an AO standing by already briefed.
Page 30 of 30
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
Appendix D Scenario Outline Form ES-D-1 Facility: ___Point Beach_____ Scenario No.: __2_____ Op-Test No.: 2011301 Examiners: D. McNeil Operators:
R. Walton D. Reeser Initial Conditions: _ Unit 1 is at 28% reactor power, Chemistry hold per OP-1C, Startup to Power Operation Unit 1, Step 5.120.3 has just been cleared.
Turnover: G01 Emergency Diesel Generator is Out of Service in day 3 of a planned 5 day maintenance outage. G02 Emergency Diesel Generator is aligned to 1A05 and 2A05 in accordance with OI-35A, Standby Emergency Power Alignment. 1P-15B, SI Pump is Out of Service in day 1 of a planned 2 day outage for seal replacement. The plant is under a severe weather watch for the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. AOP-13C, Severe Weather Conditions is in effect.
Shifting of 1P-28A and B SGFPs, for post-maintenance testing, is scheduled to be performed immediately after shift turnover, followed by a load escalation from 28% power to ~47%
power (at 15% per hour) per OP-1C, Startup to Power Operation Unit 1.
Event Malf. Event Event No. No. Type* Description N-BOP 1 Shift Steam Generator Feed Pumps N-SRO R-RO 2 Increase Reactor Power from 28% at the Normal Rate.
N-SRO I-BOP I-SRO Turbine First Stage Pressure Instrument PT-485 Fails 3 Low.
TS-SRO I-RO I-SRO 4 Pressurizer Level Instrument LT-428 Fails Low.
TS-SRO C-RO C-SRO 5 Power Operated Relief Valve 1RC-430 Seat Leakage.
TS-SRO 6 M- ALL Steam Line Break Upstream of the Unit 1 A MSIV.
7 M-ALL Reactor Trip Breakers Fail to Open (ATWS) 8 C-BOP Train A ESF Sequencer Fails to Actuate.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SITE: POINT BEACH SEG # PBN LOI NRC 006E SEG TITLE: 2011 ILT NRC EXAM SCENARIO #2 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING #: PBN LOI TPD COURSE: N/A #: N/A TOTAL TIME: 2.0 HOURS Page 2 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
QUANTITATIVE ATTRIBUTES Malfunctions:
Before EOP Entry:
- 1. 1PT-485 Turbine First Stage Pressure fails low
- 2. 1LT-428 Pressurizer Level transmitter fails Low
- 1. ATWS Reactor Trip Breakers fail to open
- 2. Train A ESF Sequencer fails to operate Abnormal Events:
- 1. Steam Leak upstream A MSIV Major Transients:
- 1. A Steam Line Break Critical Tasks:
- 1. E-2 A Isolate the faulted SG before completion of scenario.
- 2. FR-S.1C: Insert negative reactivity into the core by at least one of the following methods before completing the immediate action steps of CSP-S.1:
- Insert control rods Page 3 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO OVERVIEW:
INITIAL CONDITIONS:
- 1. This scenario can be run from the following Standard (Specific) IC sets:
- IC-96, created from IC-05
- 2. The following equipment is OOS:
- Red dot on G01 alarm windows C02 D 2-5 and 2-6.
- Red dot on alarm window C01 1B 3-5.
SEQUENCE OF EVENTS:
Event 1: Shift S/G Main Feed Pumps
Event 2: Increase power normal rate from 28%
- Crew raises power per OP-1C at 15%/hr rate.
Event 3: Turbine First Stage Pressure Transmitter PT-485 fails Low
- Crew recognizes failure and takes manual control of rods.
- SRO Addresses Technical Specifications Event 4: Pressurizer Level channel LT-428 fails Low
- RO identifies malfunction, takes manual control
- SRO addresses Technical Specifications Page 4 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
- RO restores Letdown per AOP-1D CVCS Malfunction Event 5: Power Operated Relief Valve 1RC-430 Seat Leakage
- Crew recognizes leakage from safety or relief valves
- Crew determines which valve is leaking and isolates it
- Crew recognizes steam leak
- Crew determines plant trip required and SRO enters EOP network Event 7: Reactor Trip Breakers fail to open (ATWS)
- RO recognizes failure of reactor trip breakers in EOP-0
- Crew addresses faulted S/G Event 8: Train A ESF Sequencer fails to actuate
- BOP recognizes failure while implementing Attachment A in CSP-S.1 and starts equipment as directed Page 5 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
NOTE: Table may be modified as needed to include all scenario time-line items SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS INITIAL CONDITIONS:
Standard IC-96 from IC-05 Unit 1
- Mode: 1
- Burnup: 7500 MWD/MTU
- Power: 28%
- Boron: 1099 ppm (MOL)
- Temperature: NOT
- Pressure: NOP
- Xenon: Equilibrium
- Rods: Bank D @ 167 steps
- Generator: 145 Mwe Unit 2
- Mode: 1
- Burnup: 14960 MWD/MTU
- Power: 100%
- Boron: 16 ppm (EOL)
- Temperature: NOT
- Pressure: NOP
- Xenon: Equilibrium
- Rods: Bank D @ 220 steps
- Generator: 530 Mwe Page 6 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS SIMULATOR SET UP (perform set up per the Simulator
Setup Checklist, including entering action items per the Simulator Input Summary.)
- Red dot on alarm windows C02 D 2-5, 2-6 and C01 1B 3-5.
- Ensure PPCS Blowdown adjustments are set to 10/10 prior to starting Simulator Pre-brief:
COMPLETE TURNOVER:
Review applicable current Unit Status Review relevant At-Power Risk status Review current LCOs not met and Action Requirements Verify crew performs walk down of control boards and reviews turnover checklists.
Page 7 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 1: Shift S/G Main Feed Pumps Crew Crew briefs evolution per OP-13A prior to evolution Shifts SGFPs per OP-13A to complete PMT run Communications: TH AO will be contacted to locally check status of SGFPs prior to start and ensure all personnel are clear.
Communications: TH AO may be contacted to look at the mini-recirc valve for the B SGFP. If asked the valve went full open and is currently (insert current status).
End of evolution: Proceed to next event at Lead Examiner discretion.
Event 2: Increase power normal rate from 28% Crew Briefing on power ascension may be performed in classroom prior to beginning of the scenario Withdraws rods and/or Dilute in addition to adjusting NOTE: If asked S/G B/B is 15/15 Klbs/SG through the RO steam demand as needed to establish power increase HXs.
End of evolution: Proceed to next event at Lead Examiner discretion.
Page 8 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 3: Turbine First Stage Pressure RO Identifies inward rod motion, recommends placing rod Transmitter PT-485 fails Low control in Manual SRO Concurs with recommendation, directs placing rods in Manual and enters AOP-6C, Uncontrolled Rod Motion (preferred) (May also enter AOP-24)
RO Check Rod Motion Required NOTE: IF asked for guidance, the Shift Technical Advisor (CA STEP) Maintain RCS Tavg - checks Tavg within will provide the following logic diagrams as allowed band referenced in 0-SOP-IC-001-WHITE page 38.
Sheets #172, #174, #178 and #179. Check RCS Tavg at or Trending to Tref - Tref will need to be calculated by the RO. RO should determine that Tavg is lower than Tref and needs to withdraw rods to restore Tavg to program Check Control Rods - Above Minimum Insertion Limit.
RO/SRO Determines rods are well above minimum insertion NOTE: IF asked for guidance, the Shift Technical Advisor limit will provide 0-SOP-IC-002 in its entirety. Verify AFD within limit - Checks DFMOOB Clear.
RO Alarm should be clear. This is a continuous action step which may come into play as rods are driven to stabilize Tavg SRO Check Rod Motion due to Instrument Malfunction. Go to AOP-24 Page 9 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS AOP 24 action:
Turbine First Stage Pressure Transmitter PT-485 fails Low (contd) Identify failed instrument BOP BOP/RO Check if failed instrument is controlling, the BOP should determine PT-485 is controlling Establish manual control as desired. RO takes manual RO control of rods Return affected parameters to normal Determine if failed instrument affects RTO - does not SRO Remove instrument from service per 0-SOP-IC-001 Communication: IF OS1 determines the need to enter AOP-21 PPCS Malfunction, The Shift Manager should inform OS1 that OS2 will review AOP-21 and take any Address Technical Specifications necessary actions. Table 3.3.1-1 item 17b Turbine Impulse Pressure P-7 End of evolution: Proceed to next event at Lead Examiner discretion.
Page 10 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 4: Pressurizer Level channel LT-428 fails RO Acknowledges PZR High/Lo Level alarm and informs Low Crew. RO recommends going to minimum charging due to loss of Letdown RO/BOP address the ARBs for alarms associated RO/BOP with the PZR Level failure NOTE: AOP-1D gives guidance on stabilizing plant Directs entry into AOP-1D CVCS Malfunction or AOP-with loss of Letdown as well as restoring it. SRO 24 Instrument Failure AOP-24 gives generic guidance to take manual control as needed for the failure. The AOP 24 action:
ARB guidance (ARB 1C04 1C 1-3) is used to DEFEAT Blue LT-428 so Letdown can be Identify failed instrument RO restored as well as Automatic Charging. Check if failed instrument is controlling, the RO should determine LT-428 is controlling Establish manual control as desired. RO takes manual Communication: IF asked for guidance, the Shift control of charging Manager will state OS2 will prepare the required paperwork per 0-SOP-IC-001 BLUE to remove LT-428 Return affected parameters to normal from service. Prompt OS1 to complete additional actions Determine if failed instrument affects RTO, which LT-while OS2 prepares the paperwork. 428 does not Communication: IF OS1 determines the need to enter Remove instrument from service per 0-SOP-IC-001 AOP-21 PPCS Malfunction, The Shift Manager should inform OS1 that OS2 will review AOP-21 and take any necessary actions.
Page 11 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 4: Pressurizer Level channel LT-428 fails RO/BOP Address the level condition with the ARBs.
Low (contd) - Controlling channel can be changed over per ARB to return affected parameters to Automatic NOTE: IF asked for guidance, the Shift Technical Advisor AOP-1D actions:
SRO will provide the following logic diagrams as (CA STEP) Check RCS Leak NOT in progress referenced in 0-SOP-IC-001-BLUE page 16. RO Sheets #175, #180, and #181. Determine CVCS Malfunction - Loss of Letdown go to SRO Step 48 NOTE: AOP-1D gives guidance on stabilizing plant Reduce charging to minimum with loss of Letdown as well as restoring it. RO AOP-24 gives generic guidance to take Check if Letdown can be restored - yes, see next Crew page manual control as needed for the failure. The ARB guidance (ARB 1C04 1C 1-3) is used to SRO Address Technical Specifications for LT-428 using DEFEAT Blue LT-428 so Letdown can be 0-SOP-IC-002 restored as well as Automatic Charging TSAC 3.3.1.A enter table 3.3.1-1 item 8 immediately.
Take LT-428 to trip within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 3.3.1.K TSAC 3.3.3 PAM may be referenced, only 2 PZR level NOTE: IF asked for guidance, the Shift Technical Advisor transmitters are required. (no action needed) will provide 0-SOP-IC-002 in its entirety.
Intent is to NOT take the instrument OOS per 0-SOP-IC-001-Blue, shift to auto control per ARB is desired.
Page 12 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 4: Pressurizer Level channel LT-428 fails Check if Letdown restoration can be performed Crew Low (contd )
RO Ensure Letdown Orifice isolation valves - SHUT Ensure Normal Charging In-Service Check PZR Level >20%
Establish Letdown
- Open Letdown CI valves NOTE: If asked, the Shift Manager will direct the Crew to establish Charging back to automatic. This
- Ensure CCW cooling established based on scenario timing.
- Ensure at least 20 GPM charging
- Establish Letdown NOTE: If asked, the Shift Manager will NOT ask that Check PZR Level at program Level Letdown be restored but will give direction to restore letdown if given the choice between that SRO Inform DCS or removing an instrument from service.
Return to Procedure Step in Effect End of evolution: Proceed to next event at Lead Examiner discretion.
Page 13 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 5: Power Operated Relief Valve 1RC-430 RO RO acknowledges high temperature alarm for the Seat Leakage Safety and PORV tailpipes. (1C04 1C 1-4)
RO determines the high temperature is from the PORVs using board meters RO Determines RCS leak rate Crew Crew determines which PORV is leaking and isolates per ARB (1C04 1C 1-4) or AOP-1A Reactor Coolant Leak NOTE: If asked, the Shift Manager will direct completion SRO SRO addresses Technical Specifications for RCS of ARB actions to determine which PORV is leaking. leakage - Identified LCO 3.4.13 RCS Leakage NOT met due to >10 GPM IDENTIFIED RCS leakage going to the PRT SRO should determine entry into TSAC 3.4.13.A is required End of evolution: Proceed to next event at Lead Required Action A.1 Reduce LEAKAGE to within limits Examiner discretion. (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
Page 14 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 6: Steam Line break upstream Unit 1 A Crew Crew determines leakage into containment is MSIV Secondary vice Primary SRO Enter AOP-2A Secondary Coolant Leak NOTE: Exceeding 1 psig inside containment exceeds BOP (CA STEP) Determine Secondary leakage Not parametric value, TS lists 2 psig as the max Hazardous to Personnel or Equipment pressure before not meeting LCO 3.6.4 and the RO need to enter a TSAC. (CA STEP) Maintain Plant Within Limits (CA STEP) Maintain RCS Tavg Crew Crew determines CA Step 1 applies and attempts to trip the Unit Page 15 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7: Reactor Trip Breakers fail to open RO Attempts to trip reactor using 1C04 pushbuttons.
(ATWS) Attempts to trip reactor using C01 pushbuttons Directs BOP to deenergize 1B01 and 1B02 Deenergizes 1B01. 1B02 will not deenergize BOP Announces entry into CSP-S.1 and begins driving RO control rods in Directs BOP to trip turbine manually CRITICAL TASK: Insert Negative Reactivity into Announces ATWS and contacts AO to go to Unit 1 the core before completing Immediate Action Crew Rod Drive Room Steps of CSP-S.1 Trips turbine manually, verifies turbine tripped BOP Communication: When the TH AO is contacted to locally Addresses Fold Out Page SRO open the trip breakers it will take 2 minutes to transit to the Verifies AFW actuation: checks both MDAFW pumps Rod Drive Room. If the ATWS is announced over the BOP running, checks TDAFW pump running if SG levels gaitronics the TH AO will report to the Rod Drive Room in <25% [57%]
2 minutes.
Aligns Charging suction to RWST: Open 1CV-112B, Closes 1CV-112C Establishes Emergency Boration: Establish Max Charging, Start BATP, Open 1CV-350, Emergency Borate Valve Page 16 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Reactor Trip Breakers fail to open (ATWS) RO/BOP Check SI Actuated: IF SI actuates during CSP-S.1, (contd) BOP will perform Attachment A as time permits (see event 9 for details)
Check PZR Pressure: <2335 Check RTBs open and Turbine Tripped: if AO has not yet been dispatched to Rod Drive Room, step will prompt crew to do so. Turbine should have been tripped at step 2 (CA STEP) Stabilize Intact S/G Level which is B S/G RO/BOP should check dilution flowpaths in the Control Room and may dispatch the PAB AO to check the others on the list Checks RCS Cold Leg > 543ºF. If Cold Leg Temp is <
Communications: If PAB AO contacted to locally verify 543ºF, will stop any steam dumping in progress dilution flowpaths, wait 2 minutes and report dilution flowpaths isolated. Crew should determine that an uncontrolled cooldown IS in progress and proceed to isolate A S/G Crew Isolate Both Main Steam Lines Identify Faulted S/G - A was previously faulted RO/BOP Page 17 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Reactor Trip Breakers fail to open (ATWS) RO/BOP Reset Loss of Feedwater Turbine Trip (contd)
Isolate Feed to Faulted S/G - Actions should be taken for the A S/G only Critical Task: E-2 A Isolate the faulted SG before completion of scenario. Isolate Flow from Faulted S/G - Actions should be taken for A S/G only Check Core Exit TCs and determines they are well under 1200°F Communications: When the PAB AO is contacted to locally shut 1MS-235 Radwaste Steam Isolation and 1MS- Crew determines that the RTBs are now open and 228 MSIV Upstream trap insert Trigger 14. Report both power is lowering as expected valves as closed 2 minutes after being directed. (1MS-228 is not modeled on the simulator)
(CA STEP) Stops Boration since all rods are inserted SRO Transitions back to Step 1 of EOP-0 Crew Complete Immediate Actions of EOP-0 Scenario may be terminated at Lead Evaluators discretion any time after transition back to EOP-0.
Page 18 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 8: Train A ESF Sequencer fails to actuate BOP Actions to start Train A equipment can be initiated after Immediate Actions are taken AND verified. Crew will try to manually actuate SI with no success. Each piece of equipment in Train A will be manually started per CSP-S.1 Attachment A (see next page for event response).
Page 19 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS CSP-S.1 Attachment A BOP Verify Safeguards Busses Energized Verify feedwater isolation Verify containment isolation Check SI pumps running-No manually start A pump Check RHR pumps running-No manually start A pump Check only 1 CCW pump running Verify Service Water System alignment. BOP should Communication: When contacted the PAB AO should contact the PAB to check 2 local valves report that SW-LW-61 and 62 radwaste SW isolation valves are both shut. Verify containment accident cooling-No start fans Check CR ventilation in accident mode Check if main steam lines can remain open. -No (CA STEP) Verify containment spray not required -
Yes take actions to single up trains (CA STEP) Check 4160 Safeguards Busses BOTH energized by Offsite Power Page 20 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS When the conditions are stabilized or at discretion of lead Crew:
instructor/evaluator
- No debrief or critique due to this being an End the scenario by placing the simulator in freeze evaluated scenario.
Inform Examinees they are to remain at their stations and cannot discuss the scenario. They are to wait for any follow up questions the examiners may have.
Page 21 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) 1.0 PLANT CONDITIONS:
UNIT 1 UNIT 2 Time in core life 7500 14960 (MWD/MTU):
Reactor power (%): 28% 100%
Boron concentration 1099 ppm 16 ppm (ppm):
Rod height (CBD @): CBD @ 167 CBD @ 220 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:
TSAC Description Reason TSAC 3.5.2.A One ECCS A.1 Restore train to OPERABLE status within Seal replacement train inoperable 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 3.0 EQUIPMENT OUT OF SERVICE:
- G01 EDG is in day 3 of a planned 5 day maintenance outage.
- 1P-15B Safety Injection Pump is in day 1 of a 2 day planned maintenance outage for seal replacement.
4.0 PLANNED EVOLUTIONS:
- Immediately following turnover you are to shift Main Feed Pumps on Unit 1 for Post Maintenance Testing (PMT) per OP-13A Secondary System Startup Step 5.17. There is an AO standing by and already briefed on the evolution.
- Following the shifting of Main Feed Pumps you are to continue with the load escalation (at 15% per hour) to approximately 47% per OP-1C Startup to Power Operation Unit 1 starting with Step 5.123. TH and PAB AOs have been briefed on their responsibilities per Step 5.122.
5.0 TURNOVER INFORMATION:
- Safety Monitor is Green.
- G02 EDG is aligned to 1A05 and 2A05 4160 Safeguards busses in accordance with OI-35A, Standby Emergency Power Alignment.
- G02, G03 and G04 EDGs are protected equipment.
- 1P-15A Safety Injection Pump is protected equipment.
Page 22 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
- There is a severe thunderstorm watch for the area for the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. AOP-13C, Severe Weather Conditions, is in effect.
- Unit 1 rods are in AUTO and Xenon is stable.
- Unit 1 was is in a 28% chemistry hold for sulfates per NP 3.2.3 Secondary Water Chemistry.
- P-41 Common Vacuum Priming Pump is aligned to Unit 1. Waterbox levels are low in the sightglass and the AOs are monitoring them.
- Clock time is real time and you have the normal shift complement.
Page 23 of 23
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
Facility: Point Beach Nuclear Station Scenario No.: 3 Op-Test No.: 2011301 Examiners: D. McNeil Operators:
R. Walton D. Reeser Initial Conditions: Unit 1 is at 49% reactor power, both trains of Feed and Condensate are running per OP-1C, Startup to Power Operation Unit 1.
Turnover: G01 Emergency Diesel Generator is Out of Service in day 3 of a planned 5 day maintenance outage. G02 Emergency Diesel Generator is aligned to 1A05 and 2A05 in accordance with OI-35A, Standby Emergency Power Alignment. P-38B, MDAFW Pump is Out of Service in day 1 of a planned 2 day outage for seal replacement. The plant is under a severe weather watch for the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. AOP-13C, Severe Weather Conditions is in effect. Load escalation from 49% power to ~74% power (at 15% per hour) per OP-1C, Startup to Power Operation Unit 1, is scheduled to be performed immediately after shift turnover.
Event Malf. Event Event No. No. Type* Description R-RO N-SRO Normal Up-Power 1 N-BOP I-RO I-SRO Thot Instrument TE-401A Fails High 2 TS-SRO C-BOP A CCW Pump Shaft Seizes w/Failure of B CCW Pump to Auto C-SRO Start 3 TS-SRO I-BOP Controlling SG Pressure Channel PT-478 Fails High I-SRO 4 TS-SRO C-BOP 1A05 4160 Safeguards Bus Feeder Breaker trip 5 C-SRO C-RO Small RCS Leak in A RCS Loop Degrading to Large Break 6 C-SRO 7 M-ALL Large Break LOCA 8 I-BOP Failure of SI to Auto-Actuate 9 C-BOP Failure of Containment Accident Fan W-1A1 to Auto-Start 10 C-BOP Failure of SI-852A to Auto-Open
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SITE: POINT BEACH SEG # PBN LOI NRC 007E SEG TITLE: 2011 ILT NRC EXAM SCENARIO #3 REV. # 0 PROGRAM: INITIAL LICENSE TRAINING #: PBN LOI TPD COURSE: N/A #: N/A TOTAL TIME: 2.0 HOURS Page 2 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
QUANTITATIVE ATTRIBUTES (Use this form for Evaluations only.)
Malfunctions:
Before EOP Entry:
- 1. 1TE-401A Thot instrument fails High
- 4. Loss of 1A05 4160 Safeguards Bus Feeder Breaker After EOP Entry:
- 1. Failure of Safety Injection to Auto initiate
- 2. Failure of 1W1A1 Accident Fan to Auto start
- 3. Failure of 1SI-852A to Auto open Abnormal Events:
- 1. Small RCS leak Major Transients:
- 1. Large Break LOCA Critical Tasks:
- 1. E0-D Manually actuate at least one train of SIS-actuated safeguards before transition out of EOP-0
- 2. ES-1.3-A Transfer to cold leg recirculation by establishing an ECCS flowpath prior to depleting the RWST (9%)
Page 3 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO OVERVIEW:
INITIAL CONDITIONS:
- 1. This scenario can be run from the following Standard (Specific) IC sets:
- IC-97, created from IC-04
- 2. The following equipment is OOS:
- Red dot on G01 alarm windows C02 D 2-5 and 2-6.
- Red dot on P-38A OOS alarm windows C01A 2-8 and 2-10.
SEQUENCE OF EVENTS:
Event 1: Normal Up-Power
- Crew raises power 15%/hr per OP-1C Startup to Power Operation Event 2: TE-401A Thot fails High
- Crew responds to malfunction and places Rods/Charging/Condenser Steam Dumps in manual
- SRO addresses Technical Specifications Event 3: Running CCW Pump Shaft Seizure with failure of Standby CCW Pump to Auto start.
- Crew recognizes failure and manually starts Standby CCW Pump
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
- SRO addresses Technical Specifications Event 5: 1A05 4160 Safeguards Bus Feeder Breaker trips
- Crew identifies loss of safeguards bus
- Crew identifies and quantifies the RCS leak
- SRO enters AOP-1A Reactor Coolant Leak
- Crew recognizes leakage is much worse and plant trips
- SRO enters EOP-0 Reactor Trip or Safety Injection Event 8: Failure of Safety Injection to Auto Initiate
- Crew recognizes failure and manually initiates SI and CI Event 9: Failure of 1W-1A1 Accident Fan to Auto start
- BOP recognizes failure and manually opens valve Page 5 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
NOTE: Table may be modified as needed to include all scenario time-line items SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS INITIAL CONDITIONS:
Standard IC-97 from IC-04 Unit 1
- Mode: 1
- Burnup: 800 MWD/MTU
- Power: 49%
- Boron: 1594 ppm (BOL)
- Temperature: NOT
- Pressure: NOP
- Xenon: Equilibrium
- Rods: Bank D @ 187 steps
- Generator: 260 Mwe Unit 2
- Mode: 1
- Burnup: 8800 MWD/MTU
- Power: 100%
- Boron: 696 ppm (EOL)
- Temperature: NOT
- Pressure: NOP
- Xenon: Equilibrium
- Rods: Bank D @ 220 steps
- Generator: 530 Mwe Page 6 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS SIMULATOR SET UP (perform set up per the Simulator
Setup Checklist, including entering action items per the Simulator Input Summary.)
- Red dot on alarm windows C02 D 2-5, 2-6 and C01A 2-8 and 2-10.
- Ensure PPCS Blowdown adjustments are set at 10/10 Simulator Pre-brief:
COMPLETE TURNOVER:
Review applicable current Unit Status Review relevant At-Power Risk status Review current LCOs not met and Action Requirements Verify crew performs walk down of control boards and reviews turnover checklists.
Event 1: Normal Up-Power from 49% Crew Briefing on power ascension may be performed in classroom prior to beginning of the scenario.
RO/BOP Withdraws rods and/or Dilute in addition to adjusting steam demand as needed to establish power increase of 15%/hr.
End of evolution: Proceed to next event at Lead Examiner discretion.
Page 7 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 2: TE-401A Thot fails High RO Recognizes instrument failure for the Red channel Thot. Recommends placing rods to MANUAL.
SRO SRO acknowledged recommendation and alarms.
Communications: SM may be requested to contact I&C Enter AOP 6C for uncontrolled rod motion.
to troubleshoot and repair TE-401A.
Check rod motion required - take rods to manual RO (CA STEP) Maintain RCS Tave Communications: If requested by OS1 inform them OS2 Check RCS Tave at or trending to program - Crew will be preparing the 0-SOP-IC-001 RED to remove 1TE- should discuss current temperature and a plan on how 401A from service. to restore it.
Charging may be taken to manual. With the unit at a reduced power program level will be raised to the full RO power setting based on the circuit selecting NOTE: IF asked for guidance, the Shift Technical Advisor will provide the following logic diagrams as auctioneered high Tave.
referenced in 0-SOP-IC-001-RED page 12.
Sheets #177, #179 and #180. BOP Condenser Steam Dumps may be shifted to steam pressure control mode per Alarm Response Procedure actions. (1C03 1E2 4-2)
RO Check control rods above insertion limits NOTE: IF asked for guidance, the Shift Technical Advisor (CA STEP) Verify AFD within limits will provide 0-SOP-IC-002 in its entirety.
Page 8 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS T-401A, Red Thot Fails High (contd) RO Check rod motion due to instrument failure SRO Enter AOP-24 Response to Instrument Malfunction.
Identify failed instrument Check if failed instrument is controlling channel Establish manual control as required NOTE: IF SRO determines the need to enter AOP-21 Return affected parameters to desired values PPCS Malfunction, The Shift Manager should SRO Using Attachment A verify failed instrument does not inform OS1 that OS2 will review AOP-21 and take any necessary actions.
affect PPCS RTO Remove failed instrument from service per 0-SOP-IC-001-RED SRO Review Technical Specifications. LCO 3.3.1 Instrumentation Table 3.3.1-1 items 5 and 6.
NOTE: Intent is to NOT take the instrument out of service LCO 3.3.2 ESFAS Instrumentation Table 3.3.2-1 item per 0-SOP-IC 001 RED.
4d-3.
End of evolution: Proceed to next event at Lead Examiner discretion.
Page 9 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 3: Running CCW Pump Shaft Seizure with BOP BOP identifies the A CCW Pump failure with the B failure of Standby CCW Pump to Auto CCW Pump not auto starting. BOP requests from the start. SRO to start B CCW Pump manually. (1C03 1D 2-6)
BOP or RO address ARBs as applicable.
SRO Communications: If asked, the PAB AO reports the A Enter AOP 9B CCW malfunction to address the lost CCW Pump inboard motor bearing is hot to the touch. CCW Pump. BOP will verify adequate tank level and start 1P-11B CCW Pump.
Crew will address surge tank level which will require Communications: If asked, the PAB AO will report no action.
nothing unusual with the B CCW Pump discharge pressure indicator, it reads 125 psig locally. Crew will address system leakage requiring no action.
Chemistry will be requested to analyze CCW.
Communications: If asked, the TH AO will report the A SRO OS1 will ask the SM to call DCS and Emergency Plan.
CCW Pump breaker has tripped on overcurrent.
Send AOs out locally to the pump/breaker and discharge pressure indicator to find any problems.
BOP/RO NOTE: Crew may elect to place 1P-11A in pullout to clear Motor Breaker Trip alarm. Address LCO 3.7.7 CCW and enter 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> TSAC 3.7.7.A SRO End of evolution: Proceed to next event at Lead Examiner discretion.
Page 10 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 4: SG Pressure channel PT-478 fails High BOP Determine PT-478 has failed high and respond to alarms.
Communications: SM may be requested to contact I&C BOP takes manual control of B MFRV and manually to troubleshoot and repair PT-478. closes B S/G Atmospheric Dump valve.
SRO Enter AOP-24 for instrument malfunction.
BOP Communications: If requested by OS1, SM agrees to let Identify failed instrument Crew take B FRV to auto per ARB guidance by shifting Check if failed instrument is controlling controlling feed flow channels (1C03 1E2 3-5).
Establish manual control as required. - B MFRV to manual and B S/G Atm Stm Dump to manual/closed Communications: If requested by OS1 inform them OS2 will be preparing the 0-SOP-IC-001 BLUE to remove 1PT-Return affected parameters to desired values. - B 478 from service. SRO MFRV may be placed back in auto if ARB guidance is used to swap controlling feed flow channels. Alarm will not be in due to the low power but guidance could still NOTE: Crew may enter AOP-2B Feedwater System be used. (1C03 1E2 3-5)
Malfunction to address feed systems issues. (see Using Attachment A determine if PPCS RTO is next page for actions) affected. - RTO not affected.
Remove instrument per 0-SOP-IC-001 - BLUE.
NOTE: IF SRO determines the need to enter AOP-21 Intent is to NOT take the instrument out of service per PPCS Malfunction, The Shift Manager should 0-SOP-IC 001 BLUE.
inform OS1 that OS2 will review AOP-21 and take any necessary actions.
Page 11 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 4: SG Pressure channel PT-478 fails High SRO Review 0-SOP-IC-002 Technical Specification LCO-(contd) Instruments Cross Reference.
Table 3.3.1-1 item 14-2 SF/FF Mismatch Table 3.3.2-1 item 1e SI-Steam Line Pressure-Low Table 3.3.2-1 item 3c CI-Safety Injection (no action)
NOTE: IF asked for guidance, the Shift Technical Advisor Table 3.3.2-1 item 4d-2 SLI-Coincident with SI will provide the following logic diagrams as Table 3.3.2-1 item 4e-2 SLI-Coincident with SI referenced in 0-SOP-IC-001-BLUE page 20 and Table 3.3.2-1 item 5c FI-Safety Injection (no action)
- 28. Sheets #169, #172, #176, and #179. Table 3.3.2-1 item 6c AFW-Safety Injection (no action)
Table 3.3.3-1 item 17 SG Pressure (no action)
Table 3.3.5-1 item 2 CREFS Cont. Isolation (no action)
RO NOTE: IF asked for guidance, the Shift Technical Advisor will provide 0-SOP-IC-002 in its entirety. BOP AOP-2B Feedwater System Malfunction steps:
Maintain Reactor Power<100%
Check Feedwater Regulating Valve response normal. - No, End of evolution: Proceed to next event at Lead so take RNO actions and then enter AOP-24 Examiner discretion.
Page 12 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 5: 1A05 Safeguards Bus Feeder Breaker BOP Responds to alarms on panel C02 and informs crew Trip (1A52-57) there was a loss of 1A05 with EDG G02 loading on the bus.
SRO Enters AOP-18A to restore equipment BOP Check 1A05 energized (CA STEP) Monitor EDG voltage and frequency Check Bus 1B03 energized BOP/RO Communications: If TH AO requested, inform the crew Check MCC 1B-32 energized that EDG G02 is operating normally and 1A05 feeder breaker is open with no abnormal indications. Check blender operation on both units SRO Check RHR required - No go to step 8 BOP Check CCW pumps at least one operating Communications: Unit 2 CO (Instructor) will be asked to Check CCW flow less than 3650 gpm verify blender operations for the BA Transfer Pump. 2P-4A BA Transfer pump has no power and 2P-4B will have to Check only 1 CCW pump operating be placed in Auto. Check SW Header pressure > 40 psig Check one IA compressor running Page 13 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS 1A05 Safeguards Bus Feeder Breaker Trip RO Verify Charging Flow (contd) Check if Letdown should be established BOP Check control room fans armed - W14A will have to be reset Communications: PAB AO will get asked to reset W14A Check control room ventilation in mode 1 - No Unit 2 breaker 1B52-329B. Insert LOA and report back fan has OS and 4th License will take care of this been reset. RO Check rod control in auto SRO SM make notifications and TSAC entries BOP Restart containment accident fans as necessary Communications: Unit 2 OS and the 4th License will align Control Room ventilation to Mode 1 per 0-SOP-VNCR- Restore battery chargers 002. Reenergize MCC 1B-31 Restore PAB ventilation End of evolution: Proceed to next event at Lead Examiner discretion after Battery Charger restoration.
Page 14 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 6: Small RCS leak in A loop RTD Manifold CREW Identifies RMS trends, lowering VCT level and Sump A rising which indicates an RCS leak.
Enter AOP 1A RCS leak to stabilize plant parameters.
RO controls charging as needed to determine an RCS RO leak rate.
The Crew must differentiate between a primary and secondary leak. (CA STEP) Check SI not required. Crew should not SI, leak is small.
(CA STEP) Check reactor trip not required. Crew should not trip, leak is small.
(CA STEP) Check PZR level. RO should take control of charging to restore and maintain Pressurizer level.
Letdown isolation should not be needed.
Check Pressurizer pressure. RO should have to take SRO no action for this step.
Determines LCO 3.4.13 is not met and TSAC 3.4.13.A is entered with 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to reduce leakage.
Page 15 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Small RCS leak in A loop RTD Manifold (contd) RO Check make up controls set at desired value SRO OS1 should ask the SM to notify DCS and implement Communications: Shift Manager will be asked to notify Emergency plan DCS and implement E-Plan Steps 7 through 18 in AOP-1A are diagnostic and can NOTE: Steps 7 through 18 are diagnostic and be performed in any order as the SRO determines.
may be performed in any order.
End of evolution: Proceed to next event at Lead Examiner discretion.
Page 16 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 7: Large Break LOCA RO If there is time determine RCS leak has gotten worse and plant trip is required. Recommend trip of the unit with manual SI/CI per continuous action step 1 of AOP RO should perform EOP 0 immediate actions and verify them with the SRO. RO should perform RNO for step 4 IAs with no SI and Auto signal present -
perform manual SI and CI CREW When reviewing foldout page criteria the crew should determine RCPs need to be tripped and adverse containment conditions exist. - SI pump should be manually started with injection verified prior to RCP securing SRO Direct EOP 0 Attachment A to be completed Verify secondary heat sink RO Verify RCP Lab seal D/P Page 17 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Large Break LOCA (contd) RO (CA STEP) Verify RCS temperature control.
Check PORVs shut.
Check Spray valves shut.
Check if RCPs should remain running. RCPs should have been secured per foldout page criteria, if not they should be secured here.
Communications: STA will be asked to commence monitoring Status Trees, acknowledge request.
Start monitoring CSFSTs. SRO should direct the STA to perform this function.
SRO (CA STEP) Verify containment sump recirc not required.
NOTE: CSP-P.1 will be identified as requiring entry RO Transition to EOP 1.3 containment sump recirc.
by the STA. Depending on the timing of the notification; the Crew may or may not Reset SI transition to CSP-P.1. If they do transition prior to transition to EOP 1.3, step 1 of CSP- SRO P.1 sends them back to procedure step in BOP effect.
Page 18 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Large Break LOCA (contd) SRO Check RCS break size - stay in EOP 1.3 BOP Check if containment sump pH should be adjusted.
BOP Check if train A SI flow should be stopped. - stop train A ECCS system- go to step 6 RO (CA STEP) Monitor Core Cooling Communication: PAB AO will be contacted to complete BOP Attachment A of EOP 1.3 Transfer to Containment Sump Direct PAB operator to perform Attachment A Recirc. Acknowledge request. No follow up report is RO/BOP Direct unnecessary personnel to evacuate the PAB required because the attachment will not be complete BOP prior to the end of the scenario. Check Control Room fans armed RO/BOP Isolate CCW to containment Isolate CCW to NRHX Check SW Pumps 6 running Check SW header a continuous flowpath Establish CCW to RHR HXs Ensure Core Deluge valves are open Page 19 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Large Break LOCA (contd) RO/BOP Align SI test lines for recirc Align RHR pump suction valves Communication: PAB AO will be contacted to complete step 16.b in EOP 1.3 to locally shut both SI test line return Check Train A ready for recirculation - yes isolation valves. Acknowledge report, wait 2 minutes and Check Train B ready for recirculation -yes then insert trigger 12. Report when valves are shut.
Check at least 1 train ready for recirculation - yes SRO Note reference for other procedures are now applicable that do not interfere with EOP 1.3 Critical Task ES-1.3-A Transfer to cold leg Check RWST level < 34%
BOP recirculation by establishing an ECCS flowpath prior to depleting the RWST (9%)
NOTE: Crew may have to transition to CSP-P.1 if not done earlier and stop after step 1. The next transition that should occur is procedure step in effect which is EOP-0 Step 14.
End of scenario: Lead Evaluator can end evaluation any time after sump recirc line up is established and crew is waiting for RWST level to reach 34%.
Page 20 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS Event 8: Failure of Safety Injection to Auto Initiate BOP Determine that SI did not auto actuate. Action should be taken during immediate actions step 4 RNO.
Critical Task E0-D Manually actuate at least one SI can also be actuated per OM 3.7 which allows train of SIS-actuated safeguards before transition taking action if auto actions have failed or attachment out of EOP-0 A of EOP 0 will actuate SI.
Event 9: Failure of 1W-1A1 Accident Fan to Auto BOP Determine that 1W-1A1 Accident Fan did not auto start start. Action should not be taken to manually start the fan until after immediate actions are completed and Communication: If an AO is requested to locally check verified.
the fan breaker report there is nothing abnormal from the This fan can be started per OM 3.7 which allows field. taking action if auto actions have failed or attachment A of EOP 0 will check this fan in operation.
Event 10: Failure of 1SI-852A to Auto Open BOP Determine that 1SI-852A core deluge did not auto open. Action should not be taken to manually open the Communication: If an AO is requested to locally check valve until after immediate actions are completed and the valve breaker report there is nothing abnormal from verified.
the field. This valve can be opened per OM 3.7 which allows taking action if auto actions have failed or attachment A of EOP 0 or EOP 1.3 Step 15 will check this valve in the proper position.
Page 21 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EOP 0 Attachment A BOP Verify feedwater isolation.
Verify containment isolation Verify AFW actuation.
Communication: When contacted the PAB AO should Check SI pumps running.
report that SW-LW-61 and 62 radwaste SW isolation Check RHR pumps running.
valves are both shut.
Check only 1 CCW pump running.
Verify Service Water System alignment. BOP should contact the PAB to check 2 local valves.
Verify containment accident cooling.
Check CR ventilation in accident mode.
Check if main steam lines can remain open.
Verify proper SI valve alignment.
Page 22 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS EOP 0 Attachment A (contd) BOP (CA STEP) Verify containment spray not required.
Verify SI flow.
(CA STEP) Check CSR temperature.
(CA STEP) Check AFW Area temperature.
(CA STEP) Check Computer Room temperature.
(CA STEP) Check CWPH temperature.
Communication: When contacted, wait 2 minutes and have the AO report CWPH temperature at 65F and stable.
Page 23 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
SCENARIO TIME-LINE:
SEQ SEQUENCE OF EVENTS / INSTRUCTOR NOTES CREW EXPECTED STUDENT RESPONSES POS When the conditions are stabilized or at discretion of lead Crew:
instructor/evaluator
- No debrief or critique due to this being an End the scenario by placing the simulator in freeze evaluated scenario.
Inform Examinees they are to remain at their stations and cannot discuss the scenario. They are to wait for any follow up questions the examiners may have.
Page 24 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG) 1.0 PLANT CONDITIONS:
UNIT 1 UNIT 2 Time in core life 800 14960 (MWD/MTU):
Reactor power (%): 49% 100%
Boron concentration 1594 ppm 16 ppm (ppm):
Rod height (CBD @): CBD @ 188 CBD @ 220 2.0 TECHNICAL SPECIFICATION ACTION CONDITIONS IN EFFECT:
TSAC Description Reason TSAC 3.7.5.C One motor C.1 Restore motor driven AFW pump system Seal replacement driven AFW pump system to OPERABLE status within 7 days AND 10 is inoperable in Mode 1, 2 days of discovery of failure to meet LCO or 3.
3.0 EQUIPMENT OUT OF SERVICE:
- G01 EDG is in day 3 of a planned 5 day maintenance outage.
- P-38B MDAFW Pump is in day 1 of a 2 day planned maintenance outage for seal replacement.
4.0 PLANNED EVOLUTIONS:
- Immediately following turnover, commence load escalation at 15%/hr to approximately 75% power per OP-1C Startup to Power Operation Unit 1 starting at Step 5.141, referencing the continuous actions of steps 5.125 and 5.126.
- TH and PAB AOs have been briefed on their responsibilities per Step 5.122.
- Notifications have been made for the load escalation per NP 2.1.5.
5.0 TURNOVER INFORMATION:
- Safety Monitor is Green.
- G02 EDG is aligned to 1A05 and 2A05 4160 Safeguards busses per OI-35A, Standby Emergency Power Alignment.
- G02, G03 and G04 EDGs are protected equipment.
- P-38A MDAFW Pump is protected equipment.
Page 25 of 26
Point Beach Nuclear Plant SIMULATOR EXERCISE GUIDE (SEG)
- The plant is under severe thunderstorm watch for the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
AOP-13C, Severe Weather Conditions, is in effect.
- Unit 1 rods are in AUTO and Xenon is stable
- Unit 1 is at 49% awaiting power escalation after completion of maintenance on the B Feed Train.
- Both trains of Feed and Condensate are operating.
- Clock time is real time and you have the normal shift complement.
Page 26 of 26